[Federal Register Volume 79, Number 182 (Friday, September 19, 2014)]
[Rules and Regulations]
[Pages 56238-56263]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2014-22215]


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NUCLEAR REGULATORY COMMISSION

10 CFR Part 51

[NRC-2012-0246]
RIN 3150-AJ20


Continued Storage of Spent Nuclear Fuel

AGENCY: Nuclear Regulatory Commission.

ACTION: Final rule.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is revising its 
generic determination regarding the environmental impacts of the 
continued storage of spent nuclear fuel beyond a reactor's licensed 
life for operation and prior to ultimate disposal. The NRC prepared a 
final generic environmental impact statement that provides a regulatory 
basis for this final rule. The Commission concludes that the generic 
environmental impact statement generically determines the environmental 
impacts of continued storage of spent nuclear fuel beyond the licensed 
life for operation of a reactor. The final rule also clarifies that the 
generic determination applies to license renewal for an independent 
spent fuel storage installation (ISFSI), reactor construction permits, 
and early site permits. The final rule clarifies how the generic 
determination will be used in future NRC environmental reviews, and 
makes changes to improve readability. Finally, the final rule makes 
conforming amendments to the determinations on the environmental 
effects of renewing the operating license of a nuclear power plant to 
address issues related to the onsite storage of spent nuclear fuel and 
offsite radiological impacts of spent nuclear fuel and high-level waste 
disposal.

DATES: This final rule is effective on October 20, 2014.

ADDRESSES: Please refer to Docket ID NRC-2012-0246 when contacting the 
NRC about the availability of information for this final rule. You may 
access publicly-available information related to this final rule by any 
of the following methods:
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search

[[Page 56239]]

for Docket ID NRC-2012-0246. Address questions about NRC dockets to 
Carol Gallagher; telephone: 301-287-3422; email: 
[email protected]. For technical questions, contact the 
individual listed in the FOR FURTHER INFORMATION CONTACT section of 
this final rule.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly available documents online in the 
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and 
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, 
please contact the NRC's Public Document Room (PDR) reference staff at 
1-800-397-4209, at 301-415-4737, or by email to [email protected]. 
The ADAMS accession number for each document referenced in this final 
rule (if that document is available in ADAMS) is provided the first 
time that it is mentioned in the SUPPLEMENTARY INFORMATION section. In 
addition, for the convenience of the reader, the ADAMS accession 
numbers are provided in a table in the ``Availability of Documents'' 
section of this document.
     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.

FOR FURTHER INFORMATION CONTACT: Merri Horn, Office of Nuclear Material 
Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, 
DC 20555-0001; telephone: 301-287-9167; email: [email protected].

SUPPLEMENTARY INFORMATION: 

Executive Summary

A. Need for the Regulatory Action

    The purpose of this final rule (rule) is to preserve the efficiency 
of the NRC's licensing process by adopting into the NRC's regulations 
the Commission's generic determinations of the environmental impacts of 
the continued storage of spent nuclear fuel (spent fuel) beyond the 
licensed life for operations of a reactor (continued storage). The NRC 
has prepared a final generic environmental impact statement that 
addresses the environmental impacts of continued storage and provides a 
regulatory basis for this rule. This rule codifies the results of the 
analyses from the generic environmental impact statement in Sec.  51.23 
of Title 10 of the Code of Federal Regulations (10 CFR), 
``Environmental impacts of continued storage of spent nuclear fuel 
beyond the licensed life for operation of a reactor.'' The NRC's 
licensing proceedings for nuclear reactors and ISFSIs have historically 
relied upon the generic determination in 10 CFR 51.23 to satisfy the 
agency's obligations under the National Environmental Policy Act (NEPA) 
with respect to the narrow area of the environmental impacts of 
continued storage. Environmental impact statements for future reactor 
and spent-fuel-storage facility licensing actions will not separately 
analyze the basis for the environmental impacts of continued storage 
and, as discussed in 10 CFR 51.23, the impact determinations from the 
generic environmental impact statement are deemed to be incorporated 
into these environmental impact statements. Environmental assessments 
for future reactor and spent-fuel-storage facility licensing actions 
will consider the environmental impacts of continued storage, if the 
impacts of continued storage of spent fuel are relevant to the proposed 
action.

B. Major Provisions

    The major changes to the rule are summarized as follows:
     The heading of 10 CFR 51.23 is revised to ``Environmental 
impacts of continued storage of spent nuclear fuel beyond the licensed 
life for operation of a reactor.''
     Paragraph (a) of 10 CFR 51.23 is revised to provide the 
Commission's generic determination regarding the continued storage of 
spent nuclear fuel. The amendments state that the Commission has 
generically determined that the environmental impacts of continued 
storage of spent nuclear fuel beyond the licensed life for operation of 
a reactor are those impacts identified in NUREG-2157, ``Generic 
Environmental Impact Statement for Continued Storage of Spent Nuclear 
Fuel'' (GEIS).
     Paragraph (b) of 10 CFR 51.23 is revised to clarify that 
license renewals for ISFSIs, reactor construction permits, and early 
site permits are included in the scope of the generic determination. 
The rule also makes changes to improve readability and to clarify that 
applicants do not need to address continued storage in their 
environmental reports. The rule also clarifies that the NRC shall deem 
the impact determinations in NUREG-2157 regarding continued storage of 
spent fuel to be incorporated into environmental impact statements 
(EIS) and that the impact determinations shall be considered in 
environmental assessments (EA), if the impacts of continued storage are 
relevant to the proposed action.
     Conforming changes are made to 10 CFR 51.30, 51.50, 51.53, 
51.61, 51.75, 51.80, 51.95, and 51.97 to clarify that ISFSI license 
renewals, construction permits, and early site permits are included in 
the scope of the generic determination, improve readability, clarify 
that applicants do not need to address continued storage in their 
environmental reports, clarify that the NRC shall consider the impact 
determinations in certain EAs, and clarify that the impact 
determinations are deemed incorporated into EISs.
     In Table B-1 in appendix B of subpart A of 10 CFR part 51, 
``Summary of Findings on NEPA Issues for License Renewal of Nuclear 
Power Plants,'' the ``Offsite radiological impacts of spent nuclear 
fuel and high-level waste disposal'' issue is reclassified as a 
Category 1 issue with no impact level assigned and the finding column 
entry is revised to address existing radiation standards.
     In Table B-1 in appendix B of subpart A of 10 CFR part 51, 
the finding column entry for the ``Onsite storage of spent nuclear 
fuel'' issue is revised to include the impacts during the license 
renewal term and the impacts from the continued storage period.

Table of Contents

I. Background
II. Discussion
    A. General Information
    A1. What action is the NRC taking?
    A2. What is the waste confidence proceeding?
    A3. Why is the NRC doing this now?
    A4. Whom will this action affect?
    A5. How can the NRC conduct a generic review when spent fuel is 
stored at specific sites?
    A6. What types of wastes are addressed by the GEIS and rule?
    A7. What activities are not covered by the GEIS and rule?
    A8. How does this rulemaking relate to the licensing of future 
away-from-reactor ISFSIs?
    A9. Will the rulemaking authorize the storage of spent fuel at 
the operating reactor site near me?
    A10. How will the rule and GEIS be used in site-specific 
licensing actions?
    A11. Why is there not a separate waste confidence decision 
document?
    A12. What is the status of the extended storage effort?
    A13. How can the NRC proceed with this rulemaking while research 
on the extended storage of spent fuel is ongoing?
    A14. How frequently does the NRC plan to revisit the GEIS and 
rule?
    B. Rulemaking
    B1. What is the purpose of this rulemaking?
    B2. What is meant by the phrase ``licensed life for operation of 
a reactor?''
    B3. What timeframes are considered in the GEIS?

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    B4. What are the key assumptions used in the GEIS?
    B5. How will significant changes in these assumptions be 
addressed under the NRC's regulatory framework?
    B6. What is the significance of the levels of impact in the GEIS 
(SMALL, MODERATE, LARGE)?
    B7. What are the environmental impacts of at-reactor continued 
storage?
    B8. What are the environmental impacts of away-from-reactor 
continued storage?
    B9. Does a potentially LARGE impact or a range of impacts affect 
the generic determination in the GEIS?
    B10. How does the rule address the impacts from continued 
storage of spent fuel?
    B11. What clarifying changes are addressed in the rule?
    B12. What changes in this rulemaking address continued storage 
for license renewal?
    C. Repository and continued storage conclusions
    C1. What is the basis of the NRC's conclusion that a geologic 
repository is feasible?
    C2. What is the basis for the NRC's conclusion that a repository 
will be available?
    C3. Does the rule address the feasibility and timing of a 
repository?
    C4. What is the basis for the NRC's conclusion regarding safe 
storage of spent fuel in spent fuel pools?
    C5. What is the basis for the NRC's conclusion regarding safe 
storage of spent fuel in dry casks?
    C6. How does the regulatory framework factor into the continued 
safe storage of spent fuel?
    C7. Does the rule address the safety of continued storage of 
spent fuel?
III. Rulemaking Procedure
IV. Summary and Analysis of Public Comments on the Proposed Rule
V. Discussion of Final Amendments by Section
VI. Availability of Documents
VII. Agreement State Compatibility
IX. Voluntary Consensus Standards
X. Record of Decision
XI. Paperwork Reduction Act Statement
XII. Regulatory Analysis
XIII. Regulatory Flexibility Certification
XIV. Plain Writing
XV. Backfitting and Issue Finality
XVI. Congressional Review Act

I. Background

    In the late 1970s, a number of environmental groups and States 
challenged the NRC regarding issues related to the storage and disposal 
of spent fuel. In 1977, the Commission denied a petition for rulemaking 
(PRM), PRM-50-18, filed by the Natural Resources Defense Council (NRDC) 
that asked the NRC to determine whether radioactive wastes generated in 
nuclear power reactors can be disposed of without undue risk to public 
health and safety and to refrain from granting pending or future 
requests for reactor operating licenses until the NRC made such a 
determination. The Commission stated in its denial that, as a matter of 
policy, it ``. . . would not continue to license reactors if it did not 
have reasonable confidence that the wastes can and will in due course 
be disposed of safely'' (42 FR 34391, 34393; July 5, 1977, pet. for 
rev. dismissed sub nom., NRDC v. NRC, 582 F.2d 166 (2d Cir. 1978)).
    At about the same time, interested parties challenged license 
amendments that permitted expansion of the capacity of spent fuel pools 
at two nuclear power plants: Vermont Yankee and Prairie Island. In 
1979, the U.S. Court of Appeals for the District of Columbia Circuit, 
in Minnesota v. NRC, 602 F.2d 412 (D.C. Cir. 1979), did not stay or 
vacate the license amendments, but remanded to the Commission the 
question of whether an offsite storage or disposal solution would be 
available for the spent fuel at the two facilities at the expiration of 
their licenses--at that time scheduled for 2007 and 2009-and, if not, 
whether the spent fuel could be stored safely at those reactor sites 
until an offsite solution became available.
    In 1979, the NRC initiated a generic rulemaking proceeding that 
stemmed from these challenges and the Court's remand in Minnesota v. 
NRC. At that time, the purpose of the Waste Confidence rulemaking was 
to generically assess whether the Commission could have reasonable 
assurance that radioactive wastes produced by nuclear power plants 
``can be safely disposed of, to determine when such disposal or offsite 
storage will be available, and to determine whether radioactive wastes 
can be safely stored onsite past the expiration of existing facility 
licenses until offsite disposal or storage is available'' (44 FR 61372, 
61373; October 25, 1979). On August 31, 1984, the Commission published 
the Waste Confidence Decision (Decision) (49 FR 34658) and a final rule 
(49 FR 34688), codified at 10 CFR 51.23. This Decision provided an EA 
and Finding of No Significant Impact (FONSI) to support the rule. In 
the 1984 Decision the Commission made five findings (Findings):

    1. The Commission finds reasonable assurance that safe disposal of 
radioactive waste and spent fuel in a mined geologic repository is 
technically feasible;
    2. The Commission finds reasonable assurance that one or more mined 
geologic repositories for commercial high-level radioactive waste and 
spent fuel will be available by the years 2007--2009Sec.  \1\ and that 
sufficient repository capacity will be available within 30 years beyond 
the expiration of any reactor operating license to dispose of existing 
commercial high-level radioactive waste and spent fuel originating in 
such reactor and generated up to that time;
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    \1\ The original dates by which the licenses for the facilities 
at issue in Minnesota v. NRC, 602 F.2d 412 (D.C. Cir. 1979) would 
have expired.
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    3. The Commission finds reasonable assurance that high-level 
radioactive waste and spent fuel will be managed in a safe manner until 
sufficient repository capacity is available to assure the safe disposal 
of all high-level radioactive waste and spent fuel;
    4. The Commission finds reasonable assurance that, if necessary, 
spent fuel generated in any reactor can be stored safely and without 
significant environmental impacts for at least 30 years beyond the 
expiration of that reactor's operating license at that reactor's spent 
fuel storage basin or at either onsite or offsite ISFSIs; and
    5. The Commission finds reasonable assurance that safe independent 
onsite or offsite spent fuel storage will be made available if such 
storage capacity is needed.

The rule, 10 CFR 51.23, codified the analysis in the Decision and found 
that for at least 30 years beyond the expiration of a reactor operating 
license, no significant environmental impacts would result from the 
storage of spent fuel and expressed the Commission's reasonable 
assurance that a repository was likely to be available by 2007-2009. 
The rule also stated that, as a result of this generic determination, 
the agency did not need to assess the site-specific impacts of 
continuing to store the spent fuel in either an onsite or offsite 
storage facility in new reactor licensing EISs or EAs beyond the 
expiration dates of reactor licenses (10 CFR 51.23(b)). The rulemaking 
also amended 10 CFR part 50, ``Domestic licensing of production and 
utilization facilities,'' to require operating nuclear power reactor 
licensees to submit their plans for managing spent fuel at their site 
until the fuel is transferred to the U.S. Department of Energy (DOE) 
for disposal (see 10 CFR 50.54(bb)).
    The Commission conducted its first review of the Decision and rule 
in 1989-1990. This review resulted in the revision of the second and 
fourth Findings to reflect revised expectations for the date of 
availability of the first repository, and to clarify that the 
expiration of a reactor's licensed life for operation referred to the 
full 40-year initial license for operation and an

[[Page 56241]]

additional 30 years (which may include the term of a revised or renewed 
license). On September 18, 1990, the Commission published the revised 
Decision (55 FR 38474) and the associated final rule (55 FR 38472). The 
revised Findings 2 and 4 in the 1990 revised Decision were:
    Finding 2: The Commission finds reasonable assurance that at least 
one mined geologic repository will be available within the first 
quarter of the twenty-first century, and sufficient repository capacity 
will be available within 30 years beyond the licensed life for 
operation (which may include the term of a revised or renewed license) 
of any reactor to dispose of the commercial high-level radioactive 
waste and spent fuel originating in such reactor and generated up until 
that time.
    Finding 4: The Commission finds reasonable assurance that, if 
necessary, spent fuel generated at any reactor can be stored safely and 
without significant environmental impacts for at least 30 years beyond 
the licensed life for operation (which may include the term of a 
revised or renewed license) of that reactor at its spent fuel storage 
basin or at either onsite or offsite ISFSIs.
    The Commission also amended 10 CFR 51.23(a) to reflect the revised 
timing of the availability of a geologic repository to the first 
quarter of the twenty-first century. The rule was also revised to 
reflect that the licensed life for operation may include the term of a 
revised or renewed license.
    The Commission conducted its second review of the Decision and rule 
in 1999 and concluded that experience and developments after 1990 had 
confirmed the Findings and made a comprehensive reevaluation of the 
Decision and rule unnecessary (64 FR 68005; December 6, 1999).
    In 2007, the NRC amended 10 CFR 51.23 to indicate that the generic 
determination provisions applied to combined licenses (72 FR 49352; 
August 28, 2007).
    In 2008, the Commission decided to conduct its third review of the 
Decision and rule as part of an effort to enhance the efficiency of 
upcoming combined license application proceedings. The Commission 
determined that it would be more efficient to resolve certain combined-
license-proceeding issues generically, including those related to Waste 
Confidence. This review resulted in a revision of the second and fourth 
Findings to reflect revised expectations for the date of availability 
of the first repository and that spent fuel can be stored safely for at 
least 60 years beyond the licensed life for operation.
    In December 2010, the Commission published its revised Decision (75 
FR 81032; December 23, 2010) and associated final rule (75 FR 81037; 
December 23, 2010). The revised Findings 2 and 4 in the 2010 Decision 
were:
    Finding 2: The Commission finds reasonable assurance that 
sufficient mined geologic repository capacity will be available to 
dispose of the commercial high-level radioactive waste and spent fuel 
generated by any reactor when necessary.
    Finding 4: The Commission finds reasonable assurance that, if 
necessary, spent fuel generated in any reactor can be stored safely and 
without significant environmental impacts for at least 60 years beyond 
the licensed life for operation (which may include the term of a 
revised or renewed license) of that reactor in a combination of storage 
in its spent fuel storage basin and either onsite or offsite ISFSIs.
    Section 51.23(a) of 10 CFR was amended to reflect revised Findings 
2 and 4. The changes reflected that spent fuel could be safely stored 
for at least 60 years beyond the licensed life for operation of a 
reactor and that sufficient mined geologic repository capacity would be 
available when necessary.
    In response to the 2010 Decision and rule, the States of New York, 
New Jersey, Connecticut, and Vermont; several public interest groups; 
and the Prairie Island Indian Community filed a lawsuit in the U.S. 
Court of Appeals for the District of Columbia Circuit that challenged 
the Commission's compliance with NEPA. On June 8, 2012, the Court ruled 
that some aspects of the 2010 proceeding did not satisfy the NRC's NEPA 
obligations and vacated and remanded the Decision and rule (New York v. 
NRC, 681 F.3d 471 (D.C. Cir. 2012) (ADAMS Accession No. ML12191A407). 
The Court concluded that the Waste Confidence rulemaking is a major 
federal action necessitating either an EIS or an EA that results in a 
FONSI. In vacating the 2010 Decision and rule, the Court identified 
three specific deficiencies in the analysis:
    1. Related to the Commission's conclusion that permanent disposal 
will be available ``when necessary,'' the Court held that the 
Commission needed to examine the environmental effects of failing to 
establish a repository;
    2. Related to continued storage of spent fuel, the Court concluded 
that the Commission had not adequately examined the risk of spent fuel 
pool leaks in a forward-looking fashion; and
    3. Also related to the continued storage of spent fuel, the Court 
concluded that the Commission had not adequately examined the 
consequences of potential spent fuel pool fires.
    In response to the Court's decision, on August 7, 2012, the 
Commission stated in Commission Order CLI-12-16 (ADAMS Accession No. 
ML12220A094) that it would not issue reactor or ISFSI licenses 
dependent upon the Waste Confidence Decision and rule until the Court's 
remand is appropriately addressed. The Commission stated, however, that 
this determination extends only to final license issuance and that all 
licensing reviews and proceedings should continue to move forward.
    In the September 6, 2012, Staff Requirements Memorandum (SRM), 
``Staff Requirements--COMSECY-12-0016--Approach for Addressing Policy 
Issues Resulting from Court Decision to Vacate Waste Confidence 
Decision and Rule'' (ADAMS Accession No. ML12250A032), the Commission 
directed the staff to develop a generic EIS to support an updated Waste 
Confidence Decision and rule. In response, the NRC formed the Waste 
Confidence Directorate in the Office of Nuclear Material Safety and 
Safeguards (NMSS) to oversee the development of the generic EIS and an 
update that would replace the previous Waste Confidence Decision and 
rule.

II. Discussion

    This discussion section has been divided into three subsections to 
better present information on the rule and the proceeding. Section A 
provides general information related to the proceeding. Section B 
provides information related to the rule changes. Lastly, Section C 
provides information on the technical feasibility and availability of 
safe storage and a repository. Sections A, B, and C present information 
in a question and answer format.

A. General Information

A1. What action is the NRC taking?
    The NRC is issuing a rule to codify its generic determinations 
regarding the environmental impacts of continued storage of spent fuel 
at-reactor, or away-from-reactor sites beyond a reactor's licensed life 
for operation. The analysis in NUREG-2157, ``Generic Environmental 
Impact Statement for Continued Storage of Spent Nuclear Fuel'' (GEIS) 
(ADAMS Accession No. ML14196A105) provides a regulatory basis for the 
rule.
A2. What is the waste confidence proceeding?
    Historically, the Commission's Waste Confidence proceeding 
represented the

[[Page 56242]]

Commission's generic determination and generic environmental analysis 
that spent fuel could be stored safely and without significant 
environmental impacts for a period of time past the licensed life for 
operation of a reactor. This generic environmental determination was 
reflected in 10 CFR 51.23, which addressed the NRC's NEPA obligations 
with respect to the continued storage of spent fuel.
    This rule and GEIS represent a change in the format of the 
Commission's Waste Confidence proceeding. Because the Commission has 
prepared a generic EIS, which provides a detailed analysis of the 
environmental impacts associated with continued storage, it is no 
longer necessary to make a ``finding of no significant impact,'' or 
``FONSI,'' as that term is used in NEPA. This final rule codifies the 
environmental impact determinations reflected in the GEIS. This is 
discussed in more detail in Question A.11.
A3. Why is the NRC doing this now?
    On June 8, 2012, the U.S. Court of Appeals for the District of 
Columbia Circuit vacated the Commission's 2010 Waste Confidence 
rulemaking, and remanded the rulemaking to the NRC to address 
deficiencies related to the NRC's NEPA analysis. On September 6, 2012, 
the Commission instructed NRC staff to proceed with a generic EIS to 
analyze the environmental impacts of continued storage, address the 
issues raised in the Court's decision, and update the rule in 
accordance with the analysis in the EIS. The GEIS and this final rule 
implement the Commission's direction.
A4. Whom will this action affect?
    This rule will affect any nuclear power reactor applicant and 
licensee seeking issuance or renewal of an operating license or 
construction permit for a nuclear power reactor under 10 CFR parts 50 
or 54, ``Requirements for renewal of operating licenses for nuclear 
power plants;'' issuance of a combined license or early site permit for 
a nuclear power reactor under 10 CFR part 52, ``Licenses, 
certifications, and approvals for nuclear power plants;'' or some 
amendments of a license under 10 CFR parts 50 or 52. This rule will 
also affect the issuance of an initial, amended, or renewed license for 
storage of spent fuel at an ISFSI under 10 CFR part 72, ``Licensing 
requirements for the independent storage of spent nuclear fuel, high-
level radioactive waste, and reactor-related greater than Class C 
waste.'' The rule could also affect participants in any proceeding 
addressing these licensing actions.
A5. How can the NRC conduct a generic review when spent fuel is stored 
at specific sites?
    Since 1984, the NRC has generically addressed the environmental 
impacts of continued storage though a generic NEPA analysis and rule. 
Without a generic environmental impact analysis, site-specific 
consideration of the environmental impacts of continued storage would 
be necessary. In remanding the 2010 Waste Confidence rule to the NRC 
for additional analysis, the Court of Appeals for the District of 
Columbia Circuit continued the long history of federal courts approving 
a generic approach to the analysis of the environmental impacts of 
nuclear power reactor operation. In New York v. NRC, the Court of 
Appeals endorsed the NRC's generic approach, stating that there is ``no 
reason that a comprehensive general analysis would be insufficient to 
examine on-site risks that are essentially common to all plants.'' (New 
York, 681 F.3d at 480). After conducting the analysis in the GEIS, the 
NRC concludes that the impacts of continued storage will not vary 
significantly across sites, despite variations in site-specific 
characteristics. Accordingly, the NRC believes that a generic approach 
is appropriate for this proceeding.
    The NRC has determined in the GEIS that the direct and indirect 
environmental impacts of continued storage at reactors can be analyzed 
generically. This means that, for each of the resource areas analyzed 
in the GEIS, the NRC has reached a generic determination (SMALL, 
MODERATE, LARGE, or a range) that is appropriate for all sites. As 
discussed in the GEIS, these impact determinations are not expected to 
differ from those that would result from individual site-specific 
reviews for the continued storage period.
    The NRC's evaluation of the environmental impacts of continued 
storage builds upon substantial operating experience over the licensed 
life of the reactor. The environmental impacts associated with spent 
fuel storage during the licensed life for operation are addressed 
during the NRC's review of license applications and license renewal 
applications. The environmental impacts associated with spent fuel 
storage in an at-reactor ISFSI during the licensed life for operation 
of a reactor are addressed through the 1989 environmental assessment 
supporting the final rule for 10 CFR part 72 general licenses, in the 
environmental assessments prepared to support rules approving 
Certificates of Compliance for dry cask systems, in a site-specific 
environmental assessment for specifically licensed ISFSIs, or during 
the NRC's review of license renewal applications. Site-specific 
analyses capture the characteristics that most obviously vary from site 
to site, such as seismic activity, land use, ecosystem, and local 
population variations. During operation, facility operators and the NRC 
gain significant additional experience with site-specific issues, 
including those related to issues of site configuration and maintenance 
history. During the licensed life of a facility, many factors ensure 
that operational impacts, including those from accidents or off-normal 
releases, are within regulatory limits at any given site. These factors 
include the plant's operating experience, licensee compliance with NRC 
regulations, site-specific mitigation and controls informed by the 
licensing reviews, and ongoing regulatory oversight and enforcement 
actions. In the continued storage period, many of the environmental 
impacts related to storage of spent fuel are not expected to vary 
beyond the range experienced during operations. Changes in the 
environment during the continued storage periods examined in the GEIS 
are expected to be gradual and predictable. There are inherent 
uncertainties in determining impacts for the long-term and indefinite 
timeframes, and, with respect to some resource areas, those 
uncertainties could result in impacts that, although unlikely, could be 
larger than those that are to be expected at most sites and have 
therefore been presented as ranges rather than as a single impact 
level. Those uncertainties exist, however, regardless of whether the 
impacts are analyzed generically or site-specifically. Despite 
variations in site-specific characteristics, a generic analysis is 
capable of determining and expressing the environmental impacts that 
may result from continued storage.
    The reasonableness of NRC's determinations about continued storage 
is supported by numerous environmental reviews of spent fuel storage. 
Spent fuel storage during the period of operations has been considered 
in site-specific licensing of new reactors (for spent fuel pools only), 
ISFSIs, and license renewals. Finally, concerned parties who meet the 
waiver criteria in 10 CFR 2.335 will be able to raise site-specific 
issues related to continued storage at the time of a specific license 
application.

[[Page 56243]]

A6. What types of wastes are addressed by the GEIS and rule?
    The environmental analysis in the GEIS and the rule covers low and 
high burn-up spent fuel generated in light-water nuclear power 
reactors. It also covers mixed oxide (MOX) fuel,\2\ since MOX fuel is 
substantially similar to existing light-water reactor fuel and is, in 
fact, being considered for use in existing light-water reactors in the 
United States. It also covers spent fuel from small modular light-water 
reactors. Small modular light-water reactors being developed will use 
fuel very similar in form and materials to the existing operating 
reactors and will not, therefore, introduce new technical challenges to 
the storage of spent fuel. The environmental analysis in the GEIS also 
covers the spent fuel from one high-temperature gas-cooled reactor 
(HTGR) built and commercially operated: Fort Saint Vrain.
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    \2\ Mixed oxide fuel (often called MOX fuel) is a type of 
nuclear power reactor fuel that contains plutonium oxide mixed with 
either natural or depleted uranium oxide in ceramic pellet form.
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A7. What activities are not covered by the GEIS and rule?
    The GEIS and rule do not consider disposal of spent fuel or storage 
of spent fuel during the licensed life for operation of the power 
reactor. Additionally, the GEIS and rule do not address foreign spent 
fuel, non-power reactor spent fuel (e.g., fuel from research and test 
reactors), defense waste, Greater-than-Class C low-level waste, 
reprocessing of commercial spent fuel, or the need for nuclear power 
(see also question A9).
A8. How does this rulemaking relate to the licensing of future away-
from-reactor ISFSIs?
    The GEIS and rule do not satisfy the NRC's obligations under NEPA 
to analyze the environmental impacts of spent fuel storage during the 
term of a facility's license. The NRC must conduct a site-specific 
environmental analysis to support the licensing of any future away-
from-reactor ISFSI. The NRC cannot use the rule and GEIS as a 
substitute for the environmental analysis associated with constructing 
and operating an away-from-reactor ISFSI. The site-specific NEPA 
analysis for an away-from-reactor ISFSI can only rely on the analysis 
in the GEIS and the requirements in the rule to satisfy the NRC's NEPA 
obligations with respect to the storage of spent fuel during the 
applicable continued storage period.
A9. Will the rulemaking authorize the storage of spent fuel at the 
operating reactor site near me?
    No, the rule does not authorize the storage of spent fuel at any 
site. The rule reflects only the generic environmental analysis for the 
period of spent fuel storage beyond a reactor's licensed life for 
operation and before disposal in a repository. This proceeding is not a 
substitute for licensing actions that typically include site-specific 
NEPA analysis and site-specific safety analyses (see also question 
A10).
    In addition, the NRC's GEIS and final rule do not pre-approve any 
particular waste storage or disposal site technology, nor do they 
require that a specific cask design be used for storage. Individual 
licensees and applicants, including any applicant for a high-level 
radioactive waste repository, are required to have a license from the 
NRC before storing or disposing of any spent fuel. Separately, every 10 
CFR part 50 or part 52 nuclear power reactor licensee, by virtue of 10 
CFR part 72, subpart K, has a general license authorizing storage of 
spent fuel in cask designs that are approved by the NRC.
A10. How will the rule and GEIS be used in site-specific licensing 
actions?
    The rule, which adopts the generic impact determinations regarding 
continued storage from the GEIS, satisfies the NRC's NEPA obligations 
with respect to continued storage for initial, renewed, and amended 
licenses for reactors and ISFSIs, as well as for construction permits 
and early site permits. The rule does not satisfy the NRC's obligation 
to assess the environmental impacts of spent fuel storage during a 
facility's licensed life for operation. The impacts of storage during a 
proposed license term at a specific site, as distinct from the 
timeframes of continued storage covered by the rule, would be subject 
to the safety and environmental review as part of other licensing 
reviews.
    The GEIS (NUREG-2157) only satisfies a portion of the NRC's NEPA 
obligations related to the issuance of a reactor or spent fuel storage 
facility license by generically evaluating the environmental impacts of 
continued storage. These generic determinations will not be revisited 
and may not be challenged in individual licensing proceedings without 
the grant of a waiver under 10 CFR 2.335. Taken together, the GEIS, the 
site-specific environmental review, and other applicable environmental 
reviews will provide the decision-maker in a licensing proceeding with 
a complete environmental analysis of the impacts associated with spent 
fuel storage prior to disposal in a geologic repository.
    Under final 10 CFR 51.23, the impact determinations in NUREG-2157 
are deemed incorporated into an EIS that is prepared to support a 
licensing action for a power reactor or ISFSI. For a licensing action 
supported by an EA, the NRC will consider the impact determinations in 
NUREG-2157 in the EA, if the impacts of continued storage of spent fuel 
are relevant to the proposed action. This means that NUREG-2157 
provides the determinations of the environmental impacts of continued 
storage to be used in site-specific environmental reviews. No 
additional analysis of the impacts of continued storage is required.
    The findings of the site-specific environmental review may be 
challenged during the initial licensing of a facility and at license 
renewal. As a result of this rulemaking, what may not be considered in 
those proceedings--due to the generic determination in 10 CFR 
51.23(a)--are the environmental impacts of continued storage of spent 
fuel beyond the licensed life for operation of the reactor contained in 
NUREG-2157. The NRC's regulations at 10 CFR 2.335, however, allow 
participants in NRC's licensing proceedings to request that a rule, 
including 10 CFR 51.23, not be applied, or be waived, in a particular 
proceeding because special circumstances are present that would prevent 
the application of the rule from satisfying the purpose of the rule.
    The GEIS and rule are applicable only to future NRC licensing 
actions and do not apply to completed licensing actions.
A11. Why is there not a separate waste confidence decision document?
    Historically, the Waste Confidence Decision contained five 
``Findings'' that addressed the technical feasibility of a mined 
geologic repository, the degree of assurance that disposal would be 
available by a certain time, and the degree of assurance that spent 
fuel and high-level waste could be managed safely without significant 
environmental impacts for a certain period beyond the expiration of 
plants' operating licenses. Preparation of and reliance upon a GEIS is 
a fundamental departure from the approach used in past proceedings. The 
GEIS acknowledges the uncertainties inherent in a prediction of 
repository availability and provides an environmental analysis of three 
timeframes, including one where a repository does not become available. 
The relationship between the prior

[[Page 56244]]

``Findings'' and the technical feasibility analyses in the current GEIS 
is discussed in greater detail in Section D.2.4.1. As noted in the 
GEIS, the former ``Findings'' were outputs of previous Waste Confidence 
proceedings, which included an environmental assessment and finding of 
no significant impact. In contrast, the current GEIS provides a 
detailed analysis under NEPA and provides an analysis of specific 
impacts.
    To support the analysis in the GEIS and the rule, the underlying 
assumptions in the GEIS address the issues assessed in the previous 
five ``Findings'' as conclusions regarding the technical feasibility 
and availability of a repository and conclusions regarding the 
technical feasibility of safely storing spent fuel in an at-reactor or 
away-from-reactor storage facility. The issue of the technical 
feasibility of a geologic repository was historically addressed in 
Finding 1 and is now discussed in Section B.2.1 of the GEIS and the 
availability of a repository was addressed in Finding 2 and is now 
discussed in Section B.2.2. The regulatory framework for spent fuel 
storage was previously addressed in Findings 3 and 5 and is now 
addressed in Section B.3.3. The safe storage of spent fuel pending 
ultimate disposal at a repository was previously addressed in Finding 4 
and is now addressed in Sections B.3.1 and B.3.2. Thus, the GEIS 
fulfills the NRC's NEPA obligations for analyzing the environmental 
impacts of continued storage in a more traditional NEPA format.
A12. What is the status of the extended storage effort?
    The extended storage effort is an activity that is separate from 
this proceeding and that focuses on technical and regulatory 
considerations for the continued effective regulation of spent fuel 
storage and subsequent transportation over extended periods (up to 300 
years). Presently, the NRC believes that the existing regulatory 
framework used to renew current licenses can be extended to regulate 
the management of spent fuel for multiple renewal periods. The staff is 
examining technical areas associated with multiple renewals of fixed-
term, dry storage licenses and certificates to address age-related 
degradation of dry cask storage systems, structures, and components. 
The NRC acknowledges that current licensing practices may evolve over 
time in response to improved understanding, operational experience, and 
Commission policy direction. As technical, regulatory, and policy 
issues are resolved, the NRC will revise guidance and staff 
qualification and training accordingly. Completion of the Extended 
Storage effort is planned for the end of the decade. The NRC will 
evaluate any new information that is developed during the Extended 
Storage effort to determine whether it is necessary to update the GEIS 
or 10 CFR 51.23.
A13. How can the NRC proceed with this rulemaking while research on the 
extended storage of spent fuel is ongoing?
    Development of the GEIS and the NRC's ongoing research are two 
separate efforts that are not dependent on each other. This rulemaking 
updates the NRC's environmental rules in 10 CFR part 51. The GEIS, 
NUREG-2157, which was prepared to satisfy the NRC's NEPA obligations, 
provides a regulatory basis for the rule. Under NEPA, an EIS, such as 
the one prepared to support this rulemaking, need only consider 
currently available information. As the Commission recently stated, 
``NEPA requires that we conduct our environmental review with the best 
information available today. It does not require that we wait until 
inchoate information matures into something that later might affect our 
review.'' (Luminant Generation Co. LLC (Comanche Peak Nuclear Power 
Plant, Units 3 and 4), et al., CLI-12-7, 75 NRC 379, 391-92 (2012)). 
Further, the United States Court of Appeals for the District of 
Columbia Circuit explained that ``creating [the agency's] models with 
the best information available when it began its analysis and then 
checking the assumptions of those models as new information became 
available, was a reasonable means of balancing competing 
considerations, particularly given the many months required to conduct 
full modeling with new data.'' (Village of Bensenville v. Federal 
Aviation Administration, 457 F.3d 52, 71-72 (D.C. Cir. 2006)). The 
United States Supreme Court held that ``an agency need not supplement 
an EIS every time new information comes to light after the EIS is 
finalized. To require otherwise would render agency decision making 
intractable, always awaiting updated information only to find the new 
information outdated by the time a decision is made.'' (Marsh v. Oregon 
Natural Resources Council, 490 U.S. 360, 374 (1989)).
    In the GEIS, the NRC has concluded that sufficient information 
exists to perform an analysis of continued storage impacts for the 
three timeframes analyzed. Nonetheless, the NRC continues to identify 
and resolve potential issues associated with the storage and 
transportation of spent fuel for periods beyond an ISFSI's initial 
licensing and first renewal. The ongoing research into the extended 
storage of spent fuel is part of the NRC's effort to continuously 
evaluate and update its safety regulations. The NRC is not aware of any 
deficiencies in its current regulations that would challenge the 
continued safe storage of spent fuel in spent fuel pools or dry cask 
systems.
    If, at some time in the future, the NRC were to identify a concern 
with the safe storage of spent fuel, the NRC would evaluate the issue 
and take whatever action or make whatever change in its regulatory 
program necessary to protect public health and safety. The NRC will 
continue to monitor the ongoing research into spent fuel storage. When 
warranted by significant events that may call into question the 
appropriateness of the rule, the NRC will review the GEIS and rule to 
determine if revisions are necessary.
A14. How frequently does the NRC plan to revisit the GEIS and rule?
    The Commission has reviewed the rule and supporting analysis four 
times since 1984; in 1990, 1999, 2010, and now in 2014. The NRC does 
not have a schedule for revisiting the GEIS and rule after this current 
update. The NRC will review the GEIS and rule for possible revision 
when warranted by significant events that may call into question the 
appropriateness of the rule.

B. Rulemaking

B1. What is the purpose of this rulemaking?
    Historically, the NRC and license applicants have relied on 10 CFR 
51.23 to conclusively address the environmental impacts of continued 
storage in environmental reports, EISs, and EAs. The NRC's use of 10 
CFR 51.23 to satisfy its NEPA obligations with respect to continued 
storage will enhance efficiency in individual licensing reviews by 
incorporating the determinations from the generic analysis of the 
environmental impacts of continued storage into environmental impact 
statements that need to address continued storage. For EAs that need to 
address continued storage, the NRC will consider the environmental 
impacts of continued storage, as provided in 10 CFR 51.23. Having 
confirmed that the environmental impacts of continued storage can be 
analyzed generically, the Commission has decided to codify the GEIS 
impact determinations in a revised rule, 10 CFR 51.23. Because the 
impacts of continued storage have been generically assessed in the 
GEIS, NEPA

[[Page 56245]]

analyses for relevant future reactor and spent fuel storage facility 
licensing actions will not need to separately determine the 
environmental impacts of continued storage. The analysis in the GEIS 
constitutes a regulatory basis for the rule at 10 CFR 51.23.
    Part of the environmental analysis for a nuclear power reactor or 
storage facility license includes a review of the impacts caused by the 
spent fuel generated in the reactor. That analysis must assess the 
impacts of the spent fuel from generation through disposal. As 
codified, the impact determinations in the GEIS will inform the 
decision-makers in licensing proceedings of the reasonably foreseeable 
environmental impacts of continued storage. These determinations will 
be weighed along with other impacts determined by the NRC on a site-
specific basis for the facility or an activity. Thus, in the course of 
an individual licensing proceeding, the decision-maker will be able to 
compare all the environmental impacts of a proposed licensing action 
(e.g., licensing a nuclear power reactor), including continued storage 
impacts, to the environmental impacts of reasonable alternatives, 
including the no-action alternative.
B2. What is meant by the phrase ``licensed life for operation of a 
reactor''?
    The phrase ``licensed life for operation of a reactor'' refers to 
the term of the license to operate a reactor. The GEIS assumes an 
original licensed life of 40 years and up to two 20-year license 
extensions \3\ for each reactor, for a total of up to 80 years of 
operation. The phrase, ``beyond licensed life for operation of a 
reactor,'' refers to the period beyond the initial license term to 
operate a reactor and, if the license is extended, beyond the renewed 
license term. The date of permanent cessation of operations (shut down) 
does not necessarily mark the transition to ``beyond licensed life for 
operation.'' Because the continued storage analysis informs the larger 
NEPA analysis that occurs before a license is issued, even if a reactor 
is shut down years before the end of its initial or extended license 
term, ``licensed life for operation'' continues to refer to the initial 
or renewed license term, and not the actual operational period of a 
reactor. The environmental analysis supporting spent fuel storage 
during the licensed life for operation of each reactor covers the full 
period for which the license or license renewal was issued, even if 
operation of the reactor ended before the license expired. Thus, 
continued storage begins at the end of the licensed life for operation 
of a reactor. The starting point for continued storage does not depend 
on whether the spent fuel is stored in a spent fuel pool, dry casks 
under a general license, or dry casks under a specific license.
---------------------------------------------------------------------------

    \3\ The Commission's regulations provide that renewed operating 
licenses may be subsequently renewed, although no licensee has yet 
submitted an application for such a subsequent renewal. The GEIS 
assumes two renewals in evaluating potential environmental impacts.
---------------------------------------------------------------------------

B3. What timeframes are considered in the GEIS?
    The NRC has analyzed three timeframes in the GEIS that represent 
various scenarios for the length of continued storage that may be 
needed before spent fuel is sent to a repository. The first timeframe 
is the short-term timeframe, which analyzes 60 years of continued 
storage after the end of a reactor's licensed life for operation. The 
NRC considers the short-term timeframe to be the most likely scenario 
for continued storage; and the GEIS assumes that a repository would 
become available by the end of the short-term timeframe. The GEIS also 
analyzed two additional timeframes: Long-term and indefinite. The long-
term timeframe considers the environmental impacts of continued storage 
for 160 years after the end of a reactor's licensed life for operation. 
Finally, the GEIS includes an analysis of an indefinite timeframe, 
which assumes that a repository never becomes available.
    By the end of the short-term timeframe, some spent fuel could be 
between 100 and 140 years old. Short-term storage of spent fuel 
includes the following:
     Continued storage of spent fuel in spent fuel pools (at-
reactor only) and ISFSIs;
     Routine maintenance of spent fuel pools and ISFSIs (e.g., 
maintenance of concrete pads); and
     Handling and transfer of spent fuel from spent fuel pools 
to ISFSIs (all spent fuel is assumed to be removed from the spent fuel 
pool by the end of the short-term timeframe).
    Long-term storage is continued storage of spent fuel for an 
additional 100 years after the short-term timeframe for a total of 160 
years beyond the licensed life for operation of a reactor. The GEIS 
assumes that all spent fuel has been transferred from the spent fuel 
pool to an ISFSI by the end of the short-term period. The GEIS also 
assumes that a repository would become available by the end of the 
long-term timeframe. By the end of the long-term timeframe, some spent 
fuel could be between 200 and 240 years old. Long-term storage 
activities include the following:
     Continued storage of spent fuel in ISFSIs, including 
routine maintenance;
     One time replacement of ISFSIs and spent fuel canisters 
and casks; and
     Construction, operation, and one replacement of a dry 
transfer system (DTS).
    The third timeframe analyzed by the GEIS is the indefinite 
timeframe, which assumes that a repository does not become available. 
The Commission does not believe that this scenario is likely to occur, 
but its inclusion in the analysis allows the NRC to fully analyze the 
environmental impacts associated with continued storage. The activities 
during the indefinite timeframe are the same as those that would occur 
for the long-term timeframe; however, without a repository the 
replacement activities would occur every 100 years.
B4. What are the key assumptions used in the GEIS?
    To guide its analysis, the NRC relied upon certain assumptions 
regarding storage of spent fuel. A detailed discussion of these 
assumptions is contained in Section 1.8.3 of the GEIS. Key assumptions 
used in the GEIS include, but are not limited to the following:
     Institutional controls, including the continued regulation 
of spent fuel, will continue.
     Spent fuel canisters and casks would be replaced 
approximately once every 100 years.
     A DTS would be built at each ISFSI location for fuel 
repackaging and the ISFSIs and DTS facilities would be replaced 
approximately once every 100 years.
     All spent fuel would be removed from spent fuel pools to 
dry storage by the end of the short-term timeframe (60 years after 
licensed life).
     An ISFSI of sufficient size to hold all spent fuel 
generated during licensed life for operation will be constructed before 
the end of the reactor's licensed life for operation.
     In accordance with NEPA, the NRC's analysis in the GEIS is 
based on current technology and regulations.
B5. How will significant changes in these assumptions be addressed 
under the NRC's regulatory framework?
    The NRC has historically reviewed the rule as the policy and 
technological foundations for spent fuel storage and disposal have 
evolved. Technological changes that might require revisiting the 
assumptions, such as revisions to the NRC's safety regulations that 
allow or require a shorter or longer period of

[[Page 56246]]

time before repackaging, are not likely to affect the overall 
conclusions in the GEIS that provide a regulatory basis for the rule 
and, accordingly, every future change in the assumptions underlying the 
GEIS would not necessarily justify an update to the rule. These 
technological changes could require licensees to amend their licenses, 
which would be accompanied by site-specific safety and environmental 
reviews related to the specific amendments. The NRC will continue to 
monitor changes in national policy and developments in spent fuel 
storage and disposal technology. When warranted by significant events 
that may call into question the appropriateness of the rule, the NRC 
will review the GEIS and rule to determine if revisions are necessary.
B6. What is the significance of the levels of impact in the GEIS 
(SMALL, MODERATE, LARGE)?
    The NRC describes the affected environment in terms of resource 
areas: land use, socioeconomics, environmental justice, air quality, 
climate change, geology and soils, surface water, groundwater, 
terrestrial resources, aquatic ecology, special status species and 
habitats, historic and cultural resources, noise, aesthetics, waste 
management, transportation, and public and occupational health. The 
GEIS contains analyses of the environmental impacts associated with 
each resource area. Additionally, the GEIS considers the impacts on 
resource areas caused by postulated acts of terrorism and accidents. 
The significance of the magnitude of the impact for most of the 
resource areas evaluated is expressed as SMALL, MODERATE, or LARGE. The 
general definitions of significance levels are:
    SMALL: The environmental effects are not detectable or are so minor 
that they will neither destabilize nor noticeably alter any important 
attribute of the resource. For the purposes of assessing radiological 
impacts, the Commission has concluded that radiological impacts that do 
not exceed permissible levels in the Commission's regulations are 
considered small.
    MODERATE: The environmental effects are sufficient to alter 
noticeably, but not to destabilize, important attributes of the 
resource.
    LARGE: The environmental effects are clearly noticeable and are 
sufficient to destabilize important attributes of the resource.
    The GEIS discussion of each resource area includes an explanation 
of how the significance category was determined. For issues in which 
the significance determination is based on risk (i.e., the probability 
of occurrence as well as the potential consequences), the probability 
of occurrence as well as the potential consequences have been factored 
into the determination of significance. For some resource areas, the 
impact determination language is specific to the authorizing 
regulation, executive order, or guidance.
B7. What are the environmental impacts of at-reactor continued storage?
    The environmental impacts of continued storage are analyzed in the 
GEIS. The GEIS contains a detailed analysis of the impacts for short-
term storage, long-term storage, and indefinite storage. The analysis 
considers both at-reactor storage and away-from-reactor storage.\4\ 
Impacts attributable to at-reactor storage are addressed here and the 
impacts from away-from-reactor storage are addressed in question B8.
---------------------------------------------------------------------------

    \4\ For the purposes of the GEIS impact analysis, the GEH-Morris 
facility and the DOE TMI-2 ISFSI at Idaho Falls, Idaho were 
considered under the at-reactor storage evaluation.
---------------------------------------------------------------------------

    For at-reactor storage, the unavoidable adverse environmental 
impacts for each resource area are SMALL for all timeframes with the 
exception of waste management impacts, which are SMALL to MODERATE for 
the indefinite storage timeframe, and historic and cultural resource 
impacts, which are SMALL to LARGE for the long-term and indefinite 
storage timeframes. These elevated impact conclusions are influenced, 
in part, by the uncertainties regarding the specific circumstances of 
continued storage over long timeframes, including site-specific 
characteristics that could affect the intensity of potential 
environmental impacts, and the resulting analysis assumptions that have 
been made by the NRC as documented in detail in Chapter 4 of the GEIS. 
The MODERATE waste-management impacts are associated with the volume of 
nonhazardous solid waste generated by assumed facility replacement 
activities for the indefinite timeframe. The historic and cultural 
resource impacts would range from SMALL to LARGE for the long-term and 
indefinite timeframes. This range takes into consideration routine 
maintenance and monitoring (i.e., no ground-disturbing activities), the 
absence or avoidance of historic and cultural resources, and potential 
ground-disturbing activities that could impact historic and cultural 
resources. In addition, the analysis considers uncertainties inherent 
in analyzing this resource area over long timeframes. These 
uncertainties include any future discovery of previously unknown 
historic and cultural resources; resources that gain significance 
within the vicinity and the viewshed (e.g., nomination of a historic 
district) due to improvements in knowledge, technology, and excavation 
techniques; and changes associated with predicting resources that 
future generations will consider significant. A SMALL impact would 
occur if replacement activities occur in previously disturbed areas, 
there are no historic or cultural resources present, or if historical 
and cultural resources can be avoided. A potential MODERATE or LARGE 
impact would result if historic and cultural resources are present at a 
site and, because they cannot be avoided, are impacted by ground-
disturbing activities during the long-term or indefinite timeframe.
    For some resource areas, the impact determination language is 
specific to the authorizing regulation, executive order, or guidance. 
For special status species, continued storage impacts would be 
determined as part of an Endangered Species Act consultation and the 
Magnuson-Stevens Fishery Conservation and Management Act. Continued at-
reactor storage is not expected to cause disproportionately high and 
adverse human health and environmental effects on minority and low-
income populations. In addition, as indicated in the Commission's 
policy statement, environmental justice impacts would be considered 
during site-specific environmental reviews for specific licensing 
actions.
    Table 1 provides a summary of the environmental impacts of 
continued at-reactor storage. Detailed discussion for each resource 
area can be found in Chapter 4 of the GEIS. Cumulative impacts are 
addressed in Chapter 6 of the GEIS. Chapter 8 of the GEIS provides a 
summary of the impacts.

[[Page 56247]]



                  Table 1--Environmental Impacts of At-Reactor Continued Storage of Spent Fuel
----------------------------------------------------------------------------------------------------------------
            Resource area                 Short-term storage       Long-term storage        Indefinite storage
----------------------------------------------------------------------------------------------------------------
Land Use.............................  SMALL..................  SMALL..................  SMALL.
Socioeconomics.......................  SMALL..................  SMALL..................  SMALL.
                                      --------------------------------------------------------------------------
Environmental Justice................        Disproportionately high and adverse impacts are not expected.
                                      --------------------------------------------------------------------------
Air Quality:
    Air Emissions....................  SMALL..................  SMALL..................  SMALL.
    Thermal Release..................  SMALL..................  SMALL..................  SMALL.
Climate Change.......................  SMALL..................  SMALL..................  SMALL.
Geology and Soils....................  SMALL..................  SMALL..................  SMALL.
Surface Water:
    Quality..........................  SMALL..................  SMALL..................  SMALL.
    Consumptive Use..................  SMALL..................  SMALL..................  SMALL.
Groundwater:
    Quality..........................  SMALL..................  SMALL..................  SMALL.
    Consumptive Use..................  SMALL..................  SMALL..................  SMALL.
Terrestrial Resources................  SMALL..................  SMALL..................  SMALL.
Aquatic Ecology......................  SMALL..................  SMALL..................  SMALL.
                                      --------------------------------------------------------------------------
Special Status Species and Habitats..    Impacts for Federally threatened and endangered species and Essential
                                            Fish Habitat would be determined as part of consultations for the
                                          Endangered Species Act and Magnuson-Stevens Fishery Conservation and
                                                                     Management Act.
                                      --------------------------------------------------------------------------
Historic and Cultural Resources......  SMALL..................  SMALL to LARGE.........  SMALL to LARGE.
Noise................................  SMALL..................  SMALL..................  SMALL.
Aesthetics...........................  SMALL..................  SMALL..................  SMALL.
Waste Management:
    LLW..............................  SMALL..................  SMALL..................  SMALL.
    Mixed Waste......................  SMALL..................  SMALL..................  SMALL.
    Nonradioactive Waste.............  SMALL..................  SMALL..................  SMALL to MODERATE.
Transportation:
    Traffic..........................  SMALL..................  SMALL..................  SMALL.
    Health impacts...................  SMALL..................  SMALL..................  SMALL.
Public and Occupational Health.......  SMALL..................  SMALL..................  SMALL.
Accidents............................  SMALL..................  SMALL..................  SMALL.
Sabotage or Terrorism................  SMALL..................  SMALL..................  SMALL.
----------------------------------------------------------------------------------------------------------------

B8. What are the environmental impacts of away-from-reactor continued 
storage?
    The away-from-reactor environmental impacts analyzed in the GEIS 
include the impacts from constructing the ISFSI. Although an away-from-
reactor ISFSI would be subject to a site-specific licensing review that 
includes an EIS that would assess the environmental impacts due to 
construction, the impacts due to construction are included in the GEIS 
due to the potential for that construction to occur during the 
timeframes analyzed in the GEIS. Inclusion of the away-from-reactor 
ISFSI in the GEIS does not mean that the NRC is proposing an interim or 
consolidated storage facility.
    For away-from-reactor storage, the unavoidable adverse 
environmental impacts for each resource area is SMALL except for air 
quality, terrestrial ecology, aesthetics, waste management, and 
transportation where the impacts are SMALL to MODERATE. Socioeconomic 
impacts range from SMALL (adverse) to LARGE (beneficial) and historic 
and cultural resource impacts could be SMALL to LARGE. The potential 
MODERATE impacts on air quality, terrestrial wildlife, and 
transportation are based on potential construction-related fugitive 
dust emissions, terrestrial wildlife direct and indirect mortalities, 
terrestrial habitat loss, and temporary construction traffic impacts. 
The potential MODERATE impacts on aesthetics and waste management are 
based on noticeable changes to the viewshed from constructing a new 
away-from-reactor ISFSI, and the volume of nonhazardous solid waste 
generated by assumed ISFSI and DTS replacement activities for the 
indefinite timeframe. The potential LARGE (beneficial) impacts on 
socioeconomics are due to local economic tax revenue increases from an 
away-from-reactor ISFSI. The potential impacts to historic and cultural 
resources during the short-term storage timeframes would range from 
SMALL to LARGE. The magnitude of adverse effects on historic properties 
and impacts on historic and cultural resources largely depends on where 
facilities are sited, what resources are present, the extent of 
proposed land disturbance, whether the area has been previously 
surveyed to identify historic and cultural resources, and if the 
licensee has management plans and procedures that are protective of 
historic and cultural resources. Even a small amount of ground 
disturbance (e.g., clearing and grading) could affect a small but 
significant resource. In most instances, placement of storage 
facilities on the site can be adjusted to minimize or avoid impacts on 
any historic and cultural resources in the area. However, the NRC 
recognizes that this is not always possible. The NRC's site-specific 
environmental review and compliance with the National Historic 
Preservation Act (NHPA) process could identify historic properties, 
identify adverse effects, and potentially resolve adverse effects on 
historic properties and impacts on other historic and cultural 
resources. Under the NHPA, mitigation does not eliminate a finding of 
adverse effect on historic properties. The potential impacts to 
historic and cultural resources during the long-term and indefinite 
storage timeframes would range from SMALL to LARGE. This range takes 
into consideration routine maintenance and monitoring (i.e., no

[[Page 56248]]

ground-disturbing activities), the absence or avoidance of historic and 
cultural resources, and potential ground-disturbing activities that 
could affect historic and cultural resources. The analysis also 
considers uncertainties inherent in analyzing this resource area over 
long timeframes. These uncertainties include any future discovery of 
previously unknown historic and cultural resources; resources that gain 
significance within the vicinity and the viewshed (e.g., nomination of 
a historic district) due to improvements in knowledge, technology, and 
excavation techniques and changes associated with predicting resources 
that future generations will consider significant. If construction of a 
DTS and replacement of the ISFSI and DTS occurs in an area with no 
historic or cultural resource present or construction occurs in a 
previously disturbed area that allows avoidance of historic and 
cultural resources then impacts would be SMALL. By contrast, a MODERATE 
or LARGE impact could result if historic and cultural resources are 
present at a site and, because they cannot be avoided, are impacted by 
ground-disturbing activities during the long-term and indefinite 
timeframes.
    Impacts on Federally listed species, designated critical habitat, 
and essential fish habitat would be based on site-specific conditions 
and determined as part of consultations required by the Endangered 
Species Act and the Magnuson-Stevens Fishery Conservation and 
Management Act. Continued storage at an away-from-reactor ISFSI is not 
expected to cause disproportionately high and adverse human health and 
environmental effects on minority and low-income populations. In 
addition, as indicated in the Commission's policy statement, should the 
NRC receive an application for a proposed away-from-reactor ISFSI, a 
site-specific NEPA analysis would be conducted, and this analysis would 
include consideration of environmental justice impacts.
    Table 2 provides a summary of the environmental impacts of away-
from-reactor continued storage. Detailed discussion for each resource 
area can be found in Chapter 5 of the GEIS. Cumulative impacts are 
addressed in Chapter 6 of the GEIS. Chapter 8 of the GEIS provides a 
summary of the impacts.

               Table 2--Environmental Impacts of Away-From Reactor Continued Storage of Spent Fuel
----------------------------------------------------------------------------------------------------------------
            Resource area                 Short-term storage       Long-term storage        Indefinite storage
----------------------------------------------------------------------------------------------------------------
Land Use.............................  SMALL..................  SMALL..................  SMALL
Socioeconomics.......................  SMALL (adverse) to       SMALL (adverse) to       SMALL (adverse) to
                                        LARGE (beneficial).      LARGE (beneficial).      LARGE (beneficial).
                                      --------------------------------------------------------------------------
Environmental Justice................        Disproportionately high and adverse impacts are not expected.
                                      --------------------------------------------------------------------------
Air Quality..........................  SMALL to MODERATE......  SMALL..................  SMALL.
Climate Change.......................  SMALL..................  SMALL..................  SMALL.
Geology and Soils....................  SMALL..................  SMALL..................  SMALL.
Surface Water:
    Quality..........................  SMALL..................  SMALL..................  SMALL.
    Consumptive Use..................  SMALL..................  SMALL..................  SMALL.
Groundwater:
    Quality..........................  SMALL..................  SMALL..................  SMALL.
    Consumptive Use..................  SMALL..................  SMALL..................  SMALL.
Terrestrial Resources................  SMALL to MODERATE......  SMALL..................  SMALL.
Aquatic Ecology......................  SMALL..................  SMALL..................  SMALL.
                                      --------------------------------------------------------------------------
Special Status Species and Habitats..    Impacts for Federally threatened and endangered species and Essential
                                            Fish Habitat would be determined as part of consultations for the
                                          Endangered Species Act and Magnuson-Stevens Fishery Conservation and
                                                                     Management Act.
                                      --------------------------------------------------------------------------
Historic and Cultural Resources......  SMALL to LARGE.........  SMALL to LARGE.........  SMALL to LARGE.
Noise................................  SMALL..................  SMALL..................  SMALL.
Aesthetics...........................  SMALL to MODERATE......  SMALL to MODERATE......  SMALL to MODERATE.
Waste Management:
    LLW..............................  SMALL..................  SMALL..................  SMALL.
    Mixed Waste......................  SMALL..................  SMALL..................  SMALL.
    Nonradioactive Waste.............  SMALL..................  SMALL..................  SMALL to MODERATE.
Transportation:
    Traffic..........................  SMALL to MODERATE......  SMALL to MODERATE......  SMALL to MODERATE.
    Health...........................  SMALL..................  SMALL..................  SMALL.
Public and Occupational Health.......  SMALL..................  SMALL..................  SMALL.
Accidents............................  SMALL..................  SMALL..................  SMALL.
Sabotage or Terrorism................  SMALL..................  SMALL..................  SMALL.
----------------------------------------------------------------------------------------------------------------

B9. Does a potentially LARGE impact or a range of impacts affect the 
generic determination in the GEIS?
    No, the generic determinations found in the GEIS are not affected 
by a potentially LARGE impact or a range of impacts. The NRC has 
determined in the GEIS that the direct and indirect environmental 
impacts of continued storage can be analyzed generically. This means 
that, for each of the resource areas analyzed in the GEIS, the NRC has 
reached a generic determination (SMALL, MODERATE, LARGE, or a range) 
that is appropriate for all sites. These impact determinations are not 
expected to differ from those that would result from individual site-
specific reviews for the continued storage period. There are inherent 
uncertainties in determining impacts for the long-term and indefinite 
timeframes, regardless of whether the impacts are analyzed generically 
or site-specifically. Because the impacts of continued storage are not 
expected to vary significantly across sites, despite

[[Page 56249]]

variations in site-specific characteristics, a generic analysis is 
appropriate to determine the reasonably foreseeable environmental 
impacts that may result from continued storage.
B10. How does the rule address the impacts from continued storage of 
spent fuel?
    The NRC is revising 10 CFR 51.23(a) to reflect the environmental 
impact determinations of the GEIS (NUREG-2157). Final 10 CFR 51.23(a) 
provides that the Commission has generically determined that the 
environmental impacts of continued storage of spent nuclear fuel beyond 
the licensed life for operation of a reactor are those impacts 
identified in NUREG-2157. The NRC will use the impact determinations in 
NUREG-2157 to inform the decision-makers in licensing proceedings of 
the impacts of continued storage.
B11. What clarifying changes are addressed in the rule?
    Paragraph (b) of 10 CFR 51.23 is revised to clarify that ISFSI 
license renewals, reactor construction permits, and early site permits 
are included in the scope of the generic determination in 51.23(a). 
Additionally, paragraph (b) is revised for readability by restructuring 
the paragraph and separating the requirements that apply to an 
applicant from those that apply to the NRC. This paragraph is also 
revised to provide additional clarity regarding how the generic 
determination in 10 CFR 51.23(a) will be implemented in future NRC NEPA 
reviews. These amendments to 10 CFR 51.23(b) are intended to clarify 
how the NRC has interpreted and implemented 10 CFR 51.23 and how it 
will do so in future licensing activities. The approach taken for an EA 
differs slightly from the approach for EISs because under the terms of 
the revised 10 CFR 51.23 an EA must consider the impact determinations 
from the GEIS, while for an EIS the impact determinations are deemed 
incorporated into the EIS. Consistent with current practice, applicants 
will not be required to address continued storage in environmental 
reports submitted to support applications for issuance, renewal, or 
amendment of an operating license or construction permit for a nuclear 
power reactor under 10 CFR parts 50 and 54; issuance, renewal, or 
amendment of an early site permit or combined license for a nuclear 
power reactor under 10 CFR parts 52 and 54; or the issuance, renewal, 
or amendment of a license for storage of spent nuclear fuel at an ISFSI 
under 10 CFR part 72. The impact determinations are deemed incorporated 
into any EIS prepared to support issuance, renewal, or amendment of an 
operating license or construction permit for a nuclear power reactor 
under 10 CFR parts 50 and 54; issuance, renewal, or amendment of an 
early site permit or combined license for a nuclear power reactor under 
10 CFR parts 52 and 54; or the issuance, renewal, or amendment of a 
license for storage of spent nuclear fuel at an ISFSI under 10 CFR part 
72. The impact determinations will be considered in EAs, if the impact 
determinations of continued storage of spent fuel are relevant to the 
proposed action. The NRC is making conforming changes to 10 CFR 
51.30(b), 51.50(a). 51.50(b), 51.50(c), 51.53(b), 51.53(c), 51.53(d), 
51.61, 51.75(a), 51.75(b), 51.75(c), 51.80(b), 51.95(b), 51.95(c), 
51.95(d), and 51.97(a) to clarify that ISFSI license renewals, reactor 
construction permits, and early site permits are included in the scope 
of the generic determination; to reflect how the generic determination 
will be used in future NEPA reviews; and to improve readability of the 
rule language.
    With respect to early site permits, the NRC has consistently 
acknowledged its intent to apply 10 CFR 51.23 in its early site permit 
reviews, and this interpretation has been approved by a number of 
Atomic Safety and Licensing Boards. See, (e.g., Exelon Generation Co., 
LLC (Early Site Permit for Clinton ESP Site), LBP-04-17, 60 NRC 229, 
246-47 (2004); Dominion Nuclear North Anna, LLC (Early Site Permit for 
North Anna ESP Site), LBP-04-18, 60 NRC 253, 268-69 (2004)). The 
omission of early site permits from the text of 10 CFR 51.23(b) was 
highlighted by a public comment (see Section D.2.3.5 of the GEIS), and 
the NRC has decided that clarification of its continued storage rule to 
explicitly include early site permits is appropriate. The NRC has 
further determined that the same clarification is warranted with regard 
to the environmental review of a construction permit application. A 
construction permit is issued prior to issuance of a reactor operating 
license; the construction permit holder can subsequently receive an 
operating license for the constructed facility if applicable 
requirements are met. See 10 CFR 50.23 and 50.56. Thus, like an early 
site permit, a construction permit is a precursor to issuance of a 
reactor operating license and therefore falls within the scope of 
licensing activities specified in 10 CFR 51.23(b) for which 
clarification is warranted. The NRC is therefore amending 10 CFR 
51.23(b) to clarify that the rule applies to early site permits and 
construction permits. The NRC notes that this clarification responds to 
the public comments on early site permits and builds on the 
clarification in the proposed rule to add ISFSI license renewals to the 
listed actions in 10 CFR 51.23(b), thus making the rule's application 
to these licensing activities equally explicit. See 78 FR 56804-56805.
    Given the regulatory history of the waste confidence rules, the 
NRC's use of the generic determination in early site permit 
proceedings, and the NRC's extensive discussion of the purpose and 
objectives of the proposed rule in the statements of consideration, the 
public could have reasonably ascertained that the NRC would make 
clarifying changes in the final rule, including the addition of early 
site permits and construction permits, as a natural outgrowth of the 
proposed rule. These changes clarify the Commission's approach to 
ensure consistent evaluation of the environmental impacts of continued 
storage in all proceedings where spent fuel impacts arising from 
reactor operation may be considered, including the NEPA reviews for 
early site permits and construction permits, and thereby fully 
implement the NRC's objectives for this latest rule revision.
    These changes to add early site permits and construction permits do 
not affect and are independent of the NRC's conclusions regarding the 
analysis in NUREG-2157, in 10 CFR 51.23(a), or the application of 10 
CFR 51.23(b) to the licensing actions specified in the proposed rule. 
Accordingly, the Commission has determined that the balance of the rule 
for which prior notice was given can function sensibly and 
independently without these additional changes, and therefore intends 
that the balance of the rule be treated as severable to the extent 
possible. See MD/DC/DE Broadcasters Ass'n v. FCC, 236 F.3d 13, 22 (D.C. 
Cir. 2001).
    With respect to changes to improve the rule's readability, the 
revisions do not change the requirements for applicants and do not 
modify the substantive standards by which the NRC evaluates license 
applications. The changes made to address readability do not affect and 
are independent of the NRC's conclusions regarding the analysis in 
NUREG-2157 as applied in 10 CFR 51.23(a) or the application of 10 CFR 
51.23(b) to the licensing actions specified in the proposed rule.
    The 2010 version of 10 CFR 51.23(b) provided that no discussion of 
any environmental impact of spent fuel continued storage is required in 
any NRC EA or EIS prepared in connection

[[Page 56250]]

with the issuance or amendment of an operating license for a nuclear 
power reactor under 10 CFR parts 50 and 54; or issuance or amendment of 
a combined license for nuclear power reactor under 10 CFR parts 52 and 
54; or the issuance of an initial license or amendment for an ISFSI 
under 10 CFR part 72. In practice, the NRC does include a brief 
discussion of the generic determination of 10 CFR 51.23 in these EISs. 
See, (e.g., NUREG-1947, Final Supplemental Environmental Impact 
Statement for Combined License (COLs) for Vogtle Electric Generating 
Plant Unit 3 and 4 and NUREG-1714, Final Environmental Impact Statement 
for the Construction and Operation of an Independent Spent Fuel Storage 
Installation on the Reservation of the Skull Valley Band of Goshute 
Indians and the Related Transportation Facility in Tooele County, 
Utah). Under NEPA, the NRC must analyze the impacts of continued 
storage pending ultimate disposal for both power reactors and ISFSIs. 
Although the 2010 rule as worded did not require any discussion, the 
NRC has historically met this NEPA obligation in practice in the EISs 
for power reactors and ISFSIs by relying on the generic determination. 
Because the NRC will now be relying on the GEIS for the generic 
determination instead of a FONSI, the NRC needs to clarify how the 
generic determination will be used in future NEPA documents to ensure 
consistent use. Section 51.23(b) is revised to state that the impact 
determinations in NUREG-2157 are deemed to be incorporated into EISs 
and that the NRC will consider the impact determinations in EAs, if the 
impacts of continued storage of spent fuel are relevant to the proposed 
action. This means that the NRC will use the impact determinations in 
NUREG-2157 to evaluate the contribution of the environmental impacts of 
continued storage as part of the overall NEPA analysis. For agency 
actions that have already been taken, the NRC will not prepare new 
analyses or revise the existing analyses with respect to the 
environmental impacts of continued storage; rather, when preparing EAs 
and EISs for pending and future licensing actions, the NRC's review 
will simply consider the incorporated impact determinations along with 
the other environmental impacts associated with the proposed action. 
The revisions do not change the requirements for applicants and do not 
modify the substantive standards by which the NRC evaluates license 
applications. The changes made to clarify how the generic determination 
will be used in future NEPA reviews do not affect and are independent 
of the NRC's conclusions regarding the analysis in NUREG-2157 as 
applied in 10 CFR 51.23(a).
B12. What changes in this rulemaking address continued storage for 
license renewal?
    Table B-1, ``Summary of Findings on NEPA Issues for License Renewal 
of Nuclear Power Plants,'' addresses the environmental impacts of 
license renewal activities by resource area. Table B-1 is located in 
appendix B to subpart A of 10 CFR part 51, ``Environmental Effect of 
Renewing the Operating License of a Nuclear Power Plant.'' \5\ In 1996, 
the Commission determined that offsite radiological impacts of spent 
nuclear fuel and high-level waste disposal would be a Category 1 issue 
with no impact level assigned (61 FR 28467, 28495; June 5, 1996). The 
Commission analyzed the U.S. Environmental Protection Agency (EPA) 
generic repository standards and dose limits in existence at the time 
and concluded that offsite radiological impacts warranted a Category 1 
determination (61 FR 28467, 28478; June 5, 1996). In its 2009 proposed 
rule preceding the 2013 final rule, the Commission stated its intention 
to reaffirm that determination. (74 FR 38117, 38127; July 31, 2009). 
However, when the Commission issued the 2013 final rule, which amended 
Table B-1--along with other 10 CFR part 51 regulations--it stated that 
upon finalization of the Waste Confidence rule and accompanying 
technical analyses, the NRC would make any necessary conforming 
amendments to Table B-1 (78 FR 37282, 37293; June 20, 2013).
---------------------------------------------------------------------------

    \5\ The Commission issued Table B-1 in June, 1996 (61 FR 28467; 
June 5, 1996). The Commission issued an additional rule in December, 
1996 that made minor clarifying changes to, and added language 
inadvertently omitted from, Table B-1 (61 FR 66537; December 18, 
1996). The NRC revised Table B-1 and other regulations in 10 CFR 
part 51, relating to the NRC's environmental review of a nuclear 
power plant's license renewal application in a 2013 rulemaking (78 
FR 37282; June 20, 2013).
---------------------------------------------------------------------------

    In this current rulemaking, the NRC is revising determinations 
related to two environmental issues in Table B-1: Onsite storage of 
spent fuel during the term of an extended license (resulting from the 
renewal of the plant's operating license) and the offsite radiological 
impacts of spent nuclear fuel and high-level waste disposal. Although 
the GEIS for this rulemaking does not include high-level waste disposal 
in the analysis of impacts, it does address the technical feasibility 
of a repository in Appendix B of the GEIS and concludes that a geologic 
repository for spent fuel is technically feasible and the same analysis 
applies to the feasibility of geologic disposal for high-level waste.
    The Table B-1 finding for ``Onsite storage of spent nuclear fuel'' 
is revised to add the phrase ``during the license renewal term'' in two 
places in the first paragraph to make clear that the SMALL impact is 
for the license renewal term only. Some minor clarifying changes are 
also made to the paragraph. The first paragraph of the column entry now 
reads, ``During the license renewal term, SMALL. The expected increase 
in the volume of spent nuclear fuel from an additional 20 years of 
operation can be safely accommodated onsite during the license renewal 
term with small environmental impacts through dry or pool storage at 
all plants.'' In addition, a new paragraph is added to address the 
impacts of onsite storage of spent fuel during the continued storage 
period. The second paragraph of the column entry reads, ``For the 
period after the licensed life for reactor operations, the impacts of 
onsite storage of spent nuclear fuel during the continued storage 
period are discussed in NUREG-2157 and as stated in 10 CFR 51.23(b), 
shall be deemed incorporated into this issue.'' The changes reflect 
that this issue covers the environmental impacts associated with the 
storage of spent nuclear fuel during the license renewal term as well 
as the period after the licensed life for reactors operations.
    The Table B-1 entry for ``Offsite radiological impacts of spent 
nuclear fuel and high-level waste disposal'' is revised by 
reclassifying the impact determination as a Category 1 \6\ issue with 
no impact level assigned. The finding column entry for this issue 
includes reference to the existing radiation protection standards.
---------------------------------------------------------------------------

    \6\ For purposes of Table B-1, a designation as Category 1 means 
that the generic analysis of the issue may be adopted in each site-
specific review. Category 2 means that additional plant-specific 
review is required.
---------------------------------------------------------------------------

    Although the status of a repository, including a repository at 
Yucca Mountain, is uncertain and outside the scope of the generic 
environmental analysis conducted to support this rulemaking, the NRC 
believes that it is appropriate to refer to the radiation standard for 
Yucca Mountain because it is the current standard. The changes to these 
two issues finalize the Table B-1 entries that the NRC had intended to 
promulgate in its 2013 rulemaking, but was unable to because the 2010 
Waste Confidence rule had been vacated.
    While the bases for the specific conclusions in Table B-1 are found 
elsewhere (e.g., the 1996 rule that issued

[[Page 56251]]

Table B-1 and the 1996 license renewal GEIS, which provided the 
technical basis for that rulemaking, as reaffirmed by the 2013 
rulemaking and final GEIS), the Commission has concluded in this GEIS 
that deep geologic disposal remains technically feasible. This 
rulemaking accordingly revises the entries for these two issues in 
Table B-1. The NRC provided notice of this revision in the Federal 
Register for the proposed rule (78 FR 56776; September 13, 2013) and 
received two comments on the table. See Sections D.2.3.6 and D.2.3.9 of 
Appendix D of the GEIS.

C. Repository and Continued Storage Conclusions

C1. What is the basis of the NRC's conclusion that a geologic 
repository is feasible?
    The technical feasibility of a repository is addressed in Section 
B.2.1 of the GEIS. Technical feasibility simply means whether a 
geologic repository is technically possible using existing technology 
(i.e., without any fundamental breakthroughs in science and 
technology). As discussed in Section B.2.1, the consensus within the 
scientific and technical community engaged in nuclear waste management 
is that safe geologic disposal is achievable with currently available 
technology. Currently, 25 countries, including the United States, are 
considering disposal of spent or reprocessed nuclear fuel in deep 
geologic repositories.
    As noted in Section B.2.1 of the GEIS, ongoing research in both the 
United States and other countries supports a conclusion that geological 
disposal remains technically feasible and that acceptable sites can be 
identified. After decades of research into various geological media, no 
insurmountable technical or scientific problem has emerged to challenge 
the conclusion that safe disposal of spent fuel and high-level 
radioactive waste can be achieved in a mined geologic repository. Over 
the past two decades, significant progress has been made in the 
scientific understanding and technological development needed for 
geologic disposal.
    As discussed in Section B.2.1, activities of European countries, 
experience in reviewing the DOE's Yucca Mountain license application, 
and DOE defense-related activities at the Waste Isolation Pilot Plant 
all support the technical feasibility of a deep geologic repository. 
Based on national and international research, proposals, and experience 
with geological disposal, the NRC concludes that a geologic repository 
continues to be technically feasible.
C2. What is the basis for the NRC's conclusion that a repository will 
be available?
    The availability of a repository is addressed in Section B.2.2 of 
the GEIS. Progress in development of repositories internationally 
provides useful experience in building confidence that the most likely 
scenario is that a repository can and will be developed in the United 
States in the short-term timeframe. Based on the examination of a 
number of international programs and DOE's current plans, the NRC 
continues to believe that 25 to 35 years is a reasonable period for 
repository development (i.e., candidate site selection and 
characterization, final site selection, licensing review, and initial 
construction for acceptance of waste). A discussion of international 
repository programs and DOE's current plans can be found in Section 
B.2.2 of the GEIS.
    As discussed in Section B.2.2 of the GEIS, the time DOE will need 
to develop a repository site will depend upon a variety of factors, 
including Congressional action and funding. Public acceptance will also 
influence the time it will take to implement geologic disposal. As 
stated in its ``Strategy for the Management and Disposal of Used 
Nuclear Fuel and High-Level Radioactive Waste'' (ADAMS Accession No. 
ML13011A138), DOE's current plans predict that a repository will be 
available by 2048. Although the NRC believes that 25-35 years is a 
reasonable timeframe for repository development, the NRC acknowledges 
that there is sufficient uncertainty in this estimate that the 
possibility that more time will be needed cannot be ruled out. 
International and domestic experience clearly demonstrate that 
technical knowledge and experience alone are not sufficient to bring 
about the broad social and political acceptance needed to construct a 
repository. The time needed to develop a societal and political 
consensus for a repository could add to the time to site and license a 
repository or overlap it to some degree. Given this uncertainty, the 
GEIS evaluates a range of scenarios for the timeframe of the 
development of a repository, including indefinite storage. As discussed 
in Section B.2.2, the NRC believes that the United States will open a 
repository within the short-term time frame of 60 years, but, to 
account for all possibilities, has included a second, longer time frame 
as well as the scenario in which a repository never becomes available. 
This analysis does not constitute an endorsement of extended onsite 
storage of spent fuel as the appropriate long-term solution for 
disposition of spent fuel and high-level waste.
C3. Does the rule address the feasibility and timing of a repository?
    No. As discussed in Issue 1 (see Section IV, ``Summary and Analysis 
of Public Comments on the Proposed Rule''), the NRC specifically sought 
public comment on this issue and decided not to address the feasibility 
and timing of a repository in the rule text itself, instead analyzing 
various time scenarios for repository availability in the GEIS, 
including the possibility that a repository will not be available. A 
discussion of the feasibility and timing of a repository can be found 
in Appendix B of the GEIS.
C4. What is the basis for the NRC's conclusion regarding safe storage 
of spent fuel in spent fuel pools?
    Section B.3.1 of the GEIS discusses the feasibility of safe storage 
of spent fuel in spent fuel pools and addresses a number of technical 
considerations. First, the integrity of spent fuel and cladding within 
the environment of a spent fuel pool's controlled water chemistry is 
supported by operational experience and a number of scientific studies. 
Based on available information and operational experience as discussed 
in Section B.3.1.1, degradation of the fuel cladding occurs very slowly 
over time in the spent fuel pool environment. Degradation of the spent 
fuel should be minimal over the short-term storage timeframe. In the 
GEIS, the NRC assumes that the spent fuel pool will be decommissioned 
before the end of the short-term storage timeframe; however, the NRC is 
not aware of any information that would call into question the 
technical feasibility of continued safe storage of spent fuel in spent 
fuel pools beyond the short-term storage timeframe.
    Second, the spent fuel pool's robust structural design protects 
against a range of natural and human-induced challenges, which are 
discussed in detail in Section B.3.1.2 and in the body of the GEIS. 
Spent fuel pools are massive seismically-designed structures that are 
constructed from thick, reinforced concrete walls and slabs. Section 
B.3.1.2 discusses a number of studies and evaluations on storage of 
spent fuel in a spent fuel pool and the associated accident risk. In 
Section B.3.1.2, the NRC concludes that the likelihood of major 
accidents at spent fuel pools resulting in offsite consequences is very 
remote. In

[[Page 56252]]

particular, Appendix F supports the NRC's determination that the 
environmental impacts from spent fuel pool fires are SMALL during the 
short-term storage timeframe based on the low risk of a spent fuel pool 
fire. As noted in Section B.3.1.2, the NRC is not aware of any study 
that would cause it to question the low risk of spent fuel pool 
accidents and thereby question the technical feasibility of continued 
safe storage of spent fuel in spent fuel pools for the short-term 
timeframe considered in the GEIS. Further, as described in Appendix E, 
the NRC has determined that the public health impact from potential 
spent fuel pool leaks is SMALL.
C5. What is the basis for the NRC's conclusion regarding safe storage 
of spent fuel in dry casks?
    As explained in Section B.3.2 of the GEIS, the feasibility of dry 
cask storage is supported by years of experience and technical studies 
and NRC reviews that examined and confirmed the integrity of spent fuel 
and cladding under the controlled environment within dry cask storage 
systems. The technical feasibility of these systems is further 
supported by the robustness of the structural design of the dry cask 
storage system against a variety of challenges, both natural and human-
induced. Based on available information and operational experience as 
discussed in Section B.3.2.1, degradation of the spent fuel should be 
minimal over the short-term storage timeframe if conditions inside the 
canister are appropriately maintained (e.g., consistent with the 
technical specifications for storage). Thus, it is expected that only 
routine maintenance will be needed over the short-term storage 
timeframe. In the GEIS, the NRC conservatively assumes that the dry 
casks would need to be replaced if storage continues beyond the short-
term storage timeframe. The NRC assumes replacement of dry casks after 
100 years of service life, even though studies and experience to date 
do not preclude a longer service life. Accidents associated with 
repackaging spent fuel are evaluated in Section 4.18, and the NRC 
determined that the environmental impacts are SMALL because the 
accident consequences would not exceed the NRC accident dose standard 
contained in 10 CFR 72.106. Dry cask storage systems are passive 
systems that are inherently robust, massive, and highly resistant to 
damage. To date, the NRC and licensee experience with ISFSIs and cask 
certification indicates that spent fuel can be safely and effectively 
stored using passive dry cask storage technology. As explained in 
Section B.3.2.2, technical studies and practical operating experience 
to date confirm the physical integrity of dry cask storage structures 
and thereby demonstrate the technical feasibility of continued safe 
storage in dry cask storage systems for the time periods considered in 
the GEIS.
    As noted in Sections B.3.2.1 and B.3.2.2, the NRC is not aware of 
any issue that would cause it to question the technical feasibility of 
continued safe storage of spent fuel in dry casks for the timeframes 
considered in the GEIS. However, as part of continued oversight, the 
NRC continues to evaluate aging management programs and to monitor dry 
cask storage so that it can update its service life assumptions as 
necessary and consider any circumstances that might require repackaging 
spent fuel earlier than anticipated.
C6. How does the regulatory framework factor into the continued safe 
storage of spent fuel?
    A strong regulatory framework that involves regulatory oversight, 
continuous improvement based on research and operating experience, and 
licensee compliance with regulatory requirements is important to the 
continued safe storage of spent fuel until repository capacity is 
available. As part of its oversight, the NRC can issue orders and new 
or amended regulations to address emerging issues that could impact the 
safe storage of spent fuel, as well as issue generic communications 
such as generic letters and information notices. The regulatory 
framework is discussed in Section B.3.3 of the GEIS. The NRC's upgrades 
of safety, environmental, and security requirements following historic 
events such as the September 11, 2001, terrorist attacks, and the March 
11, 2011, earthquake and subsequent tsunami that struck the Fukushima 
Dai-ichi nuclear power plant demonstrate the NRC's capability for 
prompt and vigorous response to new developments that warrant increased 
regulatory attention. Thus, the vitality and evolution of the NRC's 
regulatory requirements support a reasonable conclusion that continued 
storage, even over extended periods of time beyond those regarded as 
most likely, will continue to be safe with the same or less 
environmental impact. Section B.3.3.1 discusses the NRC's oversight 
related to routine operations, accidents, and terrorist activity in 
more detail. Section B.3.3.2 and Appendix E discuss the NRC's response 
to spent fuel pool leaks and Section B.3.3.3 discusses the regulatory 
framework related to dry cask storage.
    The NRC continues to improve its understanding of long term dry 
storage issues and is separately examining the regulatory framework and 
potential technical issues related to extended storage and subsequent 
transportation of spent fuel for multiple ISFSI license renewal periods 
extending beyond 120 years. As part of this effort, the NRC is also 
closely following DOE and industry efforts to study the effects of 
storing high burn-up spent fuel in casks. As information becomes 
available, the NRC will analyze the information to determine if 
additional or different actions are necessary. If necessary, the NRC 
will issue orders or enhance its regulatory requirements for storage of 
spent fuel, as appropriate, to continue providing adequate protection 
of public health and safety and the common defense and security.
    As discussed in Section B.3.3.4, the NRC will continue its 
regulatory control and oversight of spent fuel storage through both 
specific and general 10 CFR part 72 licenses. Decades of operating 
experience and ongoing NRC inspections demonstrate that the reactor and 
ISFSI licensees continue to meet their obligation to safely store spent 
fuel in accordance with the requirements of 10 CFR parts 50, 52, and 
72. If the NRC were to find noncompliance with these requirements or 
otherwise identify a concern with the safe storage of the spent fuel, 
the NRC would evaluate the issue and take whatever action or change in 
its regulatory program is necessary to protect the public health and 
safety and the environment.
    Section B.3.4 concludes that the NRC believes that for the storage 
timeframes considered in the GEIS, regulatory oversight will continue 
in a manner consistent with the NRC's regulatory actions and oversight 
in place today to provide for continued storage of spent fuel in a safe 
manner until sufficient repository capacity is available for the safe 
disposal of all spent fuel.
C7. Does the rule address the safety of continued storage of spent 
fuel?
    No. As discussed in Issue 2 (see Section IV, ``Summary and Analysis 
of Public Comments on the Proposed Rule''), the NRC specifically sought 
public comment on this issue and decided not to address the continued 
safe storage of spent fuel in the rule text itself. Appendix B of the 
GEIS discusses the feasibility of safe storage of spent fuel. 
Additionally, feasibility of continued safe storage and the regulatory 
framework are addressed in Questions C4, C5, and C6.
    In summary, storage of spent fuel will be necessary until a 
repository is

[[Page 56253]]

available for permanent disposal. The storage of spent fuel in any 
combination of spent fuel pools or dry casks will continue as a 
licensed activity under regulatory controls and oversight. Licensees 
continue to develop and successfully use onsite spent fuel storage 
capacity in the form of spent fuel pools and dry casks in a safe and 
environmentally sound fashion. Technical understanding and experience 
continues to support the technical feasibility of safe storage of spent 
fuel in spent fuel pools and in dry casks, based on their physical 
integrity over long periods of time. However, the safety determinations 
associated with licensing of these activities are contained in the 
appropriate regulatory provision addressing licensing requirements and 
in the specific licenses for facilities. While those safety 
determinations are not the subject of this rulemaking they serve to 
inform the analysis of likely environmental impacts. The NRC concludes 
that spent fuel can continue to be safely managed in spent fuel pools 
and dry casks and that regulatory oversight exists to ensure the aging 
management programs continue to be updated to address the monitoring 
and maintenance of structures, systems, and components that are 
important to safety. Based on all of the information set forth in 
Appendix B of the GEIS, the NRC concludes that spent fuel can be safely 
managed in spent fuel pools in the short-term timeframe and dry casks 
during the short-term, long-term, and indefinite timeframes evaluated 
in the GEIS.

III. Rulemaking Procedure

    Under the Administrative Procedure Act (5 U.S.C. 553(b)(A)), an 
agency may waive the normal notice and comment requirements if the rule 
is an interpretive rule, a general statement of policy, or a rule of 
agency organization, procedure, or practice.
    As authorized by 5 U.S.C. 553(b)(A), the NRC has waived the notice 
and comment requirements for the additional clarifying amendments to 10 
CFR 51.23(b) and conforming amendments to 10 CFR 51.50(a), 51.50(b), 
51.75(a), and 51.75(b) that were not included in the proposed rule. The 
additional amendments expand the list of licensing proceedings for 
which site-specific consideration of the environmental impacts of 
continued storage is not needed, to include construction permits and 
early site permits. Paragraph 51.23(b) of 10 CFR is a rule of agency 
procedure and practice that governs how the NRC implements NEPA. This 
paragraph describes how the NRC will implement the NRC's generic 
determination in 10 CFR 51.23(a) in site-specific NEPA reviews in 
licensing proceedings (i.e., by precluding a duplicative review in an 
individual licensing proceeding). The changes to 10 CFR 51.23(b) do not 
modify the substantive standards by which the NRC will evaluate license 
applications and do not alter the generic determination in 10 CFR 
51.23(a). Rather, the additional changes to 10 CFR 51.23(b) clarify 
that the generic finding in 10 CFR 51.23(a) also precludes a 
duplicative NRC review of the environmental effects of continued 
storage in early site permit and construction permit application 
reviews, no different than the other NRC licensing proceedings already 
listed in that paragraph. NEPA is a procedural statute directed at 
Federal agencies, and 10 CFR 51.23 (including the additional clarifying 
amendments) addresses the manner by which the NRC complies with NEPA 
with respect to the subject of continued storage. These amendments do 
not require action by any person or entity regulated by the NRC, nor do 
these amendments modify the substantive responsibilities of any person 
or entity regulated by the NRC. That the additional amendments do not 
impose any substantive responsibilities or require or prohibit action 
by any persons or entities regulated by the NRC is indicative of the 
character of the amendments as matters of NRC procedure and practice.
    As authorized by 5 U.S.C. 553(b)(A), the NRC has also waived the 
notice and comment requirements for the additional amendments to 10 CFR 
51.23(b), 51.30(b), 51.50(c), 51.53(b), 51.53(c), 51.53(d), 51.61, 
51.75(c), 51.80(b), 51.95(b), 51.95(c), 51.95(d), and 51.97(a) that 
were not included in the proposed rule. These additional amendments are 
made to improve readability and to clarify how the generic 
determination will be used in future NEPA documents for power reactors 
and ISFSIs. The changes do not modify the substantive standards by 
which the NRC will evaluate license applications and do not alter the 
generic determination in 10 CFR 51.23(a). Rather, the additional 
changes improve the readability of the regulations to make it easier to 
understand and provide consistency in how the generic finding in 10 CFR 
51.23(a) will be used in NRC NEPA documents. NEPA is a procedural 
statute directed at Federal agencies, and 10 CFR 51.23 (including the 
additional clarifying amendments) addresses the manner by which NRC 
complies with NEPA with respect to the subject of continued storage. 
These amendments do not require action by any person or entity 
regulated by the NRC, nor do these amendments change the substantive 
responsibilities of any person or entity regulated by the NRC. That the 
additional amendments do not impose any substantive responsibilities or 
require or prohibit action by any persons or entities regulated by the 
NRC is indicative of the character of the amendments as matters of NRC 
procedure and practice.

IV. Summary and Analysis of Public Comments on the Proposed Rule

    The proposed rule was published on September 13, 2013 (78 FR 
56776), for a 75-day public comment period that would have ended on 
November 27, 2013. The draft GEIS was also noticed for public comment 
on the same day. Due to the lapse in appropriations and the subsequent 
shutdown of the NRC, the NRC published a Federal Register notice on 
November 7, 2013 (78 FR 66858), that extended the public comment period 
until December 20, 2013. The NRC also held 13 public meetings during 
the comment period to obtain public comment on the proposed rule and 
draft GEIS. The NRC received 33,099 comment submissions from 
organizations and individuals. Of those comments, 924 represented 
unique comment submissions and the remainder were considered form 
comments sponsored by various organizations. In addition, a number of 
individuals provided oral comments at the public meetings that resulted 
in more than 1,600 pages of transcribed comments. The commenters on the 
proposed rule and draft GEIS included Tribal governments, State 
governments, industry groups, advocacy groups, licensees, and 
individuals. The EPA also provided comments under its authority to 
review EISs.
    In general, there was a range of views from commenters concerning 
the rulemaking and draft GEIS, both in support and in opposition. Many 
individuals provided comments that expressed opposition to or support 
for nuclear power and licensing of nuclear facilities in general and 
comments related to actions at specific nuclear power plants. 
Commenters expressed concerns related to the NEPA process, continued 
safe storage of spent fuel, repository availability, reliance on 
institutional controls, costs, climate change, pool fires, pool leaks, 
and accidents among other things. In this section the NRC summarizes 
the four issues on which the NRC specifically requested input: (1) 
Whether specific policy statements regarding the timeline for 
repository availability should be

[[Page 56254]]

removed from the rule text; (2) whether specific policy statements 
regarding the safety of continued spent fuel storage should be made in 
the rule text given the expansive and detailed information in the draft 
GEIS; (3) whether the Discussion portion of the Statements of 
Consideration should be streamlined by removing content that is 
repeated from the draft GEIS in order to improve clarity of the 
discussion; and (4) whether the title of the rule should be changed in 
light of a GEIS being issued instead of a sep(arate Waste Confidence 
Decision. Responses to the comments received on the proposed rule and 
draft GEIS are provided in Appendix D of the GEIS, Generic 
Environmental Impact Statement for Continued Storage of Spent Nuclear 
Fuel, Volume 2 (ADAMS Accession No. ML14196A107). Separately, the NRC 
published a document containing the text of all identified unique 
comments, ``Comments on the Waste Confidence Draft Generic 
Environmental Impact Statement and Proposed Rule,'' which is located in 
ADAMS under Accession No. ML14154A175. This separate document provides 
individual comments organized by comment category, and comment author 
tables.

Issue 1

    In the proposed rule, the NRC invited comment on whether the 
timeline for repository availability should be included in the rule 
text. Commenters were requested to comment on whether specific policy 
statements regarding the timeline for repository availability should be 
removed from the proposed rule text. A total of 13 commenters 
responded.
    Commenters who responded to Issue 1 generally expressed support for 
removing a statement regarding the repository availability timeline 
from the rule text. Reasons for this support varied, but commonly 
included a lack of NRC control over repository timelines; previous 
failures to predict when a repository would become available; the 
inadequacy of a basis for any particular timeline; that a timeline is 
not required under NEPA; and the concern that including a statement 
about repository availability ties the United States to repository 
disposal of spent fuel to the exclusion of reprocessing or other 
options.
    The few commenters who expressed support for retaining a statement 
regarding the timeline for repository availability indicated that the 
timeline is an important element of the ``contract'' the public has 
with the nuclear industry; that the availability of a repository is the 
most critical issue affecting long-term dry cask storage; that 
inclusion of a statement regarding repository availability in the rule 
text indicates the importance the Commission places on this key 
assumption of the GEIS; and that these findings are useful in framing 
the NRC's assessment of the safety and environmental impacts of 
continued storage.
    After considering the comments, the NRC has decided not to retain 
the timeline in the rule text. With the development of the GEIS, the 
relationship between repository availability and the consideration of 
environmental impacts from continued storage has changed from previous 
proceedings. In previous proceedings, the date of future repository 
availability was the end point of the temporal scope of the NRC's 
analysis of the environmental impacts from continued storage. In this 
rulemaking, there is no end point to the temporal scope of the NRC's 
analysis of the environmental impacts of continued storage. Further, 
the NRC agrees that there is no legal requirement to include a timeline 
in the rule text. Although future repository availability remains an 
important consideration because it provides an eventual disposition 
path for spent fuel, there no longer is a need to provide a time limit 
for the environmental impacts analysis. To support the analysis in the 
GEIS, the NRC has determined that a repository is technically feasible 
and that it is technically feasible to safely store the spent fuel. The 
removal of a timeframe from the rule language does not mean that the 
Commission is endorsing indefinite storage of spent fuel. The United 
States national policy remains disposal of spent fuel in a geologic 
repository, and, as stated in the GEIS, the NRC believes that the most 
likely scenario is that a repository will become available by the end 
of the short-term timeframe (60 years beyond the licensed life for 
operation of a reactor).
    Further, the GEIS recognizes the uncertainty inherent in predicting 
when a repository will become available. It therefore contains an 
analysis of two additional timeframes: A long-term timeframe that 
contemplates an additional 100 years of storage and an indefinite 
timeframe that looks at the environmental impacts that could occur if a 
repository never becomes available. Appendix B of the GEIS and Section 
II.C of this notice contain a discussion of repository feasibility.

Issue 2

    In the proposed rule, the NRC invited comment on the issue of 
including statements regarding the safety of continued spent fuel 
storage in the rule text. Commenters were requested to comment on 
whether specific policy statements regarding the safety of continued 
spent fuel storage should be made in the rule text given the expansive 
and detailed information in the GEIS. A total of 13 commenters provided 
responses to the specific question on this subject.
    Commenters who responded to Issue 2 generally expressed support for 
making a policy statement regarding safety of continued storage in the 
rule text. However, their reasons varied widely. Some commenters 
indicated that including a statement about safety enhanced openness and 
transparency or supported the language because storage is, in fact, 
safe. Other commenters indicated that it should be included because 
safety determinations are more important to NRC decisions and to 
members of the public than environmental issues in spent fuel matters; 
because the public should have the benefit of the NRC's determination 
that spent fuel may be stored for extended periods with reasonable 
assurance of safety; because a safety statement would facilitate 
opposition to nuclear power; because it is consistent with the long-
standing approach to addressing continued storage; and because it 
addresses legal precedents.
    Commenters who opposed a policy statement regarding safety of 
continued storage in the rule text asserted that a statement is 
unnecessary to the rule; that it is not possible to project the future 
safety of spent fuel storage; that statements related to safety of 
spent fuel storage are entirely unrelated and unnecessary to the 
intended purpose of the rule; and that there are too many unknowns and 
open issues related to storage that must be resolved before any 
statement regarding safety can be made.
    After considering the comments, the NRC has decided not to make a 
policy statement about safe storage in the rule text. The generic 
conclusion that spent fuel can be stored safely beyond the operating 
life of a power reactor has been a component of all past Waste 
Confidence proceedings. However, this continued storage rulemaking 
proceeding is markedly different from past proceedings. Unlike earlier 
proceedings, the NRC has prepared a GEIS that analyzes the impacts of 
continued storage of spent fuel. The GEIS fulfills the NRC's NEPA 
obligations and provides a regulatory basis for the rule rather than 
addressing the agency's responsibilities to protect public health and 
safety under the Atomic Energy Act (AEA), of 1954 as

[[Page 56255]]

amended. Further, Appendix B of the GEIS discusses the technical 
feasibility of continued safe storage. It is important to note that, in 
adopting revised 10 CFR 51.23 and publishing the GEIS, the NRC is not 
making a safety determination under the AEA to allow for the continued 
storage of spent fuel. AEA safety determinations associated with 
licensing of these activities are contained in the appropriate 
regulatory provision addressing licensing requirements and in the 
specific licenses for facilities. Further, there is not any legal 
requirement for the NRC to codify a generic safety conclusion in the 
rule text. By not including a safety policy statement in the rule text, 
the NRC does not imply that spent fuel cannot be stored safely. To the 
contrary, the analysis documented in the GEIS is predicated on the 
ability to store spent fuel safely over the short-term, long-term, and 
indefinite timeframes. This understanding is based upon the technical 
feasibility analysis in Appendix B of the GEIS and the NRC's decades-
long experience with spent fuel storage and development of regulatory 
requirements for licensing of storage facilities that are focused on 
safe operation of such facilities, which have provided substantial 
technical knowledge about storage of spent fuel. Further, spent fuel is 
currently being stored safely at reactor and storage sites across the 
country, which supports the NRC's conclusion that it is feasible for 
spent fuel to be stored safely for the timeframes considered in the 
GEIS. Appendix B of the GEIS and Section II.C of this notice contain a 
discussion of the technical feasibility and regulatory framework that 
supports continued safe storage.

Issue 3

    In the proposed rule, the NRC invited comment on the issue of 
streamlining the Statements of Consideration. Commenters were 
specifically requested to comment on whether the Discussion portion of 
the Statements of Consideration should be streamlined by removing 
content that is repeated from the draft GEIS to improve clarity of the 
discussion. A total of 13 commenters provided responses to the specific 
question on this subject.
    Commenters who responded to Issue 3 provided both support and 
opposition for streamlining. Commenters who supported streamlining did 
so most frequently because it would improve clarity or because it would 
reduce redundancy. Other reasons included that lengthy Federal Register 
notices are burdensome to search and that streamlining could remove 
anachronisms.
    Commenters who opposed streamlining most commonly did so because 
the information in the Discussion section supports the rule or provides 
a plain-language explanation of matters in the rule. Other commenters 
opposed streamlining because it would introduce changes upon which the 
public has not been able to comment; because the Statements of 
Consideration should address findings that the NRC historically 
included as part of the Waste Confidence Decision; and because the 
Federal Register is more readily available to the public and is easier 
to search than the GEIS. Commenters indicated that the Statements of 
Consideration should contain enough information that it can be used as 
a stand-alone document.
    After considering the comments and looking at ways to be more 
concise in presenting the information, the NRC has streamlined the 
Statements of Consideration where it is appropriate to do so without 
removing text necessary to explain the action that the NRC is taking. 
As noted in the comments, the Federal Register notice for the rule must 
contain enough information to explain the matters in the rule; however, 
it does not need to be a stand-alone document. The GEIS provides a 
regulatory basis for the rule and not everything in the GEIS needs to 
be addressed in the Statements of Consideration. Some redundancy with 
the GEIS remains to ensure adequate information is present to explain 
the nature and intent of the rule. After streamlining, the Statements 
of Consideration still contains sufficient information in plain 
language to provide the reader with an understanding of the nature and 
intent of the rule.

Issue 4

    In the proposed rule, the NRC invited comment on changing the rule 
title. Commenters were requested to comment on whether the title of the 
rule should be changed in light of a GEIS being issued instead of a 
separate Waste Confidence Decision. A total of 13 commenters provided 
responses to the specific question on this subject.
    Commenters who responded to Issue 4 expressed near-unanimous 
support for changing the title of the rule. Reasons for support, 
however, varied widely. Commenters indicated an array of reasons to 
support changing the rule name, including that the name is an 
anachronism; that the title is misleading and provides no useful 
description of the revised rule's purpose or intent; that the title 
shows a lack of transparency; that historical findings of confidence 
have proven erroneous; that confidence does not exist; that the U.S. 
Court of Appeals for the District of Columbia Circuit invalidated 
confidence as a basis for the rule; that the title should be changed to 
reflect the evolving rulemaking process (no separate Waste Confidence 
Decision and reliance on the GEIS); and that confidence requires 
transfer of all fuel to dry casks and a defined and available end 
point. Many other commenters--who did not expressly respond to this 
issue--expressed views that ``waste confidence'' is a confusing term or 
that it conveys a confidence that does not exist. Commenters noted that 
with a clearer title, the purpose and limited application of the rule 
would be more evident to members of the public who are not aware of the 
historical basis for the term ``waste confidence.'' Commenters 
suggested that the title should more accurately reflect the true 
Federal action of licensing and relicensing of reactors and ISFSIs and 
should accurately reflect the purpose of the analysis, evaluation, and 
conclusions of the study. Suggestions for a new title included 
``Storage of SNF [Spent Nuclear Fuel] after Licensed Term of 
Operations'' and ``Storage of Spent Nuclear Fuel for the Period After 
License Term of Reactor Operation.''
    Only one commenter who responded to this issue expressed opposition 
to revising the title. The commenter was opposed to changing the title 
because waste confidence is what the rulemaking has historically been 
about and the rule should still be about confidence that a repository 
will be available.
    After considering the comments, the NRC has decided to change the 
title of the rule. The title of a rule should convey the nature and 
content of the rule. This rule represents a change in the format from 
past Waste Confidence proceedings. Because of the decades of experience 
with safely storing spent fuel and the fact that the Commission has 
issued a GEIS to support the rule, which provides a detailed analysis 
of the environmental impacts associated with continued storage, the 
nature of the rule has changed and the need for a separate Waste 
Confidence Decision no longer exists. The rule codifies the 
environmental impact of continued storage of spent fuel beyond the 
licensed life for operation of a reactor at 10 CFR 51.23(a). The rule 
is used in reactor and ISFSI licensing and relicensing proceedings to 
address the environmental impacts of storage of spent fuel for the 
period after the licensed life for operation of the reactor and before 
disposal. Including ``waste

[[Page 56256]]

confidence'' in the title of the proposed rule was intended to bridge 
past rulemakings on the topic to the current effort, recognizing that 
there is no separate Waste Confidence Decision included in the current 
proceeding. However, it is clear from the comments that using the 
historical term ``waste confidence'' in the title has caused some 
confusion. The NRC agrees that a title that more accurately reflects 
the content is more appropriate. Therefore, the NRC has changed the 
title of this notice to ``Continued Storage of Spent Nuclear Fuel.'' 
The title of the GEIS was also changed accordingly.

V. Discussion of Final Amendments by Section

Sec.  51.23 Environmental Impacts of Continued Storage of Spent Nuclear 
Fuel Beyond the Licensed Life for Operation of a Reactor

    The heading of the section is revised to reflect that the section 
is no longer based on an EA and FONSI, but on an EIS and that 
environmental effects of continued storage are included in the section.
    Paragraph (a) of 10 CFR 51.23 is revised to provide the 
Commission's generic determination of the environmental impacts on the 
continued storage of spent fuel. The amendments state that the 
Commission has generically determined that the environmental impacts of 
continued storage of spent nuclear fuel beyond the licensed life for 
operation of a reactor are those impacts identified in NUREG-2157.
    Paragraph (b) of 10 CFR 51.23 is revised to clarify that ISFSI 
renewals, reactor construction permits, and early site permits are 
included in the scope of the generic determination. The final rule also 
makes changes to improve readability and by providing additional 
clarity regarding the application of the generic determination in 10 
CFR 51.23(a) in future NRC NEPA reviews. Provisions applicable to 
applicants and the NRC are separated to make it clear that applicants 
do not need to address continued storage and that for the NRC's NEPA 
documents the impact determinations in NUREG-2157 are deemed 
incorporated into EISs and will be considered in EAs, if the impacts of 
continued storage of spent fuel are relevant to the proposed action.

Sec.  51.30 Environmental Assessment

    Paragraph (b) is revised to clarify that EAs will consider the 
generic impact determinations in NUREG-2157, if the impacts of 
continued storage of spent fuel are relevant to the proposed action.

Sec.  51.50 Environmental Report--Construction Permit, Early Site 
Permit, or Combined License Stage

    Section 51.50 is revised to clarify that construction permits, 
early site permits, and combined licenses are included in the scope of 
the generic determination in Sec.  51.23 and that the applicants' 
environmental reports do not need to discuss the impacts of continued 
storage.

Sec.  51.53 Postconstruction Environmental Reports

    Section 51.53 is revised to improve readability and to clarify that 
applicants' postconstruction environmental reports do not need to 
discuss the impacts of continued storage.

Sec.  51.61 Environmental Report--Independent Spent Fuel Storage 
Installation (ISFSI) or Monitored Retrievable Storage Installation 
(MRS) License

    Section 51.61 is revised to clarify that ISFSI renewals are 
included in the scope of the generic determination in Sec.  51.23, to 
improve readability, and to clarify that an applicant's ISFSI 
environmental report does not need to discuss the impacts of continued 
storage.

Sec.  51.75 Draft Environmental Impact Statement--Construction Permit, 
Early Site Permit, or Combined License

    Section 51.75 is revised to clarify that construction permits and 
early site permits are included in the scope of the generic 
determination in Sec.  51.23 and that the impact determinations on 
continued storage that are in NUREG-2157 are deemed to be incorporated 
into the draft EIS. Although footnote 5 is included in the regulatory 
text, it is not being amended but is included to meet an Office of the 
Federal Register publication requirement.

Sec.  51.80 Draft Environmental Impact Statement--Materials License

    Paragraph (b) is revised to clarify that ISFSI renewals are 
included in the scope of the generic determination in Sec.  51.23 and 
to improve readability. Paragraph (b) is further revised to clarify 
that the impact determinations on continued storage that are in NUREG-
2157 are deemed to be incorporated into the EIS.

Sec.  51.95 Postconstruction Environmental Impact Statements

    Paragraphs (b), (c), and (d) are revised to clarify that the impact 
determinations on continued storage that are in NUREG-2157 are deemed 
to be incorporated into the EIS or considered in the EA, if the impacts 
of continued storage of spent fuel are applicable to the proposed 
action.

Sec.  51.97 Final Environmental Impact Statement--Materials License

    Paragraph (a) is revised to clarify that ISFSI renewals are 
included in the scope of the generic determination in Sec.  51.23 and 
to improve readability. Paragraph (a) is further revised to clarify 
that the impact determinations on continued storage that are in NUREG-
2157 are deemed to be incorporated into the EIS.

Table B-1--Summary of Findings on NEPA Issues for License Renewal of 
Nuclear Power Plants

    Table B-1 addresses the environmental impacts of license renewal 
activities by resource area. When the Commission issued the final rule 
on the environmental effects of license renewal (78 FR 37282; June 20, 
2013), it was not able to rely on the Waste Confidence rule for two of 
the issues. The Commission noted that upon issuance of the GEIS and 
rule, the NRC would make any necessary conforming changes to the 
license renewal rule. This final rule revises these two Table B-1 
finding column entries under the Waste Management section to address 
onsite storage and offsite radiological impact of disposal. The 
``Offsite radiological impacts of spent nuclear fuel and high-level 
waste disposal'' issue is reclassified as a Category 1 issue with no 
impact level assigned and the finding column entry is revised to 
include reference to the existing radiation protection standards. For 
the ``Onsite storage of spent nuclear fuel'' issue, the finding column 
entry is revised to address the impacts of onsite storage during the 
license renewal term and during the continued storage period. 
Additionally, footnote 7 of Table B-1 is removed. Although footnotes 1, 
2, and 3 are included in the regulatory text, they are not being 
amended but are included to meet an Office of the Federal Register 
publication requirement.

VI. Availability of Documents

    The documents identified in the following table are available to 
interested persons either through ADAMS or the Web address provided, as 
indicated.

[[Page 56257]]



----------------------------------------------------------------------------------------------------------------
                                                         Web (www.regulations.gov
              Document                      PDR         unless otherwise indicated)             ADAMS
----------------------------------------------------------------------------------------------------------------
                                                  NRC Documents
----------------------------------------------------------------------------------------------------------------
Federal Register notice--Extension                 X   X...........................  ML13294A398.
 of Comment Period (78 FR 66858;
 November 7, 2013).
Federal Register notice--Waste                     X   X...........................  ML13256A004.
 Confidence--Continued Storage of
 Spent Nuclear Fuel; Proposed Rule
 (78 FR 56776; September 13, 2013).
NUREG-2157, ``Generic Environmental                X   X...........................  ML14196A105.
 Impact Statement for Continued
 Storage of Spent Nuclear Fuel''
 Vol. 1.
NUREG-2157, ``Generic Environmental                X   X...........................  ML14196A107.
 Impact Statement for Continued
 Storage of Spent Nuclear Fuel''
 Vol. 2.
``Comments on the Waste Confidence                 X   X...........................  ML14154A175.
 Draft Generic Environmental Impact
 Statement and Proposed Rule''.
Draft NUREG-2157, ``Waste Confidence               X   X...........................  ML13224A106.
 Generic Environmental Impact
 Statement''.
Federal Register notice announcing                 X   ............................  ML13294A161.
 the 1977 Denial of PRM-50-18 (42 FR
 34391; July 5, 1977).
Federal Register notice announcing                 X
 generic proceeding on Waste
 Confidence (44 FR 61372, 61373;
 October 25, 1979).
Federal Register notice--1984 Waste                X   ............................  ML033000242.
 Confidence Final Rule (49 FR 34688;
 August 31, 1984).
Federal Register notice--1984 Final                X   ............................  ML033000242.
 Waste Confidence Decision (49 FR
 34658; August 31, 1984).
Federal Register notice--1990 Waste                X   ............................  ML031700063.
 Confidence Final Rule (55 FR 38472;
 September 18, 1990).
Federal Register notice--1990 Waste                X   ............................  ML031700063.
 Confidence Decision (55 FR 38474;
 September 18, 1990).
Federal Register notice--1999 Waste                X   ............................  ML003676331.
 Confidence Decision Review (64 FR
 68005; December 6, 1999).
Federal Register notice--``Licenses,               X   ............................  ML063060337.
 Certifications, and Approvals for
 Nuclear Power Plants'' (72 FR
 49352; August 8, 2007).
Federal Register notice--2010 Waste                X   ............................  ML103350175.
 Confidence Final Rule (75 FR 81037;
 December 23, 2010).
Federal Register notice--2010 Waste                X   ............................  ML120970147.
 Confidence Decision Update (75 FR
 81032; December 23, 2010).
Federal Register notice--License                   X   ............................  ML13101A059.
 Renewal GEIS Final Rule (78 FR
 37282: June, 20, 2013).
COMSECY-12-0016--Approach for                      X   ............................  ML12180A424.
 Addressing Policy Issues Resulting
 from Court Decision to Vacate Waste
 Confidence Decision and Rule (June
 9, 2012).
SRM-COMSECY-12-0016--Approach for                  X   ............................  ML12250A032.
 Addressing Policy Issues Resulting
 from Court Decision to Vacate Waste
 Confidence Decision and Rule
 (September 6, 2012).
Luminant Generation Co. LLC                        X   ............................  ML12076A190.
 (Comanche Peak Nuclear Power Plant,
 Units 3 and 4), et al., CLI-12-7,
 75 NRC 379, 391-92 (March 16, 2012).
NUREG 1947, ``Final Supplemental                   X   ............................  ML11076A010.
 Environmental Impact Statement for
 Combined License (COLs) for Vogtle
 Electric Generating Plant Unit 3
 and 4''.
NUREG-1714, Volume 1, ``Final                      X   ............................  ML020150170.
 Environmental Impact Statement for
 the Construction and Operation of
 an Independent Spent Fuel Storage
 Installation on the Reservation of
 the Skull Valley Band of Goshute
 Indians and the Related
 Transportation Facility in Tooele
 County, Utah''.
Exelon Generation Co., LLC (Early                  X   ............................  ML042260071.
 Site Permit for Clinton ESP Site),
 LBP-04-17, 60 NRC 229, 246-47
 (August 6, 2004).
Dominion Nuclear North Anna, LLC                   X   ............................  ML042260064.
 (Early Site Permit for North Anna
 ESP Site), LBP-04-18, 60 NRC 253,
 268-69 (August 6, 2004).
----------------------------------------------------------------------------------------------------------------
                                                Non-NRC Documents
----------------------------------------------------------------------------------------------------------------
NRDC v. NRC, 582 F.2d 166 (2d Cir.    ...............  http://scholar.google.com/
 1978).                                                 scholarcase?case=1292280692
                                                        394324643
                                                       Note: This link directs the
                                                        reader to an unofficial
                                                        copy of this case.

[[Page 56258]]

 
Minnesota v. NRC, 602 F.2d 412 (D.C.  ...............  http://scholar.google.com/    ...........................
 Cir. 1979).                                            scholarcase?case=1554474921
                                                        7851899941
                                                       Note: This link directs the
                                                        reader to an unofficial
                                                        copy of this case.
Marsh v. Oregon Natural Resources     ...............  http://scholar.google.com/
 Council, 490 U.S. 360, 374 (1989).                     scholarcase?case=1088705218
                                                        9863115558&q
                                                       Note: This link directs the
                                                        reader to an unofficial
                                                        copy of this case.
MD/DC/DE Broadcasters Ass'n v. FCC,   ...............  http://scholar.google.com/
 236 F.3d 13, 22 (D.C. Cir. 2001).                      scholarcase?case=4929117322
                                                        249877509&q=MD/DC/
                                                        DE+Broadcasters+Ass%27n+v.+
                                                        FCC&hl=en&assdt=20000006
                                                       Note: This link directs the
                                                        reader to an official copy
                                                        of the case.
Village of Bensenville v. Federal     ...............  http://scholar.google.com/
 Aviation Administration, 457 F.3d                      scholarcase?case=6559910666
 52, 71-72 (D.C. Cir. 2006).                            849441800&q=Village+of+Bene
                                                        nville&hl=en&assdt=20000003
                                                       Note: This link directs the
                                                        reader to an unofficial
                                                        copy of the case.
New York v. NRC, 681 F.3d 471 (D.C.   ...............  ............................  ML12191A407.
 Cir. 2012).
DOE, Strategy for the Management and               X   ............................  ML13011A138.
 Disposal of Used Nuclear Fuel and
 High-Level Radioactive Waste.
----------------------------------------------------------------------------------------------------------------

VII. Agreement State Compatibility

    Under the ``Policy Statement on Adequacy and Compatibility of 
Agreement State Programs,'' approved by the Commission on June 20, 
1997, and published in the Federal Register (62 FR 46517; September 3, 
1997), this rule is classified as compatibility ``NRC.'' Compatibility 
is not required for Category ``NRC'' regulations. The NRC program 
elements in this category are those that relate directly to areas of 
regulation reserved to the NRC by the AEA or the provisions of Title 10 
of the Code of Federal Regulations, and although an Agreement State may 
not adopt program elements reserved to the NRC, it may wish to inform 
its licensees of certain requirements via a mechanism that is 
consistent with a particular State's administrative procedure laws, but 
does not confer regulatory authority on the State.

IX. Voluntary Consensus Standards

    The National Technology Transfer and Advancement Act of 1995 (Pub. 
L. 104-113) requires that Federal agencies use technical standards that 
are developed or adopted by voluntary consensus standards bodies unless 
the use of such a standard is inconsistent with applicable law or 
otherwise impractical. In this final rule, the NRC is modifying its 
generic determination on the consideration of environmental impacts of 
continued storage of spent fuel beyond the licensed life for reactor 
operations. The NRC is not aware of any voluntary consensus standards 
that address the subject matter of this final rule. This action does 
not constitute the establishment of a standard that contains generally 
applicable requirements.

X. Record of Decision

    The NRC has decided to adopt the proposed revision to 10 CFR 51.23 
and additional conforming changes. This revision codifies the NRC's 
analyses and determinations regarding the environmental impacts of 
continued storage, which are documented in NUREG-2157. The NRC prepared 
NUREG-2157 in accordance with its NEPA guidance for preparation of an 
environmental impact statement, from scoping and issuance of the draft 
to receipt and consideration of public comments in the final generic 
environmental impact statement. The NRC has concluded that these 
analyses and determinations meet the NRC's NEPA obligations with 
respect to continued storage and thereby provide a regulatory basis for 
this revision to 10 CFR 51.23. Section 51.23(a) adopts into regulation 
the generic environmental impact determinations of NUREG-2157, and 
section 51.23(b) provides that the environmental impacts disclosed in 
NUREG-2157 will be deemed incorporated into future EISs and considered 
in future EAs, if the impacts of continued storage are relevant to the 
proposed action, to be considered by the decision-makers in those 
proceedings.
    The NRC's considerations in reaching this decision to adopt a rule 
are discussed in more detail in the following sections of NUREG-2157: 
The proposed action in Section 1.4, the purpose of and need for the 
proposed action in Section 1.5, the no-action alternative and options 
in Section 1.6, the alternatives considered and eliminated in Section 
1.6.2, and the costs and benefits of the proposed action and options 
under the no action alternative in Chapter 7 \7\ with supporting 
information in Appendix H. These portions of the GEIS inform the public 
and decision-makers of the environmental implications of this action.
---------------------------------------------------------------------------

    \7\ The inclusion of a cost-benefit analysis for the proposed 
action in Chapter 7 is consistent with NRC guidance for preparation 
of an environmental impact statement. The costs of continued storage 
activities and facilities are disclosed in Chapter 2, while the 
benefit that accrues from the specific action resulting in the need 
to store spent fuel (i.e., production of electrical power) will be 
discussed in the environmental assessment or impact statement 
prepared in connection with the request for authorization of that 
action, which will incorporate the impact determinations of NUREG-
2157.
---------------------------------------------------------------------------

    The NRC's rulemaking action provides efficient processes for use in 
NRC licensing proceedings and reviews to address the environmental 
impacts of continued storage, consistent with the historic efficiencies 
provided by prior rules codified at 10 CFR 51.23. In COMSECY-12-0016, 
the NRC considered a number of alternative options and tracks to 
provide processes to address these environmental impacts in licensing 
and to preserve the efficiencies historically provided by 10 CFR 51.23. 
As documented in the SRM for COMSECY-12-0016, the Commission chose to 
pursue this combination of a rulemaking to revise 10 CFR 51.23 and a 
generic environmental impact statement to provide a regulatory basis 
for that rulemaking. As discussed in Section 1.6 of NUREG-2157, none of 
the options under the no-action alternative

[[Page 56259]]

considered in the generic environmental impact statement could achieve 
the NRC's purpose of preserving the efficiency of its licensing 
proceedings with respect to the analysis of the impacts of continued 
storage; the only alternative left was no action. In the event of no 
action, NEPA would nonetheless require the NRC to consider the 
environmental impacts of continued storage for many future licensing 
actions. In Section 1.6, the NRC considered options for meeting that 
obligation without this rulemaking. The adopted rulemaking action and 
the options under the no action alternative are all administrative in 
nature and have no significant environmental impacts. Therefore, there 
is no environmentally preferable alternative and there is no 
environmental harm caused by this rulemaking action for the NRC to 
avoid or minimize.
    The costs and benefits of this rulemaking and the various options 
in the event of no action are discussed in Chapter 7 of NUREG-2157. As 
that discussion indicates, the primary advantage of this rulemaking is 
that costs are significantly lower than the costs of the NRC's options 
in the case of no action. The NRC's other options each incur costs 
associated with repetitive site-specific licensing proceedings for 
issues related to the environmental impacts of continued storage as 
well as other potentially large, unquantified costs. The NRC's adoption 
of the rule is consistent with Council on Environmental Quality (CEQ) 
guidance regarding efficiency and timeliness under NEPA (77 FR 14473). 
The NRC acknowledges that some--but not all--members of the public view 
as benefits that (1) these no action options would provide the 
opportunity to challenge impact determinations in individual licensing 
proceedings without a waiver under 10 CFR 2.335 and (2) some 
proceedings may include site-specific reviews of the environmental 
impacts of continued storage. However, the NRC concludes that the cost 
savings and efficiency afforded by this rulemaking outweigh those 
perceived benefits and notes that the waiver provision in 10 CFR 2.335 
would permit challenge to the application of this rule in appropriate 
circumstances. The NRC has therefore decided to issue this rule to 
avoid significant and unnecessary costs in conformity with the CEQ 
policy favoring efficiency in agency environmental reviews.
    As this discussion indicates, this rulemaking is procedural in 
nature and has no significant environmental impacts. In addition, this 
rulemaking is an amendment to 10 CFR part 51 that relates to procedures 
for filing and reviewing requests for licensing actions. Therefore, the 
adoption of this rule qualifies for the categorical exclusion under 10 
CFR 51.22(c)(3)(i) from the requirement to prepare an environmental 
assessment or impact statement. Nonetheless, the NRC has provided 
substantial information about this action in NUREG-2157, and the NRC is 
now issuing this record of decision.

XI. Paperwork Reduction Act Statement

    This final rule does not contain new or amended information 
collection requirements subject to the Paperwork Reduction Act of 1995 
(44 U.S.C. 3501 et seq.). Existing information collection requirements 
were approved by the Office of Management and Budget, control number 
3150-0021.

Public Protection Notification

    The NRC may not conduct or sponsor, and a person is not required to 
respond to, a request for information or an information collection 
requirement unless the requesting document displays a currently valid 
Office of Management and Budget control number.

XII. Regulatory Analysis

    A regulatory analysis has not been prepared for this regulation 
because this regulation does not establish any requirements that would 
place a burden on licensees. A cost-benefit analysis of the alternative 
options considered by the NRC was prepared as part of the GEIS (Chapter 
7). If continued storage must be assessed in site-specific licensing 
actions, the primary costs are incurred by the NRC and licensees and 
license applicants. Licensees and license applicants ultimately 
shoulder the majority of costs incurred to the NRC in the course of 
licensing actions through the NRC's license-fee program. Costs also 
accrue through the NRC's adjudicatory activities, which affect the NRC, 
licensees, license applicants, and petitioners or participants in the 
proceeding. The GEIS contains an estimate that it could cost $27.3 
million in constant dollars to address continued storage in site-
specific proceedings.

XIII. Regulatory Flexibility Certification

    In accordance with the Regulatory Flexibility Act of 1980 (5 U.S.C. 
605(b)), the NRC certifies that this rule does not have a significant 
economic impact on a substantial number of small entities. The final 
rule modifies the generic determination regarding the consideration of 
environmental impacts of continued storage. This generic determination 
provides that the impact determinations from NUREG-2157 will be 
incorporated into EISs, EAs, or any other analysis prepared in 
connection with certain actions. The final rule affects only the 
licensing of nuclear power plants or ISFSIs. Entities seeking or 
holding NRC licenses for these facilities do not fall within the scope 
of the definition of ``small entities'' set forth in the Regulatory 
Flexibility Act or the size standards established by the NRC (10 CFR 
2.810).

XIV. Plain Writing

    The Plain Writing Act of 2010 (Pub. L. 111-274) requires Federal 
agencies to write documents in a clear, concise, and well-organized 
manner. The NRC has written this document to be consistent with the 
Plain Writing Act as well as the Presidential Memorandum, ``Plain 
Language in Government Writing,'' published June 10, 1998 (63 FR 
31885).

XV. Backfitting and Issue Finality

    The NRC has determined that the backfit rules (Sec. Sec.  50.109, 
70.76, 72.62, or 76.76) and the issue finality provisions in 10 CFR 
part 52 do not apply to this final rule because this amendment does not 
involve any provisions that will either impose backfits as defined in 
10 CFR chapter I, or represent non-compliance with the issue finality 
of provisions in 10 CFR part 52. Therefore, a backfit analysis is not 
required for this final rule, and the NRC did not prepare a backfit 
analysis for this final rule.

XVI. Congressional Review Act

    In accordance with the Congressional Review Act of 1996 (5 U.S.C. 
801-808), the NRC has determined that this action is not a major rule 
and has verified this determination with the Office of Information and 
Regulatory Affairs of the Office of Management and Budget.

List of Subjects in 10 CFR Part 51

    Administrative practice and procedure, Environmental impact 
statement, Nuclear materials, Nuclear power plants and reactors, 
Reporting and recordkeeping requirements.

    For the reasons set out in the preamble and under the authority of 
the Atomic Energy Act of 1954, as amended; the Energy Reorganization 
Act of 1974, as amended; and 5 U.S.C. 552 and 553; the NRC is adopting 
the following amendments to 10 CFR part 51.

[[Page 56260]]

PART 51--ENVIRONMENTAL PROTECTION REGULATIONS FOR DOMESTIC 
LICENSING AND RELATED REGULATORY FUNCTIONS

0
1. The authority citation for part 51 continues to read as follows:

    Authority: Atomic Energy Act sec. 161, 1701 (42 U.S.C. 2201, 
2297f); Energy Reorganization Act secs. 201, 202, 211 (42 U.S.C. 
5841, 5842, 5851); Government Paperwork Elimination Act sec. 1704 
(44 U.S.C. 3504 note). Subpart A also issued under National 
Environmental Policy Act secs. 102, 104, 105 (42 U.S.C. 4332, 4334, 
4335); Pub. L. 95-604, Title II, 92 Stat. 3033-3041; Atomic Energy 
Act sec. 193 (42 U.S.C. 2243). Sections 51.20, 51.30, 51.60, 51.80. 
and 51.97 also issued under Nuclear Waste Policy Act secs. 135, 141, 
148 (42 U.S.C. 10155, 10161, 10168). Section 51.22 also issued under 
Atomic Energy Act sec. 274 (42 U.S.C. 2021) and under Nuclear Waste 
Policy Act sec. 121 (42 U.S.C. 10141). Sections 51.43, 51.67, and 
51.109 also issued under Nuclear Waste Policy Act sec. 114(f) (42 
U.S.C. 10134(f)).


0
2. In Sec.  51.23, revise the section heading and paragraphs (a) and 
(b) to read as follows:


Sec.  51.23  Environmental impacts of continued storage of spent 
nuclear fuel beyond the licensed life for operation of a reactor.

    (a) The Commission has generically determined that the 
environmental impacts of continued storage of spent nuclear fuel beyond 
the licensed life for operation of a reactor are those impacts 
identified in NUREG-2157, ``Generic Environmental Impact Statement for 
Continued Storage of Spent Nuclear Fuel.''
    (b) The environmental reports described in Sec. Sec.  51.50, 51.53, 
and 51.61 are not required to discuss the environmental impacts of 
spent nuclear fuel storage in a reactor facility storage pool or an 
ISFSI for the period following the term of the reactor operating 
license, reactor combined license, or ISFSI license. The impact 
determinations in NUREG-2157 regarding continued storage shall be 
deemed incorporated into the environmental impact statements described 
in Sec. Sec.  51.75, 51.80(b), 51.95, and 51.97(a). The impact 
determinations in NUREG-2157 regarding continued storage shall be 
considered in the environmental assessments described in Sec. Sec.  
51.30(b) and 51.95(d), if the impacts of continued storage of spent 
fuel are relevant to the proposed action.
* * * * *

0
3. In Sec.  51.30, revise paragraph (b) to read as follows:


Sec.  51.30  Environmental assessment.

* * * * *
    (b) As stated in Sec.  51.23, the generic impact determinations 
regarding the continued storage of spent fuel in NUREG-2157 shall be 
considered in the environmental assessment, if the impacts of continued 
storage of spent fuel are relevant to the proposed action.
* * * * *

0
4. In Sec.  51.50, revise paragraphs (a), (b)(2), and (c) introductory 
text to read as follows:


Sec.  51.50  Environmental report--construction permit, early site 
permit, or combined license stage.

    (a) Construction permit stage. Each applicant for a permit to 
construct a production or utilization facility covered by Sec.  51.20 
shall submit with its application a separate document, entitled 
``Applicant's Environmental Report--Construction Permit Stage,'' which 
shall contain the information specified in Sec. Sec.  51.45, 51.51, and 
51.52. Each environmental report shall identify procedures for 
reporting and keeping records of environmental data, and any conditions 
and monitoring requirements for protecting the non-aquatic environment, 
proposed for possible inclusion in the license as environmental 
conditions in accordance with Sec.  50.36b of this chapter. As stated 
in Sec.  51.23, no discussion of the environmental impacts of the 
continued storage of spent fuel is required in this report.
    (b) * * *
    (2) The environmental report may address one or more of the 
environmental effects of construction and operation of a reactor, or 
reactors, which have design characteristics that fall within the site 
characteristics and design parameters for the early site permit 
application, provided however, that the environmental report must 
address all environmental effects of construction and operation 
necessary to determine whether there is any obviously superior 
alternative to the site proposed. The environmental report need not 
include an assessment of the economic, technical, or other benefits 
(for example, need for power) and costs of the proposed action or an 
evaluation of alternative energy sources. As stated in Sec.  51.23, no 
discussion of the environmental impacts of the continued storage of 
spent fuel is required in this report.
* * * * *
    (c) Combined license stage. Each applicant for a combined license 
shall submit with its application a separate document, entitled 
``Applicant's Environmental Report--Combined License Stage.'' Each 
environmental report shall contain the information specified in 
Sec. Sec.  51.45, 51.51, and 51.52, as modified in this paragraph. For 
other than light-water-cooled nuclear power reactors, the environmental 
report shall contain the basis for evaluating the contribution of the 
environmental effects of fuel cycle activities for the nuclear power 
reactor. Each environmental report shall identify procedures for 
reporting and keeping records of environmental data, and any conditions 
and monitoring requirements for protecting the non-aquatic environment, 
proposed for possible inclusion in the license as environmental 
conditions in accordance with Sec.  50.36b of this chapter. The 
combined license environmental report may reference information 
contained in a final environmental document previously prepared by the 
NRC staff. As stated in Sec.  51.23, no discussion of the environmental 
impacts of the continued storage of spent fuel is required in this 
report.
* * * * *

0
5. In Sec.  51.53, revise paragraphs (b), (c)(2), and (d) to read as 
follows:


Sec.  51.53  Postconstruction environmental reports.

* * * * *
    (b) Operating license stage. Each applicant for a license to 
operate a production or utilization facility covered by Sec.  51.20 
shall submit with its application a separate document entitled 
``Supplement to Applicant's Environmental Report--Operating License 
Stage,'' which will update ``Applicant's Environmental Report--
Construction Permit Stage.'' Unless otherwise required by the 
Commission, the applicant for an operating license for a nuclear power 
reactor shall submit this report only in connection with the first 
licensing action authorizing full-power operation. In this report, the 
applicant shall discuss the same matters described in Sec. Sec.  51.45, 
51.51, and 51.52, but only to the extent that they differ from those 
discussed or reflect new information in addition to that discussed in 
the final environmental impact statement prepared by the Commission in 
connection with the construction permit. No discussion of need for 
power, or of alternative energy sources, or of alternative sites for 
the facility, is required in this report. As stated in Sec.  51.23, no 
discussion of the environmental impacts of the continued storage of 
spent fuel is required in this report.
    (c) * * *
    (2) The report must contain a description of the proposed action, 
including the applicant's plans to

[[Page 56261]]

modify the facility or its administrative control procedures as 
described in accordance with Sec.  54.21 of this chapter. This report 
must describe in detail the affected environment around the plant, the 
modifications directly affecting the environment or any plant 
effluents, and any planned refurbishment activities. In addition, the 
applicant shall discuss in this report the environmental impacts of 
alternatives and any other matters described in Sec.  51.45. The report 
is not required to include discussion of need for power or the economic 
costs and economic benefits of the proposed action or of alternatives 
to the proposed action except insofar as such costs and benefits are 
either essential for a determination regarding the inclusion of an 
alternative in the range of alternatives considered or relevant to 
mitigation. The environmental report need not discuss other issues not 
related to the environmental effects of the proposed action and the 
alternatives. As stated in Sec.  51.23, no discussion of the 
environmental impacts of the continued storage of spent fuel is 
required in this report.
* * * * *
    (d) Postoperating license stage. Each applicant for a license 
amendment authorizing decommissioning activities for a production or 
utilization facility either for unrestricted use or based on continuing 
use restrictions applicable to the site; and each applicant for a 
license amendment approving a license termination plan or 
decommissioning plan under Sec.  50.82 of this chapter either for 
unrestricted use or based on continuing use restrictions applicable to 
the site; and each applicant for a license or license amendment to 
store spent fuel at a nuclear power reactor after expiration of the 
operating license for the nuclear power reactor shall submit with its 
application a separate document, entitled ``Supplement to Applicant's 
Environmental Report--Post Operating License Stage,'' which will update 
``Applicant's Environmental Report--Operating License Stage,'' as 
appropriate, to reflect any new information or significant 
environmental change associated with the applicant's proposed 
decommissioning activities or with the applicant's proposed activities 
with respect to the planned storage of spent fuel. As stated in Sec.  
51.23, no discussion of the environmental impacts of the continued 
storage of spent fuel is required in this report. The `''Supplement to 
Applicant's Environmental Report--Post Operating License Stage''' may 
incorporate by reference any information contained in `''Applicants 
Environmental Report--Construction Permit Stage.''

0
6. Revise Sec.  51.61 to read as follows:


Sec.  51.61  Environmental report--independent spent fuel storage 
installation (ISFSI) or monitored retrievable storage installation 
(MRS) license.

    Each applicant for issuance of a license for storage of spent fuel 
in an independent spent fuel storage installation (ISFSI) or for the 
storage of spent fuel and high-level radioactive waste in a monitored 
retrievable storage installation (MRS) pursuant to part 72 of this 
chapter shall submit with its application to: ATTN: Document Control 
Desk, Director, Office of Nuclear Material Safety and Safeguards, a 
separate document entitled ``Applicant's Environmental Report--ISFSI 
License'' or ``Applicant's Environmental Report--MRS License,'' as 
appropriate. If the applicant is the U.S. Department of Energy, the 
environmental report may be in the form of either an environmental 
impact statement or an environmental assessment, as appropriate. The 
environmental report shall contain the information specified in Sec.  
51.45 and shall address the siting evaluation factors contained in 
subpart E of part 72 of this chapter. As stated in Sec.  51.23, no 
discussion of the environmental impacts of the continued storage of 
spent fuel in an ISFSI is required in this report.

0
7. In Sec.  51.75, revise paragraphs (a), (b), and (c) introductory 
text to read as follows:


Sec.  51.75  Draft environmental impact statement--construction permit, 
early site permit, or combined license.

    (a) Construction permit stage. A draft environmental impact 
statement relating to issuance of a construction permit for a 
production or utilization facility will be prepared in accordance with 
the procedures and measures described in Sec. Sec.  51.70, 51.71, 
51.72, and 51.73. The contribution of the environmental effects of the 
uranium fuel cycle activities specified in Sec.  51.51 shall be 
evaluated on the basis of impact values set forth in Table S-3, Table 
of Uranium Fuel Cycle Environmental Data, which shall be set out in the 
draft environmental impact statement. With the exception of radon-222 
and technetium-99 releases, no further discussion of fuel cycle release 
values and other numerical data that appear explicitly in the table 
shall be required.\5\ The impact statement shall take account of dose 
commitments and health effects from fuel cycle effluents set forth in 
Table S-3 and shall in addition take account of economic, 
socioeconomic, and possible cumulative impacts and other fuel cycle 
impacts as may reasonably appear significant. As stated in Sec.  51.23, 
the generic impact determinations regarding the continued storage of 
spent fuel in NUREG-2157 shall be deemed incorporated into the 
environmental impact statement.
---------------------------------------------------------------------------

    \5\ Values for releases of Rn-222 and Tc-99 are not given in the 
table. The amount and significance of Rn-222 releases from the fuel 
cycle and Tc-99 releases from waste management or reprocessing 
activities shall be considered in the draft environmental impact 
statement and may be the subject of litigation in individual 
licensing proceedings.
---------------------------------------------------------------------------

    (b) Early site permit stage. A draft environmental impact statement 
relating to issuance of an early site permit for a production or 
utilization facility will be prepared in accordance with the procedures 
and measures described in Sec. Sec.  51.70, 51.71, 51.72, 51.73, and 
this section. The contribution of the environmental effects of the 
uranium fuel cycle activities specified in Sec.  51.51 shall be 
evaluated on the basis of impact values set forth in Table S-3, Table 
of Uranium Fuel Cycle Environmental Data, which shall be set out in the 
draft environmental impact statement. With the exception of radon-222 
and technetium-99 releases, no further discussion of fuel cycle release 
values and other numerical data that appear explicitly in the table 
shall be required.\5\ The impact statement shall take account of dose 
commitments and health effects from fuel cycle effluents set forth in 
Table S-3 and shall in addition take account of economic, 
socioeconomic, and possible cumulative impacts and other fuel cycle 
impacts as may reasonably appear significant. As stated in Sec.  51.23, 
the generic impact determinations regarding the continued storage of 
spent fuel in NUREG-2157 shall be deemed incorporated into the 
environmental impact statement. The draft environmental impact 
statement must include an evaluation of alternative sites to determine 
whether there is any obviously superior alternative to the site 
proposed. The draft environmental impact statement must also include an 
evaluation of the environmental effects of construction and operation 
of a reactor, or reactors, which have design characteristics that fall 
within the site characteristics and design parameters for the early 
site permit application, but only to the extent addressed in the early 
site permit environmental report or otherwise necessary to determine 
whether there is any obviously superior alternative to the site 
proposed. The draft environmental impact statement must not include an

[[Page 56262]]

assessment of the economic, technical, or other benefits (for example, 
need for power) and costs of the proposed action or an evaluation of 
alternative energy sources, unless these matters are addressed in the 
early site permit environmental report.
    (c) Combined license stage. A draft environmental impact statement 
relating to issuance of a combined license that does not reference an 
early site permit will be prepared in accordance with the procedures 
and measures described in Sec. Sec.  51.70, 51.71, 51.72, and 51.73. 
The contribution of the environmental effects of the uranium fuel cycle 
activities specified in Sec.  51.51 shall be evaluated on the basis of 
impact values set forth in Table S-3, Table of Uranium Fuel Cycle 
Environmental Data, which shall be set out in the draft environmental 
impact statement. With the exception of radon-222 and technetium-99 
releases, no further discussion of fuel cycle release values and other 
numerical data that appear explicitly in the table shall be 
required.\5\ The impact statement shall take account of dose 
commitments and health effects from fuel cycle effluents set forth in 
Table S-3 and shall in addition take account of economic, 
socioeconomic, and possible cumulative impacts and other fuel cycle 
impacts as may reasonably appear significant. As stated in Sec.  51.23, 
the generic impact determinations regarding the continued storage of 
spent fuel in NUREG-2157 shall be deemed incorporated into the 
environmental impact statement.
* * * * *

0
8. In Sec.  51.80, revise paragraph (b)(1) to read as follows:


Sec.  51.80  Draft environmental impact statement--materials license.

* * * * *
    (b)(1) Independent spent fuel storage installation (ISFSI). As 
stated in Sec.  51.23, the generic impact determinations regarding the 
continued storage of spent fuel in NUREG-2157 shall be deemed 
incorporated in the environmental impact statement.
* * * * *

0
9. In Sec.  51.95, revise paragraphs (b), (c)(2), and (d) to read as 
follows:


Sec.  51.95  Postconstruction environmental impact statements.

* * * * *
    (b) Initial operating license stage. In connection with the 
issuance of an operating license for a production or utilization 
facility, the NRC staff will prepare a supplement to the final 
environmental impact statement on the construction permit for that 
facility, which will update the prior environmental review. The 
supplement will only cover matters that differ from the final 
environmental impact statement or that reflect significant new 
information concerning matters discussed in the final environmental 
impact statement. Unless otherwise determined by the Commission, a 
supplement on the operation of a nuclear power plant will not include a 
discussion of need for power, or of alternative energy sources, or of 
alternative sites, and will only be prepared in connection with the 
first licensing action authorizing full-power operation. As stated in 
Sec.  51.23, the generic impact determinations regarding the continued 
storage of spent fuel in NUREG-2157 shall be deemed incorporated into 
the environmental impact statement.
    (c) * * *
    (2) The supplemental environmental impact statement for license 
renewal is not required to include discussion of need for power or the 
economic costs and economic benefits of the proposed action or of 
alternatives to the proposed action except insofar as such benefits and 
costs are either essential for a determination regarding the inclusion 
of an alternative in the range of alternatives considered or relevant 
to mitigation. In addition, the supplemental environmental impact 
statement prepared at the license renewal stage need not discuss other 
issues not related to the environmental effects of the proposed action 
and the alternatives. The analysis of alternatives in the supplemental 
environmental impact statement should be limited to the environmental 
impacts of such alternatives and should otherwise be prepared in 
accordance with Sec.  51.71 and appendix A to subpart A of this part. 
As stated in Sec.  51.23, the generic impact determinations regarding 
the continued storage of spent fuel in NUREG-2157 shall be deemed 
incorporated into the supplemental environmental impact statement.
* * * * *
    (d) Postoperating license stage. In connection with the amendment 
of an operating or combined license authorizing decommissioning 
activities at a production or utilization facility covered by Sec.  
51.20, either for unrestricted use or based on continuing use 
restrictions applicable to the site, or with the issuance, amendment or 
renewal of a license to store spent fuel at a nuclear power reactor 
after expiration of the operating or combined license for the nuclear 
power reactor, the NRC staff will prepare a supplemental environmental 
impact statement for the post operating or post combined license stage 
or an environmental assessment, as appropriate, which will update the 
prior environmental documentation prepared by the NRC for compliance 
with NEPA under the provisions of this part. The supplement or 
assessment may incorporate by reference any information contained in 
the final environmental impact statement--for the operating or combined 
license stage, as appropriate, or in the records of decision prepared 
in connection with the early site permit, construction permit, 
operating license, or combined license for that facility. The 
supplement will include a request for comments as provided in Sec.  
51.73. As stated in Sec.  51.23, the generic impact determinations 
regarding the continued storage of spent fuel in NUREG-2157 shall be 
deemed incorporated into the supplemental environmental impact 
statement or shall be considered in the environmental assessment, if 
the impacts of continued storage of spent fuel are applicable to the 
proposed action.

0
10. In Sec.  51.97, revise paragraph (a) to read as follows:


Sec.  51.97  Final environmental impact statement--materials license.

    (a) Independent spent fuel storage installation (ISFSI). As stated 
in Sec.  51.23, the generic impact determinations regarding the 
continued storage of spent fuel in NUREG-2157 shall be deemed 
incorporated into the environmental impact statement.
* * * * *

0
11. In appendix B to subpart A of part 51, footnote 7 is removed from 
Table B-1 and the entries for ``Onsite storage of spent nuclear fuel'' 
and ``Offsite radiological impacts of spent nuclear fuel and high-level 
waste disposal'' under the ``Waste Management'' section of the table 
are revised to read as follows:

Appendix B to Subpart A--Environmental Effect of Renewing the Operating 
License of a Nuclear Power Plant

* * * * *

[[Page 56263]]



          Table B-1--Summary of Findings on NEPA Issues for License Renewal of Nuclear Power Plants \1\
----------------------------------------------------------------------------------------------------------------
                     Issue                        Category \2\                     Finding \3\
----------------------------------------------------------------------------------------------------------------
 
                                                  * * * * * * *
----------------------------------------------------------------------------------------------------------------
                                                Waste Management
----------------------------------------------------------------------------------------------------------------
 
                                                  * * * * * * *
----------------------------------------------------------------------------------------------------------------
Onsite storage of spent nuclear fuel..........               1   During the license renewal term, SMALL. The
                                                                  expected increase in the volume of spent
                                                                  nuclear fuel from an additional 20 years of
                                                                  operation can be safely accommodated onsite
                                                                  during the license renewal term with small
                                                                  environmental impacts through dry or pool
                                                                  storage at all plants.
                                                ...............  For the period after the licensed life for
                                                                  reactor operations, the impacts of onsite
                                                                  storage of spent nuclear fuel during the
                                                                  continued storage period are discussed in
                                                                  NUREG-2157 and as stated in Sec.   51.23(b),
                                                                  shall be deemed incorporated into this issue.
Offsite radiological impacts of spent nuclear                1   For the high-level waste and spent-fuel
 fuel and high-level waste disposal.                              disposal component of the fuel cycle, the EPA
                                                                  established a dose limit of 0.15 mSv (15
                                                                  millirem) per year for the first 10,000 years
                                                                  and 1.0 mSv (100 millirem) per year between
                                                                  10,000 years and 1 million years for offsite
                                                                  releases of radionuclides at the proposed
                                                                  repository at Yucca Mountain, Nevada.
                                                                 The Commission concludes that the impacts would
                                                                  not be sufficiently large to require the NEPA
                                                                  conclusion, for any plant, that the option of
                                                                  extended operation under 10 CFR part 54 should
                                                                  be eliminated. Accordingly, while the
                                                                  Commission has not assigned a single level of
                                                                  significance for the impacts of spent fuel and
                                                                  high level waste disposal, this issue is
                                                                  considered Category 1.
 
                                                  * * * * * * *
----------------------------------------------------------------------------------------------------------------
\1\ Data supporting this table are contained in NUREG-1437, Revision 1, ``Generic Environmental Impact Statement
  for License Renewal of Nuclear Plants'' (June 2013).
\2\ The numerical entries in this column are based on the following category definitions:
Category 1: For the issue, the analysis reported in the Generic Environmental Impact Statement has shown:
(1) The environmental impacts associated with the issue have been determined to apply either to all plants or,
  for some issues, to plants having a specific type of cooling system or other specified plant or site
  characteristic;
(2) A single significance level (i.e., small, moderate, or large) has been assigned to the impacts (except for
  Offsite radiological impacts--collective impacts from other than the disposal of spent fuel and high-level
  waste); and
(3) Mitigation of adverse impacts associated with the issue has been considered in the analysis, and it has been
  determined that additional plant-specific mitigation measures are not likely to be sufficiently beneficial to
  warrant implementation.
The generic analysis of the issue may be adopted in each plant-specific review.
Category 2: For the issue, the analysis reported in the Generic Environmental Impact Statement has shown that
  one or more of the criteria of Category 1 cannot be met, and therefore additional plant-specific review is
  required.
\3\ The impact findings in this column are based on the definitions of three significance levels. Unless the
  significance level is identified as beneficial, the impact is adverse, or in the case of ``small,'' may be
  negligible. The definitions of significance follow:
SMALL--For the issue, environmental effects are not detectable or are so minor that they will neither
  destabilize nor noticeably alter any important attribute of the resource. For the purposes of assessing
  radiological impacts, the Commission has concluded that those impacts that do not exceed permissible levels in
  the Commission's regulations are considered small as the term is used in this table.
MODERATE--For the issue, environmental effects are sufficient to alter noticeably, but not to destabilize,
  important attributes of the resource.
LARGE--For the issue, environmental effects are clearly noticeable and are sufficient to destabilize important
  attributes of the resource.
For issues where probability is a key consideration (i.e., accident consequences), probability was a factor in
  determining significance.

* * * * *

    Dated at Rockville, Maryland, this 11th day of September, 2014.

    For the Nuclear Regulatory Commission.
Annette L. Vietti-Cook,
Secretary of the Commission.
[FR Doc. 2014-22215 Filed 9-18-14; 8:45 am]
BILLING CODE 7590-01-P