[Federal Register Volume 76, Number 251 (Friday, December 30, 2011)]
[Rules and Regulations]
[Pages 82079-82103]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2011-33266]


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NUCLEAR REGULATORY COMMISSION

10 CFR Part 52

RIN 3150-AI81
[NRC-2010-0131]


AP1000 Design Certification Amendment

AGENCY: Nuclear Regulatory Commission.

ACTION: Final rule.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC or Commission) is 
amending its regulations to certify an amendment to the AP1000 standard 
plant design. The amendment replaces the combined license (COL) 
information items and design acceptance criteria (DAC) with specific 
design information, addresses the effects of the impact of a large 
commercial aircraft, incorporates design improvements, and increases 
standardization of the design. This action is necessary so that 
applicants or licensees intending to construct and operate an AP1000 
design may do so by referencing this regulation (AP1000 design 
certification rule (DCR)), and need not demonstrate in their 
applications the safety of the certified design as amended. The 
applicant for this amendment to the AP1000 design is Westinghouse 
Electric Company, LLC (Westinghouse).

DATES: The effective date of this rule is December 30, 2011. The 
incorporation by reference of certain material specified in this 
regulation is approved by the Director of the Office of the Federal 
Register as of December 30, 2011. The applicability date of this rule 
for those entities who receive actual notice of this rule is the date 
of receipt of this rule.

ADDRESSES: You can access publicly available documents related to this 
action (see Section VI. Availability of Documents) using the following 
methods:
     NRC's Public Document Room (PDR): The public may examine 
and have copied, for a fee, publicly available documents at the NRC's 
PDR, O1-F21, One White Flint North, 11555 Rockville Pike, Rockville, 
Maryland 20852.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): Publicly available documents created or received at the NRC 
are available online in the NRC Library at http://www.nrc.gov/reading-rm/adams.html. From this page, the public can gain entry into ADAMS, 
which provides text and image files of the NRC's public documents. If 
you do not have access to ADAMS or if there are problems in accessing 
the documents located in ADAMS, contact the NRC's PDR reference staff 
at 1-(800) 397-4209, (301) 415-4737, or by email to 
[email protected].
     Federal Rulemaking Web site: Public comments and 
supporting materials related to this final rule can be found at http://www.regulations.gov by searching on Docket ID NRC-2010-0131. Address 
questions and concerns regarding NRC dockets to Carol Gallagher; 
telephone at (301) 492-3668; email: [email protected].

FOR FURTHER INFORMATION CONTACT: Ms. Serita Sanders, Office of New 
Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone at (301) 415-2956; email: [email protected].

SUPPLEMENTARY INFORMATION:

I. Background
II. Summary of Analysis of Public Comments on the AP1000 Proposed 
Rule
    A. Overview of Public Comments
    B. Description of Key Structures of the AP1000 Design
    C. Significant Public Comments and Overall NRC Responses
III. Discussion
    A. Technical Evaluation of Westinghouse Amendment to the AP1000 
Design
    B. Changes to Appendix D
    C. Immediate Effectiveness of Final Rule: Provision of Actual 
Notice to Southern Nuclear Operating Company
IV. Section-by-Section Analysis
    A. Scope and Contents (Section III)
    B. Additional Requirements and Restrictions (Section IV)
    C. Applicable Regulations (Section V)
    D. Issue Resolution (Section VI)
    E. Processes for Changes and Departures (Section VIII)
    F. Records and Reporting (Section X)
V. Agreement State Compatibility
VI. Availability of Documents
VII. Voluntary Consensus Standards
VIII. Finding of No Significant Environmental Impact: Availability
IX. Paperwork Reduction Act Statement
X. Regulatory Analysis
XI. Regulatory Flexibility Act Certification
XII. Backfitting and Issue Finality
XIII. Congressional Review Act

I. Background

    Title 10 of the Code of Federal Regulations (10 CFR), Part 52, 
``Licenses, Certifications, and Approvals for Nuclear Power Plants,'' 
Subpart B, presents the process for obtaining standard design 
certifications. Section 52.63, ``Finality of standard design 
certifications,'' provides criteria for determining when the Commission 
may amend the certification information for a previously certified 
standard design in response to a request for amendment from any person.
    The NRC originally approved the AP1000 design certification in a 
final rule in 2006 (71 FR 4464; January 27, 2006). The final AP1000 DCR 
incorporates by reference Revision 15 of the design control document 
(DCD) (ADAMS Accession No. ML053460400), which describes the AP1000 
certified design. During its initial certification of the AP1000 
design, the NRC issued a final safety evaluation report (FSER) for the 
AP1000 as NUREG-1793, ``Final Safety Evaluation Report Related to 
Certification of the AP1000 Standard Design,'' in September 2004 (ADAMS 
Accession No. ML043570339) and Supplement No. 1 to NUREG-1793 (ADAMS 
Accession No. ML053410203).
    From March 2006 through May 2007, NuStart Energy Development, LLC 
(NuStart) \1\ and Westinghouse provided the NRC with a number of 
technical reports (TRs) for pre-application review of a possible 
amendment to the approved AP1000 certified design, in order to: (1) 
close specific, generically applicable COL information items 
(information to be supplied by COL

[[Page 82080]]

applicants/holders) in the AP1000 certified standard design; (2) 
identify standard design changes resulting from the AP1000 detailed 
design efforts; and (3) provide specific standard design information in 
areas or for topics where the AP1000 DCD was focused on the design 
process and acceptance criteria. TRs typically addressed a topical area 
(e.g., redesign of a component, structure or process) and included the 
technical details of a proposed change, design standards, analyses and 
justifications as needed, proposed changes to the DCD, and 
Westinghouse's assessment of the applicable regulatory criteria (e.g., 
the assessment of the criteria in 10 CFR part 52, Appendix D, Section 
VIII, ``Processes for Changes and Departures''). The NRC identified 
issues associated with the TRs and engaged Westinghouse in requests for 
additional information and meetings during the pre-application phase to 
resolve them.
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    \1\ The NuStart member companies are: Constellation Generation 
Group, LLC, Duke Energy Corporation, EDF-International North 
America, Inc., Entergy Nuclear, Inc, Exelon Generation Company, LLC, 
Florida Power and Light Company, Progress Energy, and Southern 
Company Services, Inc.
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    On May 26, 2007, Westinghouse submitted, via transmittal letter 
(ADAMS Accession No. ML071580757), an application to amend the AP1000 
DCR. The application included Revision 16 of the DCD (ADAMS Accession 
No. ML071580939). This application was supplemented by letters dated 
October 26 (ADAMS Accession No. ML073120415), November 2 (ADAMS 
Accession No. ML073090471), and December 12, 2007 (ADAMS Accession No. 
ML073610541), and January 11 (ADAMS Accession No. ML080150513) and 
January 14, 2008 (ADAMS Accession No. ML080220389). The application 
noted, in part, that:
    (1) Generic amendments to the design certification, including 
additional design information to resolve DAC and design-related COL 
information items, as well as design information to make corrections 
and changes, would result in further standardization and improved 
licensing efficiency for the multiple COL applications referencing the 
AP1000 DCR that were planned for submittal in late 2007 and early 2008.
    (2) Westinghouse, in conjunction with NuStart, has been preparing 
TRs since late 2005. These TRs were developed with input, review, 
comment, and other technical oversight provided by NuStart members, 
including the prospective AP1000 COL applicants. Submittal of these TRs 
to the NRC was initiated in March 2006. The TRs contain discussion of 
the technical changes and supplemental information that is used to 
support the detailed information contained in the DCD.
    In Attachment 2 to the May 26, 2007, application, Westinghouse 
identified the criteria of 10 CFR 52.63(a)(1) that apply to the changes 
described in each TR and associated COL information items, if 
applicable.
    On January 18, 2008, the NRC notified Westinghouse that it accepted 
the May 26, 2007, application, as supplemented, for docketing (Docket 
No. 52-006) and published a notice of acceptance (ADAMS Accession No. 
ML073600743) in the Federal Register (73 FR 4926; January 28, 2008). On 
September 22, 2008, Westinghouse submitted Revision 17 to the AP1000 
DCD. Revision 17 contained changes to the DCD that had been previously 
accepted by the NRC in the course of its review of Revision 16 of the 
DCD. In addition, Revision 17 proposed changes to DAC in the areas of 
piping design (Chapter 3), instrumentation and control (I&C) systems 
(Chapter 7) and human factors engineering (HFE) (Chapter 18).
    The NRC issued guidance on the finalization of design changes in 
Interim Staff Guidance (ISG) DC/COL-ISG-011, ``Finalizing Licensing-
basis Information,'' (ADAMS Accession No. ML092890623), which describes 
various categories of design changes that should not be deferred and 
those that should be included in the DCR.
    By letter dated January 20, 2010, Westinghouse submitted a list of 
design change packages that would be included in Revision 18 of the 
AP1000 DCD (ADAMS Accession No. ML100250873). A number of subsequent 
submittals were made by Westinghouse to narrow the focus of those 
design changes to the categories of changes that should not be 
deferred, as recommended by DC/COL-ISG-011.
    Revision 18 to the AP1000 DCD (ADAMS Accession Nos. ML103480059 and 
ML103480572) was submitted on December 1, 2010, and contains both 
proposed changes previously described in the design change packages and 
changes already accepted by the NRC in the review process of Revision 
17 to the AP1000 DCD.
    In the course of its ongoing review of the amendment application, 
the NRC determined that changes from information in Revision 15 to the 
DCD were needed. In response to NRC questions, Westinghouse proposed 
such changes. Once the NRC was satisfied with these DCD markups, they 
were documented in the advance safety evaluation report (SER) as 
confirmatory items (CIs). The use of CIs is restricted to cases where 
the NRC has reviewed and approved specific DCD proposals. With the 
review of Revision 18, the NRC has confirmed that Westinghouse has made 
those changes to the DCD accepted by the NRC that were not addressed in 
Revision 17 to the AP1000 DCD. For the final rule, the NRC has 
completed the review of the CIs and prepared a FSER reflecting that 
action. The CIs were closed based upon an acceptable comparison between 
the revised DCD text and the text required by the CI. As further 
discussed later, Revision 19 is the version being certified in the 
final rule.
    In order to simplify the NRC's review of the design change 
documentation, and to simplify subsequent review by the NRC's Advisory 
Committee on Reactor Safeguards (ACRS), the design changes pursuant to 
DC/COL-ISG-011 are reviewed in a separate chapter (Chapter 23) of the 
FSER. This chapter indicates which areas of the DCD are affected by 
each design change and the letters from Westinghouse that submitted 
them. In some cases, the NRC's review of the design changes reviewed in 
Chapter 23 may be incorporated into the chapters of the FSER where this 
material would normally be addressed because of the relationship 
between individual design changes and the review of prior DCD changes 
from Revisions 16 and 17 of the DCD.
    The Westinghouse Revision 18 DCD includes an enclosure providing a 
cross-reference to the DCD changes and the applicable 10 CFR 
52.63(a)(1) criteria. Revision 17 provides a similar cross-reference 
within the September 22, 2008, Westinghouse letter for those changes 
associated with the revised DCD. Revision 16, on the other hand, uses 
TRs to identify the DCD changes and lists the corresponding applicable 
10 CFR 52.63(a)(1) criteria via Westinghouse letter, dated May 26, 2007 
(Table 1). Revision 19 has a cross-reference similar to Revisions 17 
and 18.
    As of the date of this document, the application for amendment of 
the AP1000 design certification has been referenced in the following 
COL applications:

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                                                                .
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Vogtle, Units 3 and 4.........  Docket No. 05200025/6.  73 FR 33118.
Bellefonte Nuclear Station,     Docket Nos. 05200014/5  73 FR 4923.
 Units 3 and 4.
Levy County, Units 1 and 2....  Docket Nos. 05200029/   73 FR 60726.
                                 30.
Shearon Harris, Units 2 and 3.  Docket Nos. 05200022/3  73 FR 21995.
Turkey Point, Units 6 and 7...  Docket Nos. 05200040/1  74 FR 51621.

[[Page 82081]]

 
Virgil C. Summer, Units 2 and   Docket Nos. 05200027/8  73 FR 45793.
 3.
William States Lee III, Units   Docket Nos. 05200018/9  73 FR 11156.
 1 and 2.
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II. Summary of Analysis of Public Comments on the AP1000 Proposed Rule

A. Overview of Public Comments

    The NRC published the proposed rule amending the AP1000 DCR in the 
Federal Register on February 24, 2011 (76 FR 10269). The public comment 
period for the proposed rule closed on May 10, 2011. The NRC received a 
large number of comment submissions for the proposed rule (AP1000 
rulemaking) from members of the public, non-governmental organizations, 
and the nuclear industry. A comment submission means a communication or 
document submitted to the NRC by an individual or entity, with one or 
more distinct comments addressing a subject or an issue. A comment, on 
the other hand, refers to statements made in the submission addressing 
a subject or issue.
    The NRC received more than 13,500 comment submissions, which appear 
to be variations of two letters with largely similar content. These 
comment submissions also contained approximately 100 separate comments. 
The NRC also received 66 additional comment submissions containing over 
100 comments. Finally, the NRC received four ``petitions'' to suspend 
or terminate this rulemaking, which are being treated as public 
comments. The petitions set forth approximately 39 comments. As stated 
in the proposed rule, ``Comments received after May 10, 2011 will be 
considered if it is practical to do so, but assurance of consideration 
of comments received after this date cannot be given.'' The NRC 
determined that it was practical to consider comment submissions 
received on or before June 30, 2011. Five of the comment submissions 
were received after the 75-day comment period closed, and the NRC has 
addressed these late-filed comment submissions as part of this final 
rule (the numbers above reflect those late-filed comments, which were 
deemed practical to consider). These late comment submissions consisted 
of one petition, two submissions requesting the NRC to reconsider 
comments made during the initial AP1000 DC rulemaking, and two 
submissions with supplemental information to support suspending this 
rulemaking. The NRC also received several comment submissions after 
June 30, 2011. The NRC deemed that it was not practical to consider, in 
this rulemaking, comments received after June 30, 2011 and, therefore, 
does not provide responses to those comments. The NRC has briefly 
reviewed them to ensure that they contain no health and safety matters.
    There were several commenters in favor of completing the AP1000 
rulemaking, while some were unconditionally opposed to completing the 
proposed amendment to the AP1000 design. The vast majority of 
commenters favored delaying (in some fashion) the AP1000 amendment 
rulemaking until lessons are learned from the Fukushima Daiichi Nuclear 
Power Plant (Fukushima) accident that occurred on March 11, 2011, and 
the NRC applies the lessons learned to U.S. nuclear power plants, 
including the AP1000 design.
    Before responding to specific comments based upon the Fukushima 
Daiichi Nuclear Power Plant Event, the NRC is providing this discussion 
about the ongoing actions underway in response to this event. The 
Commission created a Near-Term Task Force (NTTF) to conduct an analysis 
of the lessons that can be learned from the event. The task force was 
established to conduct a systematic and methodical review of NRC 
processes and regulations to determine whether the NRC should make 
additional improvements to its regulatory system. The NTTF issued a 
report (ADAMS Accession No. ML111861807) evaluating currently available 
technical and operational information from the event, and presented a 
set of recommendations to the Commission. The task force concluded that 
continued operation and continued licensing activities do not pose an 
imminent risk to public health and safety. Among other recommendations, 
the NTTF supports completing the AP1000 design certification rulemaking 
activity without delay (see pages 71-72 of the report).
    In an August 19, 2011, Staff Requirements Memoranda (SRM) (ADAMS 
Accession No. ML112310021), the Commission set forth actions related to 
the NTTF report together with a schedule for the conduct of those 
actions. Two of those actions have been completed and are documented in 
the following reports: ``Recommended Actions to Be Taken Without Delay 
from the Near-Term Task Force Report,'' September 9, 2011 (SECY-11-
0124) (ADAMS Accession No. ML11245A127) and ``Prioritization of 
Recommended Actions To Be Taken In Response to Fukushima Lessons 
Learned,'' October 3, 2011 (SECY-11-0137) (ADAMS Accession No. 
ML11269A204).
    The NTTF recommendations relevant to the AP1000 design 
certification are limited to: Seismic and flooding protection 
(Recommendation 2); mitigation of prolonged station blackout 
(Recommendation 4); and enhanced instrumentation and makeup capability 
for spent fuel pools (Recommendation 7). The task force concluded that, 
by the nature of its passive design and inherent 72-hour coping 
capability, the AP1000 design has many of the features and attributes 
necessary to address the Task Force recommendations, and the NRC 
concludes that no changes to the AP1000 DCR are required at this time. 
Moreover, even if the Commission concludes at a later time that some 
additional action is needed for the AP1000, the NRC has ample 
opportunity and legal authority to modify the AP1000 DCR to implement 
NRC-required design changes, as well as to take any necessary action to 
ensure that holders of COLs referencing the AP1000 also make the 
necessary design changes.
    The NRC organized the comments on the AP1000 amendment into the 
following subject areas: Fukushima-related, shield building, 
containment, severe accident mitigation design alternative (SAMDA), 
spent fuel, environmental, other AP1000 topics, and general concerns. 
Some comments opposed the AP1000 rulemaking until purported shield 
building flaws are corrected. Many comments opposed completing the 
AP1000 rulemaking for reasons outside the scope of this rulemaking. For 
example, many comments opposed the completion of the AP1000 rulemaking 
until there is resolution of high level radioactive waste storage 
issues.
    Due to the large number of comments received and the length of the 
NRC responses provided, this section of the statement of considerations 
(SOC) for the final rule amending the AP1000 design certification only 
provides a summary of the categories of comments with a general 
description of the resolution of those comments. A detailed description 
of comments and the NRC's response is contained in a comment response 
document, which is available electronically through ADAMS Accession No. 
ML113480018.

[[Page 82082]]

B. Description of Key Structures of the AP1000 Design

    This section is provided to help readers understand the issues and 
the NRC's responses. The following is a brief description of the three 
design features that were commented on, and a summary of the design 
changes that are being approved by the AP1000 amendment.
Containment
    The containment vessel is a single steel pressure vessel, inside 
which is located the reactor vessel with the nuclear fuel, the steam 
generators, the refueling water storage tank, and various equipment for 
power generation, refueling, and emergency response, and supporting 
electric power, control, and communications equipment.
    The steel containment building stands independently inside the 
shield building. The containment's primary purpose is to retain 
pressure up to the maximum ``design pressure'' should an accident occur 
in which the reactor vessel or associated equipment releases reactor 
coolant into the containment atmosphere. The containment also acts as 
the passive safety-grade interface to the ultimate heat sink.
    The primary containment vessel prevents the uncontrolled release of 
radioactivity to the environment. The AP1000 primary containment 
consists of a cylindrical steel shell with ellipsoidal upper and lower 
heads. The steel thickness is increased in the transition region where 
the cylindrical shell enters the foundation concrete to provide 
additional margin in consideration of corrosion.
    Safety-related coatings are applied to both the interior and 
exterior surfaces of the containment vessel. These coatings have 
several functions. For the exterior surface, the corrosion-resistant 
paint or coating for the containment vessel is specified to enhance 
surface wetability and film formation, as well as for corrosion 
protection. Wetability and film formation are important to the passive 
cooling function. For the interior containment surfaces, the coatings 
are designed to remain intact within the zone-of-influence of any 
postulated pipe break (or to result in settling of any resultant 
debris) to facilitate heat transfer to the containment vessel and for 
corrosion protection. Periodic inspections are required of the 
containment internal and external surfaces and of the coatings on those 
surfaces.
    As the interface to the ultimate heat sink (the surrounding 
atmosphere), the primary containment is an integral component of the 
passive containment cooling system. The exterior of the containment 
vessel provides a surface for evaporative film cooling and works in 
conjunction with the natural draft airflow created by the shield 
building baffle and chimney arrangement to reduce the pressure and 
temperature of the containment atmosphere following a design-basis 
accident (DBA). The source of water for the evaporative cooling is the 
passive containment cooling water storage tank, located at the top of 
the shield building.
    Design changes within the scope of the amendment with respect to 
the containment vessel are certain details about coatings with respect 
to long-term core cooling capability and the calculated peak accident 
pressure (from correction of errors). Other changes included addition 
of a vacuum relief system to provide protection for external pressure 
events.
Shield Building
    The shield building performs multiple functions (e.g., to provide a 
biological shield to high-energy radiation, to support the primary 
containment cooling water storage tank on the roof, to shield the steel 
containment from high-velocity debris that may be generated by 
tornadoes or other natural phenomena, to protect the containment from 
aircraft impact, and to function as a ``chimney'' to enhance airflow 
over the primary steel containment to remove heat from the containment 
and reduce containment pressure in the event that post-accident cooling 
of the containment would be necessary). While other designs have 
included shield buildings of reinforced concrete, with the exception of 
the AP600 design, they did not perform cooling functions. The shield 
building is not intended to be a pressure retaining structure or to 
mitigate the effects of a containment failure. The shield building 
construction is primarily a steel-concrete composite module wall, with 
a reinforced concrete roof and reinforced concrete where the wall meets 
the foundation. The wall is appropriately reinforced and sized where 
the composite wall module joins the reinforced concrete sections and as 
appropriate to accommodate seismic loads and aircraft loads. This 
design is new to the amendment; previously the structure was all 
reinforced concrete.
    The shield building and the containment are designed with a gap, or 
annulus, that ensures that both the shield building and steel 
containment are physically separate, excluding their foundation, and 
are considered to be ``freestanding.'' In the shield building, air 
flows from the environment through openings in the shield building 
wall. The air then flows down along an interior baffle, turns toward 
the steel containment vessel, and then rises alongside the steel 
containment vessel where it absorbs heat. This heated air naturally 
rises and is then exhausted through the chimney located in the center 
of the primary containment cooling water storage tank.
    Design changes to the passive containment cooling system and shield 
building principally involve the redesign of the shield building to a 
steel-composite design, with related changes to air inlet sizing, 
height of the building, and gratings above the chimney opening. Revised 
safety analyses were performed to confirm adequate containment pressure 
control, capability of the shield building to withstand external events 
(tornado, seismic), as well as aircraft impact assessment. The shield 
building functions to protect the containment and facilitate passive 
containment cooling were not changed in the current amendment.
Spent Fuel Pool
    The spent fuel pool (SFP) is a safety-related structure that is 
housed in the auxiliary building, which provides protection from 
aircraft impact or other external hazards.
    For the first 72 hours after loss of normal SFP cooling, including 
response to a station blackout (SBO) event, the SFP relies upon the 
natural heat capacity of the water in the pool to absorb the heat from 
spent fuel elements, and boil the water in the pool. Thus, the safety-
related means of heat removal for 72 hours is by heat-up of the volume 
of water in the pool and in safety-related water sources such as the 
cask washdown pit. The AP1000 design (as initially certified) included 
safety-related water level indication with readout and alarm in the 
main control room. A nonsafety-related spent fuel pool cooling system 
is also installed. Onsite, protected sources of water are available for 
up to 7 days, controlled from areas away from the pool. During high 
heat load conditions in the pool, two sources of alternating current 
(ac) power are required to be available. Water can be sprayed into the 
pool from two nozzle headers on opposite sides of the pool. A cross-
connection also exists to the residual heat removal system. Those 
design features needed to provide make-up water after 72 hours and up 
to 7 days, such as the passive containment cooling water ancillary 
storage tank, and ancillary diesel generators, are protected from 
external hazards including the

[[Page 82083]]

safe-shutdown earthquake (SSE), tornado, and flooding.
    Design changes within the scope of the current amendment are the 
number of fuel assemblies stored, the rack designs for new and spent 
fuel storage, the criticality analysis for spent fuel in the pool 
(including use of boron material attached to the storage cells), 
installation of spray headers, and credit for additional water sources 
for pool makeup.

C. Significant Public Comments and Overall NRC Responses

    Comment: Many comments noted the NRC staff nonconcurrence on the 
shield building design and requested that the NRC should reconsider the 
views expressed in the nonconcurrence.
    NRC Response: The NRC disagrees with these comments. Professional 
opinions may vary, and the NRC has mechanisms in place for making 
differing views known.
    NRC employees can choose to exercise the nonconcurrence process as 
a way of communicating their views and ensuring their opinions are 
heard by NRC management. The NRC staff individual who authored the 
nonconcurrence used this open process to express concerns regarding the 
safety of the AP1000 shield building design. The specific concerns and 
staff response to the nonconcurrence are publically available (ADAMS 
Accession No. ML103370648).
    The NRC concluded that the AP1000 shield building design is safe, 
meets the Commission's regulations, and provides reasonable assurance 
that the building will remain functional under design-basis loads. The 
comments did not offer new information on the matters related to the 
nonconcurrence nor did they include a rationale showing the NRC's 
resolution of the technical matters raised in the nonconcurrence to be 
incorrect. No change was made to the final rule, DCD, or environmental 
assessment (EA) as a result of these comments.
    Comment: One comment noted that the spent fuel racks' design in 
Revision 18 increased the density. The higher density fuel pools 
require boron shields between stored assemblies to reduce the risk of 
criticality. The comment stated that such re-racking introduces 
potential partial loss of cooling water, possible fire of spent fuel 
assemblies, and release of large inventories of cesium-137 and other 
radionuclides.
    NRC Response: The NRC agrees that, under the proposed amendment of 
the AP1000 DCR, the capacity of the spent fuel pool racks would be 
increased from 619 to 889 (rather than 884 as asserted by the comment) 
fuel assemblies, and that the increased density of fuel assemblies 
being stored in the spent fuel pool requires the use of boron shields 
as part of the amendment.
    However, the NRC disagrees with this comment's assertion that the 
increased capacity and density would introduce potential loss of 
cooling water, resulting in a possible fire of spent fuel assemblies 
and large releases of radionuclides. The comment did not explain how 
increased fuel capacity and concomitant increase in density of the 
spent fuel pool would ``introduce'' potential loss of cooling water as 
compared with the capacity and density described in DCD Revision 15. 
The NRC does not believe that the increased capacity and density leads 
to a new (previously un-described or unconsidered) way of losing spent 
fuel pool cooling water. The NRC evaluated the proposed increase in 
fuel assembly capacity and density, and the effectiveness of the 
Westinghouse-proposed boron shields to ensure against re-criticality of 
the spent fuel stored in the spent fuel pool. The AP1000 DCD Revision 
18 SFP criticality analysis was reviewed following the guidance found 
in NUREG-0800 Section 9.1.1, Revision 3, ``Criticality Safety of Fresh 
and Spent Fuel Storage and Handling,'' to ensure that the applicant is 
in compliance with the applicable regulations (General Design Criterion 
62, ``Prevention of Criticality in Fuel Storage and Handling,'' and 10 
CFR 50.68, ``Criticality Accident Requirements''). These requirements 
are generally performance-based with limitations on the reactivity 
values, and as such, there are no specific physical design requirements 
such as minimum geometric spacing which must be met. The AP1000 SFP 
criticality analysis demonstrates that, with the proposed storage 
arrangement of the SFP, the reactivity requirements are met, and no 
regulations are violated. Therefore, the NRC determined that that the 
AP1000 spent fuel pool storage arrangement is acceptable. No change was 
made to the rule, the DCD, or the EA as a result of this comment.
    Comment: Several comments stated that given the recent event at the 
Fukushima plant in Japan, the 75-day comment period is not adequate and 
should be extended.
    NRC Response: The NRC disagrees with this comment, and believes 
that the 75-day public comment period, which is consistent with most 
other NRC technical rulemakings, is adequate. The Commission 
established a NTTF to review relevant NRC regulatory requirements, 
programs, and processes, and their implementation, and to recommend 
whether the agency should make near-term improvements to its regulatory 
system. The public comment period for the proposed rule on the AP1000 
design certification amendment closed on May 10, 2011, and the NTTF 
issued its report (ML111861807) on July 12, 2011. The NTTF considered 
the AP1000 design certification amendment in its report and noted that 
it has passive safety systems. By nature of their passive designs and 
inherent 72-hour coping capability for core, containment, and spent 
fuel pool cooling, the AP1000 designs have many of the design features 
and attributes necessary to address the NTTF recommendations. The NTTF 
supports completing the AP1000 design certification rulemaking 
activities without delay.
    The NRC believes that the AP1000 final rulemaking can and should 
proceed without extending the public comment period because: (i) The 
NRC has determined that the AP1000 design certification amendment meets 
current regulations; (ii) the NRC will provide an opportunity for the 
public to provide input on NTTF recommendations, and (iii) if the NRC 
imposes additional requirements on the AP1000 design, existing 
regulations already define the process for doing so. No change was made 
to the rule, the DCD, or the EA as a result of this comment.
    Comment: One comment questioned whether the NRC endorsed NQA-1-1994 
for work performed for the AP1000 project, where the NRC documented 
that NQA-1-1994 adequately meets the NRC requirements in the Code of 
Federal Regulations, and whether the Westinghouse's AP1000 design meets 
the requirements of 10 CFR Part 50, Appendix B.
    NRC Response: The NRC has, in application-specific requests for NRC 
approval of quality assurance programs, approved the use of NQA-1-1994 
as an acceptable method to meet the requirements of Appendix B to 10 
CFR Part 50. The NRC's approvals of NQA-1-1994 have been documented in 
NRC SERs on those requests.
    The NRC believes that the AP1000 design meets the requirements of 
10 CFR Part 50, Appendix B. By letter dated February 23, 1996 (ADAMS 
Accession No. ML11280A309), the NRC issued a safety evaluation report 
approving Revision 1 of the Westinghouse Quality Systems Manual 
(Westinghouse Quality Assurance (QA) Manual). The Westinghouse QA 
Manual is based upon the guidance in NQA-1-1994. The NRC found that the 
Westinghouse QA Manual meets all the

[[Page 82084]]

requirements of Appendix B. In addition, the NRC concluded in its FSER 
for the amendment that Revision 5 of the Westinghouse Quality Systems 
Manual, as described in the AP1000 Design Control Document, Revision 
17, meets the criteria of Appendix B with respect to AP1000 quality 
assurance. No change was made to the final rule, the DCD, or the EA as 
a result of this comment.
    Comment: Several comments claimed the containment design was flawed 
because the containment cooling method includes convective air flow and 
because the steel containment could be subject to corrosion. As a 
result, they state that Westinghouse has not satisfactorily proved that 
the thin steel containment shell over the reactor would be effective 
during severe accidents.
    NRC Response: The NRC considers these comments to be outside the 
scope of the rulemaking amending the AP1000 DCR. These features of the 
AP1000 design that demonstrate that the containment shell would be 
effective during severe accident conditions, as well as resistant to 
corrosion have already been certified with Revision 15. The proposed 
amendment to the AP1000 design does not propose any modification to 
these features and, therefore, the comment is outside the scope of this 
rulemaking.
    The NRC considers a single metal containment vessel to be 
acceptable if it meets the requirements of the American Society of 
Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section 
III, Subsection NE. This part of the ASME Code contains requirements 
for the material, design, fabrication, examination, inspection, 
testing, and overpressure protection of metal containment vessels. Many 
such vessels are in use at operating nuclear power plants. The AP1000 
containment is designed to meet ASME requirements for a pressure of 6.9 
kPa (59 psi) and a temperature of 149 degrees C (300 degrees F). Its 
thickness includes an allowance for corrosion that may occur over the 
60-year design life of the plant.
    The AP1000 containment building has an additional function--
transferring heat from containment to the atmosphere. The staff has 
reviewed the applicant's analysis, which shows that the containment 
building and the shield building, working as a system, would transfer 
heat to the atmosphere during severe accidents as well as design-basis 
earthquakes. Experiments were conducted to demonstrate that these 
predictions are based upon physical phenomena that can be relied upon 
to work even when there is no ac power. In short, Westinghouse has 
demonstrated that the containment building is robust and will perform 
its safety functions effectively if a severe accident occurs at an 
AP1000 plant.
    The commenters did not offer any basis for Westinghouse to revise 
its design or for the NRC to revise its evaluation. No change was made 
to the final rule, the DCD, or the EA as a result of these comments.
    Comment: Many comments stated that Westinghouse has not proven that 
the reactor could be properly cooled in conditions similar to those at 
Fukushima.
    NRC Response: The NRC considers these comments to be outside the 
scope of the rulemaking amending the AP1000 DCR. The Fukushima event 
involved an extended SBO (loss of offsite and onsite ac power). 
Westinghouse has shown that the AP1000 includes design features that 
keep the reactor properly cooled under these conditions. The features 
of the AP1000 design ensuring that the reactor can be properly cooled 
in an extended SBO are already part of the certified design for the 
AP1000, and are not being changed or modified by this final rule 
amending the AP1000 design. Therefore, these comments are out of scope 
for this rulemaking.
    In addition, even if these comments are assumed to be within the 
scope of the rulemaking, the NRC disagrees with the comment. If a 
severe accident occurs, seriously damaging the core, the AP1000 
containment can be adequately cooled for 3 days--even if a loss-of-
coolant accident (LOCA) occurred and without any ac power--because the 
AP1000 containment is cooled by gravity-fed water from a tank located 
at the top of the containment. After 3 days with no ac power, only a 
small ``ancillary'' generator is needed. This generator is used to 
power a small pump that re-fills the tank that supplies water to the 
outside surface of the containment. The generator could be brought to 
the site; however, in an AP1000 design, two such generators are 
installed in a seismically qualified structure (along with fuel and 
supporting equipment). After 1 week, the containment can be cooled 
indefinitely as long as fuel for at least one ancillary generator is 
provided and there is water to replenish the water tank above the 
shield building, as discussed in the DCD.
    These comments did not present any basis that would support an NRC 
determination that the AP1000 design is deficient in this regard. No 
change was made to the final rule, the DCD, or the EA as a result of 
these comments.
    Comment: Some comments stated that there are significant unresolved 
technical issues related to Revision 19 changes and that the NRC has 
not fully disclosed its analysis of these weaknesses, and the existence 
of such weaknesses is evidenced by the concerns identified by Dr. Susan 
Sterrett, Mr. Arnie Gundersen of Fairewinds Associates, and Dr. John 
Ma.
    NRC Response: The NRC disagrees with this comment. As discussed in 
more detail in the comment response document, the NRC concludes these 
issues were either resolved as part of the initial AP1000 rulemaking, 
or are resolved as part of this rulemaking. Elsewhere in this notice, 
NRC discusses the Revision 19 changes and summarizes the response to 
the other technical issues.
    Comment: Many comments expressed views that nuclear power plants 
are too expensive or too dangerous, or that alternative energy sources 
should be pursued.
    NRC Response: The NRC considers these comments to be outside the 
scope of the rulemaking amendment the AP1000 DCR. The NRC has concluded 
that the AP1000 design meets its regulatory requirements, and the 
comments do not offer any basis that this is not supported. Other 
issues about expense or alternative energy sources are outside the 
scope of the rulemaking amending the AP1000 DCR. A design certification 
rule is not an NRC license or authorization for construction or 
operation. No change was made to the final rule, the DCD, or the EA as 
a result of these comments.
    Comment: Many comments expressed concerns about nuclear waste.
    NRC Response: These comments address matters that are outside the 
scope of the rulemaking amending the AP1000 DCR. These comments do not 
address whether the AP1000 design changes, as reflected in the 
amendment application and evaluated in the NRC's SER and EA, meet the 
applicable NRC requirements. No change was made to the final rule, the 
DCD, or the EA as a result of these comments.

III. Discussion

A. Technical Evaluation of Westinghouse Amendment to the AP1000 Design

    Westinghouse's request to amend the AP1000 design contained several 
classes of changes. Each class is discussed below:
Editorial Changes
    Westinghouse requested changes to the AP1000 DCD to correct 
spelling,

[[Page 82085]]

punctuation, grammar, designations, and references. None of these 
changes make substantive changes to the certified design, and NUREG-
1793, ``Final Safety Evaluation Report Related to Certification of the 
AP1000 Standard Design,'' Supplement 2 (SER) does not address these 
changes.
Changes To Address Consistency and Uniformity
    Westinghouse requested changes to the currently-approved AP1000 DCD 
(Revision 15) to achieve consistency and uniformity in the description 
of the certified design throughout the DCD. For example, a change to 
the type of reactor coolant pump (RCP) motor is evaluated in Chapter 5 
of the SER on the application for the AP1000 amendment; Westinghouse 
requested that wherever this RCP motor is described in the DCD, the new 
description of the changed motor be used. The NRC reviewed the proposed 
change (to be used consistently throughout the DCD) to ensure that the 
proposed changes needed for uniformity and consistency are technically 
acceptable and do not adversely affect the previously approved design 
description. The NRC's bases for approval of these changes are set 
forth in the SER for the AP1000 amendment.
    Substantive Technical Changes to the AP1000 Design (other than 
those needed for compliance with the AIA rule)
    Among the many technical changes to the currently-approved DCD 
Revision 15 that are proposed by Westinghouse for inclusion in Revision 
19 of the AP1000 DCD, the NRC selected 15 substantive changes for 
specific discussion in this final rule document, based on their safety 
significance:
     Removal of HFE DAC from the DCD.
     Change to I&C DAC and Inspections, Tests, Analyses, and 
Acceptance Criteria (ITAACs).
     Minimization of Contamination.
     Extension of Seismic Spectra to Soil Sites and Changes to 
Stability and Uniformity of Subsurface Materials and Foundations.
     Long-Term Cooling.
     Control Room Emergency Habitability System.
     Changes to the Component Cooling Water System (CCWS).
     Changes to I&C Systems.
     Changes to the Passive Core Cooling System (PCCS)--Gas 
Intrusion.
     Integrated Head Package (IHP)--Use of the QuickLoc 
Mechanism.
     Reactor Coolant Pump Design.
     Reactor Pressure Vessel (RPV) Support System.
     SFP Decay Heat Analysis and Associated Design Changes.
     Spent Fuel Rack Design and Criticality Analysis.
     Vacuum Relief System.
    The NRC evaluated each of the proposed changes and concluded that 
they are acceptable. The NRC's bases for approval of these changes are 
set forth in the FSER for the AP1000 amendment and are summarized in 
Section XII, ``Backfitting and Issue Finality,'' of this document, as 
part of the discussion as to how each of the 15 changes satisfy the 
criteria in 10 CFR 52.63(a).
Changes To Address Compliance With the AIA Rule
    Westinghouse requested changes to the AP1000 design in order to 
comply with the requirements of the AIA rule, 10 CFR 50.150. The NRC 
confirmed that Westinghouse has adequately described key AIA design 
features and functional capabilities in accordance with the AIA rule 
and conducted an assessment reasonably formulated to identify design 
features and functional capabilities to show, with reduced use of 
operator action, that the facility can withstand the effects of an 
aircraft impact. In addition, the NRC determined that there will be no 
adverse impacts from complying with the requirements for consideration 
of aircraft impacts on conclusions reached by the NRC in its review of 
the original AP1000 design certification. The NRC's bases for approval 
of these changes are set forth in the FSER for the AP1000 amendment. As 
a result of these changes, the AP1000 design will achieve the 
Commission's objectives of enhanced public health and safety and 
enhanced common defense and security through improvement of the 
facility's inherent robustness to the impact of a large commercial 
aircraft at the design stage.
AP1000 Design Control Document Changes Since Revision 18
Introduction
    The NRC staff's (staff's) review of DCD Revision 18 (ADAMS 
Accession No. ML103260072) identified a few areas where the DCD wording 
should be revised for clarity, to resolve internal inconsistencies, or 
to provide updated versions of referenced technical reports. In 
addition, three technical issues were noted: a load combination for the 
shield building, the method used to evaluate tank sloshing, and 
containment peak pressure analysis error correction. As a result of 
these activities, Westinghouse submitted Revision 19 of the DCD on June 
13, 2011 (ADAMS Accession No. ML11171A315), and this is the version of 
the DCD that is being certified by this final rule. The NRC has 
determined that none of the changes from Revision 18 to Revision 19 of 
the DCD require an additional opportunity for public comment. These 
changes, which are organized into five subject areas, are discussed 
below.
    The NRC has also determined, in its review of Revision 19, that 
three of the five subject areas must be identified as Tier 2* matters 
in the Section VIII of the final rule. The NRC has determined that none 
of the three new Tier 2* designations in Section VIII.B.6 of the rule 
require an additional opportunity for public comment. The bases for the 
NRC's determinations are set forth below.
DCD Structural Design Information and Shield Building Tier 2* 
Information
    Revision 18 of the DCD moved some design details regarding 
structures, including the shield building, from supporting Westinghouse 
documents into the DCD itself. Some of the details were marked as Tier 
2*, based upon initial NRC staff comments. For example, information 
about penetrations was brought out of TR-9 into the DCD, and the shield 
building structural description was added to Section 3.8.4 in Revision 
18.
    The advanced final safety evaluation report (AFSER) included a 
confirmatory item to verify that the DCD appropriately reflected all 
necessary details regarding the structural design and shield building, 
and clearly showed which design details were to be Tier 2* (see AFSER 
Section 3.8.4 under ADAMS Accession No. ML103430502). The staff was 
able to close the confirmatory item after Westinghouse submitted 
Revision 19 of the DCD by verifying the appropriate structural details 
were in the DCD and the design details were identified as Tier 2*. 
These DCD revisions enhanced the description of the design and were not 
a result of changes to the design itself. Westinghouse report GLR-603, 
submitted on March 28, 2011 (ADAMS Accession No. ML110910541), was the 
nonproprietary version of the report that presented shield building 
information to be made Tier 2*, in addition to the DCD information 
separately added to Section 3.8 and Appendix 3H. The scope of the 
report was materials, connection details, and tie bar spacing.
    Use of steel composite modules was the heart of the revised shield 
building design, including the NRC's determination that existing 
consensus standards are not techinically applicable in all respects to 
the analysis for such modules. This was a key factor in the NRC 
conclusion that design details about the shield building are Tier 2* so

[[Page 82086]]

that any future changes to that information by the COL would receive 
prior staff review and approval. The staff considered the existing rule 
language as it relates to Tier 2* designation for structural 
information. For example, the existing rule includes use of ACI-349, 
definition of critical locations and thicknesses, nuclear island 
structural dimensions, and design summary of critical sections. Some of 
the critical sections are within the shield building, and ACI-349 was 
part of the design criteria. However, the staff concluded, during the 
course of final rule preparation, that the rule would be more clear if 
the use of steel composite module details that are designated in the 
DCD as Tier 2* was explicitly stated in the final rule (at Section 
VIII.B.6.c) and requested that Westinghouse designate this information 
at Tier 2* in Revision 19 of the DCD. Westinghouse included this change 
in Revision 19. As a result of the Tier 2* markings, a conforming 
change is being made to the final rule language to Section VIII.B.6.c 
about the categories of Tier 2* information that would expire at fuel 
load.
    The NRC does not believe that the DCD changes or the designation of 
this information as Tier 2* in the final rule require re-noticing. The 
material was publicly available in referenced reports, the staff's 
intention that the composite steel module design be designated Tier 2* 
was clear at the time of the public comment period, and there were no 
comments regarding the extent of Tier 2* inclusion in Revision 18.
Implementation of Revision 18 Commitments for the Shield Building
Load Combinations for Shield Building
    In the NRC staff's follow-up to an apparent editorial error in a 
table in the Westinghouse shield building report, the staff determined 
that Westinghouse had not documented in its calculations the numerical 
combination of the loads for external temperature conditions (minus 40 
degrees F) and a safe-shutdown earthquake (SSE). On April 12, 2011, the 
staff requested Westinghouse to document in the shield building report 
the numerical combination of loads for extreme ambient thermal loads 
and SSE loads, as specified in DCD Table 3.8.4-1 for steel structures 
and Table 3.8.4-2 for concrete structures. See meeting summary dated 
May 17, 2011 (ADAMS Accession No. ML111440298). By letter dated June 
15, 2011, Westinghouse responded to this request (ADAMS Accession No. 
ML111950098), and concluded that the current design is acceptable when 
the load combinations are explicitly analyzed. The analysis results are 
discussed in detail in Revision 4 of the shield building report. 
Changes were made to the DCD to reflect the results of this load 
combination analysis, but the changes did not involve any changes to 
the methodology or the design of the shield building. The specific DCD 
changes were the addition of Section 3.8.4.5.5 to discuss the load 
combination analysis, and updating of tables of results in Appendix 3H. 
No change to the language of the AP1000 DCR in 10 CFR part 52, Appendix 
D was made as a result of the DCD changes.
    The NRC does not believe these DCD changes require re-noticing 
because Revision 18 of the DCD stated that the design would be verified 
using the required load combinations, and these load combinations had 
previously been approved by the NRC for use in AP1000 analyses similar 
to those for the shield building elements requiring reanalysis. There 
was no change to the methodology or the actual design of the shield 
building was needed, and there was no change to the language of the 
AP1000 DCR. The also NRC notes that the June 16, 2011 ``petition'' 
(filed by John Runkle) that requested the NRC terminate the rulemaking 
specifically raised the three technical issues in Revision 19, 
including the load combination topic.
Passive Containment Cooling Water Storage Tank
    During the analysis of the thermal plus earthquake load combination 
for the passive containment cooling water storage tank (located on top 
of the shield building), Westinghouse determined that it had not 
performed an analysis of hydrodynamic loads using an equivalent static 
analysis as stated in Westinghouse's response (ADAMS Accession No. 
ML102650098) to an action item from the NRC's shield building report 
review (documented in AFSER Chapter 3, ADAMS Accession No. 
ML103430502). Instead, the analysis had been done by response spectrum 
analysis. Both the equivalent static method and the response spectrum 
method had previously been approved by the NRC for use in the AP1000 
design for structural analyses as described in Revision 18 of the DCD. 
This issue was discussed in a May 17, 2011, public meeting (see meeting 
summary dated May 26, 2011 (ADAMS Accession No. ML111430775)). In 
response, Westinghouse performed the analysis with the equivalent 
static method and presented the results in the revised shield building 
report and in DCD Revision 19 as follows. The use of the equivalent 
static method for the tank is discussed in Section 3.7 and Appendix 3G, 
and a table and figure were added to Appendix 3H. The revised shield 
building report included the results of the load combination for the 
containment cooling water storage tank using the equivalent static 
analytical method, which demonstrated that the design remained adequate 
when evaluated using the equivalent static analytical method. No change 
to the language of the AP1000 DCR in 10 CFR Part 52, Appendix D was 
made as a result of the DCD changes.
    The NRC does not believe these DCD changes require renoticing. 
Revision 18 of the DCD stated that the design would be verified through 
the use of the equivalent static method, and that method had been 
previously approved by the NRC for AP1000 analyses equivalent to that 
peformed for the containment cooling water tank. No change to the 
actual design of the tank was needed, and there was no change to the 
language of the AP1000 DCR. The NRC also notes that one of the 
petitions (dated June 16, 2011) that the NRC is responding to in the 
comment response document specifically raised this issue and the NRC 
has provided an answer similar to that described above.
Debris Limits
    In its December 20, 2010, letter on long-term core cooling (ADAMS 
Accession No. ML103410348), the ACRS concluded that the regulatory 
requirements for long-term core cooling for design-basis accidents have 
been adequately met, based on cleanliness requirements specified in the 
amendment. In particular, the amount of latent debris that might be 
present in the containment is an important parameter. The ACRS further 
stated that any future proposed relaxation of the cleanliness 
requirements will require substantial additional data and analysis. In 
their January 24, 2011, (ADAMS Accession No. ML110170006) report on the 
Vogtle COL application, which references the AP1000 design, the ACRS 
recommended that the containment interior cleanliness limits on latent 
debris should be included in the Technical Specifications (TSs) for the 
Vogtle plant.
    In a letter dated February 23, 2011 (ADAMS Accession No. 
ML110590455), Westinghouse proposed DCD markups to designate 
information in Section 6.3 including debris sources such as latent 
debris (and the amount of fiber) as Tier 2*. Revision 19 of the DCD 
includes changes to mark selected information as Tier 2*.

[[Page 82087]]

    The NRC made a conforming change to the final rule language to 
provide a new item as Section VIII.B.6.b(7), ``Screen design 
criteria,'' for this new type of Tier 2* information. The NRC believes 
that inclusion of debris limits in the AP1000 DCD as Tier 2* 
information, rather than including such limits in each plant 
referencing the AP1000, represents a better regulatory approach for 
achieving the intent of the ACRS. Inclusion of debris limits in the 
AP1000 and its designation as Tier 2* would ensure that there is 
consistency across all referencing plants with repect to debris 
control, and ensures NRC regulatory control of any future relaxations 
of the limits, as discussed in the staff's March 3, 2011, response to 
the ACRS (ADAMS Accession No. ML110350198).
    The NRC does not believe that this change to the DCD marking or to 
the final rule language requires renoticing because the ACRS letter, 
the staff response, and the Westinghouse letter, were all publicly 
available during the comment period, and the public had a fair 
opportunity to comment on this matter. In this regard, the staff notes 
that the April 6, 2011, ``petition'' (filed by John Runkle) that 
requested the NRC to suspend the AP1000 amendment rulemaking, included 
discussion about this topic with specific reference to the ACRS letter 
(ADAMS Accession No. ML11108A077). Numerous other comment submissions 
pointed to this petition as part of their comments. This lends support 
to the NRC's view that the public had adequate notice and an 
opportunity to comment on this matter. In addition, the inclusion of 
debris limits as Tier 2* represents a new limitation, not present in 
the prior revisions of the AP1000 DCD, which will require a referencing 
COL holder to use debris limits as specified in the AP1000 DCD. Given 
that the designation of the debris limits as Tier 2* represents a new 
restriction agreed to by Westinghouse, a matter on which the NRC 
received public comment, the staff does not believe that an additional 
opportunity for public comment need be provided on the inclusion of 
debris limits in Revision 19 of the DCD and the designation of those 
limits as Tier 2*.
Heat Sinks and Containment Pressure Analysis
    In its December 13, 2010, letter on the AP1000 design 
certification, the ACRS identified an error in the previously certified 
Revision 15 of the DCD (ADAMS Accession No. ML103410351) concerning the 
containment cooling analysis. The error affected the time at which 
steady-state film coverage is achieved on the exterior of the 
containment vessel. In a February 5, 2011, letter, the NRC staff agreed 
with the ACRS, and indicated that Westinghouse agreed that the error 
existed and should be corrected. The letter also indicated that the NRC 
staff would monitor Westinghouse's corrective actions and review any 
needed revisions to the DCD (ADAMS Accession No. ML103560411).
    In the course of correcting the steady-state film coverage error, 
after the proposed rule was published, Westinghouse identified other 
errors and modeling updates in supporting analyses that affected the 
calculated post-accident peak containment pressure (the highest peak 
pressure in the event of a large break loss-of-coolant accident). The 
net impact of correcting the steady-state film error and the subsequent 
Westinghouse-identified errors and modeling updates was an increase in 
calculated peak containment pressure from 57.8 psig to 59.2 psig, which 
would have exceeded the 59 psig post-accident peak containment pressure 
acceptance criterion in the existing AP1000 DCR.
    Therefore, as part of the revised analysis to account for all the 
identified errors, Westinghouse relied upon a limited number of 
existing structural elements (gratings) within the containment as heat 
sinks, in order to remain within the 59 psig post-accident peak 
containment pressure acceptance criterion. Westinghouse's revised 
analysis used the NRC-approved methodology in the existing AP1000 DCR 
containment pressure calculation, and the method for crediting heat 
sink capacity as described in Westinghouse documents WCAP-15846 
(proprietary) and WCAP-15862 (nonproprietary) ``WGOTHIC Application to 
AP600 and AP1000,'' Revision 1, March 2004, which are incorporated by 
reference in the previously certified Revision 15 of the DCD. In 
addition, the Westinghouse-revised analysis used the NRC-approved 59 
psig post-accident peak containment pressure acceptance criterion in 
the existing AP1000 DCD, Revision 15.
    The staff safety evaluation of the Westinghouse revised analysis is 
included in Sections 23.X and 23.Y of the FSER (ADAMS Accession No. 
ML112061231). Table 6.2.1.1-10 of Revision 19 of the DCD includes the 
credited elements. The ACRS reviewed the Westinghouse corrections, and 
agreed that Westinghouse's revised analysis continues to demonstrate 
that the containment will be able to withstand the post-accident peak 
containment pressure (ADAMS Accession No. ML11256A180), and that the 
reevaluated pressure is based on a sufficiently conservative 
methodology. The final AP1000 rule language designates this ``heat sink 
data for containment analysis'' by adding it as a new Tier 2* item in 
Section VIII.B.6.b(8). The NRC decided to control any future changes to 
the credited elements by designating the material as Tier 2* because 
the geometry and location of the heat sinks could impact their 
effectiveness.
    The NRC does not believe that the revisions to Table 6.2.1.1-10 of 
Revision 19 of the DCD require renoticing for several reasons. The 
gratings to be credited as heat sinks were already part of the approved 
AP1000 design and were not part of the proposed amendment to the AP1000 
DCR described design. Thus, the actual DCD did not involve any new 
design elements being added. The use of heat sinks as part of the 
containment pressure calculation and the method for crediting heat sink 
capacity were described in the DCD Revision 15. The criterion for 
evaluating the acceptability of the change continues to be the 
calculated post-accident peak containment pressure of 59 psig. 
Therefore, the revised Westinghouse analysis did not involve the use of 
any previously unapproved design methodologies or acceptance criteria; 
the methodology used and the acceptance criterion (59 psig post-
accident peak containment pressure) is in the already-approved AP1000 
DCR. Finally, crediting of the gratings as heat sinks in the revised 
analysis did not introduce any new safety issues not previously 
addressed. Therefore, the NRC does not believe that opportunity for 
public comment need be provided on the rule language change.
    The NRC does not believe that the designation of the heat sink as 
Tier 2* requires renoticing. As discussed above, the Tier 2* change is 
a direct result of the Westinghouse revised analysis that does not 
warrant an additional opportunity for public comment. The designation 
of this information as Tier 2* adds a new limitation, not present in 
the prior revisions of the AP1000 DCD, which limits a referencing 
combined license applicant/holder to alter the heat sink information 
for the grating and all other heat sinks credited in the containment 
peak pressure analysis. Given that the designation of the heat sink 
information as Tier 2* represents a new restriction agreed to by 
Westinghouse, the staff does not believe that opportunity for public 
comment need be provided on the Westinghouse revised analysis and the 
designation of the heat sink information as Tier 2*.

[[Page 82088]]

B. Changes to Appendix D

1. Scope and Contents (Section III)
    The purpose of Section III is to describe and define the scope and 
contents of this design certification and to set forth how 
documentation discrepancies or inconsistencies are to be resolved. 
Paragraph A is the required statement of the Office of the Federal 
Register (OFR) for approval of the incorporation by reference of Tier 
1, Tier 2, and the generic TSs into this appendix. The NRC is updating 
the revision number of the DCD that is incorporated by reference to the 
revision Westinghouse provided to the NRC in its application for 
amendment to this DCR. In this final rule, the revision of the DCD that 
is incorporated by reference is Revision 19.
    The effect of this incorporation by reference is that the 
incorporated material has the same legal status as if it were published 
in the Federal Register and in NRC's regulations at 10 CFR part 52. 
This material, like any other properly issued regulation, has the force 
and effect of law. The AP1000 DCD was prepared to meet the technical 
information contents of application requirements for design 
certifications under 10 CFR 52.47(a) and the requirements of the OFR 
for incorporation by reference under 1 CFR part 51. One requirement of 
the OFR for incorporation by reference is that the applicant for the 
design certification (or amendment to the design certification) makes 
the generic DCD available upon request after the final rule becomes 
effective. Therefore, paragraph A identifies a Westinghouse 
representative to be contacted to obtain a copy of the AP1000 DCD.
    The AP1000 DCD is electronically accessible under ADAMS Accession 
No. ML11171A500, at the OFR, and at www.regulations.gov by searching 
under Docket ID NRC-2010-0131. Copies of the generic DCD are also 
available at the NRC's PDR. Questions concerning the accuracy of 
information in an application that references Appendix D will be 
resolved by checking the master copy of the generic DCD in ADAMS. If a 
generic change (rulemaking) is made to the DCD by the revision process 
provided in Section VIII of Appendix D, then, at the completion of the 
rulemaking process, the NRC would request approval of the Director, 
OFR, for the revised incorporation by reference and revise its copies 
of the generic DCD, provide a revised copy to the OFR, and notify the 
design certification applicant to change its copy. The Commission 
requires that the design certification applicant maintain an up-to-date 
copy of the master DCD under Section X.A.1 of Appendix D because it is 
likely that most applicants intending to reference the standard design 
will obtain the generic DCD from the design certification applicant. 
Plant-specific changes to and departures from the generic DCD will be 
maintained by the applicant or licensee that references Appendix D in a 
plant-specific DCD under Section X.A.2 of Appendix D.
    The NRC is also making a change to paragraph D. Paragraph D 
establishes the generic DCD as the controlling document in the event of 
an inconsistency between the DCD and the design certification 
application or the FSER for the certified standard design. The revision 
renumbers paragraph D as paragraph D.1, clarifies this requirement as 
applying to the initial design certification, and adds a similar 
paragraph D.2 to indicate that this is also the case for an 
inconsistency between the generic DCD and the amendment application and 
the NRC's associated FSER for the amendment.
2. Additional Requirements and Restrictions (Section IV)
    Section IV of this appendix sets forth additional requirements and 
restrictions imposed upon an applicant who references this appendix. 
Paragraph A sets forth the information requirements for these 
applicants. Paragraph A.3 requires the applicant to physically include, 
not simply reference, the proprietary information (PI) and safeguards 
information (SGI) referenced in the AP1000 DCD, or its equivalent, to 
ensure that the applicant has actual notice of these requirements. The 
NRC revised paragraph A.3 to indicate that a COL applicant must 
include, in the plant-specific DCD, the sensitive unclassified non-
safeguards information (SUNSI) (including PI) and SGI referenced in 
AP1000 DCD. This revision addresses a wider class of information 
(SUNSI) to be included in the plant-specific DCD, rather than limiting 
the required information to PI. The requirement to include SGI in the 
plant-specific DCD would not change.
    The NRC also added a new paragraph A.4 to indicate requirements 
that must be met in cases where the COL applicant is not using the 
entity that was the original applicant for the design certification (or 
amendment) to supply the design for the applicant's use. Paragraph A.4 
requires that a COL applicant referencing Appendix D to 10 CFR Part 52 
include, as part of its application, a demonstration that an entity 
other than Westinghouse is qualified to supply the AP1000 certified 
design unless Westinghouse supplies the design for the applicant's use. 
In cases where a COL applicant is not using Westinghouse to supply the 
AP1000 certified design, this information is necessary to support any 
NRC finding under 10 CFR 52.73(a) that the entity is qualified to 
supply the certified design.
3. Applicable Regulations (Section V)
    The purpose of Section V is to specify the regulations applicable 
and in effect when the design certification is approved (i.e., as of 
the date specified in paragraph A, which is the date of publication of 
this rule in the Federal Register). The NRC is redesignating paragraph 
A as paragraph A.1 to indicate that this paragraph applies to that 
portion of the design that was certified under the initial design 
certification. The NRC is further adding a new paragraph A.2, similar 
to paragraph A.1, to indicate the regulations that would apply to that 
portion of the design within the scope of this amendment, as approved 
by the Commission and signed by the Secretary of the Commission.
4. Issue Resolution (Section VI)
    The purpose of Section VI is to identify the scope of issues that 
were resolved by the Commission in the original certification 
rulemaking and, therefore, are ``matters resolved'' within the meaning 
and intent of 10 CFR 52.63(a)(5).
    Paragraph B presents the scope of issues that may not be challenged 
as a matter of right in subsequent proceedings and describes the 
categories of information for which there is issue resolution. 
Paragraph B.1 provides that all nuclear safety issues arising from the 
Atomic Energy Act of 1954 (the Act), as amended, that are associated 
with the information in the NRC's FSER related to certification of the 
AP1000 standard design (ADAMS Accession No. ML112061231) and the Tier 1 
and Tier 2 information and the rulemaking record for Appendix D to 10 
CFR part 52, are resolved within the meaning of 10 CFR 52.63(a)(5). 
These issues include the information referenced in the DCD that are 
requirements (i.e., ``secondary references''), as well as all issues 
arising from PI and SGI, which are intended to be requirements. 
Paragraph B.2 provides for issue preclusion of PI and SGI.
    The NRC revised paragraph B.1 to extend issue resolution to the 
information contained in the NRC's FSER (Supplement No. 2), Appendix 1B 
of Revision 19 of the generic DCD, and the rulemaking record for this 
amendment. In addition, the NRC revised paragraph B.2 to extend issue

[[Page 82089]]

resolution to the broader category of SUNSI, including PI, referenced 
in the generic DCD.
    The NRC also revised paragraph B.7, which identifies as resolved 
all environmental issues concerning severe accident mitigation design 
alternatives (SAMDAs) arising under the National Environmental Policy 
Act of 1969 (NEPA) associated with the information in the NRC's final 
EA for the AP1000 design and Appendix 1B of the generic DCD (Revision 
15) for plants referencing Appendix D to 10 CFR part 52 whose site 
parameters are within those specified in the SAMDA evaluation. The NRC 
revised this paragraph to identify all resolved environmental issues 
concerning SAMDA associated with the information in the NRC's final EA 
for this amendment and Appendix 1B of Revision 19 of the generic DCD 
for plants referencing Appendix D to 10 CFR part 52 whose site 
parameters are within those specified in the SAMDA evaluation.
    Finally, the NRC is revising paragraph E, which provides the 
procedure for an interested member of the public to obtain access to 
SUNSI (including PI) and SGI for the AP1000 design in order to request 
and participate in proceedings, as identified in paragraph B, involving 
licenses and applications that reference Appendix D to 10 CFR part 52. 
The NRC is replacing the current information in this paragraph with a 
statement that the NRC will specify at an appropriate time the 
procedure for interested persons to review SGI or SUNSI (including PI) 
for the purpose of participating in the hearing required by 10 CFR 
52.85, the hearing provided under 10 CFR 52.103, or in any other 
proceeding relating to Appendix D to 10 CFR part 52 in which interested 
persons have a right to request an adjudicatory hearing. The NRC will 
follow its current practice of establishing the procedures by order 
when the notice of hearing is published in the Federal Register (e.g., 
Florida Power and Light Co., Combined License Application for the 
Turkey Point Units 6 and 7, Notice of Hearing, Opportunity To Petition 
for Leave To Intervene and Associated Order Imposing Procedures for 
Access to Sensitive Unclassified Non-Safeguards Information and 
Safeguards Information for Contention Preparation (75 FR 34777; June 
18, 2010); Notice of Receipt of Application for License; Notice of 
Consideration of Issuance of License; Notice of Hearing and Commission 
Order and Order Imposing Procedures for Access to Sensitive 
Unclassified Non-Safeguards Information and Safeguards Information for 
Contention Preparation; In the Matter of AREVA Enrichment Services, LLC 
(Eagle Rock Enrichment Facility) (74 FR 38052; July 30, 2009)).
    In the four currently approved design certifications (10 CFR part 
52, Appendices A through D), paragraph E presents specific directions 
on how to obtain access to PI and SGI on the design certification in 
connection with a license application proceeding referencing that DCR. 
The NRC is changing this because these provisions were developed before 
the terrorist events of September 11, 2001. After September 11, 2001, 
Congress changed the statutory requirements governing access to SGI, 
and the NRC revised its rules, procedures, and practices governing 
control and access to SUNSI and SGI. The NRC now believes that generic 
direction on obtaining access to SUNSI and SGI is no longer appropriate 
for newly approved DCRs. Accordingly, the specific requirements 
governing access to SUNSI and SGI contained in paragraph E of the four 
currently approved DCRs will not be included in the DCR for the AP1000. 
Instead, the NRC will specify the procedures to be used for obtaining 
access at an appropriate time in the COL proceeding referencing the 
AP1000 DCR. The NRC will include the new rule language in any future 
amendments or renewals of the currently existing DCRs, as well as in 
new (i.e., initial) DCRs. However, the NRC will not initiate rulemaking 
to change paragraph E of the existing DCRs, in an effort to minimize 
unnecessary resource expenditures by both the original DCR applicant 
and the NRC.
5. Processes for Changes and Departures (Section VIII)
    The purpose of Section VIII of this appendix is to set forth the 
processes for generic changes to, or plant-specific departures 
(including exemptions) from, the DCD. The Commission adopted this 
restrictive change process in order to achieve a more stable licensing 
process for applicants and licensees that reference this DCR. The 
change processes for the three different categories of Tier 2 
information, namely, Tier 2, Tier 2*, and Tier 2* with a time of 
expiration, are presented in paragraph B.
    Departures from Tier 2 that a licensee may make without prior NRC 
approval are addressed under paragraph B.5 (similar to the process in 
10 CFR 50.59). The NRC is modifying Section VIII to address the change 
control process specific to departures from the information required by 
10 CFR 52.47(a)(28) to address the NRC's AIA requirements in 10 CFR 
50.150. Specifically, the NRC revised paragraph B.5.b to indicate that 
the criteria in this paragraph for determining if a proposed departure 
from Tier 2 requires a license amendment do not apply to a proposed 
departure affecting information required by 10 CFR 52.47(a)(28) to 
address 10 CFR 50.150. In addition, the NRC redesignated paragraphs 
B.5.d, B.5.e, and B.5.f as paragraphs B.5.e, B.5.f, and B.5.g, 
respectively, and added a new paragraph B.5.d. Paragraph B.5.d requires 
an applicant or licensee who proposed to depart from the information 
required by 10 CFR 52.47(a)(28) included in the final safety analysis 
report (FSAR) for the standard design certification to consider the 
effect of the changed feature or capability on the original assessment 
required by 10 CFR 50.150(a). The FSAR information required by the AIA 
rule, which is subject to this change control requirement, includes the 
descriptions of the design features and functional capabilities 
incorporated into the final design of the nuclear power facility and 
the description of how the identified design features and functional 
capabilities meet the assessment requirements in 10 CFR 50.150(a)(1). 
The objective of the change controls is to determine whether the design 
of the facility, as changed or modified, is shown to withstand the 
effects of the aircraft impact with reduced use of operator actions. In 
other words, the applicant or licensee must continue to show, with the 
modified design, that the acceptance criteria in 10 CFR 50.150(a)(1) 
are met with reduced use of operator actions. The AIA rule does not 
require an applicant or a licensee implementing a design change to redo 
the complete AIA to evaluate the effects of the change. The NRC 
believes it may be possible to demonstrate that a design change is 
bounded by the original design or that the change provides an 
equivalent level of protection, without redoing the original 
assessment.
    Consistent with the NRC's intent when it issued the AIA rule, under 
this section, plant-specific departures from the AIA information in the 
FSAR would not require a license amendment, but may be made by the 
licensee upon compliance with the substantive requirements of the AIA 
rule (i.e., the AIA rule acceptance criteria). The applicant or 
licensee is required to document, in the plant-specific departure, how 
the modified design features and functional capabilities continue to 
meet the assessment requirements in 10 CFR 50.150(a)(1), in accordance 
with Section X of Appendix D to 10 CFR part 52. Applicants and

[[Page 82090]]

licensees making changes to design features or capabilities included in 
the certified design may also need to develop alternate means to cope 
with the loss of large areas of the plant from explosions or fires to 
comply with the requirements in 10 CFR 50.54(hh). The addition of these 
provisions to Appendix D to 10 CFR part 52 is consistent with the NRC's 
intent when it issued the AIA rule in 2009, as noted in the SOC for 
that rule (74 FR 28112; June 12, 2009).
    Paragraph B.6 of Appendix D to 10 CFR Part 52 provides a process 
for departing from Tier 2* information. The creation of, and 
restrictions on changing, Tier 2* information resulted from the 
development of the Tier 1 information for the ABWR design certification 
(Appendix A to 10 CFR part 52) and the ABB-CE [ASEA Brown Boveri--
Combustion Engineering] System 80+ design certification (Appendix B to 
10 CFR part 52). During this development process, these applicants 
requested that the amount of information in Tier 1 be minimized to 
provide additional flexibility for an applicant or licensee who 
references these appendices. Also, many codes, standards, and design 
processes that would not be specified in Tier 1, but were acceptable 
for meeting ITAAC, were specified in Tier 2. The result of these 
actions was that certain significant information only exists in Tier 2 
and the Commission did not want this significant information to be 
changed without prior NRC approval. This Tier 2* information was 
identified in the generic DCD with italicized text and brackets (see 
Table 1-1 of the AP1000 DCD Introduction for a list of the Tier 2* 
items). Although the Tier 2* designation was originally intended to 
last for the lifetime of the facility, like Tier 1 information, the NRC 
determined that some of the Tier 2* information could expire when the 
plant first achieves full power (100 percent), after the finding 
required by 10 CFR 52.103(g), while other Tier 2* information must 
remain in effect throughout the life of the facility. The factors 
determining whether Tier 2* information could expire after the first 
full power was achieved were whether the Tier 1 information would 
govern these areas after first full power and the NRC's determination 
that prior approval was required before implementation of the change 
due to the significance of the information. Therefore, certain Tier 2* 
information listed in paragraph B.6.c would cease to retain its Tier 2* 
designation after full power operation is first achieved following the 
NRC finding under 10 CFR 52.103(g). Thereafter, that information would 
be deemed to be Tier 2 information that would be subject to the 
departure requirements in paragraph B.5. By contrast, the Tier 2* 
information identified in paragraph B.6.b would retain its Tier 2* 
designation throughout the duration of the license, including any 
period of license renewal.
    The NRC is revising certain items designated as Tier 2*. As 
discussed in the proposed rule, the Commission is adding an item to 
Section VIII.B.6.b for reactor coolant pump type. In addition, a new 
item was added to paragraph B.5.b for RCP type. The NRC determined that 
certain specific characteristics of the RCP were significant to the 
safety review and that prior approval of changes affecting those 
characteristics would be required. This Tier 2* designation does not 
expire.
    In the final rule, two additional items are being added to Section 
VIII.B.6.b. First, in its December 20, 2010, letter on long-term core 
cooling, the ACRS concluded that the regulatory requirements for long-
term core cooling for designbasis accidents have been adequately met, 
based on cleanliness requirements specified in the amendment. In 
particular, the amount of latent debris that might be present in the 
containment is an important parameter. The ACRS further stated that any 
future proposed relaxation of the cleanliness requirements will require 
substantial additional data and analysis. In their January 24, 2011, 
report on the Vogtle COL application, which references the AP1000 
design, the ACRS recommended that the containment interior cleanliness 
limits on latent debris should be included in the TSs. In a letter 
dated February 23, 2011, Westinghouse proposed DCD markups to designate 
information in Section 6.3 including debris sources such as latent 
debris (and the amount of fiber) as Tier 2*. The NRC believes this is a 
better approach to achieving the intent of the ACRS for regulatory 
control of any future relaxations of the limits and would thus require 
prior NRC approval, as discussed in the staff's March 3, 2011, response 
to the ACRS. Revision 19 includes DCD changes to mark selected 
information as Tier 2*. No changes to the content itself were made. The 
NRC made a conforming change to the final rule language to provide a 
new item as Section VIII.B.6.b(7), entitled ``Screen design criteria,'' 
for this new type of Tier 2* information.
    The second change, which was also discussed in the December 13, 
2010, ACRS letter report on the DC amendment, concerned an error ACRS 
identified in the previously certified Revision 15, concerning the 
containment cooling analysis. The error affected the time at which 
steady-state film coverage is achieved on the exterior of the 
containment vessel. In the corrected analysis, the calculated peak 
containment pressure for a LOCA increases somewhat, but remains below 
the design pressure. In the course of reviewing the correction of the 
error for the peak containment pressure, after the proposed rule was 
published, Westinghouse identified other errors in supporting analyses 
that affect the calculated post-accident peak containment pressure. The 
net impact is an increase in calculated peak containment pressure in 
the event of a large break LOCA (the highest peak pressure) of about 
0.3 psi. As part of the revised analysis for all of the changes, 
Westinghouse relied upon a limited number of structural elements within 
the containment as heat sinks for the peak pressure analysis in order 
to maintain margin to the design limit. The NRC's safety evaluation is 
included in the FSER. Table 6.2.1.1-10 of Revision 19 of the DCD 
includes the credited elements. The final rule language designates this 
``heat sink data for containment analysis'' by adding it as new Tier 2* 
in Section VIII.B.6.b(8). Because the geometry and location of the heat 
sinks could impact their effectiveness, the staff decided to control 
any future changes to the credited elements by designating the material 
as Tier 2*.
    As discussed in the proposed rule, the NRC is clarifying some of 
the Tier 2* designations for structural requirements, with respect to 
Tier 2* information that expires at first full power operation. The 
item on human factors engineering (HFE) moved from paragraph B.5.b to 
paragraph B.5.c, with the effect that the Tier 2* designation on that 
information expires after full power operation is achieved rather than 
never expiring. In the final rule, an additional item (paragraph 
B.6.c(16)) is added to provide Tier 2* designation for certain details 
about the steel composite modules (as identified within the DCD); the 
designation expires at first full power operation. The NRC concludes 
that the details are the key elements of this unique design, and 
therefore warrant Tier 2* regulatory control.
    The NRC also concluded that the Tier 2* designation is not 
necessary for the specific Code edition and addenda for the American 
Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME 
Code), as listed in item VIII.B.6.c(2). At the time of the initial 
certification, the NRC determined that this information should be Tier 
2*.

[[Page 82091]]

Subsequently, 10 CFR Part 50 was modified to include provisions in 10 
CFR 50.55a(b)(1)(iii) to provide restrictions in the use of certain 
editions/addenda to the ASME Code, Section III, that the NRC found 
unacceptable. In addition, 10 CFR 50.55a(c)(3), (d)(2) and (e)(2), for 
reactor coolant pressure boundary, Quality Group B Components, and 
Quality Group C Components, respectively, provide regulatory controls 
on the use of later edition/addenda to the ASME Code, Section III, 
through the conditions NRC established on use of paragraph NCA-1140 of 
the Code. As a result, these rule requirements adequately control the 
ability of a licensee to use a later edition of the ASME Code and 
addenda such that Tier 2* designation is not necessary. Thus, the Tier 
2* item in paragraph B.6.c(2) for ASME Code was modified to be limited 
to ASME Code piping design restrictions as identified in Section 
5.2.1.1 of the AP1000 DCD and to include certain Code cases, including 
Code Case N-284-1, as discussed in Section 3.8.2.2 and other Code cases 
as designated in Table 5.2-3 of the DCD (Code Case N-284-1 is the only 
case currently specified in Appendix D to 10 CFR Part 52). The NRC 
retained the Tier 2* designation for applying ASME Code, Section III, 
Subsection NE to containment design, by moving this provision to the 
end of Section VIII.B.6.c(14). Section 3.8.2.2 of the DCD identifies 
the specific edition and addenda for containment design (2001 Edition 
of ASME Code, Section III, including 2002 Addenda) with the Tier 2* 
markings.
6. Records and Reporting (Section X)
    The purpose of Section X is to set forth the requirements that 
apply to maintaining records of changes to and departures from the 
generic DCD, which would be reflected in the plant-specific DCD. 
Section X also sets forth the requirements for submitting reports 
(including updates to the plant-specific DCD) to the NRC. Paragraph A.1 
requires that a generic DCD and the PI and SGI referenced in the 
generic DCD be maintained by the applicant for this rule. The NRC 
revised paragraph A.1 to replace the term ``proprietary information,'' 
or PI, with the broader term ``sensitive unclassified non-safeguards 
information,'' or SUNSI. Information categorized as SUNSI is 
information that is generally not publicly available and encompasses a 
wide variety of categories. These categories include information about 
a licensee's or applicant's physical protection or material control and 
accounting program for special nuclear material not otherwise 
designated as SGI or classified as National Security Information or 
Restricted Data (security-related information), which is required by 10 
CFR 2.390 to be protected in the same manner as commercial or financial 
information (i.e., they are exempt from public disclosure). This change 
is necessary because the NRC is approving PI and security-related 
information. This change also ensures that Westinghouse (as well as any 
future applicants for amendments to the AP1000 DCR who intend to supply 
the certified design) are required to maintain a copy of the applicable 
generic DCD, and maintain the applicable SUNSI (including PI) and SGI--
developed by that applicant--that were approved as part of the relevant 
design certification rulemakings.
    The NRC notes that the generic DCD concept was developed, in part, 
to meet OFR requirements for incorporation by reference, including 
public availability of documents incorporated by reference. However, 
the PI and SGI were not included in the public version of the DCD. Only 
the public version of the generic DCD is identified and incorporated by 
reference into this rule. Nonetheless, the SUNSI for this amendment was 
reviewed by the NRC and, as stated in paragraph B.2, the NRC considers 
the information to be resolved within the meaning of 10 CFR 
52.63(a)(5). Because this information is in the nonpublic version of 
the DCD, this SUNSI (including PI) and SGI, or its equivalent, is 
required to be provided by an applicant for a license referencing this 
DCR.
    In addition, the NRC is adding a new paragraph A.4.a that requires 
the applicant for the AP1000 design to maintain a copy of the AIA 
performed to comply with the requirements of 10 CFR 50.150(a) for the 
term of the certification (including any period of renewal). The NRC 
added a new paragraph A.4.b that requires an applicant or licensee who 
references this appendix to maintain a copy of the AIA performed to 
comply with the requirements of 10 CFR 50.150(a) throughout the 
pendency of the application and for the term of the license (including 
any period of renewal). The addition of paragraphs A.4.a and A.4.b is 
consistent with the NRC's intent when it issued the AIA rule in 2009 
(74 FR 28112; June 12, 2009).

C. Immediate Effectiveness of Final Rule; Provision of Actual Notice to 
Southern Nuclear Operating Company

    The NRC is making this final rule immediately effective, and is 
also providing notice of this final rule (including the NRC-approved 
DCD, Revision 19) to Southern Nuclear Operating Company (SNOC). Under a 
provision of the Administrative Procedure Act (APA), 5 U.S.C. 553(d), 
there ordinarily must be a 30-day waiting period before a new rule is 
effective, subject to certain exceptions, including ``good cause:''

    The required publication or service of a substantive rule shall 
be made not less than 30 days before its effective date, except: (1) 
A substantive rule which grants or recognizes an exemption or 
relieves a restriction; (2) interpretive rules and statements of 
policy; or (3) as otherwise provided by the agency for good cause 
found and published with the rule.

Consistent with the APA, 10 CFR 2.807 provides that the NRC may make a 
rule effective in less than 30 days after publication in the Federal 
Register upon making the good cause finding as noted in the third 
exception listed in 5 U.S.C. 553(d). For the following reasons, the NRC 
has determined that good cause exists for making this design 
certification rulemaking immediately effective.
    Good cause can be demonstrated by any number of circumstances. Here 
the circumstances demonstrate that the basis for the 30-day waiting 
period--to allow those regulated by a new rule time to conform their 
activities to it--is absent. Several sources of guidance on Section 
553(d) support the NRC's good cause finding for this rulemaking.
    Specifically, in the legislative history of the 30-day provision, 
the final report of the House Committee on the Judiciary offered the 
following explanation of the ``good cause'' exception in 5 U.S.C. 
553(d)(3):

    [The purpose of the 30-day delay is to] afford persons affected 
a reasonable time to prepare for the effective date of a rule or 
rules or to take any other action which the issuance of rules may 
prompt * * *. Many rules * * * may be made operative in less than 30 
days * * * because the parties subject to them may during the 
usually protracted hearing and decision procedures anticipate the 
regulation. (Senate Document (S. Doc. No.) 79-249, Administrative 
Procedure Act: Legislative History 259-60 (1946))

Additional guidance is found in the Attorney General's Manual on the 
APA, which provides:

    The requirement of publication not less than thirty days prior 
to the effective date may be shortened by an agency `upon good

[[Page 82092]]

cause found and published with the rule'. This discretionary 
exception was provided primarily to take care of the cases in which 
the public interest requires the agency to act immediately or within 
a period less than thirty days. Senate Hearings (1941) pp. 70, 441, 
588, 650, 812, 1506. Where the persons concerned request that a rule 
be made effective within a shorter period, this circumstance would 
ordinarily constitute good cause. Also, it is clear from the 
legislative history that for good cause an agency may put a 
substantive rule into effect immediately; in such event, the 
requirement of prior publication is altogether absent, and the rule 
will become effective upon issuance as to persons with actual 
notice, and as to others upon filing with the Division of the 
Federal Register in accordance with section 7 of the Federal 
Register Act. Senate Hearings (1941) pp. 594, 599, 1340, 1455. (U.S. 
Department of Justice, Attorney General's Manual on the 
Administrative Procedure Act 37 (1947) (emphasis added))

In light of this background, the NRC believes that there is good cause 
for making this final rule amending the AP1000 DCR immediately 
effective.
    On May 27, 2011, one of the first COL applicants to which this 
amended AP1000 DCR would potentially apply, SNOC, submitted a ``white 
paper'' that set forth alternatives to making the final AP1000 rule 
effective 30 days after publication (ADAMS Accession No. ML11152A189). 
Thereafter, SNOC submitted a July 20, 2011, letter (ADAMS Accession No. 
ML11210B421), indicating that making the certified design rule 
immediately effective would serve important policy objectives.\2\ 
SNOC's letter thus requested Commission action. During the Vogtle 
uncontested, or ``mandatory,'' hearing held by the Commission on SNOC's 
applications for a COL and a limited work authorization (LWA), SNOC 
reiterated its request that the NRC issue the COL and LWA immediately 
upon Commission affirmation of the final rule amending the AP1000 DCR. 
Transcript of Vogtle COL Mandatory Hearing at 22-23, 350 (September 27, 
2011; ADAMS Accession No. ML11305A228).
---------------------------------------------------------------------------

    \2\ The letter by SNOC, requesting that the final rule amending 
the AP1000 DCR be made effective before 30 days after Federal 
Register publication, was filed on the docket for the Vogtle 
Electric Generating Plant, Units 3 and 4 (Docket Nos. 52-025-COL and 
52-026-COL) (Vogtle). SNOC's request is more appropriately addressed 
in this rulemaking proceeding to amend the AP1000 DCR.
---------------------------------------------------------------------------

    Here, SNOC, which is likely to use (and be bound by) the AP1000 DCR 
in the short-term if the Commission otherwise authorizes issuance of 
the COL, wishes the rule be made immediately effective. Given SNOC's 
longstanding awareness of and participation in the AP1000 rulemaking, 
it does not need the 30-day waiting period to come into compliance with 
the final rule. Under the Attorney General's Manual, supra, at 37, 
SNOC's request that the rule be made effective in a shorter time period 
constitutes good cause to waive the 30-day waiting period. As noted 
previously, the extensive process for consideration of this design 
certification rulemaking would clearly constitute a situation where 
``the parties subject to [the regulation] may during the usually 
protracted hearing and decision procedures anticipate the regulation.'' 
S. Doc. No. 79-249, Administrative Procedure Act: Legislative History 
259-60 (1946). In fact, that ``anticipation'' is clearly manifested in 
SNOC's use of the design certification rulemaking, as well as use by 
other applicants for COLs referencing the AP1000 DCR, which would occur 
only after the completion of a public process that includes NRC 
adjudicatory processes for each COL application. The determination of 
good cause regarding the effective date of the final AP1000 rule is 
separate from, and does not prejudge, the licensing determinations that 
are otherwise required in the COL proceedings.
    Finally, the NRC is providing actual service of the final AP1000 
rule (including the NRC-approved DCD, Revision 19) to SNOC concurrently 
with the NRC's transmission of the final rule to the OFR for 
publication.\3\ Thus, either before, or simultaneous with, any issuance 
of a COL for Vogtle (and any other COL application referencing the 
AP1000, upon request), SNOC (and any other COL applicant referencing 
the AP1000, upon request) will have actual notice of the requirements 
of the final AP1000 rule and Revision 19 of the DCD for which their 
NRC-licensed activities under the COL must conform.
---------------------------------------------------------------------------

    \3\ The NRC would also provide actual notice of the final AP1000 
rule to any other COL applicant upon request. On the date of the 
transmission of the final rule package to the OFR, the NRC will 
issue an announcement of its transmission and make the final rule 
package as transmitted to the OFR available on the NRC Web site.
---------------------------------------------------------------------------

    The immediately effective rule cannot be used by anyone until the 
agency has made the necessary health and safety findings and completed 
the environmental review processes that necessarily precede the 
issuance of a COL relying on the design certification rulemaking. Each 
finding necessary under the Atomic Energy Act would have been made 
through public rulemaking and the NRC's adjudicatory processes that 
serve to allow consideration of public input before the agency issues 
its determination on an application referencing the AP1000. The rule 
itself does not force anyone to take action immediately based on its 
effective date because it does not compel, but rather permits, action. 
Therefore, from the standpoint of regulatory efficiency, delaying 
issuance of a licensing decision when the decision is ready to be 
issued is not in the public interest, whether the decision is to deny 
or grant the requested license.
    On October 14, 2011, counsel for several organizations who were 
previously admitted as Joint Intervenors in the contested portion of 
the Vogtle COL proceeding indicated that they would be adversely 
affected by the issuance of an immediately effective rule. Letter from 
Mindy Goldstein, Counsel for Southern Alliance for Clean Energy, 
Georgia Women's Action for New Directions, and Center for a Sustainable 
Coast (Goldstein Letter) (ADAMS Accession No. ML11287A054).\4\ The 
Goldstein Letter states that SNOC has requested a waiver of 10 CFR 
2.807 during the uncontested hearing, which the letter states is an 
improper forum, and that waiver of 10 CFR 2.807 would not afford them 
time to prepare for issuance of the Vogtle COL or LWA. The Goldstein 
Letter states that a waiver of 10 CFR 2.807 is required to be submitted 
under 10 CFR 2.335. The Goldstein Letter explains that when the DCR 
becomes effective, a COL and LWA will be issued, resulting in a nuclear 
power plant that will affect all persons located near the site. The 
Vogtle Joint Intervenors believe the 30-day effective period is 
necessary to determine whether they wish to appeal the rule and seek a 
stay of construction.
---------------------------------------------------------------------------

    \4\ Because the Goldstein Letter was submitted in response to 
SNOC's request, which is being considered in this AP1000 design 
certification rulemaking, the NRC is, in its discretion, considering 
the Goldstein Letter here as well. Therefore, the NRC need not 
address the matters raised in the Goldstein Letter with respect to 
SNOC's compliance with the adjudicatory requirements in 10 CFR 
2.335.
---------------------------------------------------------------------------

    First, a waiver of 10 CFR 2.807 is not required to make a rule 
immediately effective; a rule can be made immediately effective 
pursuant to the requirements of 10 CFR 2.807. The Commission in this 
rulemaking has determined to use the good cause exception to the 30-day 
effective date for the rulemaking and thus, is acting consistently with 
the provisions of 10 CFR 2.807 rather than waiving its provisions.
    Second, as noted previously in the discussion of the legislative 
history of the 30-day effective date provision, the primary purpose of 
the 30-day requirement is to allow affected persons time to comply with 
the new rule. The final rule amending the AP1000 design

[[Page 82093]]

certification is focused on the conduct of regulatory activities 
licensed by the NRC. But, the Vogtle Joint Intervenors are neither 
current NRC licensees who must comply with the final rule amending the 
AP1000 rule, nor applicants for NRC licenses referencing the final 
AP1000 rule. Thus, the final AP1000 rule imposes no substantive legal 
obligations on them. The NRC does not believe that the Goldstein Letter 
describes any legally-cognizable harm within the scope of protection 
afforded to third parties by the APA's 30-day waiting period provision. 
That an immediately effective AP1000 rule may facilitate issuance of a 
COL for the Vogtle plant does not appear to adversely affect the rights 
or capability of any public stakeholder to do what they would otherwise 
do if the AP1000 rule were made effective 30 days after publication in 
the Federal Register. Whether the AP1000 rule is immediately effective 
or not does not change any public stakeholder's legal rights or 
options; it merely affects the timing of asserting such rights or 
exercising those options.
    Further, the Commission is not aware of any regulatory history 
indicating that the purpose of the 30-day effective date is tied to or 
affects appeal rights. Regardless of the immediate effectiveness of the 
rule, the Vogtle Joint Intervenors may seek legal action on the 
immediately effective rule in Federal court, or they may file an 
appropriate motion in the Vogtle COL proceeding if they satisfy the 
requirements in 10 CFR Part 2 to reopen the record and submit late-
filed contentions. See 10 CFR 2.309, 2.326. Thus, an immediately 
effective AP1000 rule does not foreclose, or render moot, challenges to 
the rule, including stay remedies. For these reasons, the NRC concludes 
that making the final AP1000 rule immediately effective would not 
adversely affect these organizations or any other public stakeholders.
    In sum, the NRC finds good cause for making the final rule amending 
the AP1000 DCR immediately effective upon publication in the Federal 
Register. Therefore, the NRC is making the final rule immediately 
effective. In addition, there is sufficient reason to provide prompt 
actual notice of this final rule (including the NRC-approved DCD, 
Revision 19) to SNOC (and potentially to any other combined license 
applicant referencing the amended AP1000 DCR in its application).

IV. Section-by-Section Analysis

    The following discussion sets forth each amendment to the AP1000 
DCR being made in this final rule. All section and paragraph references 
are to the provisions in the amendment to Appendix D to 10 CFR part 52, 
unless otherwise noted.

A. Scope and Contents (Section III)

    The NRC is amending Section III, Scope and Contents, to revise 
paragraph A to update the revision number of the DCD, from Revision 15 
to Revision 19, approved for incorporation by reference by the Office 
of the Federal Register; update the contact information of the 
Westinghouse representative to be contacted should a member of the 
public request a copy of the generic DCD; and update other locations 
(e.g., the NRC's PDR) where a member of the public could request a copy 
of or otherwise view the generic DCD.
    The NRC is revising paragraph D to establish the generic DCD as the 
controlling document in the event of an inconsistency between the DCD 
and either the application or the FSER for the certified standard 
design. This clarification further distinguishes between the conflict 
scenarios presented in paragraphs D.1 (for the initial certification of 
the design) and D.2 (for Amendment 1 to the design).

B. Additional Requirements and Restrictions (Section IV)

    The NRC is amending Section IV, Additional Requirements and 
Restrictions, to set forth additional requirements and restrictions 
imposed upon an applicant who references Appendix D to 10 CFR part 52. 
Paragraph A sets forth the information requirements for these 
applicants. The NRC is revising paragraph A.3 to replace the term 
``proprietary information'' with the broader term ``sensitive 
unclassified non-safeguards information.''
    The NRC is also adding a new paragraph A.4 to indicate requirements 
that must be met in cases where the COL applicant is not using the 
entity that was the original applicant for the design certification (or 
amendment) to supply the design for the applicant's use.

C. Applicable Regulations (Section V)

    The NRC is revising paragraph A to distinguish between the 
regulations that were applicable and in effect at the time the initial 
design certification was approved (paragraph A.1) and the regulations 
that are applicable and in effect as of the effective date of the final 
rule (paragraph A.2).

D. Issue Resolution (Section VI)

    The NRC is amending Section VI, Issue Resolution, by revising 
paragraph B.1 to provide that all nuclear safety issues arising from 
the Act that are associated with the information in the NRC's FSER 
(NUREG-1793), the Tier 1 and Tier 2 information (including the 
availability controls in Section 16.3 of the generic DCD), and the 
rulemaking record for Appendix D to 10 CFR Part 52 are resolved within 
the meaning of 10 CFR 52.63(a)(5). These issues include the information 
referenced in the DCD that are requirements (i.e., secondary 
references), as well as all issues arising from SUNSI (including PI) 
and SGI, which are intended to be requirements. This paragraph is 
revised to extend issue resolution beyond that of the previously 
certified design to also include the information in Supplement No. 2 of 
the 2011 FSER (Supplement 1 supported the initial certification) and 
the rulemaking record associated with Amendment 1 to the AP1000 design.
    The NRC is revising paragraph B.2 to replace the term ``proprietary 
information'' with the broader term ``sensitive unclassified non-
safeguards information.''
    Paragraph B.7 is revised to extend environmental issue resolution 
beyond that of the previously certified design to also include the 
information in Amendment 1 to the AP1000 design and Appendix 1B of 
Revision 19 of the generic DCD.
    A new paragraph E is added to allow the NRC to specify at the 
appropriate time the procedures for interested persons to obtain access 
to PI, SUNSI, and SGI for the AP1000 DCR. Access to such information is 
for the sole purpose of requesting or participating in certain 
specified hearings, such as (1) the hearing required by 10 CFR 52.85 
where the underlying application references Appendix D to 10 CFR Part 
52; (2) any hearing provided under 10 CFR 52.103 where the underlying 
COL references Appendix D to 10 CFR part 52; and (3) any other hearing 
relating to Appendix D to 10 CFR Part 52 in which interested persons 
have the right to request an adjudicatory hearing.

E. Processes for Changes and Departures (Section VIII)

    The NRC is revising Section VIII to address the change control 
process specific to departures from the information required by 10 CFR 
52.47(a)(28) to address the NRC's AIA requirements in 10 CFR 50.150. 
Specifically, the NRC is revising the introductory text of paragraph 
B.5.b to indicate that the criteria in this paragraph for determining 
if a proposed departure from Tier 2 requires a license amendment do not 
apply to a proposed departure affecting information required

[[Page 82094]]

by 10 CFR 52.47(a)(28) to address aircraft impacts.
    In addition, the NRC is redesignating paragraphs B.5.d, B.5.e, and 
B.5.f as paragraphs B.5.e, B.5.f, and B.5.g, respectively, and adding a 
new paragraph B.5.d. Paragraph B.5.d requires an applicant referencing 
the AP1000 DCR, who proposes to depart from the information required by 
10 CFR 52.47(a)(28) to be included in the FSAR for the standard design 
certification, to consider the effect of the changed feature or 
capability on the original 10 CFR 50.150(a) assessment.
    The NRC is revising certain items designated as Tier 2*. As 
discussed in the proposed rule, the NRC is adding an item to Section 
VIII.B.6.b for RCP type. In addition, a new item is added to paragraph 
B.5.b for RCP type. The NRC determined that certain specific 
characteristics of the RCP were significant to the safety review and 
that prior approval of changes affecting those characteristics would be 
required. This Tier 2* designation does not expire.
    In the final rule, two additional items are added to Section 
VIII.B.6.b. Section VIII.B.6.b(7) provides Tier 2* designation for 
certain analysis assumptions related to latent debris and the effects 
on screens and fuel assemblies in post-LOCA conditions where debris is 
transported to the recirculation sump and into the in-containment 
refueling water storage tank. Finally, new paragraph VIII.B.6.b(8) is 
added to include the containment heat sinks credited in the peak 
pressure analysis. The Tier 2* designation for the requirements in this 
section of the rule does not expire.
    As discussed in the proposed rule, the NRC is clarifying some of 
the Tier 2* designations for structural requirements, with respect to 
Tier 2* information that expires at first full power operation. The 
item on HFE moved from paragraph B.5.b to paragraph B.5.c, with the 
effect that the Tier 2* designation on that information expires after 
full power operation is achieved rather than never expiring. In the 
final rule, an additional item (paragraph B.6.c(16)) is added to 
provide Tier 2* designation for certain details about the steel 
composite modules (as identified within the DCD); the designation 
expires at first full power operation.
    Finally, the NRC also concluded that the Tier 2* designation was 
not necessary for the specific Code edition and addenda for the ASME 
Code as listed in paragraph VIII.B.6.c(2). Thus, the item in paragraph 
VIII.B.6.c(2) for ASME Code was modified to be limited to piping and 
welding restrictions identified in Section 5.2.1.1, and to include 
certain Code cases, N-284-1 is discussed in Section 3.8.2.2 and other 
code cases designated as Tier 2* are listed in Table 5.2-3. The NRC 
retained the Tier 2* designation for applying ASME Code Section III to 
containment design, by moving this provision to the end of Section 
VIII.B.6.c(14). Section 3.8.2.2 identifies the specific edition and 
addenda for containment design (2001 Edition of ASME Code, Section III, 
including 2002 Addenda).

F. Records and Reporting (Section X)

    The NRC is amending Section X, Records and Reporting, to revise 
paragraph A.1 to replace the term ``proprietary information'' with the 
broader term ``sensitive unclassified non-safeguards information.'' 
Paragraph A.1 is revised to require the design certification amendment 
applicant to maintain the SUNSI, which it developed and used to support 
its design certification amendment application. This would ensure that 
the referencing applicant has direct access to this information from 
the design certification amendment applicant, if it has contracted with 
the applicant to provide the SUNSI to support its license application. 
The AP1000 generic DCD and the NRC-approved version of the SUNSI would 
be required to be maintained for the period that Appendix D to 10 CFR 
part 52 may be referenced.
    The NRC is also adding a new paragraph A.4.a, which requires 
Westinghouse to maintain a copy of the AIA performed to comply with the 
requirements of 10 CFR 50.150(a) for the term of the certification 
(including any period of renewal). This provision, which is consistent 
with 10 CFR 50.150(c)(3), would facilitate any NRC inspections of the 
assessment that the NRC decides to conduct.
    Similarly, the NRC is adding a new paragraph A.4.b, which requires 
an applicant or licensee who references Appendix D to 10 CFR Part 52 to 
maintain a copy of the AIA performed to comply with the requirements of 
10 CFR 50.150(a) throughout the pendency of the application and for the 
term of the license (including any period of renewal).

V. Agreement State Compatibility

    Under the ``Policy Statement on Adequacy and Compatibility of 
Agreement States 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 Act or the provisions of this 
section. Although an Agreement State may not adopt program elements 
reserved to the NRC, it may wish to inform its licensees of certain 
requirements by a mechanism that is consistent with the particular 
State's administrative procedure laws. Category ``NRC'' regulations do 
not confer regulatory authority on the State.

VI. Availability of Documents

    The NRC is making the documents identified below available to 
interested persons through one or more of the following methods, as 
indicated. To access documents related to this action, see the 
ADDRESSES section of this document.

------------------------------------------------------------------------
                Document                    PDR     Web        ADAMS
------------------------------------------------------------------------
SECY-11-0145, ``Final Rule--AP1000            X       X      ML112380823
 Design Certification Amendment''.......
AP1000 Final Rule Environmental               X       X      ML113480019
 Assessment.............................
AP1000 Final Rule Public Comment              X       X      ML113480018
 Response Document......................
SECY-11-0002, ``Proposed Rule--AP1000         X       X      ML103000397
 Design Certification Amendment''.......
AP1000 Proposed Rule Federal Register         X       X      ML103000412
 Notice.................................
AP1000 Proposed Rule Environmental            X       X      ML103000415
 Assessment.............................
NUREG-1793, Supplement 2 to Final Safety      X       X      ML112061231
 Evaluation Report for Revision 19 to
 the AP1000 Standard Design
 Certification (publicly available).....
NUREG-1793, Final Safety Evaluation           X       X      ML043570339
 Report Related to Certification of the
 AP1000 Standard Design, September 2004.
NUREG-1793, Supplement 1 to Final Safety      X       X      ML053410203
 Evaluation Report Related to
 Certification of the AP1000 Standard
 Design.................................

[[Page 82095]]

 
Emergency Petition to Suspend All             X       X      ML111040355
 Pending Reactor Licensing Decisions and                     ML111110862
 Related Rulemaking Decisions Pending
 Investigation of Lessons Learned From
 Fukushima Daiichi Nuclear Power Station
 Accident, April 14-18, 2011............
AP1000 Design Control Document (DCD),         X       X      ML11171A315
 Revision 19, Transmittal Letter........
AP1000 DCD, Revision 19 (Public Version)      X       X      ML11171A500
Redacted Version of Dissenting View on        X       X      ML103370648
 AP1000 Shield Building Safety
 Evaluation Report With Respect to the
 Acceptance of Brittle Structural Model
 to be Used for the Cylindrical Shield
 Building Wall, December 3, 2010........
AP1000 Containment Cleanliness--DCD           X       X      ML110590455
 Markup for Revision 19, February 23,
 2011...................................
Interim Staff Guidance DC/COL-ISG-011,        X       X      ML092890623
 ``Finalizing Licensing-basis
 Information''..........................
Design Changes Submitted by                   X       X      ML100250873
 Westinghouse, Revision 18..............
AP1000 Technical Reports (Appendix).....      X       X      ML103350501
TR-3, AP1000 Standard COL Technical           X       X      ML110691050
 Report Submittal of APP-GW-S2R-010,
 ``Extension of Nuclear Island Seismic
 Analysis to Soil Sites,'' Revision 5,
 February 28, 2011......................
TR-26, ``AP1000 Verification of Water         X       X      ML102170123
 Sources for Long-Term Recirculation
 Cooling Following a LOCA,'' Revision 8.
TR-34, APP-GW-GLN-016, ``AP1000               X       X      ML063250306
 Licensing Design Change Document for
 Generic Reactor Coolant Pump,''
 Revision 0, November 17, 2006..........
TR-54, ``Spent Fuel Storage Racks             X       X      ML101580475
 Structure and Seismic Analysis,''
 Revision 4.............................
TR-65, ``Spent Fuel Storage Racks             X       X      ML100082093
 Criticality Analysis,'' Revision 2.....
TR-97, ``Evaluation of the Effect of the      X       X      ML11168A041
 AP1000 Enhanced Shield Building Design
 on the Containment Response and Safety
 Analysis,'' Revision 3.................
TR-98, AP1000 COL Standard Technical          X       X      ML071010536
 Report Submittal of APP-GW-GLN-098,
 ``Compliance with 10CFR20.1406,''
 (Technical Report Number 98), Revision
 0, April 10, 2007......................
TR[dash]103, ``Fluid System Changes,''        X       X      ML072830060
 Revision 2.............................
TR-108, AP1000 Standard COL Technical         X       X      ML072750137
 Report Submittal of APP-GW-GLN-108,
 ``AP1000 Site Interface Temperature
 Limits,'' Revision 2, September 28,
 2007...................................
TR-111, AP1000 Standard COL Technical         X       X      ML071500563
 Report Submittal of APP-GW-GLN-111,
 ``Component Cooling System and Service
 Water System Changes Required for
 Increased Heat Loads,'' Revision 0, May
 25, 2007...............................
TR-134, AP1000 Standard COL Technical         X       X      ML073120415
 Report Submittal of APP-GW-GLR-134,
 ``AP1000 DCD Impacts to Support COLA
 Standardization,'' Revision 0, October
 26, 2007...............................
AP1000 Standard COL Technical Report          X       X      ML073610541
 Submittal of APP-GW-GLR-134, ``AP1000
 DCD Impacts to Support COLA
 Standardization,'' Revision 1, December
 12, 2007...............................
AP1000 Standard COL Technical Report,         X       X      ML080220389
 APP-GW-GLR-134, ``AP1000 DCD Impacts to
 Support COLA Standardization,''
 Revision 3, January 14, 2008...........
NRC Acceptance Review of AP1000 Design        X       X      ML073090471
 Certification Amendment Application,
 November 2, 2007.......................
AP1000 Piping DAC/Component COL               X       X      ML080150513
 Information Item 3.9-2 Acceptance
 Issue, Revision 16, January 11, 2008...
AP1000 License Report APP-GW-GLR-603,         X       X      ML110910541
 Revision 0, ``AP1000 Shield Building
 Design Details for Select Wall and RC/
 SC Connections''.......................
AP1000 Design Control Document (DCD),         X       X      ML103480059
 Revision 18, Transmittal Letter........
Westinghouse AP1000 DCD, Revision 18          X       X      ML103480572
 (public version).......................
Advanced Final Safety Evaluation Report       X       X      ML103260072
 for Revision 18 to the AP1000 Standard
 Design Certification (publicly
 available).............................
AP1000 DCD Transmittal Letter, Revision       X       X      ML083220482
 17.....................................
AP1000 DCD, Revision 17.................      X       X      ML083230868
AP1000 DCD Transmittal Letter, Revision       X       X      ML071580757
 16.....................................
AP1000 DCD, Revision 16.................      X       X      ML071580939
NRC Notice of Acceptance, Revision 16...      X       X      ML073600743
AP1000 DCD, Revision 15.................      X       X      ML053460400
December 13, 2010, ACRS Letter to             X       X      ML103410351
 Chairman (Report on FSER to AP1000 DCD)
December 20, 2010, ACRS Letter to             X       X      ML103410348
 Chairman (Long-Term Core Cooling)......
January 19, 2011, ACRS Letter to EDO          X       X      ML110210462
 (Aircraft Impact)......................
January 24, 2011, ACRS Letter to EDO          X       X      ML110350282
 (Containment interior cleanliness
 limits on latent debris in Technical
 Specifications)........................
EDO response to January 24, 2011 ACRS         X       X      ML110480429
 Letter.................................
May 17, 2011, ACRS Letter to EDO........      X       X      ML11144A188
Regulatory History of Design                  X       X      ML003761550
 Certification..........................
Commission Memorandum and Order, CLI-11-      X       X      ML11252B074
 05, September 9, 2011..................
Commission Memo and Order on Petitions        X       X      ML112521039
 to Suspend adjudicatory, licensing, and
 rulemaking activities..................
ABWR Final Rule.........................      X       X      ML111040636
ABWR Proposed Rule......................      X       X      ML102100129
Request for ACRS to Waive review of the       X       X      ML112420188
 AP1000 DCR final rule..................
ACRS Waiver of review of AP1000 DCR           X       X      ML11266A070
 final rule.............................
Design Report for the AP1000 Enhanced         X       X      ML111950098
 Shield Building........................
SER Approving Rev. 1 of the Westinghouse      X       X      ML11280A309
 Quality Systems Manual.................
ACRS Letter on AP1000 Long-Term Cooling.      X       X      ML103410348
ACRS Letter on Staff's review of Vogtle,      X       X      ML110170006
 including discussion of containment
 interior cleanliness...................
Staff's response to ACRS' January 24,         X       X      ML110350198
 2011, Letter...........................
Petition to Suspend AP1000 DCR                X       X      ML110970673
 Rulemaking.............................
Green Ticket for Runkle Petition........      X       X      ML11108A077
ACRS letter on AP1000 DCD Revision 19         X       X      ML11256A180
 and Staff's Review.....................
Petition to Suspend AP1000 DCR                X       X      ML111110851
 Rulemaking.............................
Emergency Petition......................      X       X      ML111110862
Petition to Terminate the Rulemaking on       X       X      ML11171A014
 Design Certification of the AP1000.....

[[Page 82096]]

 
AP1000 Proposed Rule Package (Rule, FRN,      X       X      ML103000394
 and EA)................................
ISG-01, ``Seismic Issues Associated with      X       X      ML081400293
 High Frequency Ground Motion''.........
Green Ticket Containing Letter from           X       X      ML110680273
 Congressman Markey.....................
Cover letter for Response to Congressman      X       X      ML11080A015
 Markey, August 15, 2011................
Near-Term Task Force Review of Fukushima      X       X      ML111861807
SRM responding to Near-Term Task Force        X       X      ML112310021
 Report and Recommendations.............
Response to Congressman Markey Letter...      X       X      ML112450407
Revision 19 to the AP1000 Design Control      X       X      ML11256A180
 Document and the AP1000 Final Safety
 Evaluation Report......................
Advanced Final Safety Evaluation Report,      X       X      ML103430502
 Section 3.8.4..........................
Presentation Slides ``AP1000 Shield           X       X      ML111440298
 Building Design,'' Meeting with NRC
 Staff, May 17, 2011 (Proprietary and
 Non-Proprietary).......................
Summary of a Category 1 Meeting With          X       X      ML111430775
 Westinghouse Electric Company Regarding
 AP1000 Shield Building Design
 Methodology, May 17, 2011..............
G20100734/LTR-10-0528/EDATS: SECY-2010-       X       X      ML103560411
 0595--Ltr. Said Abdel-Khalik re: Report
 on the Final Safety Evaluation Report
 Associated with the Amendment to the
 AP1000 Design Control Document.........
Transmittal of WEC Shield Building            X       X      ML102650098
 Action Item 21.........................
White Paper--Requirements for COL and         X       X      ML11152A189
 LWA Issuance, Relative to the
 Finalization of Standard Design
 Certification Rulemaking...............
G20110559/LTR-11-0429/EDATS: SECY-2011-       X       X      ML11210B421
 0429--Ltr. Stephen E. Kuczynski re:
 Vogtle Electric Generating Plant Units
 3 and 4 Combined License Application--
 Final Standard Design Certification
 Rulemaking for LWA-B Request...........
Order (Adopting Proposed Transcript           X       X      ML11305A228
 Corrections, Admitting Post-Hearing
 Responses, and Closing the Record of
 the Proceeding)........................
Southern Nuclear Operating Company's          X       X      ML11287A054
 Request to Waive the Requirements of 10
 CFR 2.807..............................
------------------------------------------------------------------------

VII. Voluntary Consensus Standards

    The National Technology Transfer and Advancement Act of 1995, 
Public Law 104-113, requires that Federal agencies use technical 
standards that are developed or adopted by voluntary consensus 
standards bodies unless using such a standard is inconsistent with 
applicable law or is otherwise impractical. In this final rule, the NRC 
is approving an amendment to the AP1000 standard plant design for use 
in nuclear power plant licensing under 10 CFR parts 50 or 52. Design 
certifications (and amendments thereto) are not generic rulemakings 
establishing a generally applicable standard with which all parts 50 
and 52 nuclear power plant licensees must comply. Design certifications 
(and amendments thereto) are NRC approvals of specific nuclear power 
plant designs by rulemaking. Furthermore, design certifications (and 
amendments thereto) are initiated by an applicant for rulemaking, 
rather than by the NRC. For these reasons, the NRC concludes that the 
National Technology Transfer Advancement Act of 1995 does not apply to 
this final rule.

VIII. Finding of No Significant Environmental Impact: Availability

    The Commission has determined under NEPA, and the Commission's 
regulations in subpart A, ``National Environmental Policy Act; 
Regulations Implementing Section 102(2),'' of 10 CFR part 51, 
``Environmental Protection Regulations for Domestic Licensing and 
Related Regulatory Functions,'' that this DCR is not a major Federal 
action significantly affecting the quality of the human environment 
and, therefore, an environmental impact statement (EIS) is not 
required. The basis for this determination, as documented in the final 
EA, is that the Commission has made a generic determination under 10 
CFR 51.32(b)(2) that there is no significant environmental impact 
associated with the issuance of an amendment to a design certification. 
This amendment to 10 CFR part 52 does not authorize the siting, 
construction, or operation of a facility using the amended AP1000 
design; it only codifies the amended AP1000 design in a rule. The NRC 
will evaluate the environmental impacts and issue an EIS as appropriate 
under NEPA as part of the application for the construction and 
operation of a facility referencing this amendment to the AP1000 DCR. 
In addition, as part of the final EA for the amendment to the AP1000 
design, the NRC reviewed Westinghouse's evaluation of various design 
alternatives to prevent and mitigate severe accidents in Appendix 1B of 
the AP1000 DCD Tier 2. According to 10 CFR 51.30(d), an EA for a design 
certification amendment is limited to the consideration of whether the 
design change, which is the subject of the proposed amendment renders a 
SAMDA previously rejected in the earlier EA to become cost beneficial, 
or results in the identification of new SAMDAs, in which case the costs 
and benefits of new SAMDAs and the bases for not incorporating new 
SAMDAs in the design certification must be addressed. Based upon review 
of Westinghouse's evaluation, the NRC concludes that the proposed 
design changes: (1) Do not cause a SAMDA previously rejected in the EA 
for the initial AP1000 design certification to become cost-beneficial; 
and (2) do not result in the identification of any new SAMDAs that 
could become cost beneficial.
    The NRC prepared a final EA following the close of the comment 
period for the proposed standard design certification. With the 
issuance of this final rule, all environmental issues concerning SAMDAs 
associated with the information in the final EA and Appendix 1B of the 
AP1000 DCD Tier 2 will be considered resolved for plants referencing 
Amendment 1 to the AP1000 design whose site parameters are within those 
specified in SAMDA evaluation. The existing site parameters specified 
in the SAMDA evaluation are not affected by this design certification 
amendment.
    The final EA, upon which the NRC's finding of no significant impact 
is based, and Revision 19 of the AP1000 DCD are available as discussed 
in Section IV, Availability of Documents. The NRC sent a copy of the EA 
and final rule to every State Liaison Officer and no comments were 
received.

IX. Paperwork Reduction Act Statement

    This final rule contains new or amended information collection 
requirements that are subject to the Paperwork Reduction Act of 1995 
(44 U.S.C. 3501 et seq.). These requirements were approved by the 
Office of Management and Budget, approval number 3150-0151.

[[Page 82097]]

    The burden to the public for these information collections is 
estimated to average 3 hours per response, including the time for 
reviewing instructions, searching existing data sources, gathering and 
maintaining the data needed, and completing and reviewing the 
information collection. Send comments on any aspect of these 
information collections, including suggestions for reducing the burden, 
to the Information Services Branch (T-5F53), U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001, or by Internet electronic mail 
to [email protected]; and to the Desk Officer, Office of 
Information and Regulatory Affairs, NEOB-10202, (3150-0151), Office of 
Management and Budget, Washington, DC 20503.

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 
OMB control number.

X. Regulatory Analysis

    The NRC has not prepared a regulatory analysis for this final rule. 
The NRC prepares regulatory analyses for rulemakings that establish 
generic regulatory requirements applicable to all licensees. Design 
certifications are not generic rulemakings in the sense that design 
certifications do not establish standards or requirements with which 
all licensees must comply. Rather, design certifications are Commission 
approvals of specific nuclear power plant designs by rulemaking, which 
then may be voluntarily referenced by applicants for COLs. Furthermore, 
design certification rulemakings are initiated by an applicant for a 
design certification, rather than the NRC. Preparation of a regulatory 
analysis in this circumstance would not be useful because the design to 
be certified is proposed by the applicant rather than the NRC. For 
these reasons, the Commission concludes that preparation of a 
regulatory analysis is neither required nor appropriate.

XI. Regulatory Flexibility Act Certification

    Under the Regulatory Flexibility Act of 1980, 5 U.S.C. 605(b), the 
Commission certifies that this final rule will not have a significant 
economic impact upon a substantial number of small entities. The final 
rule provides for certification of an amendment to a nuclear power 
plant design. Neither the design certification amendment applicant, nor 
prospective nuclear power plant licensees who reference this DCR, 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). Thus, this rule does not fall within the 
purview of the Regulatory Flexibility Act.

XII. Backfitting and Issue Finality

    The NRC has determined that this final rule meets the requirements 
of the backfit rule, 10 CFR 50.109, and the requirements governing 
changes to DCRs in 10 CFR 52.63(a)(1).
    The final rule does not constitute backfitting as defined in the 
backfit rule (10 CFR 50.109) with respect to operating licenses under 
10 CFR Part 50 because there are no operating licenses referencing this 
DCR.
    Westinghouse requested many changes to the currently approved 
AP1000 DCD Revision 15 to correct spelling, punctuation, or similar 
errors, which result in text that has the same essential meaning. The 
NRC concludes that these Westinghouse-requested changes, which are 
editorial in nature, neither constitute backfitting as defined in 10 
CFR 50.109(a)(1), nor are these changes inconsistent with the issue 
finality provisions of 10 CFR 52.63 or 10 CFR 52.83. The backfitting 
and issue finality provisions were not meant to apply to such editorial 
changes in as much as such changes would have insubstantial impact on 
licensees with respect to their design and operation, and are not the 
kind of changes falling within the policy considerations that underlie 
the backfit rule and the issue finality provisions of 10 CFR 52.63 and 
10 CFR 52.83.
    Westinghouse also made proposed changes to Revision 15 of the 
AP1000 DCD, which the NRC understands were the result of requests to 
Westinghouse from COL applicants referencing the AP1000 design, to 
achieve consistency in description and approach in different portions 
of the DCD. In the absence of a generic change to the AP1000, the 
referencing COL applicants stated to Westinghouse and the NRC that each 
would likely take plant-specific departures to address the 
inconsistency. While this could result in more consistency within any 
given COL application, it would result in inconsistencies among the 
different referencing COLs, which is inconsistent with the overall 
standardization goal of 10 CFR part 52. Accordingly, the NRC concludes 
that the Westinghouse-requested changes to the AP1000 to address 
consistency do not constitute backfitting under the backfit rule (in as 
much as they are voluntary) and are not otherwise inconsistent with the 
issue finality provisions of 10 CFR 52.63 and 52.83.
    Westinghouse also proposed numerous substantive changes to the 
AP1000 design described in Revision 15 of the DCD, including, but not 
limited to, minor component design details, replacement of a design 
feature with another having similar performance (e.g., turbine 
manufacturer, power for the auxiliary boiler), and changes allowing 
additional capability for operational flexibility (e.g., liquid waste 
holdup tanks, unit reserve transformer). Westinghouse included within 
its application a detailed list of each DCD content change and the 
basis for concluding that one or more of the criteria in 10 CFR 
52.63(a)(1) are satisfied for each change.
    In the course of the NRC review of the technical changes proposed 
by Westinghouse, the NRC considered the basis offered by Westinghouse 
and made conclusions about whether the criteria of 10 CFR 52.63(a) were 
satisfied. These conclusions are included in the chapters of the FSER 
under ADAMS Accession No. ML112061231. The NRC concluded that all of 
these changes met at least one of the criteria in 10 CFR 52.63(a) and 
are not otherwise inconsistent with the issue finality provisions of 10 
CFR 52.63 and 52.83. Fifteen of the most significant changes are 
discussed below, to show that each of the 15 substantive changes to the 
AP1000 certified design meet at least one of the criteria in 10 CFR 
52.63(a)(1)(i) through (a)(1)(vii) and, therefore, do not constitute a 
violation of the finality provisions in that section.

A. 10 CFR 52.63 Criterion (a)(1)(iv): Provides the Detailed Design 
Information To Be Verified Under Those ITAAC, Which Are Directed at 
Certification Information (i.e., DAC)

    Title: Removal of Human Factors Engineering Design Acceptance 
Criteria from the Design Control Document.
    Item: 1 of 15.
    Description of Change: The ITAAC Design Commitments for HFE are in 
Tier 1, Table 3.2-1. In Revision 17 of the AP1000 DCD, Westinghouse 
proposed deletion of the Human Factors DAC (Design Commitments 1 
through 4) and provided sufficient supporting documentation to meet the 
requirements of these ITAAC. Design Commitment 1 pertains to the 
integration of human reliability analysis with HFE design. Design 
Commitment 2 pertains to the HFE task analysis. Design Commitment 3 
pertains to the human-system

[[Page 82098]]

interface. Design Commitment 4 pertains to the HFE program verification 
and validation implementation. The information developed by 
Westinghouse to satisfy these ITAAC is included in Chapter 19 of the 
DCD.
    Location within the Safety Evaluation (SER) where the changes are 
principally described: The details of the NRC's evaluation of 
Westinghouse's design features associated with the HFE DAC are in 
Sections 18.7.6 (Design Commitment 1), 18.5.9 (Design Commitment 2), 
18.2.8 (Design Commitment 3), and 18.11 (Design Commitment 4) of the 
FSER.
    Evaluation of the Criteria in 10 CFR 52.63(a)(1): The additional 
information included in Tier 2 provides detailed design information on 
human factors design that would otherwise have to be addressed through 
verification of implementation of the human factors DAC. Therefore, the 
changes to the DCD eliminate the need for DAC on human factors and meet 
the finality criteria in 10 CFR 52.63(a)(1)(iv).
    Title: Change to Instrumentation and Control DAC and Associated 
ITAAC.
    Item: 2 of 15.
    Description of Change: In the proposed revision to DCD Chapter 7, 
Westinghouse chose the Common Q platform to implement the Protection 
and Safety Monitoring System (PMS) and removed all references to the 
Eagle 21 platform. This design change, coupled with the development of 
other information about the PMS system definition design phase, was the 
basis for Westinghouse's proposed removal of its Tier 1, Chapter 2, 
Section 2.5.2, Design Commitment 11(a) Design Requirements phase from 
Table 2.5.2-8, ``Inspections, Tests, Analyses, and Acceptance 
Criteria,'' for the PMS.
    In its proposed revision to the DCD in Chapter 7, Westinghouse 
altered its design for the Diverse Actuation System (DAS) by 
implementing it with Field Programmable Gate Array (FPGA) technology 
instead of microprocessor-based technology. Additional information 
about the design process for the DAS was added as the basis for 
Westinghouse's proposed completion of its Tier 1, Chapter 2, Section 
2.5.1, Design Commitments 4(a) and 4(b) Design Requirements and System 
Definition phases from Table 2.5.1-4 ``Inspections, Tests, Analyses, 
and Acceptance Criteria'' for the DAS.
    Location within the Safety Evaluation (SER) where the changes are 
principally described: The details of the NRC's evaluation of 
Westinghouse's design features associated with I&C DAC and ITAAC are in 
Sections 7.2.2.3.14, 7.2.5, 7.8.2, 7.9.2, and 7.9.3 of the FSER.
    Evaluation of the Criteria in 10 CFR 52.63(a)(1): Westinghouse 
provided additional information that incorporates the results of the 
design process implementation for the PMS and DAS (which both support 
completion of Design Commitment 11(a) from Table 2.5.2-8 and 4a and 4b 
from Table 2.5.1-4, respectively) into the DCD. The additional 
information included in Tier 2 provides detailed design information on 
I&C design that would otherwise have to be addressed through 
verification of implementation of the I&C DAC. Therefore, the changes 
to the DCD eliminate the need for DAC on I&Cs and meet the finality 
criteria in 10 CFR 52.63(a)(1)(iv).

B. 10 CFR 52.63 Criterion (a)(1)(vii): Contributes to Increased 
Standardization of the Certification Information

    The changes in the AP1000 amendment generally fall into one of two 
categories: (1) Changes that provide additional information or a 
greater level of detail not previously available in the currently-
approved version of the AP1000 DCD (Revision 15); or (2) changes 
requested by COL applicants referencing the AP1000 who would plan to 
include these changes in their application as departures if they were 
not approved in the AP1000 DCR amendment. The Commission concludes that 
both categories of changes meet the 10 CFR 52.63 criterion of 
``contributes to increased standardization.'' The bases for the 
Commission's conclusions, including each category of change, are 
discussed below.
Additional and More Detailed Information
    Westinghouse proposes that the DCD be changed by adding new, more 
detailed design information that expands upon the design information 
already included in the DCD. This information would be used by every 
COL referencing the AP1000 DCR. Incorporating these proposed changes 
into the AP1000 DCR as part of this amendment contributes to the 
increased standardization of the certification information by 
eliminating the possibility of multiple departures. Therefore, these 
changes enhance standardization, and meet the finality criterion for 
changes in 10 CFR 52.63(a)(1)(vii).
Changes for Which COL Applicants Would Otherwise Request Departures
    Westinghouse proposes several changes to its DCD with the stated 
purpose of contributing to increased standardization. Westinghouse 
represents that these changes were requested by the lead COL applicants 
currently referencing the AP1000. The NRC, in meetings with these 
applicants as part of the ``Design-Centered Working Group'' process for 
jointly resolving licensing issues, confirmed that these applicants 
requested these changes and committed to pursue plant-specific 
departures from the AP1000 if Westinghouse did not initiate such 
changes to the AP1000 DCR. Such departures may be pursued by individual 
COL applicants (and licensees) as described in part VIII, ``Processes 
for Changes and Departures'' of the AP1000 DCR (Appendix D to 10 CFR 
part 52). Incorporating these proposed changes into the AP1000 DCR as 
part of this amendment contributes to the increased standardization of 
the certification information by eliminating the possibility of 
multiple departures. Therefore, all Westinghouse-initiated changes for 
the purpose of eliminating plant-specific departures enhance 
standardization, and meet the finality criterion for changes in 10 CFR 
52.63(a)(1)(vii).
    Title: Minimization of Contamination (10 CFR 20.1406(b)).
    Item: 3 of 15.
    Description of Change: In DCD Section 12.1.2.4, Westinghouse 
discussed features incorporated into the amended design certification 
to demonstrate compliance with 10 CFR 52.47(a)(6), which requires that 
a design certification application include the information required by 
10 CFR 20.1406(b), which was adopted in 2007 as part of the general 
revisions to 10 CFR Part 52. This regulation requires design 
certification applicants whose applications are submitted after August 
20, 1997, to describe how the design will minimize, to the extent 
practicable, contamination of the facility and the environment, 
facilitate decommissioning and minimize the generation of radioactive 
waste. The DCD changes are documented in Westinghouse Technical Report 
98, ``Compliance with 10 CFR 20.1406'' (APP-GW-GLN-098), Revision 0 
(ADAMS Accession No. ML071010536). Westinghouse evaluated contaminated 
piping, the SFP air handling systems, and the radioactive waste drain 
system to show that piping and components utilize design features that 
will prevent or mitigate the spread of contamination within the 
facility or the environment. Westinghouse has incorporated 
modifications and features such as elimination of underground 
radioactive tanks, RCPs without mechanical seals, fewer embedded pipes, 
less radioactive

[[Page 82099]]

piping in the auxiliary building and containment vessel, and monitoring 
the radwaste discharge pipeline to demonstrate that the AP1000 design 
certification, as amended, will be in compliance with the subject 
regulation and Regulatory Guidance (RG) 4.21, ``Minimization of 
Contamination and Radioactive Waste Generation: Life-Cycle Planning'' 
(June 2008).
    Location within the SER where the changes are principally 
described: The details of the NRC's evaluation of Westinghouse's design 
features are in Section 12.2 of the FSER.
    Evaluation of the Criteria in 10 CFR 52.63(a)(1)(vii): Inclusion in 
the DCD of the more detailed information about the features for 
minimization of contamination provides additional information to be 
included in the DCD for the AP1000 that increases standardization of 
the AP1000 design. Thus, the changes meet the finality criterion for 
changes in 10 CFR 52.63(a)(1)(vii).
    Title: Extension of Seismic Spectra to Soil Sites and Changes to 
Stability and Uniformity of Subsurface Materials and Foundations.
    Item: 4 of 15.
    Description of Change: In AP1000 DCD Tier 2, Sections 2.5.2 and 
3.7, Westinghouse extended the AP1000 design to sites with five soil 
profiles, ranging from hard rock to soft soil, for Category I 
structures, systems, and components. The certified design included only 
hard rock conditions. To support the technical basis for the extension, 
Westinghouse provided: Seismic analysis methods, procedures for 
analytical modeling, soil-structure interaction analysis with three 
components of earthquake motion, and interaction of non-seismic 
Category I structures with seismic Category I structures. Also, in DCD 
Section 2.5.4, Westinghouse extended the AP1000 design with ``Stability 
and Uniformity of Subsurface Materials and Foundations,'' where the DCD 
presents the requirements related to subsurface materials and 
foundations for COL applicants referencing AP1000 standard design. The 
site-specific information includes excavation, bearing capacity, 
settlement, and liquefaction potential. On February 28, 2011, 
Westinghouse submitted Revision 5 to TR-03, ``Extension of Nuclear 
Island Seismic Analysis to Soil Sites,'' and summarized the report in 
DCD Appendix 3G, to provide more detail about its analyses.
    Location within the SER where the changes are principally 
described:The details of the NRC's evaluation of Westinghouse's design 
features associated with extension of seismic spectra to soil sites are 
in Section 3.7 of the FSER. The details of the NRC's evaluation of 
Westinghouse's design features associated with stability and uniformity 
of subsurface materials and foundations are in Sections 2.5.2 and 2.5.4 
of the FSER.
    Evaluation of the Criteria in 10 CFR 52.63(a)(1): Westinghouse 
submitted a change to the DCD that provides the seismic design and 
supporting analysis for a range of soil conditions representative of 
expected applicants for a COL referencing the AP1000 design. As a 
result, the certified design can be used at more sites without the need 
for departures to provide site-specific analyses or design changes, 
thus leading to a more uniform analysis and seismic design for all the 
AP1000 plants. Including in the DCD the information demonstrating 
adequacy of the design for seismic events for a wider range of soil 
conditions is a change that provides additional information leading to 
increased standardization of this aspect of the design. In addition, 
the change reduces the need for COL applicants to seek departures from 
the current AP1000 design in as much as most sites do not conform to 
the currently approved hard rock sites. Therefore, the change increases 
standardization and meets the finality criterion for changes in 10 CFR 
52.63(a)(1)(vii).
    Title: Long-Term Cooling.
    Item: 5 of 15.
    Description of Change: DCD Tier 2, Section 6.3.8, describes the 
changes to COL information items related to containment cleanliness and 
verification of water sources for long-term recirculation cooling 
following a LOCA. The COL information item related to verification of 
water sources for long-term recirculation cooling following a LOCA was 
closed based on Westinghouse TR-26, ``AP1000 Verification of Water 
Sources for Long-Term Recirculation Cooling Following a LOCA,'' APP-GW-
GLR-079 (ADAMS Accession No. ML102170123) and other information 
contained in DCD Chapter 6. Section 6.3.2.2.7 describes the evaluation 
of the water sources for long-term recirculation cooling following a 
LOCA, including the design and operation of the AP1000 PCCS debris 
screens. DCD Tier 1, Section 2.2.3, includes the associated design 
descriptions and ITAAC.
    The COL information item requires a cleanliness program to limit 
the amount of latent debris in containment consistent with the analysis 
and testing assumptions.
    Location within the SE where the changes are principally described: 
The details of the NRC's evaluation of Westinghouse's design features 
associated with long-term cooling in the presence of LOCA-generated and 
latent debris and General Design Criteria 35 and 38 are in Subsection 
6.2.1.8 of the FSER.
    Evaluation of the Criteria in 10 CFR 52.63(a)(1): Inclusion in the 
DCD of the design and analysis information that demonstrates adequacy 
of long-term core cooling provides additional information leading to 
increased standardization of this aspect of the design. Therefore, the 
change meets the finality criterion for changes in 10 CFR 
52.63(a)(1)(vii).
    Title: Control Room Emergency Habitability System.
    Item: 6 of 15.
    Description of Change: DCD Tier 2, Section 6.4, has undergone 
significant revision. Westinghouse redesigned its main control room 
emergency habitability system to meet control room radiation dose 
requirements using the standard assumed in-leakage of 5 cubic feet per 
minute in the event of a release of radiation. The changes include the 
addition of a single-failure proof passive filter train. The flow 
through the filter train is provided by an eductor downstream of a 
bottled air supply. These changes were prompted by Westinghouse's 
proposal to revise the atmospheric dispersion factors from those 
certified in Revision 15 to larger values to better accommodate COL 
sites. As a result, other design changes were needed to maintain doses 
in the control room within acceptable limits.
    Location within the SER where the changes are principally 
described: The details of the NRC's evaluation of Westinghouse's design 
features associated with radiation dose to personnel under accident 
conditions are in Section 6.4 of the FSER.
    Evaluation of the Criteria in 10 CFR 52.63(a)(1): Incorporation of 
design changes to the main control room ventilation systems would 
contribute to increased standardization of this aspect of the design. 
Therefore, the change meets the finality criterion for changes in 10 
CFR 52.63(a)(1)(vii).
    Title: Changes to the Component Cooling Water System.
    Item: 7 of 15.
    Description of Change: In Revision 18 to AP1000 DCD Tier 2, 
Westinghouse proposed changes to the design of the component cooling 
water system (CCWS) to modify the closure logic for system motor-
operated containment isolation valves and install safety-class relief 
valves on system supply and return lines. The closure logic would close 
the isolation valves upon a high RCP bearing water temperature signal,

[[Page 82100]]

which might be indicative of a RCP heat exchanger tube rupture. This 
change would automatically isolate this potential leak to eliminate the 
possibility of reactor coolant from a faulted heat exchanger 
discharging to portions of the CCWS outside containment.
    Location within the SER where the changes are principally 
described: The details of the NRC's evaluation of Westinghouse's design 
features associated with the CCWS are in Chapter 23, Section V, of the 
FSER.
    Evaluation of the Criteria in 10 CFR 52.63(a)(1): Westinghouse 
included changes to the component cooling water in the DCD. These 
changes will contribute to increased standardization of this aspect of 
the design. Therefore, the change meets the finality criterion for 
changes in 10 CFR 52.63(a)(1)(vii).
    Title: Changes to Instrumentation and Control Systems.
    Item: 8 of 15.
    Description of Change: In AP1000 DCD Tier 2, Sections 7.1 through 
7.3, Westinghouse completed planning activities related to the 
architecture of its safety related I&C protection system, referred to 
as the PMS. Westinghouse also proposed changes to the DCD to reflect 
resolution of PMS interdivisional data communications protocols and 
methods utilized to ensure a secure development and operational 
environment. A secure development and operational environment in this 
context refers to a set of protective actions taken against a 
predictable set of non-malicious acts (e.g., inadvertent operator 
actions, undesirable behavior of connected systems) that could 
challenge the integrity, reliability, or functionality of a digital 
safety system. The establishment of a secure development and 
operational environment for digital safety systems involves: (i) 
Measures and controls taken to establish a secure environment for 
development of the digital safety system against undocumented, unneeded 
and unwanted modifications and (ii) protective actions taken against a 
predictable set of undesirable acts (e.g., inadvertent operator actions 
or the undesirable behavior of connected systems) that could challenge 
the integrity, reliability, or functionality of a digital safety system 
during operations.
    Location within the SER where the changes are principally 
described: The details of the NRC's evaluation of Westinghouse's design 
features associated with I&C systems are in Sections 7.1 through 7.3, 
and 7.9 of NRC's Chapter 7 FSER.
    Evaluation of the Criteria in 10 CFR 52.63(a)(1): Inclusion in the 
DCD of the more detailed information about the I&C architecture and 
communications provides additional information leading to increased 
standardization of this aspect of the design. Therefore, the change 
meets the finality criterion for changes in 10 CFR 52.63(a)(1)(vii).
    Title: Changes to the Passive Core Cooling System--Gas Intrusion.
    Item: 9 of 15.
    Description of Change: In AP1000 DCD Tier 1 and Tier 2, 
Westinghouse proposed changes to the design of the PCCS to add manual 
maintenance vent valves and manual maintenance drain valves, and to 
reroute accumulator discharge line connections in order to address 
concerns related to gas intrusion. In addition, Westinghouse provided 
descriptions of surveillance and venting procedures to verify gas void 
elimination during plant startup and operations. These proposed changes 
are responsive to the actions requested by Generic Letter 2008-01, 
``Managing Gas Accumulation in Emergency Core Cooling, Decay Heat 
Removal, and Containment Spray Systems.''
    The passive core cooling system (PCCS) provides rapid injection of 
borated water, which provides negative reactivity to reduce reactor 
power to residual levels and ensures sufficient core cooling flow. 
Noncondensible gas accumulation in the PCCS has the potential to delay 
injection of borated water, which would impact the moderating and heat 
removal capabilities, thus providing a challenge to the primary fission 
product barrier and maintenance of a coolable core geometry. As part of 
its review, the NRC determined that the proposed changes in the design 
of the PCCS were acceptable for providing protection for design-basis 
events, such as LOCAs.
    Location within the SER where the changes are principally 
described: The NRC's evaluation of proposed changes to the DCD 
associated with changes to the PCCS is in Chapter 23, Section L, of the 
FSER.
    Evaluation of the Criteria in 10 CFR 52.63(a)(1): Inclusion in the 
DCD of the design and analysis information that provides for venting of 
non-condensible gases provides additional information leading to 
increased standardization of this aspect of the design. Therefore, the 
change meets the finality criterion for changes in 10 CFR 
52.63(a)(1)(vii).
    Title: Integrated Head Package--Use of the QuickLoc Mechanism.
    Item: 10 of 15.
    Description of Change: In DCD Tier 2, Section 5.3.1.2, Westinghouse 
describes a revised integrated head package (IHP) design. The inclusion 
of eight QuickLoc penetrations in lieu of the forty-two individual in-
core instrument thimble-tube-assembly penetrations on the reactor 
vessel head is a significant decrease in the number of reactor pressure 
vessel (RPV) closure head penetrations for access to in-core and core 
exit instrumentation. The QuickLoc mechanism allows the removal of the 
RPV closure head without removal of in-core and core exit 
instrumentation and, thus, decreases refueling outage time and overall 
occupational exposure. This head package design has been installed on a 
number of operating plants and, as noted, has several operational and 
safety advantages.
    Location within the SER where the changes are principally 
described: The details of the NRC's evaluation of Westinghouse's design 
features associated with the (1) IHP and QuickLoc mechanism are in 
Section 5.2.3 of the FSER and (2) radiation protection pertaining to 
the addition of the integrated reactor head package and QuickLoc 
connectors are in Subsection 12.4.2.3 of the FSER.
    Evaluation of the Criteria in 10 CFR 52.63(a)(1): Inclusion in the 
DCD of the changes to the IHP would contribute to the increased 
standardization of this aspect of the design. Therefore, the change 
meets the finality criterion for changes in 10 CFR 52.63(a)(1)(vii).
    Title: Reactor Coolant Pump Design.
    Item: 11 of 15.
    Description of Change: In AP1000 DCD Tier 2, Subsection 5.4.1, 
Westinghouse proposed changes related to the RCP design. These changes 
include: Change to a single-stage, hermetically sealed, high inertia, 
centrifugal sealless RCP of canned motor design; use of an externally 
mounted heat exchanger; and change of the RCP flywheel to bimetallic 
construction. These DCD changes are documented in: TR-34, ``AP1000 
Licensing Design Change Document for Generic Reactor Coolant Pump,'' 
APP-GW-GLN-016, November 2006 and in other documentation in response to 
NRC inquiries. The supporting documentation includes an analysis 
demonstrating that failure of the flywheel would not generate a missile 
capable of penetrating the surrounding casing, and, therefore, that 
such failure would not damage the reactor coolant pressure boundary.
    Location within the SER where the changes are principally 
described: The details of the NRC's evaluation of Westinghouse's design 
features associated with the RCP design are in Section 5.4.1 of the 
NRC's Chapter 5 FSER.

[[Page 82101]]

    Evaluation of the Criteria in 10 CFR 52.63(a)(1): Inclusion in the 
DCD of the changes to the RCP would reduce the possibility of plant-
specific departure requests by COL applicants referencing the AP1000 
DCR. Therefore, the change meets the finality criterion for changes in 
10 CFR 52.63(a)(1)(vii).
    Title: Reactor Pressure Vessel Support System.
    Item: 12 of 15.
    Description of Change: The RPV structural support system of the 
AP1000 standard design is designed to provide the necessary support for 
the heavy RPV in the AP1000 standard design. The original anchorage 
design was bolting into embedded plates of the CA04 structural module. 
Subsection 3.8.3.1.1 of the AP1000 DCD Tier 2 would be changed to 
reflect modifications to the RPV support design. In the revised design, 
there are four support ``boxes'' or ``legs'' located at the bottom of 
the RPV's cold leg nozzles. The support boxes are anchored directly to 
the primary shield wall concrete base via steel embedment plates. This 
CA04 structural module is no longer used in the new design. The four 
RPV support boxes are safety-related and the design of the RPV 
associated support structures is consistent with the safe shutdown 
earthquake design of Seismic Category I equipment. Subsections 
3.8.3.5.1 and 5.4.10.2.1 of the DCD are modified.
    Location within the SER where the changes are principally 
described: The details of the NRC's evaluation of Westinghouse's design 
features associated with RPV supports are in Chapter 23, Section R, of 
the FSER.
    Evaluation of the Criteria in 10 CFR 52.63(a)(1): Inclusion in the 
DCD of the changes to the RPV supports contributes to the increased 
standardization of this aspect of the design. Therefore, the change 
meets the finality criterion for changes in 10 CFR 52.63(a)(1)(vii).
    Title: Spent Fuel Pool Decay Heat Analysis and Associated Design 
Changes.
    Item: 13 of 15.
    Description of Change: In AP1000 DCD Tier 2, Section 9.1.3, 
Westinghouse proposed changes to the SFP cooling system. Westinghouse 
proposed to increase the number of spent fuel storage locations from 
619 to 889 fuel assemblies and implement the following associated 
design changes: (1) Increase in component cooling system (CCS) pump 
design capacity, (2) increase in the CCS supply temperature to plant 
components, and (3) changes in the CCS parameters related to the RCPs. 
The increase in the number of assemblies affects the decay heat 
removal/SFP heatup analyses. The supporting bases for these DCD changes 
are documented in: TR-111, ``Component Cooling System and Service Water 
System Changes Required for Increased Heat Loads,'' APP-GW-GLN-111, 
Revision 2, dated May 2007 (ADAMS Accession No. ML071500563); TR-103, 
``Fluid System Changes,'' APP-GW-GLN-019, Revision 2, dated October 
2007 (ADAMS Accession No. ML072830060); TR-108, ``AP1000 Site Interface 
Temperature Limits,'' APP-GW-GLN-108, Revision 2, dated September 2007 
(ADAMS Accession No. ML072750137), and TR-APP-GW-GLR-097, ``Evaluation 
of the Effect of the AP1000 Enhanced Shield Building on the Containment 
Response and Safety Analysis,'' Revision 3, dated June 2011 (ADAMS 
Accession No. ML11168A041).
    Location within the SER where the changes are principally 
described: The details of the NRC's evaluation of Westinghouse's design 
features associated with the SFP decay heat analysis are in Section 
9.2.2 of the FSER.
    Evaluation of the Criteria in 10 CFR 52.63(a)(1): Inclusion in the 
DCD of the changes to the SFP decay heat analysis would contribute to 
the increased standardization of this aspect of the design. Therefore, 
the change meets the finality criterion for changes in 10 CFR 
52.63(a)(1)(vii).
    Title: Spent Fuel Rack Design and Criticality Analysis.
    Item: 14 of 15.
    Description of Change: In DCD Tier 2, Section 9.1.2, Westinghouse 
proposed changes to the spent fuel racks: (1) To increase the storage 
capacity by 270 additional fuel assemblies, and (2) to integrate a new 
neutron poison into the rack design. These changes included a different 
rack design and associated structural analysis and a revised 
criticality analysis. These DCD changes are documented in TR-54, 
``Spent Fuel Storage Racks Structure and Seismic Analysis,'' APP-GW-
GLR-033, Revision 4, dated June 2, 2010 (ADAMS Accession No. 
ML101580475); and TR-65, ``Spent Fuel Storage Racks Criticality 
Analysis,'' APP-GW-GLR-029, Revision 2, dated January 5, 2010 (ADAMS 
Accession No. ML100082093).
    Location within the SER where the changes are principally 
described: The details of the NRC's evaluation of Westinghouse's design 
features associated with the spent fuel rack design and criticality 
analysis are in Section 9.1.2 of the FSER.
    Evaluation of the Criteria in 10 CFR 52.63(a)(1): Inclusion in the 
DCD of the changes to the spent fuel rack design and criticality 
analysis would contribute to the increased standardization of this 
aspect of the design. Therefore, the change meets the finality 
criterion for changes in 10 CFR 52.63(a)(1)(vii).
    Title: Vacuum Relief System.
    Item: 15 of 15.
    Description of Change: In Revision 18 to AP1000 DCD Tier 2, 
Chapters 3, 6, 7, 9, and 16, Westinghouse proposed a change to the 
design of the containment, which adds a vacuum relief system to the 
existing containment air filtration system vent line penetration. The 
proposed vacuum relief system consists of redundant vacuum relief 
devices inside and outside containment sized to prevent differential 
pressure between containment and the shield building from exceeding the 
design value of 1.7 psig, which could occur under extreme temperature 
conditions.
    Each relief flow path consists of a check valve inside containment 
and a motor operated butterfly valve outside of containment. The 
redundant relief devices outside containment share a common inlet line 
with redundant outside air flow entry points. The outlet lines 
downstream of the outside containment relief devices are routed to a 
common header connected to the vent line penetration. The redundant 
relief devices inside containment share a common inlet line from the 
vent line penetration and have independent discharge lines into 
containment.
    Location within the SER where the changes are principally 
described: The details of the NRC's evaluation of Westinghouse's design 
features associated with the addition of the vacuum relief system are 
in Chapter 23, Section W, of the FSER.
    Evaluation of the Criteria in 10 CFR 52.63(a)(1): Inclusion in the 
DCD of the introduction of a containment vacuum relief system would 
contribute to the increased standardization of this aspect of the 
design. Therefore, the change meets the finality criterion for changes 
in 10 CFR 52.63(a)(1)(vii).
Other Technical Changes
    The above discussion on selected technical changes is illustrative 
of the NRC's consideration of applicability of the finality provisions 
to other technical changes proposed from Revision 15 of the DCD, which 
are reflected in Revision 19. As noted earlier, Westinghouse provided 
its proposed basis for each change as part of the application. The NRC 
concludes that the other technical changes meet one or more of the 
finality criteria and thus do not constitute a violation of the 
finality provisions of 10 CFR 52.63.

[[Page 82102]]

Changes Addressing Compliance With Aircraft Impact Assessment Rule (10 
CFR 50.150)
    The final rule amends the existing AP1000 DCR, in part, to address 
the requirements of the AIA rule. The AIA rule itself mandated that a 
DCR be revised, if not during the DCR's current term, then no later 
than its renewal to address the requirements of the AIA rule. In 
addition, the AIA rule provided that any COL issued after the effective 
date of the final AIA rule must reference a DCR complying with the AIA 
rule, or itself demonstrate compliance with the AIA rule. The AIA rule 
may therefore be regarded as inconsistent with the finality provisions 
in 10 CFR 52.63(a) and Section VI of the AP1000 DCR. However, the NRC 
provided an administrative exemption from these finality requirements 
when the final AIA rule was issued (74 FR 28112; June 12, 2009). 
Accordingly, the NRC has already addressed the backfitting implications 
of applying the AIA rule to the AP1000 with respect to the AP1000 and 
referencing COL applicants.
Conclusion
    The amended AP1000 DCR does not constitute backfitting and is 
consistent with the finality provisions in 10 CFR part 52. Accordingly, 
the NRC has not prepared a backfit analysis or documented evaluation 
for this rule.

XIII. Congressional Review Act

    In accordance with the Congressional Review Act of 1996, 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 52

    Administrative practice and procedure, Antitrust, Backfitting, 
Combined license, Early site permit, Emergency planning, Fees, 
Incorporation by reference, Inspection, Limited work authorization, 
Nuclear power plants and reactors, Probabilistic risk assessment, 
Prototype, Reactor siting criteria, Redress of site, Reporting and 
recordkeeping requirements, Standard design, Standard design 
certification.

    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 52.

PART 52--LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER 
PLANTS

0
1. The authority citation for 10 CFR part 52 continues to read as 
follows:

    Authority: Secs. 103, 104, 161, 182, 183, 186, 189, 68 Stat. 
936, 948, 953, 954, 955, 956, as amended, sec. 234, 83 Stat. 444, as 
amended (42 U.S.C. 2133, 2201, 2232, 2233, 2236, 2239, 2282); secs. 
201, 202, 206, 88 Stat. 1242, 1244, 1246, as amended (42 U.S.C. 
5841, 5842, 5846); sec. 1704, 112 Stat. 2750 (44 U.S.C. 3504 note); 
Energy Policy Act of 2005, Pub. L. 109-58, 119 Stat. 594 (2005), 
secs. 147 and 149 of the Atomic Energy Act.


0
2. In Appendix D to 10 CFR Part 52:
0
a. In Section III, revise paragraphs A and D;
0
b. In Section IV, revise paragraph A.3 and add paragraph A.4;
0
c. In Section V, redesignate paragraph A as paragraph A.1 and add a new 
paragraph A.2;
0
d. In Section VI, revise paragraphs B.1, B.2, B.7, and E;
0
e. In Section VIII, revise the introductory text of paragraph B.5.b, 
redesignate paragraphs B.5.d, B.5.e, and B.5.f as paragraphs B.5.e, 
B.5.f, and B.5.g, respectively, and add a new paragraph B.5.d, and 
revise paragraphs B.6.b and B.6.c; and
0
f. In Section X, revise paragraph A.1 and add a new paragraph A.4.
    The revisions and additions read as follows:

Appendix D to Part 52--Design Certification Rule for the AP1000 Design

* * * * *

III. Scope and Contents

    A. Tier 1, Tier 2 (including the investment protection short-
term availability controls in Section 16.3), and the generic TSs in 
the AP1000 Design Control Document, Revision 19, (Public Version) 
(AP1000 DCD), APP-GW-GL-702, dated June 13, 2011, are approved for 
incorporation by reference by the Director of the Office of the 
Federal Register under 5 U.S.C. 552(a) and 1 CFR part 51. Copies of 
the generic DCD may be obtained from Stanley E. Ritterbusch, 
Manager, AP1000 Design Certification, Westinghouse Electric Company, 
1000 Westinghouse Drive, Cranberry Township, Pennsylvania 16066, 
telephone (412) 374-3037. A copy of the generic DCD is also 
available for examination and copying at the NRC's PDR, Room O-1F21, 
One White Flint North, 11555 Rockville Pike, Rockville, Maryland 
20852. Copies are available for examination at the NRC Library, Two 
White Flint North, 11545 Rockville Pike, Rockville, Maryland 20852, 
telephone (301) 415-5610, email [email protected]. The DCD 
can also be viewed online in the NRC Library at http://www.nrc.gov/reading-rm/adams.html by searching under ADAMS Accession No. 
ML11171A500. All approved material is available for inspection at 
the National Archives and Records Administration (NARA). For 
information on the availability of this material at NARA, call (202) 
741-6030 or go to http://www.archives.gov/federal-register/cfr/ibr-locations.html.
* * * * *
    D. 1. If there is a conflict between the generic DCD and either 
the application for the initial design certification of the AP1000 
design or NUREG-1793, ``Final Safety Evaluation Report Related to 
Certification of the Westinghouse Standard Design,'' and Supplement 
No. 1, then the generic DCD controls.
    2. If there is a conflict between the generic DCD and either the 
application for Amendment 1 to the design certification of the 
AP1000 design or NUREG-1793, ``Final Safety Evaluation Report 
Related to Certification of the Westinghouse Standard Design,'' 
Supplement No. 2, then the generic DCD controls.
* * * * *

IV. Additional Requirements and Restrictions

    A. * * *
    3. Include, in the plant-specific DCD, the sensitive 
unclassified non-safeguards information (including proprietary 
information) and safeguards information referenced in the AP1000 
DCD.
    4. Include, as part of its application, a demonstration that an 
entity other than Westinghouse is qualified to supply the AP1000 
design, unless Westinghouse supplies the design for the applicant's 
use.
* * * * *

V. Applicable Regulations

    A. * * *
    2. The regulations that apply to those portions of the AP1000 
design approved by Amendment 1 are in 10 CFR parts 20, 50, 73, and 
100, codified as of December 30, 2011, that are applicable and 
technically relevant, as described in the Supplement No. 2 of the 
FSER (NUREG-1793).
* * * * *

VI. Issue Resolution

* * * * *
    B. * * *
    1. All nuclear safety issues, except for the generic TS and 
other operational requirements, associated with the information in 
the FSER and Supplement Nos. 1 and 2, Tier 1, Tier 2 (including 
referenced information, which the context indicates is intended as 
requirements, and the investment protection short-term availability 
controls in Section 16.3 of the DCD), and the rulemaking records for 
initial certification and Amendment 1 of the AP1000 design;
    2. All nuclear safety and safeguards issues associated with the 
referenced sensitive unclassified non-safeguards information 
(including proprietary information) and safeguards information 
which, in context, are intended as requirements in the generic DCD 
for the AP1000 design;
* * * * *
    7. All environmental issues concerning severe accident 
mitigation design alternatives

[[Page 82103]]

associated with the information in the NRC's EA for the AP1000 
design, Appendix 1B of Revision 15 of the generic DCD, the NRC's 
final EA for Amendment 1 to the AP1000 design, and Appendix 1B of 
Revision 19 of the generic DCD, for plants referencing this appendix 
whose site parameters are within those specified in the severe 
accident mitigation design alternatives evaluation.
* * * * *
    E. The NRC will specify at an appropriate time the procedures to 
be used by an interested person who wishes to review portions of the 
design certification or references containing safeguards information 
or sensitive unclassified non-safeguards information (including 
proprietary information, such as trade secrets or financial 
information obtained from a person that are privileged or 
confidential (10 CFR 2.390 and 10 CFR part 9)), for the purpose of 
participating in the hearing required by 10 CFR 52.85, the hearing 
provided under 10 CFR 52.103, or in any other proceeding relating to 
this appendix in which interested persons have a right to request an 
adjudicatory hearing.
* * * * *

VIII. Processes for Changes and Departures

* * * * *
    B. * * *
    5. * * *
    b. A proposed departure from Tier 2, other than one affecting 
resolution of a severe accident issue identified in the plant-
specific DCD or one affecting information required by 10 
CFR52.47(a)(28) to address 10 CFR 50.150, requires a license 
amendment if it would:
* * * * *
    d. If an applicant or licensee proposes to depart from the 
information required by 10 CFR 52.47(a)(28) to be included in the 
FSAR for the standard design certification, then the applicant or 
licensee shall consider the effect of the changed feature or 
capability on the original assessment required by 10 CFR 50.150(a). 
The applicant or licensee must also document how the modified design 
features and functional capabilities continue to meet the assessment 
requirements in 10 CFR 50.150(a)(1) in accordance with Section X of 
this appendix.
* * * * *
    6. * * *
    b. A licensee who references this appendix may not depart from 
the following Tier 2* matters without prior NRC approval. A request 
for a departure will be treated as a request for a license amendment 
under 10 CFR 50.90.
    (1) Maximum fuel rod average burn-up.
    (2) Fuel principal design requirements.
    (3) Fuel criteria evaluation process.
    (4) Fire areas.
    (5) Reactor coolant pump type.
    (6) Small-break loss-of-coolant accident (LOCA) analysis 
methodology.
    (7) Screen design criteria.
    (8) Heat sink data for containment pressure analysis.
    c. A licensee who references this appendix may not, before the 
plant first achieves full power following the finding required by 10 
CFR 52.103(g), depart from the following Tier 2* matters except 
under paragraph B.6.b of this section. After the plant first 
achieves full power, the following Tier 2* matters revert to Tier 2 
status and are subject to the departure provisions in paragraph B.5 
of this section.
    (1) Nuclear Island structural dimensions.
    (2) American Society of Mechanical Engineers Boiler & Pressure 
Vessel Code (ASME Code) piping design and welding restrictions, and 
ASME Code Cases.
    (3) Design Summary of Critical Sections.
    (4) American Concrete Institute (ACI) 318, ACI 349, American 
National Standards Institute/American Institute of Steel 
Construction (ANSI/AISC)-690, and American Iron and Steel Institute 
(AISI), ``Specification for the Design of Cold Formed Steel 
Structural Members, Part 1 and 2,'' 1996 Edition and 2000 
Supplement.
    (5) Definition of critical locations and thicknesses.
    (6) Seismic qualification methods and standards.
    (7) Nuclear design of fuel and reactivity control system, except 
burn-up limit.
    (8) Motor-operated and power-operated valves.
    (9) Instrumentation and control system design processes, 
methods, and standards.
    (10) Passive residual heat removal (PRHR) natural circulation 
test (first plant only).
    (11) Automatic depressurization system (ADS) and core make-up 
tank (CMT) verification tests (first three plants only).
    (12) Polar crane parked orientation.
    (13) Piping design acceptance criteria.
    (14) Containment vessel design parameters, including ASME Code, 
Section III, Subsection NE.
    (15) Human factors engineering.
    (16) Steel composite structural module details.
* * * * *

X. Records and Reporting

    A. * * *
    1. The applicant for this appendix shall maintain a copy of the 
generic DCD that includes all generic changes it makes to Tier 1 and 
Tier 2, and the generic TS and other operational requirements. The 
applicant shall maintain sensitive unclassified non-safeguards 
information (including proprietary information) and safeguards 
information referenced in the generic DCD for the period that this 
appendix may be referenced, as specified in Section VII of this 
appendix.
* * * * *
    4.a. The applicant for the AP1000 design shall maintain a copy 
of the AIA performed to comply with the requirements of 10 CFR 
50.150(a) for the term of the certification (including any period of 
renewal).
    b. An applicant or licensee who references this appendix shall 
maintain a copy of the AIA performed to comply with the requirements 
of 10 CFR 50.150(a) throughout the pendency of the application and 
for the term of the license (including any period of renewal).
* * * * *

    Dated at Rockville, Maryland, this 22nd day of December 2011.

    For the Nuclear Regulatory Commission.
Annette L. Vietti-Cook,
Secretary of the Commission.
[FR Doc. 2011-33266 Filed 12-29-11; 8:45 am]
BILLING CODE 7590-01-P