[Federal Register Volume 86, Number 65 (Wednesday, April 7, 2021)]
[Notices]
[Pages 18076-18080]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2021-07172]


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NUCLEAR REGULATORY COMMISSION

[Docket Nos. 50-424 and 50-425; NRC-2021-0088]


Southern Nuclear Operating Company, Inc; Vogtle Electric 
Generating Plant, Units 1 and 2

AGENCY: Nuclear Regulatory Commission.

ACTION: Environmental assessment and finding of no significant impact; 
issuance.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is considering 
issuance of exemptions that would permit the Southern Nuclear Operating 
Company, Inc. (SNC, the licensee) to make changes to the Vogtle 
Electric Generating Plant (Vogtle), Unit 1 and 2, licensing basis. 
Specifically, the licensee is seeking exemptions that would allow the 
use of both a risk-informed approach to address safety issues discussed 
in Generic Safety Issue (GSI)-191 and to close Generic Letter (GL) 
2004-02. The NRC staff is issuing a final Environmental Assessment (EA) 
and final Finding of No Significant Impact (FONSI) associated with the 
proposed exemptions.

DATES: The EA and FONSI referenced in this document are available on 
April 7, 2021.

ADDRESSES: Please refer to Docket ID NRC-2021-0088 when contacting the 
NRC about the availability of information regarding this document. You 
may obtain publicly available information related to this document 
using any of the following methods:
     Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2021-0088. Address 
questions about Docket IDs in Regulations.gov to Stacy Schumann; 
telephone: 301-415-0624; email: [email protected]. For technical 
questions, contact the individual listed in the FOR FURTHER INFORMATION 
CONTACT section of this document.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly available documents online in the 
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``Begin Web-based ADAMS 
Search.'' For problems with ADAMS, please contact the NRC's Public 
Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or 
by email to [email protected]. For the convenience of the reader, 
instructions about obtaining materials referenced in this document are 
provided in the ``Availability of Documents'' section.
     Attention: The PDR, where you may examine and order copies 
of public documents, is currently closed. You may submit your request 
to the PDR via email at [email protected] or call 1-800-379-4209 or 
301-415-4737, between 8:00 a.m. and 4:00 p.m. (EST), Monday through 
Friday, except Federal holidays.

FOR FURTHER INFORMATION CONTACT: John G. Lamb, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001; telephone: 301-415-3100, email: [email protected].

SUPPLEMENTARY INFORMATION:

I. Introduction

    The NRC is considering issuance of exemptions and license 
amendments of Renewed Facility Operating Licenses NPF-68 and NPF-81, 
issued to Southern Nuclear Operating Company (SNC, the licensee), for 
operation of the Vogtle Electric Generating Plant (Vogtle), Units 1 and 
2, located in Burke County, Georgia. The license amendments and 
regulatory exemptions would allow SNC to incorporate the use of a risk-
informed approach to address safety issues discussed in GSI-191 and to 
close GL 2004-02. Therefore, as required by section 51.21 of title 10 
of the Code of Federal Regulations (10 CFR), ``Criteria for and 
identification of licensing and regulatory actions requiring 
environmental assessments,'' the NRC performed an EA. Based on the 
results of the EA that follows, and in accordance with 10 CFR 51.31(a), 
the NRC has determined not to prepare an environmental impact statement 
for the proposed licensing action and is issuing a FONSI.
    The NRC established GSI-191 to determine whether the transport and 
accumulation of debris from a loss-of-coolant accident (LOCA) in the 
pressurized-water reactor (PWR) containment structure would impede the 
operation of the emergency core cooling system (ECCS) or containment 
spray system (CSS). A LOCA within the containment structure is assumed 
to be caused by a break in the primary coolant loop piping. Water 
discharged from the pipe break and debris would collect on the 
containment structure floor and within the containment emergency sump. 
During this type of accident, the ECCS and CSS would initially draw 
cooling water from the refueling water storage tank (RWST). However, 
realigning the ECCS pumps to the containment emergency sump would 
provide long-term cooling of the reactor core. Therefore, successful 
long-term cooling depends on the ability of the containment emergency 
sump to provide adequate flow to the residual heat removal (RHR) 
recirculation pumps for extended periods of time.
    One of the concerns addressed by the implementation of GSI-191 is 
that material, such as insulation installed on piping and components, 
within the containment structure could be dislodged by jets of high-
pressure water and steam during the LOCA. Water, along with debris, 
would accumulate at the bottom of the containment structure and flow 
towards the emergency sumps. Insulation and other fibrous material 
could block the emergency sump screens and suction strainers, which in 
turn could prevent the containment emergency sump from providing 
adequate water flow to the residual heat removal pumps (for more 
information, see NUREG-0897, ``Containment Emergency Sump 
Performance,'' Revision 1).
    By letter dated September 30, 2019, the NRC issued the ``Final 
Staff Evaluation for Vogtle Electric Generating Plant, Units 1 and 2, 
Systematic Risk-Informed Assessment of Debris Technical Report (EPID L-
2017-TOP-0038).'' SNC proposes to use the ``Final Staff Evaluation for 
Vogtle Electric Generating Plant, Units 1 and 2, Systematic Risk-
Informed Assessment of Debris Technical Report'' to demonstrate 
compliance with 10 CFR 50.46 through both plant-specific testing and a 
risk-informed approach (described in more detail in the following 
paragraphs). Since the use of a risk-

[[Page 18077]]

informed approach is not recognized in the regulations, SNC requested 
an exemption to 10 CFR 50.46(a)(1) for certain conditions associated 
with the treatment of debris. If approved, the proposed action would 
result in physical modifications to reduce the overall height of the 
RHR sump strainers at Vogtle, Units 1 and 2, by removing the two top 
disks from each stack of the RHR strainer assemblies. In addition, 
emergency operating procedures would be revised to inject additional 
RWST inventory for piping breaks that do not initiate containment 
sprays. These physical and procedural modifications will ensure that 
the RHR strainers are completely submerged for an increased number of 
postulated LOCA scenarios, which reduces the risk associated with post-
accident debris effects.

II. Environmental Assessment

Description of the Proposed Action

    The proposed action would allow SNC to incorporate the use of a 
risk-informed approach to address safety issues discussed in GSI-191 
and to close GL 2004-02. The proposed action is in response to the 
licensee's application dated August 17, 2020, as supplemented by 
letters dated December 17, 2020, and February 15, 2021.

Need for the Proposed Action

    The proposed action is needed because, as the holder of Renewed 
Facility Operating License Nos. NPF-68 and NPF-81, SNC is expected to 
address the safety issues discussed in GSI-191 and to close GL 2004-02 
with respect to Vogtle, Units 1 and 2. Consistent with SECY-12-0093, 
SNC chose an approach which requires, in part, that SNC request that 
the NRC amend the renewed facility operating licenses and grant certain 
regulatory exemption for each unit.

Environmental Impacts of the Proposed Action

    The NRC staff has completed its evaluation of the environmental 
impacts of the proposed action.
    Vogtle, Units 1 and 2, are located on an approximately 3,169-acre 
site on a Coastal Plain bluff on the southwest side of the Savannah 
River in Burke County, Georgia, approximately 15 miles east-northeast 
of Waynesboro, Georgia, and 26 miles southeast of Augusta, Georgia.
    Vogtle consists of two four-loop Westinghouse PWR units. The 
reactor core of each unit heats water, which is pumped to four steam 
generators, where the heated water is converted to steam. The steam is 
then used to turn turbines, which are connected to electrical 
generators that produce electricity. A simplified drawing of a PWR can 
be viewed at https://www.nrc.gov/reactors/pwrs.html.
    The reactor, steam generators, and other components are housed in a 
concrete and steel containment structure (building). The containment 
structure is a reinforced concrete cylinder with a concrete slab base 
and hemispherical dome. A welded steel liner is attached to the inside 
face of the concrete shell to ensure a high degree of leak tightness. 
In addition, the 4-foot (1.2-meter)-thick concrete walls of the 
containment structure serve as a radiation shield. Additional 
information on the plant structures and systems, as well as the 
environmental impact statement for license renewal, can be found in 
NUREG-1437, Supplement 34, ``Generic Environmental Impact Statement for 
License Renewal of Nuclear Plants: Supplement 34 Regarding Vogtle 
Electric Generating Plant, Units 1 and 2.''
    Radiological and non-radiological impacts on the environment that 
may result from issuing the license amendments and granting the 
regulatory exemptions are summarized in the following sections.
Non-Radiological Impacts
    The proposed action would reduce the overall height of the RHR sump 
strainers by removing the two top disks from each stack of the RHR 
strainer assemblies. No other changes would be made to structures or 
land use within the Vogtle, Units 1 and 2, site, and non-radiological 
liquid effluents or gaseous emissions would not change. In addition, 
the license amendments and regulatory exemptions would not result in 
any changes to the use of resources or create any new environmental 
impacts.
    Therefore, there would be no non-radiological impacts to 
environmental resources or any irreversible and irretrievable 
commitments.
    Since issuing the license amendment and granting the regulatory 
exemption would not result in environmental effects, there would be no 
non-radiological cumulative impact.
Radiological Impacts
Radioactive Gaseous and Liquid Effluents and Solid Waste
    Vogtle, Units 1 and 2, use waste treatment systems to collect, 
process, recycle, and dispose of gaseous, liquid, and solid wastes that 
contain radioactive material in a safe and controlled manner within NRC 
and Environmental Protection Agency radiation safety standards.
    The license amendments and regulatory exemptions would not require 
any physical change to the nuclear plant or reactor operations that 
would affect the types and quantities of radioactive material generated 
during plant operations; therefore, there would be no changes to the 
plant radioactive waste treatment systems. A detailed description of 
the Vogtle radioactive waste handling and disposal activities is 
presented in Chapter 2.1.4 of Supplement 34 to NUREG-1437.
Radioactive Gaseous Effluents
    The objectives of the Vogtle gaseous waste management system (GWMS) 
are to process and control the release of radioactive gaseous effluents 
into the environment to be within the requirements of 10 CFR 20.1301, 
``Dose limits for individual members of the public,'' and to be 
consistent with the as low as is reasonably achievable (ALARA) dose 
objectives set forth in appendix I to 10 CFR part 50. The GWMS is 
designed so that radiation exposure to plant workers is within the dose 
limits in 10 CFR 20.1201, ``Occupational dose limits for adults.''
    The license amendments and regulatory exemptions would not require 
any physical change to the nuclear plant or reactor operations that 
would affect the release of radioactive gaseous effluents into the 
environment; therefore, there would be no changes to the GWMS. The 
existing equipment and plant procedures that control radioactive 
releases to the environment would continue to be used to maintain 
radioactive gaseous releases within the dose limits in 10 CFR 20.1301 
and the ALARA dose objectives in appendix I to 10 CFR part 50.
Radioactive Liquid Effluents
    The function of the Vogtle liquid waste processing system (LWPS) is 
to collect and process radioactive liquid wastes to reduce 
radioactivity and chemical concentrations to levels acceptable for 
discharge to the environment or to recycle the liquids for use in plant 
systems. The principal objectives of the LWPS are to collect liquid 
wastes that may contain radioactive material and to maintain sufficient 
processing capability so that liquid waste may be discharged to the 
environment below the regulatory limits in 10 CFR 20.1301 and 
consistent with the ALARA dose objectives in appendix I to 10 CFR part 
50. The waste is routed through a monitor that measures the 
radioactivity and can automatically

[[Page 18078]]

terminate the release in the event radioactivity exceeds predetermined 
levels. The liquid waste is discharged into the main cooling reservoir. 
The entire main cooling reservoir is within the Vogtle site boundary 
and the public is prohibited from access to the area.
    The license amendments and regulatory exemptions would not require 
any physical change to the nuclear plant or reactor operations that 
would affect the release of radioactive liquid effluents into the 
environment; therefore, there would be no changes to the LWPS. The 
existing equipment and plant procedures that control radioactive 
releases to the environment would continue to be used to maintain 
radioactive liquid releases within the dose limits in 10 CFR 20.1301 
and the ALARA dose objectives in appendix I to 10 CFR part 50.
Radioactive Solid Wastes
    The function of the Vogtle solid waste processing system (SWPS) is 
to process, package, and store the solid radioactive wastes generated 
by nuclear plant operations until they are shipped off site to a vendor 
for further processing or for permanent disposal at a licensed burial 
facility, or both. The storage areas have restricted access and 
shielding to reduce radiation rates to plant workers. The principal 
objectives of the SWPS are to package and transport the waste in 
compliance with NRC regulations in 10 CFR part 61, ``Licensing 
Requirements for Land Disposal of Radioactive Waste,'' and 10 CFR part 
71, ``Packaging and Transportation of Radioactive Material,'' and the 
U.S. Department of Transportation regulations in 49 CFR parts 170 
through 179; and to maintain the dose limits in 10 CFR 20.1201, 10 CFR 
20.1301, and appendix I to 10 CFR part 50.
    The existing equipment and plant procedures that control 
radioactive solid waste handling would continue to be used to maintain 
exposures within the dose limits in 10 CFR 20.1201, 10 CFR 20.1301, and 
10 CFR part 50 appendix I. Thus, there will be no changes to the SWPS 
and issuing the license amendment and granting the regulatory exemption 
will not result in any physical changes to the nuclear plant or reactor 
operations that would affect the release of radioactive solid wastes 
into the environment.
Occupational Radiation Doses
    The license amendments and regulatory exemptions would not require 
any physical change to the nuclear plant (except for reducing the 
overall height of the RHR sump strainers) or changes to reactor 
operations; therefore, there would be no change to any in-plant 
radiation sources. In addition, no new operator actions would be 
implemented that could affect occupational radiation exposure. The 
licensee's radiation protection program monitors radiation levels 
throughout the nuclear plant to establish appropriate work controls, 
training, temporary shielding, and protective equipment requirements so 
that worker doses remain within the dose limits in 10 CFR part 20, 
subpart C, ``Occupational Dose Limits.'' The license amendments and 
regulatory exemptions would not change radiation levels within the 
nuclear plant and, therefore, there would be no increased radiological 
impact to the workers.
Offsite Radiation Dose
    The primary sources of offsite doses to members of the public from 
the Vogtle are radioactive gaseous and liquid effluents. As discussed 
previously, there would be no change to the operation of Vogtle 
radioactive gaseous and liquid waste management systems or their 
ability to perform their intended functions. Also, there would be no 
change to the Vogtle radiation monitoring system and procedures used to 
control the release of radioactive effluents in accordance with 
radiation protection standards in 10 CFR 20.1301, 40 CFR 190, 
``Environmental Radiation Protection Standards for Nuclear Power 
Operations,'' and the ALARA dose objectives in appendix I to 10 CFR 
part 50.
    Based on this information, the offsite radiation doses to members 
of the public would not change and would continue to be within 
regulatory limits. Therefore, the license amendments and regulatory 
exemptions would not change offsite dose levels and, consequently, 
there would be no significant health effects from the proposed action.
Design-Basis Accidents
    Design-basis accidents at Vogtle, Units 1 and 2, are evaluated by 
both the licensee and the NRC to ensure that the units would continue 
to withstand the spectrum of postulated accidents without undue hazard 
to the public health and safety and to ensure the protection of the 
environment.
    Separate from the environmental review, the NRC is evaluating the 
licensee's technical and safety analyses provided in support of the 
proposed action. The results of the safety review and conclusion will 
be documented in a publicly available safety evaluation. The safety 
evaluation must conclude that the proposed action will (1) provide 
reasonable assurance that the health and safety of the public will not 
be endangered by operation in the proposed manner, (2) provide 
reasonable assurance that such activities will be conducted in 
compliance with the Commission's regulations, and (3) not be inimical 
to the common defense and security or to the health and safety of the 
public. The NRC would not take the proposed action absent such a safety 
conclusion.
Radiological Cumulative Impacts
    The radiological dose limits for protection of the public and plant 
workers have been developed by the NRC and the Environmental Protection 
Agency to address the cumulative impact of acute and long-term exposure 
to radiation and radioactive material. These dose limits are codified 
in 10 CFR part 20, ``Standards for Protection Against Radiation,'' and 
40 CFR part 190.
    Cumulative radiation doses are required to be within the limits set 
forth in the regulations cited in the previous paragraph. The license 
amendments and exemptions would not require physical changes to the 
plant (except for reducing the overall height of the RHR sump 
strainers) or changes to plant activities; in-plant radiation sources 
would not change and offsite radiation dose to members of the public 
would not change. Therefore, there would be no significant cumulative 
radiological impact from the proposed action.
Radiological Impacts Summary
    Based on these evaluations, the license amendments and exemptions 
would not result in any significant radiological impacts. Therefore, 
the safety evaluation must conclude that the proposed action will (1) 
provide reasonable assurance that the health and safety of the public 
will not be endangered by operation in the proposed manner, (2) provide 
reasonable assurance that such activities will be conducted in 
compliance with the Commission's regulations, and (3) not be inimical 
to the common defense and security or to the health and safety of the 
public. The NRC would not take the proposed action absent such a safety 
conclusion.

Environmental Impacts of the Alternatives to the Proposed Action

    As discussed earlier, licensees have options for responding to GL 
2004-02 and for demonstrating compliance with 10 CFR 50.46. Consistent 
with these options, as an alternative to the proposed action, the 
licensee could choose to remove and replace insulation

[[Page 18079]]

within the reactor containment building. This would require the 
physical removal and disposal of significant amounts of insulation from 
a radiation area within the reactor containment building and the 
installation of new insulation less likely to impact sump performance.
    Removal of the existing insulation from the containment building 
would generate radiologically contaminated waste. SNC estimated that 
between 4,000 and 5,000 cubic feet of fiberglass insulation per unit 
would have to be removed from Vogtle, Units 1 and 2, containment. This 
estimate is based on calculations performed for South Texas Project 
(STP) and the similarities between Vogtle and STP. The removed 
insulation would require special handling and packaging so that it 
could be safely transported from the site. The licensee would likely 
use existing facilities to process and store this material until it 
could be transported to a low-level radioactive or hazardous waste 
disposal site. Energy (fuel) would be expended to transport the 
insulation and land would be expended at the disposal site.
    The removal of the old insulation and installation of new 
insulation would expose workers to radiation. In its application, SNC 
estimated generically that the expected total dose for replacing 
insulation in Vogtle, Units 1 and 2, is about 200 rem (100 rem per 
unit), based on the calculations performed for STP. The NRC reviewed 
NUREG-0713, Volume 40, ``Occupational Radiation Exposure at Commercial 
Nuclear Power Reactors and Other Facilities 2018: Fifty-First Annual 
Report,'' and determined that SNC's average baseline collective 
radiation exposure is approximately 62 person-rem. This additional 200 
person-rem collective exposure would be shared across the entire work 
force involved with removing and reinstalling insulation. In SECY-12-
0093, the NRC attempted to develop a total occupational dose estimate 
for the work involved in insulation removal and replacement associated 
with GSI-191. Due to uncertainties in the scope of work required to 
remove and replace insulation at a specific nuclear plant and other 
site-specific factors such as source term and hazardous materials, the 
NRC was unable to estimate the total occupational dose associated with 
this work. However, dose estimates were provided by the Nuclear Energy 
Institute (NEI) in a letter to the NRC dated March 30, 2012, based on 
information collected on occupational radiation exposures that have 
been, or could be, incurred during insulation removal and replacement. 
In the letter, NEI noted similar difficulties in estimating the 
potential amount of radiation exposure, but provided a ``per unit'' 
estimate of between 80 and 525 person-rem. Given uncertainties in the 
scope of work and other nuclear plant-specific factors such as source 
term and hazardous materials, there is no basis to conclude that the 
NEI estimates were unreasonable. Therefore, since SNC's estimate of 
radiation exposure for insulation removal and replacement is within the 
NEI estimated range, SNC's estimate of an increase of 200 person-rem 
over baseline exposure is reasonable.
    As stated in the ``Occupational Radiation Doses'' section of this 
document, SNC's radiation protection program monitors radiation levels 
throughout the nuclear plant to establish appropriate work controls, 
training, temporary shielding, and protective equipment requirements so 
that worker doses are expected to remain within the dose limits in 10 
CFR 20.1201.
    In addition, as stated in the ``Offsite Radiation Dose'' section of 
this document, SNC also has a radiation monitoring system and 
procedures in place to control the release of radioactive effluents in 
accordance with radiation protection standards in 10 CFR 20.1301, 40 
CFR part 190, and the ALARA dose objectives in appendix I to 10 CFR 
part 50. Therefore, radiation exposure to members of the public would 
be maintained within the NRC dose criteria in 10 CFR 20.1301, 40 CFR 
part 190, and the ALARA dose objectives of appendix I to 10 CFR part 
50.
    Based on this information, impacts to members of the public from 
removing and replacing insulation within the reactor containment 
building would not be significant. However, impacts to plant workers 
and the environment from implementing this alternative would be greater 
than implementing the proposed action.

Alternative Use of Resources

    The proposed action would not involve the use of any different 
resources (e.g., water, air, land, nuclear fuel) not previously 
considered in NUREG-1437, Supplement 34.

Agencies and Persons Consulted

    In accordance with its stated policy, on March 11, 2021, the NRC 
staff consulted with the State of Georgia officials, Ms. Shelby Naar, 
Mr. Sean Hayes, Mr. David Matos, and Mr. Richard Dunn, regarding the 
environmental impact of the proposed action. The State of Georgia 
officials had no comments on the EA and FONSI.

III. Finding of No Significant Impact

    The licensee requested to amend Facility Operating License Nos. 
NPF-68 and NPF-81 to grant exemptions for Vogtle, Units 1 and 2, from 
certain requirements of 10 CFR 50.46(a)(1). This proposed action would 
not significantly affect plant safety, would not have a significant 
adverse effect on the probability of an accident occurring, and would 
not have any significant radiological or non-radiological impacts. It 
would also not result in any changes to radioactive effluents or 
emissions, exposures to nuclear plant workers and members of the 
public, or any changes to radiological and non-radiological impacts to 
the environment.
    Consistent with 10 CFR 51.21, the NRC conducted an environmental 
review of the proposed action, and this FONSI incorporates Section II 
of the EA by reference in this notice. Therefore, the NRC concludes 
that the proposed action will not have a significant effect on the 
quality of the human environment. Accordingly, the NRC has determined 
there is no need to prepare an environmental impact statement for the 
proposed action.
    As required by 10 CFR 51.32(a)(5), the related environmental 
document is the ``Generic Environmental Impact Statement for License 
Renewal of Nuclear Plants: Regarding Vogtle Electric Generating Plant, 
Units 1 and 2, Final Report,'' NUREG-1437, Supplement 34, dated 
November 2008, which provides the latest environmental review of 
current operations and description of environmental conditions at 
Vogtle.
    This FONSI and other related environmental documents are accessible 
online in the ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS or who 
encounter problems in accessing the documents located in ADAMS should 
contact the NRC's PDR reference staff by telephone at 1-800-397-4209 or 
301-415-4737, or by email to [email protected].

IV. Availability of Documents

    The documents identified in the following table are available to 
interested persons through one or more of the following methods, as 
indicated.

[[Page 18080]]



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                   Document                       Adams accession No.
------------------------------------------------------------------------
NUREG-0897, Containment Emergency Sump         ML112440046
 Performance: Technical Findings Related to
 Unresolved Safety Issue A-43, Revision 1,
 October 1985.
NRC Generic Letter 2004-02, Potential Impact   ML042360586
 of Debris Blockage on Emergency
 Recirculation During Design Basis Accidents
 at Pressurized-Water Reactors, September 13,
 2004.
NEI letter to NRC, Nuclear Energy Institute,   ML12095A319
 GSI-191 Dose Estimates, March 30, 2012.
Commission SECY-12-0093, Closure Options for   ML121320270 *
 Generic Safety Issue-191, Assessment of
 Debris Accumulation on Pressurized-Water
 Reactor Sump Performance, July 9, 2012.
Commission SRM-SECY-12-0093, Staff             ML12349A378
 Requirements--SECY-12-0093--Closure Options
 for Generic Safety Issue-191, Assessment of
 Debris Accumulation on Pressurized-Water
 Reactor Sump Performance, December 14, 2012.
NUREG-1437, Supplement 34, Generic             ML083380325
 Environmental Impact Statement for License
 Renewal of Nuclear Plants: Supplement 34
 Regarding Vogtle Electric Generating Plant,
 Units 1 and 2: Final Report, December 2008.
STPNOC Letter, ``Revised STP Pilot Submittal   ML13175A211
 and Requests for Exemptions and License
 Amendment for a Risk-Informed Approach to
 Resolving Generic Safety Issue (GSI)-191,
 June 19, 2013.
NUREG-0713, Volume 40, Occupational Radiation  ML20087J424
 Exposure at Commercial Nuclear Power
 Reactors and Other Facilities 2012: Fifty-
 First Annual Report, March 2018.
NRC Letter, ``Final Staff Evaluation for       ML19120A469
 Vogtle Electric Generating Plant, Units 1
 and 2, Systematic Risk-Informed Assessment
 of Debris Technical Report,'' September 30,
 2019.
SNC Letter, ``Exemption Request and License    ML20230A346
 Amendment Request for a Risk-Informed
 Resolution to GSI-191,'' August 17, 2020.
SNC Letter, ``Response to Request for          ML20352A228
 Additional Information Regarding Risk-
 Informed Resolution to GSI-191,'' December
 17, 2020.
SNC Letter, ``Vogtle Electric Generating       ML21046A094
 Plant--Units 1 and 2, Supplement to Request
 for Exemption to Support Risk-Informed
 Resolution to Generic Letter 2004-02,''
 February 15, 2021.
------------------------------------------------------------------------
* (package).


    Dated: April 2, 2021.

    For the Nuclear Regulatory Commission.
Craig G. Erlanger,
Director, Division of Operator Reactor Licensing, Office of Nuclear 
Reactor Regulation.
[FR Doc. 2021-07172 Filed 4-6-21; 8:45 am]
BILLING CODE 7590-01-P