[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.
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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.
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* (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