[Federal Register Volume 87, Number 166 (Monday, August 29, 2022)]
[Notices]
[Pages 52816-52821]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2022-18498]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-483; NRC-2022-0139]
Union Electric Company, dba Ameren Missouri, Callaway Plant, Unit
No. 1
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 issuing an
environmental assessment (EA) prepared under the National Environmental
Policy Act of 1969 (NEPA) and NRC's regulations. This EA summarizes the
results of the NRC staff's environmental review, which evaluates the
potential environmental impacts of granting exemptions from NRC
regulations and issuing an associated license amendment in response to
a request from the Union Electric Company, doing business as (dba)
Ameren Missouri (Ameren, the licensee) for Renewed Facility Operating
License NPF-30, for the Callaway Plant, Unit No. 1 (Callaway).
Specifically, the licensee is seeking a license amendment and
regulatory exemptions that would, if granted, allow the licensee to use
both a deterministic and risk-informed approach to address safety
issues discussed in Generic Safety Issue (GSI)-191, ``Assessment of
Debris Accumulation in PWR [Pressurized Water Reactor] Sump Pump
Performance'' and to close Generic
[[Page 52817]]
Letter (GL) 2004-02, ``Potential Impact of Debris Blockage on Emergency
Recirculation During Design Basis Accidents at Pressurized-Water
Reactors.'' The NRC staff is issuing a final EA and finding of no
significant impact (FONSI) associated with the proposed exemptions.
DATES: The EA and FONSI referenced in this document is available on
August 29, 2022.
ADDRESSES: Please refer to Docket ID NRC-2022-0139 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-2022-0139. 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.
NRC's PDR: You may examine and purchase copies of public
documents, by appointment, at the NRC's PDR, Room P1 B35, One White
Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. To make
an appointment to visit the PDR, please send an email to
[email protected] or call 1-800-397-4209 or 301-415-4737, between
8:00 a.m. and 4:00 p.m. Eastern Time (ET), Monday through Friday,
except Federal holidays.
FOR FURTHER INFORMATION CONTACT: Mahesh Chawla, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001; telephone: 301-415-8371, email: [email protected].
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is considering a request to grant certain regulatory
exemptions and issue a license amendment for Renewed Facility Operating
License NPF-30, issued to Ameren, for Callaway, located in Callaway
County, Missouri. The regulatory exemptions and associated license
amendment, if granted, would allow Ameren to incorporate the use of a
risk-informed approach to address safety issues discussed in GSI-191
and respond to GL 2004-02. Pursuant to 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 has prepared an EA summarizing the findings of
the NEPA review of the proposed action. The NRC concluded that the
proposed action will have no significant environmental impact. In
accordance with 10 CFR 51.31(a), the NRC has determined not to prepare
an environmental impact statement for the proposed licensing actions
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
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. 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 debris material, such as insulation installed on piping and
components, within the containment structure, could be dislodged by a
jet 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 sump pumps. Insulation and other fibrous
debris material could block the emergency sump screens and suction
strainers, which in turn could prevent the ability of the containment
emergency sump to provide adequate water flow to the RHR pumps (for
more information, see NUREG-0897, ``Containment Emergency Sump
Performance: Technical Finding Related to Unresolved Safety Issue A-
43,'' Revision 1).
The NRC issued GL 2004-02 to address this safety concern by
requesting PWR licensees, pursuant to 10 CFR 50.54(f), to use an NRC-
approved methodology to perform a ``mechanistic evaluation of the
potential for the adverse effects of post-accident debris blockage and
operation with debris-laden fluids to impede or prevent the
recirculation functions of the ECCS and CSS following all postulated
accidents for which the recirculation of these systems is required''
and submit this information to the NRC for evaluation.
In 2012, the NRC staff developed options for resolution of GSI-191,
which are discussed in SECY-12-0093, ``Closure Options for Generic
Safety Issue 191, Assessment of Debris Accumulation on Pressurized-
Water Reactor Sump Performance,'' dated July 9, 2012. The licensee has
proposed to use both a deterministic method, with plant-specific
testing, and a risk-informed approach to demonstrate compliance with 10
CFR 50.46, ``Acceptance criteria for emergency core colling systems for
light-water nuclear power reactors,'' and 10 CFR part 50, appendix A,
General Design Criteria (GDC) 35, ``Emergency core cooling,'' GDC 38,
``Containment heat removal,'' and GDC 41, ``Containment atmosphere
cleanup,'' and to resolve GSI-191 for Callaway. Because, historically,
the NRC staff has not allowed licensees to use a risk-informed approach
to show compliance with the requirements of 10 CFR 50.46, the licensee
requested exemptions from 10 CFR 50.46(a)(1) and GDC 35, 38, and 41, as
well as an amendment to the associated technical specifications to
allow the use of a risk-informed approach to resolve GSI-191. If
approved, the proposed action would not authorize any modifications
within the containment structure, physical changes to the ECCS, or
other modifications to the plant. Rather, the proposed action would
only allow the use of an alternate methodology to show compliance with
the regulations that require the ECCS and CSS function during certain
LOCA events.
II. Environmental Assessment
Description of the Proposed Action
The proposed action as requested by the licensee is to grant
certain regulatory exemptions and amend Facility Operating License NPF-
30. The regulatory exemptions would allow
[[Page 52818]]
Ameren to change the licensing basis LOCA analysis identified in the
updated final safety analysis report to use a risk-informed approach to
address safety issues discussed in GSI-191 and to close GL 2004 02. If
approved, no physical modifications to the nuclear plant or changes to
reactor operations involving the ECCS would be required. The proposed
action is in response to the licensee's application dated March 31,
2021, as supplemented by letters dated May 27, 2021; July 22, 2021;
August 23, 2021; October 7, 2021; January 27, 2022; March 8, 2022; and
May 26, 2022.
Need for the Proposed Action
The proposed action is needed because, as the holder of Renewed
Facility Operating License No. NPF-30, Ameren is expected to address
the safety issues discussed in GSI-191 and to close GL 2004-02 for
Callaway. Consistent with SECY-12-0093, the licensee chose an approach,
which requires, in part, that Ameren request that the NRC amend the
renewed facility operating license and grant certain regulatory
exemptions for Callaway.
Environmental Impacts of the Proposed Action
Callaway is located on an approximately 7,354-acre (2,976 hectare)
site in Callaway County, Missouri, approximately 10 miles (16
kilometers) southeast of Fulton, Missouri, and 80 miles (129
kilometers) west of the St. Louis metropolitan area.
Callaway consists of a single four-loop Westinghouse PWR unit. The
reactor core of the 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 51, ``Generic Environmental Impact Statement for
License Renewal of Nuclear Plants: Supplement 51 Regarding Callaway
Plant, Unit 1: Final Report.''
Radiological and non-radiological impacts on the environment that
may result from granting the regulatory exemptions and issuing the
license amendment are summarized in the following sections.
Non-Radiological Impacts
No changes would be made to structures or land use within the
Callaway site as a result of the proposed action, and non-radiological
liquid effluents or gaseous emissions would not change. In addition,
the license amendment 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 granting the regulatory exemptions and issuing the license
amendment would not result in environmental effects, there would be no
non-radiological cumulative impact.
Radiological Impacts
Radioactive Gaseous and Liquid Effluents and Solid Waste
Callaway uses 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 (EPA) radiation safety standards.
The license amendment and regulatory exemptions, if granted, would
not require any physical change to the nuclear plant or reactor
operations; therefore, there would be no changes to the plant
radioactive waste treatment systems. A detailed description of the
Callaway radioactive waste handling and disposal activities is
presented in chapter 2.1.2 of Supplement 51 to NUREG-1437.
Radioactive Gaseous Effluents
The objectives of the Callaway 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 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.''
Granting the regulatory exemptions and issuing the license
amendment would not require any physical changes 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 Callaway 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
effluents (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 liquid effluent is routed through a monitor that
measures the radioactivity and can automatically terminate the release
in the event radioactivity exceeds predetermined levels. The liquid
effluent is discharged from the plant into the Missouri River via a
pipeline.
Granting the regulatory exemptions and issuing the license
amendment would not require any physical change to the nuclear plant or
reactor operations; therefore, there would be no changes to the LWPS.
The existing equipment and plant procedures that control radioactive
releases to the environment will 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 Callaway 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
[[Page 52819]]
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. Therefore, there will be no changes to the
SWPS and issuing the license amendment and granting the regulatory
exemptions 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 amendment and regulatory exemptions, if granted, would
not require any physical change to the nuclear plant 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,
``Standards for Protection Against Radiation,'' subpart C,
``Occupational Dose Limits.'' The license amendment 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 dose to members of the public from
Callaway are radioactive gaseous and liquid effluents. As discussed
previously, there would be no change to the operation of Callaway
radioactive GWMS and LWPS or their ability to perform their intended
functions. Also, there would be no change to the Callaway 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 part 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 dose to members of
the public would not change and would continue to be within regulatory
limits. Therefore, the license amendment 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 Callaway, are evaluated by both the
licensee and the NRC to ensure that the unit 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 its environmental review, the NRC is evaluating the
licensee's technical and safety analyses provided in support of the
proposed action. The results of the NRC staff's safety review and
conclusion will be documented in a publicly available safety
evaluation. The NRC staff must conclude in its safety evaluation that
taking 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 will 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 EPA 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
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
amendment and exemptions would not require physical changes to the
plant 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, the NRC staff concludes that there would be no
significant cumulative radiological impact from the proposed action.
Radiological Impacts Summary
Based on these evaluations, the license amendment 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 and as an alternative to the proposed action, the
licensee could choose to remove and replace insulation within the
reactor containment building. This alternative 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.
The removal of the existing insulation from the containment
building would generate radiologically contaminated waste. Ameren
estimated that approximately 5,500 cubic feet (6.6 tons) of fiberglass
insulation would have to be removed from the Callaway containment. 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. Based on planning
documents prepared in 2010, Ameren estimated that the expected total
dose for replacing insulation in Callaway, would be between 350 and 400
person-rem. This estimate was considered in line with estimates from
[[Page 52820]]
other utilities impacted by this same issue. Ameren also indicated that
this initial estimate would now likely be higher due to the intervening
12 years of continuous plant operation. The NRC reviewed NUREG-0713,
Volume 41, ``Occupational Radiation Exposure at Commercial Nuclear
Power Reactors and Other Facilities: Fifty-Second Annual Report,'' and
determined that Ameren's average baseline collective radiation exposure
is approximately 22 person-rem. The additional 350 to 400-plus person-
rem collective exposure would be shared across the entire work force
involved with removing and reinstalling insulation. In SECY-12-0093,
the NRC staff 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 staff 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, the NRC staff
found no basis to conclude that the NEI estimates were unreasonable.
Accordingly, because Ameren's estimate of potential additional
radiation exposure resulting from the alternative approach of removing
and replacing insulation is consistent with the NEI estimated range,
the NRC staff considers Ameren's estimate to be reasonable.
As stated in the ``Occupational Radiation Doses'' section of this
document, Ameren'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, Ameren 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 51.
Agencies and Persons Consulted
In accordance with its stated policy, on June 27, 2022, the NRC
staff consulted with the State of Missouri official, Mr. Aaron Schmidt,
regarding the environmental impact of the proposed action. The State of
Missouri official has not provided any comments on the EA and FONSI.
III. Finding of No Significant Impact
The licensee requested to amend Renewed Facility Operating License
No. NPF-30 to grant exemptions for Callaway, from certain requirements
of 10 CFR 50.46(a)(1) and 10 CFR part 50, appendix A, GDC 35, 38, and
41. 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. Based on the EA included in Section II
of this notice and incorporated by reference in this FONSI, the NRC
staff finds 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.
The NRC staff's evaluation considered the information provided in
the licensee's application as supplemented, and the NRC staff's review
of related environmental documents. Section IV of this notice lists
documents related to the proposed action and includes information on
the availability of the documents, including the related environmental
document NUREG-1437, Supplement 51, which provides the latest
environmental review of current operations and description of
environmental conditions at Callaway.
This FONSI and other related environmental documents may be
examined, and/or copied for a fee, at the NRC's PDR, located at One
White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852.
Publicly available records are also 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.
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Document ADAMS accession No.
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U.S. Nuclear Regulatory Commission. Generic Letter 2004-02: ML042360586
``Potential Impact of Debris Blockage on Emergency
Recirculation During Design Basis Accidents at Pressurized-
Water Reactors,'' dated September 13, 2004.
U.S. Nuclear Regulatory Commission. NUREG-0897, ML112440046
``Containment Emergency Sump Performance: Technical
Findings Related to Unresolved Safety Issue A-43, Revision
1, October 1985.
Ameren Missouri. Letter ULNRC-06526, ``Request for License ML21090A184 (package).
Amendment and Regulatory Exemptions for a
Risk[dash]Informed Approach to Address GSI-191 and Respond
to GL 2004-02,'' dated March 31, 2021.
[[Page 52821]]
Ameren Missouri. Letter ULNRC-06664, ``Supplement to ML21147A222
Request for License Amendment and Regulatory Exemptions
for a Risk-Informed Approach to Address GSI-191 and
Respond to GL 2004-02 (LDCN 19-0014),'' dated May 27, 2021.
Ameren Missouri. Letter ULNRC-06651, ``Supplement to ML21203A192 (package).
Request for License Amendment and Regulatory Exemptions
for a Risk-Informed Approach to Address GSI-191 and
Respond to GL 2004-02 (LDCN 19-0014),'' dated July 22,
2021.
Ameren Missouri. Letter ULNRC-06683, ``Transmittal of ML21237A135 (package).
Documents Identified from NRC Audit of License Amendment
Request Regarding Risk-Informed Approach to Closure of
Generic Safety Issue 191 (EPID L-2021-LLA-0059),'' dated
August 23, 2021.
Ameren Missouri. Letter ULNRC-06692, ``Third Supplement to ML21280A378 (package).
Request for License Amendment and Regulatory Exemptions
for a Risk-Informed Approach to Address GSI-191 and
Respond to GL 2004-02 (LDCN 19-0014),'' dated October 7,
2021.
Ameren Missouri. Letter ULNRC-06690, ``Fourth (Post-Audit) ML22027A804 (package).
Supplement to Request for License Amendment and Regulatory
Exemptions for a Risk-Informed Approach to Address GSI-191
and Respond to GL 2004-02 (LDCN 19-0014),'' dated January
27, 2022.
Ameren Missouri. Letter ULNRC-06721, ``Fifth (Post-Audit) ML22068A027 (package).
Supplement to Request for License Amendment and Regulatory
Exemptions for a Risk-Informed Approach to Address GSI-191
and Respond to GL 2004-02 (LDCN 19-0014),'' dated March 8,
2022.
Ameren Missouri. Letter ULNRC-06735, ``Response to Request ML22146A337 (package).
for Additional Information Regarding Request for License
Amendment and Regulatory Exemptions for Risk[dash]Informed
Approach to Address GSI-191 and Respond to Generic Letter
2004-02,'' dated May 26, 2022.
Nuclear Energy Institute. GSI-191 Dose Estimates, dated ML12095A319
March 30, 2012.
SECY-12-0093, ``Closure Options for Generic Safety Issue-- ML121320270 (package).
191, Assessment of Debris Accumulation on Pressurized-
Water Reactor Sump Performance,'' dated July 9, 2012.
SRM-SECY-12-0093, ``Staff Requirements--SECY-12-0093-- ML12349A378
Closure Options for Generic Safety Issue--191, Assessment
of Debris Accumulation on Pressurized-Water Reactor Sump
Performance,'' dated December 14, 2012.
U.S. Nuclear Regulatory Commission. NUREG-1437, Supplement ML14289A140
51, ``Generic Environmental Impact Statement for License
Renewal of Nuclear Plants: Supplement 51 Regarding
Callaway Plant, Unit 1: Final Report,'' October 2014.
U.S. Nuclear Regulatory Commission. NUREG-0713, Volume 41, ML22111A013
``Occupational Radiation Exposure at Commercial Nuclear
Power Reactors and Other Facilities 2019: Fifty-Second
Annual Report,'' April 2022.
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Dated: August 23, 2022.
For the Nuclear Regulatory Commission.
Siva P. Lingam,
Project Manager, Plant Licensing Branch IV, Division of Operator
Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. 2022-18498 Filed 8-26-22; 8:45 am]
BILLING CODE 7590-01-P