ML22182A406
| ML22182A406 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 08/23/2022 |
| From: | Siva Lingam NRC/NRR/DORL/LPL4 |
| To: | |
| Chawla M, NRR/DORL/LPL4 | |
| Shared Package | |
| ML22182A401 | List: |
| References | |
| 87 FR 52816; 8/29/2022, EPID L-2021-LLA-0059, EPID L-2021-LLE-0021, NRC-2022-0139 | |
| Download: ML22182A406 (18) | |
Text
[7590-01-P]
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.
SUMMARY
- The U.S. Nuclear Regulatory Commission (NRC) is issuing an
environmental assessment (EA) prepared under the National Envir onmental Policy Act
of 1969 (NEPA) and NRCs regulations. This EA summarizes the r esults of the NRC
staffs environmental review, which evaluates the potential env ironmental impacts of
granting exemptions from NRC regu lations and issuing an associa ted license
amendment in response to a request from the Union Electric Comp any, doing business
as (dba) Ameren Missouri (Ameren, the licensee) for Renewed Fac ility Operating
License NPF-30, for the Callaway Plant, Unit No. 1 (Callaway). Specifically, the licensee
is seeking a license amendment and regulatory exemptions that w ould, if granted, allow
the licensee to use both a deterministic and risk-informed appr oach to address safety
issues discussed in Generic Safety Issue (GSI)-191, Assessment of Debris
Accumulation in PWR [Pressurized Water Reactor] Sump Pump Perfo rmance and to
close Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency
Recirculation During Design Basis Accidents at Pressurized-Wate r Reactors. The NRC
staff is issuing a final EA and finding of no significant impac t (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; ema il:
Stacy.Schumann@nrc.gov. For technical questions, contact the i ndividual listed in the
For Further Information Contact section of this document
- NRCs Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly available documents online in the ADA MS Public
Documents collection at https://www.nrc.gov/reading-rm/adams.ht ml. To begin the
search, select Begin Web-based ADAMS Search. For problems wi th ADAMS, please
contact the NRCs Public Document Room (PDR) reference staff at 1-800-397-4209,
301-415-4737, or by email to PDR.Resource@nrc.gov. For the con venience of the
reader, instructions about obtaining materials referenced in th is document are provided
in the Availability of Documents section.
- NRCs PDR: You may examine and purchase copies of public documents,
by appointment, at the NRCs PDR, Room P1 B35, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852. To make an appointm ent to visit the PDR,
please send an email to PDR.Resource@nrc.gov 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.
2 FOR FURTHER INFORMATION CONTACT: Mahesh Chawla, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washing ton, DC 20555-
0001; telephone: 301-415-8371, email: Mahesh.Chawla@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is considering a request to grant certain regulatory ex emptions and
issue a license amendment for Renewed Facility Operating Licens e NPF-30, issued to
Ameren, for Callaway, located in Callaway County, Missouri. Th e regulatory exemptions
and associated license amendment, if granted, would allow Amere n to incorporate the
use of a risk-informed approach to address safety issues discus sed in GSI-191 and
respond to GL 2004-02. Pursuant to Section 51.21 of title 10 o f the Code of Federal
Regulations (10 CFR), Criteria for and identification of licensing and re gulatory actions
requiring environmental assessments, the NRC has prepared an E A summarizing the
findings of the NEPA review of the proposed action. The NRC co ncluded 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 envir onmental impact
statement for the proposed licensing actions and is issuing a F ONSI.
The NRC established GSI-191 to determine whether the transport and
accumulation of debris from a loss-of-coolant accident (LOCA) i n the PWR containment
structure would impede the operation of the emergency core cool ing 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. Wa ter discharged from the
pipe break and debris would collect on the containment structur e 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 t ank. However, realigning
3 the ECCS pumps to the containment emergency sump would provide long-term cooling
of the reactor core. Therefore, successful long-term cooling d epends on the ability of the
containment emergency sump to provide adequate flow to the resi dual 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 a nd steam during the
LOCA. Water, along with debris, would accumulate at the bottom of the containment
structure and flow towards the emergency sump pumps. Insulatio n and other fibrous
debris material could block the emergency sump screens and suct ion strainers, which in
turn could prevent the ability of the containment emergency sum p to provide adequate
water flow to the RHR pumps (for more information, see NUREG-08 97, Containment
Emergency Sump Performance: Technical Finding Related to Unres olved Safety Issue
A-43, Revision 1).
The NRC issued GL 2004-02 to address this safety concern by req uesting 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 adve rse 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 postu lated 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 de terministic method, with
4 plant-specific testing, and a risk-informed approach to demonst rate compliance with
10 CFR 50.46, Acceptance criteria for emergency core colling s ystems for light-water
nuclear power reactors, and 10 CFR Part 50, Appendix A, Genera l Design Criteria
(GDC) 35, Emergency core cooling, GDC 38, Containment heat r emoval, and GDC 41, Containment atmosphere cleanup, and to resolve GSI-191 fo r 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 lice nsee requested
exemptions from 10 CFR 50.46(a)(1) and GDC 35, 38, and 41, as w ell as an
amendment to the associated technical specifications to allow t he 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 change s 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 t hat 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 ce rtain regulatory
exemptions and amend Facility Operating License NPF-30. The re gulatory exemptions
would allow Ameren to change the li censing basis LOCA analysis identified in the
updated final safety analysis report to use a risk-informed app roach to address safety
issues discussed in GSI 191 and to close GL 2004 02. If approv ed, no physical
modifications to the nuclear plant or changes to reactor operat ions involving the ECCS
would be required. The proposed action is in response to the l icensees 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, 20 22; and May 26, 2022.
5 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. Con sistent with SECY 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 hecta re) site in
Callaway County, Missouri, approximately 10 miles (16 kilometer s) southeast of Fulton,
Missouri, and 80 miles (129 kilometers) west of the St. Louis m etropolitan 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 gen erators, 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 st ructure is a reinforced
concrete cylinder with a concrete slab base and hemispherical d ome. A welded steel
liner is attached to the inside face of the concrete shell to e nsure 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 Impa ct Statement for
6 License Renewal of Nuclear Plants: Supplement 51 Regarding Cal laway Plant, Unit 1:
Final Report.
Radiological and non-radiological impacts on the environment th at 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 C allaway site as
a result of the proposed action, and non-radiological liquid ef fluents or gaseous
emissions would not change. In addition, the license amendment and regulatory
exemptions would not result i n any changes to the use of resour ces or create any new
environmental impacts. Therefore, there would be no non-radiol ogical impacts to
environmental resources or any irre versible and irretrievable c ommitments.
Since granting the regulatory exemptions and issuing the licens e amendment
would not result in environmental effects, there would be no no n-radiological cumulative
impact.
Radiological Impacts
Radioactive Gaseous and Liquid Effluents and Solid Waste
Callaway uses waste treatment systems to collect, process, recy cle, and dispose
of gaseous, liquid, and solid wastes that contain radioactive m aterial in a safe and
controlled manner within NRC and Environmental Protection Agenc y (EPA) radiation
safety standards.
The license amendment and regulatory exemptions, if granted, wo uld 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
7 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 efflu ents into the environment
to be within the requirements of 10 CFR 20.1301, Dose limits f or 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 i n 10 CFR 20.1201,
Occupational dose limits for adults.
Granting the regulatory exemptions and issuing the license amen dment would
not require any physical changes to the nuclear plant or reacto r operations that would
affect the release of radioactive gaseous effluents into the en vironment; therefore, there
would be no changes to the GWMS. The existing equipment and pl ant 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 2 0.1301 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 (LW PS) is to collect
and process radioactive liquid wastes to reduce radioactivity a nd chemical
concentrations to levels acceptable for discharge to the enviro nment 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
8 in Appendix I to 10 CFR Part 50. The liquid effluent is routed through a monitor that
measures the radioactivity and c an automatically terminate the release in the event
radioactivity exceeds predetermined levels. The liquid effluen t is discharged from the
plant into the Missouri River via a pipeline.
Granting the regulatory exemptions and issuing the license amen dment 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 conti nue 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 (SWP S) is to
process, package, and store the solid radioactive wastes genera ted by nuclear plant
operations until they are shipped off site to a vendor for furt her 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 pl ant workers. The principal
objectives of the SWPS are to package and transport the waste i n compliance with NRC
regulations in 10 CFR Part 61, Licensing Requirements for Land Disposal of
Radioactive Waste, and 10 CFR Part 71, Packaging and Transpor tation of Radioactive
Material, and the U.S. Department of Transportation regulation s 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 radioa ctive 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
9 will be no changes to the SWPS and issuing the license amendmen t and granting the
regulatory exemptions will not result in any physical changes t o 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, wo uld 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 rad iation exposure. The
licensees radiation protection program monitors radiation leve ls throughout the nuclear
plant to establish appropriate work controls, training, tempora ry shielding, and protective
equipment requirements so that worker doses remain within the d ose limits in
10 CFR Part 20, Standards for Protection Against Radiation, S ubpart 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 fr om Callaway are
radioactive gaseous and liquid effluents. As discussed previou sly, there would be no
change to the operation of Callaway radioactive GWMS and LWPS o r their ability to
perform their intended functions. Also, there would be no chan ge 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.
10 Based on this information, the offsite radiation dose to member s of the public
would not change and would continue to be within regulatory lim its. Therefore, the
license amendment and regulatory exemptions would not change of fsite 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 l icensee and the
NRC to ensure that the unit would continue to withstand the spe ctrum 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 t he licensees
technical and safety analyses provided in support of the propos ed action. The results of
the NRC staffs 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 mann er, (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 ta ke the proposed action
absent such a safety conclusion.
Radiological Cumulative Impacts
The radiological dose limits for protection of the public and p lant 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. Thes e dose limits are codified
in 10 CFR Part 20 and 40 CFR Part 190.
11 Cumulative radiation doses are required to be within the limits set forth in the
regulations cited in the previous paragraph. The license amend ment and exemptions
would not require physical changes to the plant or changes to p lant activities; in-plant
radiation sources would not change and offsite radiation dose t o members of the public
would not change. Therefore, the NRC staff concludes that ther e would be no significant
cumulative radiological impact from the proposed action.
Radiological Impacts Summary
Based on these evaluations, the license amendment and exemption s would not
result in any significant radiological impacts. Therefore, the safety evaluation must
conclude that the proposed action will (1) provide reasonable a ssurance 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 c onducted in compliance
with the Commission's regulations, and (3) not be inimical to t he common defense and
security or to the health and safety of the public. The NRC wo uld 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 wit h these options and as
an alternative to the proposed action, the licensee could choos e to remove and replace
insulation within the reactor containment building. This alter native would require the
physical removal and disposal of significant amounts of insulat ion from a radiation area
within the reactor containment building, and the installation o f new insulation less likely
to impact sump performance.
The removal of the existing insulation from the containment bui lding would
generate radiologically contaminated waste. Ameren estimated t hat approximately
12 5,500 cubic feet (6.6 tons) of fiberglass insulation would have to be removed from the
Callaway containment. The removed insulation would require spe cial 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 unti l 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 insul ation 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 i n line with estimates
from other utilities impacted by this same issue. Ameren also indicated that this initial
estimate would now likely be higher due to the intervening 12 y ears of continuous plant
operation. The NRC reviewed NUREG-0713, Volume 41, Occupation al Radiation
Exposure at Commercial Nuclear Power Reactors and Other Facilit ies: Fifty-Second
Annual Report, and determined that Amerens average baseline c ollective radiation
exposure is approximately 22 person-rem. The additional 350 to 400-plus person-rem
collective exposure would be shared across the entire work forc e involved with removing
and reinstalling insulation. In SECY-12-0093, the NRC staff at tempted 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 si te-specific factors such as
source term and hazardous materials, the NRC staff was unable t o estimate the total
occupational dose associated with this work. However, dose est imates were provided
by the Nuclear Energy Institute (NEI) in a letter to the NRC da ted March 30, 2012, based
on information collected on occupational radiation exposures th at have been, or could
13 be, incurred during insulation removal and replacement. In the letter, NEI noted similar
difficulties in estimating the potential amount of radiation ex posure, but provided a per
unit estimate of between 80 and 525 person-rem. Given uncerta inties in the scope of
work and other nuclear plant-specific factors such as source te rm and hazardous
materials, the NRC staff found no basis to conclude that the NE I estimates were
unreasonable. Accordingly, because Amerens estimate of potent ial additional radiation
exposure resulting from the alternative approach of removing an d replacing insulation is
consistent with the NEI estimated range, the NRC staff consider s Amerens estimate to
be reasonable.
As stated in the Occupational Radiation Doses section of this document,
Amerens radiation protection program monitors radiation levels throughout the nuclear
plant to establish appropriate work controls, training, tempora ry shielding, and protective
equipment requirements so that worker doses are expected to rem ain 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 p rotection 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 th e public would be
maintained within the NRC dose criteria in 10 CFR 20.1301, 40 C FR 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 fro m removing and
replacing insulation within the reactor containment building wo uld not be significant.
However, impacts to plant workers and the environment from impl ementing this
alternative would be greater than implementing the proposed act ion.
14 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 NU REG-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, regardi ng 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 Lice nse 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 propo sed action would not
significantly affect plant safet y, would not have a significant adverse effect on the
probability of an accident occurring, and would not have any si gnificant radiological or
non-radiological impacts. It would also not result in any chan ges 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 env ironment.
Consistent with 10 CFR 51.21, the NRC conducted an environmenta l 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 th at the proposed action will
not have a significant effect on the quality of the human envir onment. Accordingly, the
NRC has determined there is no need to prepare an environmental impact statement for
the proposed action.
15 The NRC staffs evaluation considered the information provided in the licensees
application as supplemented, and the NRC staffs review of rela ted environmental
documents.Section IV of this notice lists documents related t o the proposed action and
includes information on the availability of the documents, incl uding the related
environmental document NUREG-1437, Supplement 51, which provide s the latest
environmental review of current operations and description of e nvironmental conditions
at Callaway.
This FONSI and other related environmental documents may be exa mined,
and/or copied for a fee, at the NRCs PDR, located at One White Flint North,
11555 Rockville Pike, Rockville, Maryland 20852. Publicly avai lable 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 loca ted in ADAMS
should contact the NRCs PDR reference staff by telephone at 1-800-397-4209 or 301-
415-4737, or by email to PDR.Resource@nrc.gov.
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 indica ted.
DOCUMENT ADAMS ACCESSION NO.
U.S. Nuclear Regulatory Commission. ML042360586 Generic Letter 2004-02: 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. ML112440046 NUREG-0897, Containment Emergency Sump Performance: Technical Findings Related to Unresolved Safety Issue A-43, Revision 1, October 1985.
16 DOCUMENT ADAMS ACCESSION NO.
Ameren Missouri. ML21090A184 (package)
Letter ULNRC-06526, "Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02," dated March 31, 2021.
Ameren Missouri. ML21147A222 Letter ULNRC-06664, "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 May 27, 2021.
Ameren Missouri. ML21203A192 (package)
Letter ULNRC-06651, "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 July 22, 2021.
Ameren Missouri. ML21237A135 (package)
Letter ULNRC-06683, Transmittal of 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. ML21280A378 (package)
Letter ULNRC-06692, "Third 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 October 7, 2021.
Ameren Missouri ML22027A804 (package)
Letter ULNRC-06690, "Fourth (Post-Audit) 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. ML22068A027 (package)
Letter ULNRC-06721, "Fifth (Post-Audit) 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.
17 DOCUMENT ADAMS ACCESSION NO.
Ameren Missouri. ML22146A337 (package)
Letter ULNRC-06735, Response to Request for Additional Information Regarding Request for License Amendment and Regulatory Exemptions for Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004-02, dated May 26, 2022.
Nuclear Energy Institute. ML12095A319 GSI-191 Dose Estimates, dated March 30, 2012.
SECY-12-0093, Closure Options for Generic Safety ML121320270 (package)
Issue - 191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance, dated July 9, 2012.
SRM-SECY-12-0093, Staff Requirements - SECY ML12349A378 0093 - 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. ML14289A140 NUREG-1437, Supplement 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. ML22111A013 NUREG-0713, Volume 41, Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2019: Fifty-Second Annual Report, April 2022.
Dated: August 23, 2022.
For the Nuclear Regulatory Commission.
/RA/
Siva P. Lingam, Project Manager, Plant Licensing Branch IV, Division of Operator Reactor Licensing, Office of Nuclear Reactor Regulation.
18