ML25154A351
| ML25154A351 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 06/27/2025 |
| From: | Mahesh Chawla Plant Licensing Branch IV |
| To: | Diya F Ameren Missouri, Callaway Energy Center |
| Chawla M | |
| References | |
| EPID L-2024-LLA-0165 | |
| Download: ML25154A351 (1) | |
Text
June 27, 2025 Mr. Fadi Diya Senior Vice President and Chief Nuclear Officer Ameren Missouri Callaway Energy Center 8315 County Road 459 Steedman, MO 65077
SUBJECT:
CALLAWAY PLANT, UNIT NO. 1 - ISSUANCE OF AMENDMENT NO. 240 TO REVISE TECHNICAL SPECIFICATIONS TO ADOPT TSTF-591, REVISE RISK INFORMED COMPLETION TIME (RICT) PROGRAM (EPID L-2024-LLA-0165)
Dear Mr. Diya:
The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 240 to Renewed Facility Operating License No. NPF-30 for the Callaway Plant, Unit No. 1. The amendment consists of changes to the technical specifications (TSs) in response to your application dated December 5, 2024, as supplemented by letters dated February 4, 2025, and March 11, 2025.
The amendment revises TS 5.5.19, Risk Informed Completion Time Program, by referencing Regulatory Guide (RG) 1.200, Revision 3, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities, instead of RG 1.200, Revision 2, based on Technical Specifications Task Force (TSTF) Traveler TSTF-591, Revision 0, Revise Risk Informed Completion Time (RICT) Program (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22081A224), and the associated NRC staff safety evaluation (SE) of Traveler TSTF-591 (ML23262B230).
The changes also add a requirement in TS section 5.6, Reporting Requirements, for the licensee to submit a report to the NRC before calculating a RICT using a newly developed method.
Copies of the related SE and Notices and Environmental Findings are also enclosed. Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Mahesh L. Chawla, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483
Enclosures:
- 1. Amendment No. 240 to NPF-30
- 2. Safety Evaluation
- 3. Notices and Environmental Findings cc: Listserv
UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT NO. 1 DOCKET NO. 50-483 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 240 License No. NPF-30
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Union Electric Company (UE, the licensee),
dated December 5, 2024, as supplemented by letters dated February 4, 2025, and March 11, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-30 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan*
The Technical Specifications contained in Appendix A, as revised through Amendment No. 240 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This amendment is effective as of its date of issuance, and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Tony Nakanishi, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. NPF-30 and the Technical Specifications Date of Issuance: June 27, 2025 TONY NAKANISHI Digitally signed by TONY NAKANISHI Date: 2025.06.27 13:16:08 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 240 TO TO RENEWED FACILITY OPERATING LICENSE NO. NPF-30 CALLAWAY PLANT, UNIT NO. 1 DOCKET NO. 50-483 Replace the following pages of Renewed Facility Operating License No. NPF-30 and the Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Renewed Facility Operating License REMOVE INSERT Technical Specifications REMOVE INSERT TOC 4 TOC 4 5.0-24 5.0-24 5.0.29 5.0.29 5.0-30 5.0-30 5.0-31 5.0-31 5.0-32 5.0-32 5.0-33 5.0-33 5.0-34
Renewed License No. NPF-30 Amendment No. 240 (3)
UE, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
UE, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source of special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
UE, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level UE is authorized to operate the facility at reactor core power levels not in excess of 3565 megawatts thermal (100% power) in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan*
The Technical Specifications contained in Appendix A, as revised through Amendment No. 240 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Environmental Qualification (Section 3.11, SSER #3)**
Deleted per Amendment No. 169.
Amendments 133, 134, & 135 were effective as of April 30, 2000 however these amendments were implemented on April 1, 2000.
The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
TABLE OF CONTENTS 3.8 ELECTRICAL POWER SYSTEMS (continued)
CALLAWAY PLANT 4
Amendment 240 3.8.10 Distribution Systems - Shutdown.....................................................3.8-40 3.9 REFUELING OPERATIONS.................................................................3.9-1 3.9.1 Boron Concentration........................................................................3.9-1 3.9.2 Unborated Water Source Isolation Valves.......................................3.9-3 3.9.3 Nuclear Instrumentation...................................................................3.9-5 3.9.4 Containment Penetrations...............................................................3.9-7 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level...................................................3.9-9 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level....................................................3.9-11 3.9.7 Refueling Pool Water Level.............................................................3.9-14 4.0 DESIGN FEATURES...............................................................................4.0-1 4.1 Site Location....................................................................................4.0-1 4.2 Reactor Core...................................................................................4.0-1 4.3 Fuel Storage....................................................................................4.0-1 5.0 ADMINISTRATIVE CONTROLS...........................................................5.0-1 5.1 Responsibility...................................................................................5.0-1 5.2 Organization....................................................................................5.0-2 5.3 Unit Staff Qualifications...................................................................5.0-4 5.4 Procedures......................................................................................5.0-5 5.5 Programs and Manuals.....................................................................5.0-6 5.6 Reporting Requirements..................................................................5.0-25 5.7 High Radiation Area.........................................................................5.0-31
Programs and Manuals 5.5 5.5 Programs and Manuals CALLAWAY PLANT 5.0-24 Amendment No. 240 5.5.19 Risk Informed Completion Time Program (continued) e.
A RICT calculation must include the following hazard groups:
Internal Events PRA (IEPRA) model (includes internal floods)
Internal Events Fire PRA (FPRA) model Seismic PRA (SPRA) model High Winds PRA (HW PRA) model Changes to these means of assessing the hazard groups require prior NRC approval.
f.
The PRA models used to calculate a RICT shall be maintained and upgraded in accordance with the processes endorsed in the regulatory positions of Regulatory Guide 1.200, Revision 3, "Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities."
g.
A report shall be submitted in accordance with Specification 5.6.11 before a newly developed method is used to calculate a RICT.
Reporting Requirements 5.6 5.6 Reporting Requirements (continued)
CALLAWAY PLANT 5.0-29 Amendment No. 240 5.6.10 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with Specification 5.5.9, Steam Generator (SG) Program. The report shall include:
a.
The scope of inspections performed on each SG; b.
The nondestructive examination techniques utilized for tubes with increased degradation susceptibility; c.
For each degradation mechanism found; 1.
The nondestructive examination techniques utilized; 2.
The location, orientation (if linear), measured size (if available),
and voltage response for each indication. For tube wear at support structures less than 20 percent through-wall, only the total number of indications needs to be reported; 3.
A description of the condition monitoring assessment and results, including the margin to the tube integrity performance criteria and comparison with the margin predicted to exist at the inspection by the previous forward-looking tube integrity assessment; and 4.
The number of tubes plugged during the inspection outage; d.
An analysis summary of the tube integrity conditions predicted to exist at the next scheduled inspection (the forward-looking tube integrity assessment) relative to the applicable performance criteria, including the analysis methodology, inputs, and results; e.
The number and percentage of tubes plugged to date, and the effective plugging percentage in each steam generator; and f.
The results of any SG secondary side inspections.
(continued)
Reporting Requirements 5.6 5.6 Reporting Requirements (continued)
CALLAWAY PLANT 5.0-30 Amendment No. 240 5.6.11 Risk Informed Completion Time (RICT) Program Upgrade Report A report describing newly developed methods and their implementation must be submitted following a probabilistic risk assessment (PRA) upgrade associated with newly developed methods and prior to the first use of those methods to calculate a RICT. The report shall include:
a.
The PRA models upgraded to include newly developed methods; b.
A description of the acceptability of the newly developed methods consistent with Section 5.2 of PWROG-19027-NP, Revision 2, "Newly Developed Method Requirements and Peer Review";
c.
Any open findings from the peer review of the implementation of the newly developed methods and how those findings were dispositioned; and d.
All changes to key assumptions related to newly developed methods or their implementation.
CALLAWAY PLANT 5.0-31 Amendment No. 240 l High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601 (a) and (b) of 10 CFR Part 20:
5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation:
a.
Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment; b.
Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.
c.
Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.
d.
Each individual or group entering such an area shall possess:
1.
A radiation monitoring device that continuously displays radiation dose rates in the area; or 2.
A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the devices dose alarm setpoint is reached, with an appropriate alarm setpoint, or 3.
A radiation monitoring device that continuously transmits does rate and cumulative dose rate information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or 4.
A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and (continued)
High Radiation Area 5.7 5.7 High Radiation Area CALLAWAY PLANT 5.0-32 Amendment No. 240 l 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation: (continued)
(i)
Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii)
Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.
e.
Except for individuals qualified in radiation protection procedures, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them.
5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation:
a.
Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:
1.
All such door and gate keys shall be maintained under the administrative control of the Shift Manager/Operating Supervisor or Radiation Protection Department Supervision, or his or her designee.
2.
Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.
b.
Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.
(Continued)
High Radiation Area 5.7 5.7 High Radiation Area CALLAWAY PLANT 5.0-33 Amendment No. 240 l 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation: (continued) c.
Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.
d.
Each individual or group entering such an area shall possess:
1.
A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the devices dose alarm setpoint is reached, with an appropriate alarm setpoint, or 2.
A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or 3.
A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and (i)
Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii)
Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area, or 4.
In those cases where options (2) and (3), above, are impractical or determined to be inconsistent with the As Low As is Reasonably (Continued)
High Radiation Area 5.7 5.7 High Radiation Area CALLAWAY PLANT 5.0-34 Amendment No. 240 l 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation: (continued)
Achievable principle, a radiation monitoring device that continuously displays radiation dose rates in the area.
e.
Except for individual qualified in radiation protection procedures or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them.
f.
Such individual areas that are within a larger area, such as PWR containment, where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 240 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-30 UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT NO. 1 DOCKET NO. 50--483 Application (i.e., initial and supplements)
Safety Evaluation Date December 5, 2024, ML24340A175 February 4, 2025, ML25035A300 March 11, 2025, ML25070A260 June 27, 2025 Principal Contributors to Safety Evaluation Chris Rojas Khadijah West
1.0 PROPOSED CHANGE
S Union Electric Company, doing business as Ameren Missouri (the licensee), requested changes to the technical specifications (TSs) for Callaway Plant, Unit No. 1 (Callaway) by license amendment request (LAR, application). In its application, the licensee requested that the U.S.
Nuclear Regulatory Commission (NRC, the Commission) process the proposed amendment under the Consolidated Line Item Improvement Process (CLIIP). The proposed changes would revise the TSs based on Technical Specifications Task Force (TSTF) Traveler TSTF-591, Revision 0, Revise Risk Informed Completion Time (RICT) Program (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22081A224), and the associated NRC staff safety evaluation (SE) of Traveler TSTF-591 (ML23262B230).
The proposed changes would revise the TS 5.5.19, Risk Informed Completion Time Program, by referencing Regulatory Guide (RG) 1.200, Revision 3, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities, Revision 3, December 2020 (ML20238B871),
instead of RG 1.200, Revision 2, An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk Informed Activities, March 2009 (ML090410014). The proposed changes would also add a requirement in TS section 5.6, Reporting Requirements, for the licensee to submit a report to the NRC before calculating a RICT using a newly developed method.
The supplemental letters dated February 4 and March 11, 2025, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staffs proposed finding that the amendment involves no significant
hazards consideration, as published in the Federal Register (FR) on January 21, 2025 (90 FR 7194).
Description of RICT Program The TS limiting conditions for operation (LCOs) are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When an LCO is not met, the licensee must shut down the reactor or follow any remedial or required action (e.g.,
testing, maintenance, or repair activity) permitted by the TSs until the condition can be met. The remedial actions (i.e., ACTIONS) associated with an LCO contain Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are required action(s) and completion times (CTs). The CTs are referred to as the front stops in the context of this SE. For certain Conditions, the TS require exiting the Mode of Applicability of an LCO (i.e., shutdown the reactor).
Topical Report Nuclear Energy Institute (NEI) 06-09, Risk Informed Technical Specifications Initiative 4b: Risk Managed Technical Specifications (RMTS), Revision 0-A (NEI 06-09-A)
(ML122860402) provides a methodology for extending existing CTs and thereby delay exiting the operational mode of applicability or taking Required Actions if risk is assessed and managed within the limits and programmatic requirements established by a RICT Program.
1.1 Proposed TS Changes to Adopt TSTF-591 TS 5.5.19 Risk Informed Completion Time Program TS 5.5.19, which describes the RICT program, would be revised. Existing paragraph e would be replaced with the paragraph e below. Paragraphs f and g would be added.
- e.
A RICT calculation must include the following hazard groups:
Internal Events PRA (IEPRA) model (includes internal floods)
Internal Events Fire PRA (FPRA) model Seismic PRA (SPRA) model High Winds PRA (HW PRA) model Changes to these means of assessing the hazard groups require prior NRC approval.
- f.
The PRA models used to calculate a RICT shall be maintained and upgraded in accordance with the processes endorsed in the regulatory positions of Regulatory Guide 1.200, Revision 3, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities.
- g.
A report shall be submitted in accordance with Specification 5.6.11 before a newly developed method is used to calculate a RICT.
TS 5.6.11, Risk Informed Completion Time Program Upgrade Report A new specification, TS 5.6.11, would be added as follows:
Risk Informed Completion Time (RICT) Program Upgrade Report A report describing newly developed methods and their implementation must be submitted following a probabilistic risk assessment (PRA) upgrade associated with newly developed methods and prior to the first use of those methods to calculate a RICT. The report shall include:
- a.
The PRA models upgraded to include newly developed methods;
- b.
A description of the acceptability of the newly developed methods consistent with Section 5.2 of PWROG-19027-NP, Revision 2, Newly Developed Method Requirements and Peer Review;
- c.
Any open findings from the peer review of the implementation of the newly developed methods and how those findings were dispositioned; and
- d.
All changes to key assumptions related to newly developed methods or their implementation.
1.2 Additional Proposed TS Changes In addition to the changes proposed consistent with TSTF-591 discussed in section 1.1, the licensee proposed the variation below.
1.2.1 Editorial Variations The licensee noted that the applicable table of contents numbering changes are to be made, as well as Callaway TSs have different numbering in section 5.0 than standard technical specifications (STSs).
2.0 REGULATORY EVALUATION
2.1 Applicable Regulatory Requirements and Guidance Title 10 of the Code of Federal Regulations (10 CFR) 50.36(b) requires that:
Each license authorizing operation of a utilization facility will include technical specifications. The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to [10 CFR] 50.34 [Contents of applications; technical information]. The Commission may include such additional technical specifications as the Commission finds appropriate.
The categories of items required to be in the TSs are listed in 10 CFR 50.36(c).
The regulation at 10 CFR 50.36(c)(5), states that [a]dministrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner.
NRC RGs provide one way to ensure that the regulations continue to be met. The NRC staff considered during its review of the proposed changes, along with industry guidance endorsed by the NRC, the guidance in RG 1.200, Revision 3, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities, December 2020 (ML20238B871).
NUREG-0800, Revision 3, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition (SRP):
o Chapter 19, Section 19.2, Review of Risk Information Used to Support Permanent Plant-Specific Changes to the Licensing Basis: General Guidance, June 2007 (ML071700658).
o Chapter 16, Section 16.0, Technical Specifications, Revision 3, March 2010 (ML100351425). The NRC staffs review includes consideration of whether the proposed changes are consistent with the NRC NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Volume 1, Specifications, and Volume 2, Bases, Revision 5.0, September 2021 (ML21259A155 and ML21259A159, respectively).
o Chapter 16, Section 16.1, Risk-Informed Decision Making: Technical Specifications, March 2007 (ML070380228).
NEI 06-09-A, Revision 0, Risk-Informed Technical Specifications Initiative 4b, Risk---Managed Technical Specifications (RMTS) Guidelines (ML063390639), provides guidance for risk--informed TS. The NRC staff issued a final SE approving NEI 06-09 on May 17, 2007 (ML071200238).
NEI 17-07, Revision 2, Performance of PRA Peer Reviews Using the ASME/ANS
[American Society of Mechanical Engineers/American Nuclear Society] PRA Standard, provides guidance material for conducting and documenting a PRA peer review using the ASME/ANS PRA Standard, issued August 2019 (ML19231A182).
Pressurized Water Reactor Owners Group (PWROG) topical report PWROG-19027-NP, Revision 2, Newly Developed Method Requirements and Peer Review, establishes the definitions, processes, and technical requirements necessary to implement newly developed methods, issued July 2020 (ML20213C660). RG 1.200, Revision 3, endorsed specified portions of PWROG-19027-NP.
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes to Adopt TSTF-591 The NRC staff compared the licensees proposed TS changes in section 1.1 of this SE against the changes approved in Traveler TSTF-591. The NRC staff finds that the licensees proposed
changes to the Callaway TSs in section 1.1 of this SE are consistent with those found acceptable in TSTF-591.
In the final SE for TSTF-591, the NRC staff concluded that the TSTF-591 proposed changes to STS 5.5.20, Risk Informed Completion Time Program, and the proposed addition of STS 5.6.8, Risk Informed Completion Time (RICT) Program Upgrade Report, were acceptable. These modifications were acceptable because, as discussed in the final SE, they continued to ensure the PRA models used to calculate a RICT are maintained and upgraded by the licensees appropriate use of endorsed guidance (i.e., the ASME/ANS PRA Standard requirements, and specific industry guidance that the NRC staff has determined are sufficient for determining the acceptability of PRA models and newly developed methods for use in the RICT program). Furthermore, as discussed in the SE for TSTF-591, the addition of reporting requirements does not preclude any NRC staff oversight of PRA changes performed to ensure the PRA model(s) continue to be maintained and upgraded consistent with RG 1.200, Revision 3. Therefore, the NRC staff found that the proposed changes to the RICT Program and addition of the RICT Program Upgrade Report requirements were acceptable because they continued to meet the requirements of 10 CFR 50.36(c)(5) by providing administrative controls necessary to assure operation of the facility in a safe manner. For these same reasons, the NRC staff concludes that the corresponding proposed changes to the Callaway TSs in section 1.1 of this SE continue to meet the requirements of 10 CFR 50.36(c)(5).
3.2 Additional Proposed Changes In addition to the changes proposed, consistent with the TSTF-591 discussed in section 1.1, the licensee proposed the variation below.
3.2.1 Variations That Do Not Affect the Applicability of the Traveler The LAR noted that applicable table of contents numbering changes are to be made, as well as Callaway TSs has different numbering in section 5.0 than STSs. The NRC staff finds that these variations are acceptable because they do not alter TS requirements.
3.3 TS Change Consistency The NRC staff reviewed the proposed TS changes for technical clarity and consistency with the existing requirements for customary terminology and formatting. The NRC staff finds that the proposed changes are consistent with chapter 16.0 of the SRP and are therefore acceptable.
4.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
NOTICES AND ENVIRONMENTAL FINDINGS RELATED TO AMENDMENT NO. 240 TO RENEWEDFACILITY OPERATING LICENSE NO. NPF-30 UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT NO. 1 DOCKET NO. 50--483 Application (i.e., initial and supplements)
Safety Evaluation Date December 5, 2024, ML24340A175 February 4, 2025, ML25035A300 March 11, 2025,. ML25070A260 June 27, 2025
1.0 INTRODUCTION
Union Electric Company, doing business as Ameren Missouri (the licensee), requested changes to the technical specifications (TSs) for Callaway Plant, Unit No. 1 (Callaway) by license amendment request (application). In its application, the licensee requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed amendment under the Consolidated Line Item Improvement Process (CLIIP). The proposed changes would revise the TSs based on Technical Specifications Task Force (TSTF) Traveler TSTF-591, Revision 0, Revise Risk Informed Completion Time (RICT) Program (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22081A224), and the associated NRC staff safety evaluation of Traveler TSTF-591 (ML23262B230).
2.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Missouri State official was notified of the proposed issuance of the amendment on June 2, 2025. The State official had no comments
3.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in Title 10 of the Code of Federal Regulations (10 CFR) Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration as published in the Federal Register on January 21, 2025 (90 FR 7194), and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need to be prepared in connection with the issuance of the amendment.
- by email NRR-058 OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DSS/STSB/BC NAME MChawla PBlechman SMehta DATE 06/05/2025 06/05/2025 06/05/2025 OFFICE OGC - NLO*
NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME MChwedczuk TNakanishi MChawla DATE 06/11/2025 6/27/2025 6/27/2025