IR 05000263/2025011
| ML25136A353 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 05/16/2025 |
| From: | Fay K NRC/RGN-III/DORS/EB2 |
| To: | Hafen S Northern States Power Co, Nuclear Management Co |
| References | |
| IR 2025011 | |
| Download: ML25136A353 (1) | |
Text
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT - NOTIFICATION OF TITLE 10 OF THE CODE OF FEDERAL REGULATIONS 50.69, RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS, AND COMPONENTS FOR NUCLEAR POWER REACTORS, INSPECTION (INSPECTION REPORT 05000263/2025011)
AND REQUEST FOR INFORMATION (RFI)
Dear Shawn Hafen:
The purpose of this letter is to notify you that U.S. Nuclear Regulatory Commission (NRC) staff will conduct a Title 10 of the Code of Federal Regulations (10 CFR) 50.69 program inspection at Monticello Nuclear Generating Plant, in July 2025. The inspection team will be composed of personnel from the Region III Office and led by Kevin Fay. The inspection will be conducted in accordance with Inspection Procedure 37060, the NRC's special and infrequently performed inspection procedure. The inspection is being performed because the requirements of 10 CFR 50.69 have been implemented at Monticello Nuclear Generating Plant Nuclear Plant.
The schedule for the inspection is as follows:
Preparation week:
July 21-25, 2025
Onsite weeks:
July 28-Aug 01, 2025 An initial list of the documents that the team will review during the conduct of the inspection are listed in the Enclosure. The team leader will contact you with any additional specific document requests prior to the start of the inspection. Your cooperation and support during this inspection will be appreciated.
If you have questions concerning this inspection, or the inspection teams information request or logistical needs, please contact Kevin Fay, Team Leader at (630) 829-9629 or via email at Kevin.Fay@nrc.gov.
This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, Control Number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to May 16, 2025 respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget Control Number.
This letter and its enclosure will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Kevin Fay Senior Reactor Inspector Engineering Branch 2 Division of Operating Reactor Safety Docket Nos. 50-263 License Nos. DPR-22 Enclosure:
10 CFR 50.69 Program Supporting Documentation Request for Information cc: Distribution via LISTSERV Signed by Fay, Kevin on 05/16/25
SUNSI Review
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available OFFICE RIII NAME KFay:gmp DATE 05/16/2025
Enclosure 10 CFR 50.69 Program Supporting Documentation Contact the lead inspector as soon as possible if you have any questions regarding this information request. Provide the information electronically in pdf files, Excel, or other searchable formats, preferably via an electronic sharing service (CERTREC, ShareFile, Box, etc.). Specific Excel formats for various enclosure items may be requested to assist in inspection sample selection. If you do not have access to any of these services or similar, we can provide you access to Box, which can be used to upload/download and share documents. The files should contain descriptive names and be indexed and hyperlinked to facilitate ease of use. Information in lists should contain enough information to be easily understood by someone who has knowledge of light water reactor technology.
This document request is based on typical documents that a generic plant might have.
As such, this generic document request is not meant to imply that any specific plant is required to have all of the listed documents. It is recognized that some documents listed below may not be available for your plant. In addition, the document titles listed below are based on typical industry document names; your plant specific document titles may vary.
I.
LOGISTICS Email the following inspection logistics to the lead inspector by July 7, 2025, or sooner:
1.
Entrance meeting time and location.
2.
Inspection room name/number, directions from the main access facility, and phone number.
3.
Current management and engineering organizational chart.
4.
Response team contact information (names and phone numbers) and team roles (e.g., management sponsor, lead, inspector counterpart).
5.
Any potential resource conflicts during the inspection (e.g., emergency drills and all-staff meetings).
II. INFORMATION REQUEST The following information is requested by July 14, 2025, or sooner:
Note: If you are unable to provide the following items, please reach out to the lead inspector as soon as possible.
1.
Licensing bases documents:
a. Monticello 10 CFR 50.69 License Amendment Request (LAR)
b.
Responses to Requests for Additional Information (RAI) regarding the Monticello 10 CFR 50.69 LAR c.
U.S. NRC Safety Evaluation Report and approval of 10 CFR 50.69 LAR d.
Updated Final Safety Analysis changes associated with the implementation of 10 CFR 50.69 at Monticello e. NEI 00-04 f.
Unit 1 Facility Operating License 2.
Copy (latest revision) of 10 CFR 50.69 program procedures 3.
10 CFR 50.69 categorization documents for all systems which have completed system categorization 4.
Probabilistic Risk Assessment (PRA) system notebooks for systems that have completed system categorization 5.
List of Risk-Informed Safety Class (RISC)-1, RISC-2, and RISC-3 component failures (issue report designator and title will be acceptable) since implementing the program requirements on associated systems. If applicable, provide any performance indicators utilized to monitor performance of RISC-1, RISC-2, and RISC-3 SSCs consistent with categorization process assumptions and in the PRA model 6.
Administrative procedures that are utilized to implement alternative treatment of regulatory requirements under 10 CFR 50.69 (example: changes to In-service Testing Program procedures, Maintenance Rule Program procedures, Reportability Manual, etc.)
7.
Meeting Minutes for all Integrated Decision-Making Panel (IDP) meetings to date 8.
List of Corporate and Monticello issue reports (designator and title) associated with the implementation of the 10 CFR 50.69 process at Monticello. Do not include issue reports only associated with the submittal and approval of the 10 CFR 50.69 license amendment.
9.
Audits and self-assessments of the Monticello/Corporate 10 CFR 50.69 Program since the issuance of the 10 CFR 50.69 license amendment (August 29, 2019)
10. List of all changes or upgrades made to the PRA model of record utilized for 10 CFR 50.69 Program since the issuance of the 10 CFR 50.69 license amendment on August 29, 2019 11. Applicable credentials of IDP members 12. Provide program requirements that implement the requirement for feedback and process adjustments per 10 CFR 50.69(e). Provide a summary of updates, if applicable, to the categorization or treatment processes as a result of changes to the plant, operational practices, operating experience, or as a result of the performance issues of RISC-1, 2, or 3 SSCs.
13. License event reports associated with any reportable events per 10 CFR 50.69(g) since implementation of the program at Monticello.
14. PRA model information (e.g., Excel spreadsheet) providing a listing of all basic events with all available importance measures (e.g., Birnbaum, F-V, RAW and RRW) and an associated list of cutsets. This information shall be taken from the PRA model of record used in the 10 CFR 50.69 categorization process 15. System drawings identifying the RISC category or passive system components for systems that have completed the categorization process 16. If a seismic PRA was not used for passive risk categorization, please provide the Safe Shutdown Equipment List (used for Seismic Margins Analysis)
17. The plants Individual Plant Examination of External Events 18. The latest revision on the UFSAR, technical specifications, technical specifications basis and technical requirements manual.
19. The design basis documents and system training documents for the categorized systems.
If you have questions regarding the information requested, please contact the lead inspector.