ML25022A156
| ML25022A156 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 01/22/2025 |
| From: | James Park NRC/RGN-III/DORS/ERPB |
| To: | Conboy T Northern States Power Company, Minnesota |
| References | |
| IR 2025012 | |
| Download: ML25022A156 (1) | |
See also: IR 05000282/2025012
Text
Thomas A. Conboy
Site Vice President
Prairie Island Nuclear Generating Plant
Northern States Power Company, Minnesota
1717 Wakonade Drive East
Welch, MN 55089-9642
SUBJECT:
PRAIRIE ISLAND 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 05000282/2025012;
05000306/2025012) AND REQUEST FOR INFORMATION (RFI)
Dear Thomas A. Conboy:
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 Prairie Island Nuclear Generating Plant, Units 1 and 2, in April 2025. The
inspection team will be composed of personnel from the Region III Office and led by
Joon S. Park. 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
Prairie Island Nuclear Generating Plant Nuclear Plant, Units 1 and 2.
The schedule for the inspection is as follows:
Information Gathering Trip
March 10-14, 2025
Preparation week:
April 21-25, 2025
Onsite weeks:
April 28-May 2, 2025, and May 12-16, 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 Joon S. Park, Team Leader at (630) 829-9715 or via email
at joon.park@nrc.gov.
This letter does not contain new or amended information collection requirements subject to the
January 22, 2025
T. Conboy
2
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 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,
Joon S. Park
Reactor Inspector
Engineering Reactor and Projects Branch
Division of Operating Reactor Safety
Docket Nos. 50-282; 50-306
Enclosure:
10 CFR 50.69 Program Supporting
Documentation Request for Information
cc: Distribution via LISTSERV
Signed by Park, Joon
on 01/22/25
SUNSI Review
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available
OFFICE
RIII
NAME
JPark:gmp
DATE
01/22/2025
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 April 16, 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 March 7, 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.
Prairie Island 10 CFR 50.69 License Amendment Request (LAR)
b.
Responses to Requests for Additional Information (RAI) regarding the Prairie
Island 10 CFR 50.69 LAR
c.
U.S. NRC Safety Evaluation Report and approval of 10 CFR 50.69 LAR
2
d.
Updated Final Safety Analysis changes associated with the implementation of
10 CFR 50.69 at Prairie Island
e.
f.
Units 1 and 2 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 Prairie Island issue reports (designator and title) associated
with the implementation of the 10 CFR 50.69 process at Prairie Island. 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 Prairie Island/Corporate 10 CFR 50.69 Program
since the issuance of the 10 CFR 50.69 license amendment (November 12, 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 November 12, 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 Prairie Island
14. PRA model information (e.g., Excel spreadsheet) providing a listing of all basic
3
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
If you have questions regarding the information requested, please contact the lead inspector.