ML24271A292
| ML24271A292 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 11/20/2024 |
| From: | Ballard B Plant Licensing Branch III |
| To: | Conboy T Northern States Power Co |
| Ballard, Brent | |
| References | |
| EPID-L-2022-LLA-0184 | |
| Download: ML24271A292 (1) | |
Text
November 20, 2024 Thomas Conboy Site Vice President Northern States Power Company -
Minnesota Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -
CORRECTION TO THE TECHNICAL SPECIFICATIONS AND CHANGE TO SAFETY EVALUATION FOR LICENSE AMENDMENT NOS. 243 AND 231 RE:
REVISE TECHNICAL SPECIFICATION 5.6.6, REACTOR COOLANT SYSTEM (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
Dear Thomas Conboy:
By letter dated January 17, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23356A003), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 243 to Renewed Facility Operating License No. DPR-42 and Amendment No. 231 to Renewed Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2, respectively. The amendments were in response to the license amendment request (LAR) by Northern States Power Company, a Minnesota Corporation (NSPM, the licensee), doing business as Xcel Energy, dated December 2, 2022 (ML22343A257), as supplemented by letters dated March 28, 2023 (ML23087A250), and December 20, 2023 (ML23354A155). The amendments revised Technical Specification (TS) 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR), to replace the current PTLR method with more recent analytical methods and remove a reference to an American Society of Mechanical Engineers Code Case that is no longer needed with the updated methods.
When these amendments were issued, the revised TS page 5.6-9 contained a typo for TS 5.6.7, Steam Generator Tube Inspection Report. Specifically, on the top of page 5.6-9, the continuation of the Steam Generator Tube Inspection Report TS from page 5.6-8 is incorrectly identified as 5.6.8 but should be 5.6.7. The amendments did not make any changes to TS 5.6.7.
The NRC staff concludes that the error was introduced during the preparation of the amendments and is entirely editorial in nature. The corrected Prairie Island, Units 1 and 2, TS page 5.6-9 is enclosed. Please remove the current page 5.6-9 and insert the corrected page 5.6-9.
Additionally, the NRC staffs safety evaluation supporting the amendment contained errors in section 3.4, Surveillance Data. Specifically, the section references WCAP-18794, which contains a typo. The correct reference is WCAP-18795. Additionally, the safety evaluation
stated surveillance forging data and weld data for Prairie Island, Unit 2 were non-credible, and the margin term was not reduced. However, as stated in the enclosure to the March 28, 2023, LAR supplement, the surveillance weld data was deemed credible, and a reduced margin term was used.
The corrections do not change any of the conclusions in the safety evaluation associated with the amendments referenced above and do not affect the associated notices to the public.
If you have any questions, please contact me at (301) 415-0680 or Brent.Ballard@nrc.gov.
Sincerely,
/RA/
Brent T. Ballard, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosure:
Corrected TS page 5.6-9 cc: Listserv
Enclosure ENCLOSURE NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT NOS. 1 AND 2 CORRECTED TECHNICAL SPECIFICATIONS PAGE 5.6-9 DOCKET NOS. 50-282 AND 50-306
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ML24271A292 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DNRL/NVIB/BC NAME BBallard SRohrer ABuford DATE 9/27/2024 9/30/2024 11/12/2024 OFFICE OGC (NLO)
NRR/DORL/LPL3/BC(A)
NRR/DORL/LPL3/PM NAME MChwedczuk RKuntz BBallard DATE 11/20/2024 11/20/2024 11/20/2024