ML24324A353
| ML24324A353 | |
| Person / Time | |
|---|---|
| Site: | 99902037, PROJ0694 |
| Issue date: | 12/27/2024 |
| From: | Leslie Fields Licensing Processes Branch |
| To: | Andrachek J, Holderbaum C, Olinski D Westinghouse |
| Shared Package | |
| ML24324A169 | List: |
| References | |
| EPID L-2021-TOP-0027, PWROG-18068-NP, Rev. 1 | |
| Download: ML24324A353 (1) | |
Text
From:
Leslie Fields To:
Holderbaum, Chad M.; Andrachek, James D; Olinski, Dewey C.
Cc:
Gerond George; Lois James; Karen Thomson; Angie Buford; John Tsao; David Dijamco
Subject:
NRC Transmittal of the Final Safety Evaluation for PWROG-18068, Revision1 Date:
Friday, December 27, 2024 3:11:39 PM Mr. Dewey Olinski, PE PWR Owners Group, Program Management Office Westinghouse Electric Company 1000 Westinghouse Drive, Suite 172 Cranberry Township, PA 16066
SUBJECT:
U.S. NUCLEAR REGULATORY COMMISSION TRANSMITTAL OF THE FINAL SAFETY EVALUATION FOR PRESSURIZED WATER REACTOR OWNERS GROUP TOPICAL REPORT PWROG-18068-NP, REVISION 1, USE OF DIRECT FRACTURE TOUGHNESS FOR EVALUATION OF RPV
[REACTOR PRESSURE VESSEL] INTEGRITY (EPID: L2021-TOP0027)
Dear Mr. Olinski,
By letter dated July 27, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21209A932), as supplemented by letters dated March 8, and July24, 2024 (ADAMS Accession Nos. ML24068A101 and ML24206A042, respectively),
the Pressurized Water Reactor Owners Group (PWROG) submitted Topical Report (TR)
PWROG18068-NP, Revision1, Use of Direct Fracture Toughness for Evaluation of RPV
[Reactor Pressure Vessel] Integrity (ADAMS Accession No. ML21209A933), to the U.S.Nuclear Regulatory Commission (NRC) for review and approval.
The PWROG provided comments on the draft safety evaluation (SE) on October 1, 2024 (ADAMS Accession No. ML24275A041). A copy of the final SE for TR PWROG-18068-NP, Revision 1, has been placed on BOX.com and access has been granted for review. It will be made publicly available in ADAMS two weeks from the date of this email as ADAMS Accession No. ML24324A169 after a courtesy proprietary review is completed by PWROG.
The NRC staff concludes that the TR proposes an alternative methodology to the structural integrity requirements for RPV materials specified in Title 10 of the Code of Federal Regulations Part 50, Domestic Licensing of Production and Utilization Facilities (10 CFR Part 50). The proposed alternative methodology is based on the use of the ductile-brittle reference temperature (T0) in lieu of the nil-ductility reference temperature (RTNDT) for RPV material integrity evaluations. The details of the alternative methodology are discussed in the SE.The final SE defines the basis of NRCs acceptance of the TR.The NRCs acceptance applies only to information provided in the subject TR.In accordance with the guidance provided on the NRC website, the NRC requests that PWROG publish an accepted version of the TR, within three months of receipt of the date of this email.The accepted version shall incorporate this email and the enclosed SE after the title page.
This email has been placed in ADAMS as Accession No. ML24324A353 and has been declared as an Official Agency Record for public availability.
Please be informed that the accepted versions of this TR must contain historical review information, including NRC requests for additional information (RAI) questions and the associated responses.The accepted versions shall also include a -A (designating approved) following the TR identification symbol.
As an alternative to including the RAI questions and RAI responses behind the title page, if changes to the TR provided to the NRC staff to support the resolution of RAI responses, and if the NRC staff reviewed and approved those changes as described in the RAI responses, there are two ways that the accepted version can capture the RAIs:
(1.) The RAI questions and responses can be included as an Appendix to the accepted version.
(2.) The RAI questions and responses can be captured in the form of a table (inserted after the final SE) which summarizes the changes as shown in the accepted version of the TR. The table should reference the specific RAI questions and RAI responses which resulted in any changes, as shown in the accepted version of the TR.
If future changes to the NRCs regulatory requirements affect the acceptability of this TR, PWROG will be expected to revise the TR appropriately.Licensees referencing this TR would be expected to justify its continued applicability or evaluate their plant using the revised TR.
If you have any questions, please contact the Project Manager for the review,Leslie Fields,at301-415-1186or via electronic mail atleslie.fields@nrc.gov.
Sincerely, Leslie C. Fields, US NRC Senior Project Manager NRR/DORL