ML18038A347

Transmittal Letter for Final Safety Evaluation for Pressurized Water Reactor Owners Group Topical Report BAW-1543, Revision 4, Supplement 7

ML18038A347
Person / Time
Site:	PROJ0694, 99902037
Issue date:	03/27/2018
From:	Dennis Morey NRC/NRR/DLP/PLPB
To:	Nowinowski W PWR Owners Group
Benney B
References
BAW-1543
Download: ML18038A347 (7)

Text

March 27, 2018 Mr. W. Anthony Nowinowski, Program Manager PWR Owners Group, Program Management Office Westinghouse Electric Company 1000 Westinghouse Drive, Suite 380 Cranberry Township, PA 16066

SUBJECT:

FINAL SAFETY EVALUATION FOR PRESSURIZED WATER REACTOR OWNERS GROUP TOPICAL REPORT BAW-1543, REVISION 4, SUPPLEMENT 7, SUPPLEMENT TO THE MASTER INTEGRATED REACTOR VESSEL SURVEILLANCE PROGRAM

Dear Mr. Nowinowski:

By letter dated January 23, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15033A086), the Pressurized Water Reactors Owners Group (PWROG), submitted Topical Report (TR) BAW-1543, Revision 4, Supplement 7, Supplement to the Master Integrated Reactor Vessel Surveillance Program to the U.S. Nuclear Regulatory Commission (NRC) for review and acceptance for referencing in regulatory actions. The revisions contained in this supplement were necessary to show updates to the surveillance capsule withdrawal schedules and the change of status of Capsules A2 and A4 to withdrawal not planned.

The NRC staff has found the revised and updated information to the withdrawal schedules and change in capsule status, as indicated in Topical Report BAW-1543, Revision 4, Supplement 7, acceptable for referencing in licensing applications for the B&W-designed 177-FA plants and the Westinghouse-designed plants with B&W-fabricated reactor vessels to the extent specified and under the limitations delineated in the TR and in the enclosed final SE. The final SE defines the basis for our acceptance of the TR.

The proposed withdrawal schedules satisfy the requirements of Appendix H to Title 10 of the Code of Federal Regulations (10 CFR) Part 50 and are consistent with XI.M31, Reactor Vessel Surveillance, in NUREG-1801, the Generic Aging Lessons Learned Report, for the license renewal period.

Our acceptance applies only to material provided in the subject TR. We do not intend to repeat our review of the acceptable material described in the TR. When the TR appears as a reference in licensing action requests, our review will ensure that the material presented applies to the specific plant involved. Requests for licensing actions that deviate from this TR will be subject to a plant-specific review in accordance with applicable review standards.

W. Nowinowski In accordance with the guidance provided on the NRC website, we request that the PWROG publish approved proprietary and non-proprietary versions of TR BAW-1543, Revision 4, Supplement 7, within 3 months of receipt of this letter. The approved versions shall incorporate this letter and the enclosed final SE after the title page. Also, they must contain historical review information, including NRC requests for additional information and your responses. The approved versions shall include an -A (designating approved) following the TR identification symbol.

As an alternative to including the request for additional information (RAIs) and RAI responses behind the title page, if changes to the TR were 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 RAIs and RAI responses can be included as an Appendix to the accepted version.

2. The RAIs and RAI responses can be captured in the form of a table (inserted after the final SE) which summarizes the changes as shown in the approved version of the TR. The table should reference the specific RAIs 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 or justify its continued applicability for subsequent referencing. Licensees referencing this TR would be expected to justify its continued applicability or evaluate their plant using the revised TR.

Sincerely,

/RA/

Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Processes Office of Nuclear Reactor Regulation Docket No. 99902037

Enclosure:

Final Safety Evaluation (Non-Proprietary)

ML18038A347 (Letter); ML18038A345 (Enclosure);

ML18038a332 (Package); *concurrence via e-mail NRR-106 OFFICE NRR/DLP/PLPB NRR/DLP/PLPB* NRR/DE/EMIB* NRR/DLP/PLPB NAME BBenney DHarrison SRuffin DMorey DATE 3/26/18 3/14/18 3/6/18 3/27/18