ML18081A007

Letter for Draft Safety Evaluation for Pressurized Water Reactor Owners Group Topical Report WCAP-17661, Improved RAOC and CAOC Fq Surveillance Technical Specifications

ML18081A007
Person / Time
Site:	PROJ0694, 99902037
Issue date:	04/24/2018
From:	Dennis Morey NRC/NRR/DLP/PLPB
To:	Nowinowski W PWR Owners Group, Westinghouse
Benney B
Shared Package
ML18081A006	List: ML18081A007
References
Download: ML18081A007 (3)

Text

OFFICIAL USE ONLY - PROPRIETARY INFORMATION April 24, 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:

DRAFT SAFETY EVALUATION FOR PRESSURIZED WATER REACTOR OWNERS GROUP TOPICAL REPORT WCAP-17661, IMPROVED RAOC AND CAOC FQ SURVEILLANCE TECHNICAL SPECIFICATIONS

Dear Mr. Nowinowski:

By letter dated January 2, 2014 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML14009A098), the Pressurized Water Reactors Owners Group (PWROG), submitted for Nuclear Regulatory Commission approval, Topical Report WCAP-17661, Improved RAOC and CAOC FQ Surveillance Requirements. The topical report (TR) was supplemented by letters dated September 13, 2016, and February 15, 2018 (ADAMS Package Accession Nos. ML16291A531 and ML18053A269, respectively). The TR provides the technical basis for updates to Technical Specification (TS) 3.2.1, Heat Flux Hot Channel Factor, as presently contained in NUREG-1431, Standard Technical Specifications -

Westinghouse Plants (ADAMS Accession Nos. ML12100A222 (Volume 1) and ML12100A228 (Volume 2)).

The NRC staff review determined that the revisions to the heat flux hot channel factor TS were acceptable. The revisions provide a more robust means for performing the FQW(Z) surveillance, a series of more restrictive operating spaces if the FQW(Z) LCO is not met, and a more clearly defined set of Surveillance Requirements and Required Actions. The TS changes also provide reasonable assurance that a core operated in accordance with these TS will remain within the power distribution limits assumed in the facility safety analyses.

Pursuant to Section 2.390 of Title 10 of the Code of Federal Regulations (10 CFR), we believe that the enclosed draft SE may contain proprietary information. If you believe that any information in the enclosure is proprietary, please identify such information line-by-line and define the basis pursuant to the criteria of 10 CFR 2.390. Twenty working days are provided for you to comment on the proprietary aspects and provide any factual errors or clarity concerns contained in the SE. The final SE will be issued after making any necessary changes and a non-proprietary version will be made publicly available. The NRC staff's disposition of your comments on the draft SE will be discussed in the final SE.

NOTICE: The enclosure transmitted herewith contains Proprietary Information. When separated from the enclosure, this transmittal document is decontrolled.

OFFICIAL USE ONLY - PROPRIETARY INFORMATION

OFFICIAL USE ONLY - PROPRIETARY INFORMATION W. Nowinowski To facilitate the NRC staff's review of your comments, please provide a marked-up copy of the revised draft SE showing proposed changes and provide a summary table of the proposed changes.

If you have any questions, please contact Brian Benney at 301-415-2767.

Sincerely,

/RA/

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

Enclosure:

Draft Safety Evaluation OFFICIAL USE ONLY - PROPRIETARY INFORMATION

ML18081A007 (Letter); ML18081A009 (Enclosure);

ML18081A006 (Package); *concurrence via e-mail NRR-106 OFFICE NRR/DLP/PLPB NRR/DLP/PLPB* NRR/DSS/SNPB* NRR/DLP/PLPB NAME BBenney DHarrison Sanderson DMorey DATE 4/16/18 4/10/18 3/13/18 4/24/18