ML18094A260
| ML18094A260 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse, PROJ0700 |
| Issue date: | 04/30/2018 |
| From: | Dennis Morey NRC/NRR/DLP/PLPB |
| To: | Gresham J Westinghouse |
| Lenning E | |
| Shared Package | |
| ML17334A102 | List: |
| References | |
| WCAP-17203-NP, Rev 0-2, WCAP-17203-P, Rev 0-2 | |
| Download: ML18094A260 (3) | |
Text
OFFICIAL USE ONLY - PROPRIETARY INFORMATION April 30, 2018 Mr. James A. Gresham, Manager Regulatory Compliance and Plant Licensing Westinghouse Electric Company 1000 Westinghouse Drive Cranberry Township, PA 16066
SUBJECT:
DRAFT SAFETY EVALUATION FOR WESTINGHOUSE ELECTRIC COMPANY TOPICAL REPORT WCAP-17203-P/WCAP-17203-NP, REVISION 0-2, FAST TRANSIENT AND ATWS METHODOLOGY
Dear Mr. Gresham:
By letter dated June 30, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML101830262), Westinghouse Electric Company (Westinghouse) submitted for U. S. Nuclear Regulatory Commission (NRC) staff review Topical Report (TR)
WCAP-17203-P/WCAP-17203-NP, Fast Transient and ATWS [anticipated transient without scram] Methodology. This TR provided a methodology for analyzing both limiting and non-limiting fast transients in initial and reload cores for currently operating boiling water reactors (BWRs) and advanced BWRs (ABWRs). The NRC staff requested responses to several requests for additional information (RAIs) as a result of the review of WCAP-17203-P, Revision 0, and the applicant incorporated issues resolved through the RAI process into a revised version of WCAP-17203-P/WCAP-17203-NP. The revised TR WCAP-17203-P/
WCAP-17203-NP, Fast Transient and ATWS Methodology, was submitted by Nuclear Innovation North America, LLC to the NRC for the review and approval by letter dated October 20, 2014 (ADAMS Accession No. ML14301303). By letter dated May 6, 2015, the NRC staff issued a revised acceptance for review of WCAP-17203-P/ WCAP-17203-NP, Revision 0-2 (ADAMS Accession No. ML15111A272) that captured Westinghouses request for the review of this TR to be applicable to the operating boiling-water reactors.
Enclosed for Westinghouse review and comment is a copy of the NRC staff's draft safety evaluation (SE) for the TR WCAP-17203-P/WCAP-17203-NP, Revision 0-2, applicable to BWR 2 through 6.
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.
OFFICIAL USE ONLY - PROPRIETARY INFORMATION
OFFICIAL USE ONLY - PROPRIETARY INFORMATION J. Gresham To facilitate the NRC staff's review of your comments, please provide a marked-up copy of the draft SE showing proposed changes and provide a summary table of the proposed changes.
If you have any questions, please contact Ekaterina Lenning at 301-415-3151.
Sincerely,
/RA/
Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Project No. 99902038
Enclosure:
Draft SE (Proprietary)
OFFICIAL USE ONLY - PROPRIETARY INFORMATION
Pkg: ML17334A102; Letter: ML18094A260; *via e-mail NRR-106 OFFICE NRR/DLP/PLPB/PM NRR/DLP/PLPB/LA* NRR/DSS/SNPB/BC* NRR/DLP/PLPB/BC NAME ELenning DHarrison RLukes DMorey DATE 4/4/18 4/25/18 4/26/18 4/30/18