ML19158A266
| ML19158A266 | |
| Person / Time | |
|---|---|
| Site: | 99902037 |
| Issue date: | 06/25/2019 |
| From: | Dennis Morey Research and Test Reactors Oversight Projects Branch |
| To: | Nowinowski W PWR Owners Group |
| J. Drake, NRR/DLP, 301-415-8378 | |
| References | |
| EPID L-2018-TOP-0009 | |
| Download: ML19158A266 (2) | |
Text
June 25, 2019 Mr. W. Anthony Nowinowski Executive Director PWR Owners Group, Program Management Office Westinghouse Electric Company 1000 Westinghouse Drive, Suite 380 Cranberry Township, PA 16066
SUBJECT:
DRAFT SAFETY EVALUATION BY THE OFICE OF NUCLEAR REACTOR REGULATION FOR TOPICAL REPORT PWROG-15109-NP, REVISION 0, PWR PRESSURE VESSEL NOZZLE APPENDIX G EVALUATION (EPID L-2018-TOP-0009)
Dear Mr. Nowinowski:
By letter dated March 5, 2018 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML18067A228), as supplemented by letter dated March 27, 2019 (ADAMS Accession No. ML19091A089), the Pressurized Water Reactor (PWR) Owners Group (PWROG) submitted to the U.S. Nuclear Regulatory Commission (NRC) topical report (TR)
PWROG-15109-NP, Revision 0, PWR Pressure Vessel Nozzle Appendix G Evaluation (ADAMS Accession No. ML18067A229), for review and approval.
The staff has reviewed the TR including the supplemental information, and based on the evaluation in Section 4 of the enclosed safety evaluation (SE), finds that the TR, as modified by the SE, provides an acceptable means for addressing the potential for pressure-temperature (P-T) limit curves for inlet or outlet nozzle corners of U.S. PWRs to be more limiting than the current NRC-approved P-T limits (as of the time of issuance of this SE) of the shell (and associated welds) in the traditional beltline region of the reactor pressure vessel. Accordingly, the TR, as modified by the SE, is acceptable for referencing to satisfy the fracture toughness requirements in Appendix G to Title 10 of the Code of Federal Regulations Part 50 for U.S.
PWR inlet and outlet nozzles only, which provide adequate margins of safety during any condition of normal operation, including anticipated operational occurrences and system hydrostatic tests, to which the pressure boundary may be subjected over its service lifetime.
Applicants who utilize the TR will be required to adhere to the conditions that the NRC staff imposed in the SE and shall be subject to NRC staff review and approval on a case-by-case basis.
Twenty working days are provided for you to comment on any factual errors or clarity concerns contained in the draft SE. The final SE will be issued after making any necessary changes and will be made publicly available. The NRC staff's disposition of your comments on the draft SE will be discussed in the final SE.
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 Jason Drake at 301-415-8378.
Sincerely,
/RA/
Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 99902037
Enclosure:
Draft SE
ML19158A230 -Package ML19158A266 -Cover Letter ML19158A265 -Enclosure *concurrence via e-mail NRR-106 OFFICE NRR/DLP/PLPB/PM NRR/DLP/PLPB/LA* NRR/DMLR/MVIB/BC NRR/DLP/PLPB/BC NAME JDrake DHarrison DAlley DMorey DATE 6/7/19 6/18/19 6/20/19 6/25/19