ML19198A051
| ML19198A051 | |
| Person / Time | |
|---|---|
| Site: | 99902037 |
| Issue date: | 09/11/2019 |
| From: | Dennis Morey NRC/NRR/DLP/PLPB |
| To: | Nowinowski W PWR Owners Group, Westinghouse |
| Drake J, NRR/DLP/PLPB, 415-8378 | |
| Shared Package | |
| ML19198A050 -Pkg. | List: |
| References | |
| EPID: L-2018-TOP-0019 | |
| Download: ML19198A051 (3) | |
Text
September 11, 2019 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 PWROG-17011-NP, REVISION 2 REPORT, UPDATE FOR SUBSEQUENT LICENSE RENEWAL: WCAP-14535A, TOPICAL REPORT ON REACTOR COOLANT PUMP FLYWHEEL INSPECTION ELIMINATION AND WCAP-15666-A, EXTENSION OF REACTOR COOLANT PUMP MOTOR FLYWHEEL EXAMINATION (EPID: L-2018-TOP-0019)
Dear Mr. Nowinowski:
By letter dated May 15, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18143B465), the Pressurized Water Reactor Owners Group (PWROG) submitted Topical Report (TR) PWROG-17011-NP, Revision 1, "Update for Subsequent License Renewal: WCAP-14535A, Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination and WCAP-15666-A, Extension of Reactor Coolant Pump Motor Flywheel Examination," to the U.S. Nuclear Regulatory Commission (NRC) staff for review. By letter dated January 28, 2019 (ADAMS Package Accession No. ML19036A684), the PWROG submitted Revision 2 of Topical Report (TR) PWROG-17011-NP to address an NRC Request for Additional Information (Set 5, RAI 4.3.5-2), on the Turkey Point Units 3 and 4 Subsequent License Renewal (ADAMS Accession No. ML18362A146). By letter dated August 6, 2019 (ADAMS Accession No. ML19221B588), the PWROG provided clarification on the intent of the Revision 2 submission and requested that the NRC prepare the final safety evaluation for PWROG-17011-NP against Revision 2.
The NRC staff review determined that the information provided in the TR provides the technical and regulatory basis for continuing the 20-year inservice inspection interval approved for reactor coolant pump motor flywheels for the period of extended operation (60 years) in WCAP-15666-A (ADAMS Accession No. ML18303A413), to the subsequent period of extended operation (80 years). The NRC staff has reviewed PWROG-17011-NP, Revision 2 and concludes that the subject report, as modified by the conditions and limitations summarized in Section 4.0 of the enclosed safety evaluation, provides an acceptable methodology that can be used to support such a request.
By letter dated March 19, 2019 (ADAMS Accession No. ML19072A103), the NRC staff provided the draft safety evaluation (SE) to the PWROG for review and comment. Per email correspondence on June 17, 2019 (ADAMS Accession No. ML19198A037), the PWROG identified that they had no comments on the draft SE.
W. Nowinowski In accordance with the guidance provided on the NRC website, we request that the PWROG publish an approved version of PWROG-17011-NP, Revision 2 within 3 months of receipt of this letter. The approved version shall incorporate this letter and the enclosed final SE after the title page. Also, it must contain historical review information, including NRC requests for additional information (RAIs) and your responses. The approved version shall include an -A (designating approved) following the TR identification symbol. As an alternative to including the 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:
- 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 these TRs, PWROG will be expected to revise the TRs appropriately or justify their continued applicability for subsequent referencing. Licensees referencing these TRs would be expected to justify their continued applicability or evaluate their plant using the revised TRs.
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:
Final SE
ML19198A050 -Package ML19198A051 -Cover Letter ML19198A056 -Enclosure ML19198A037 -Incoming *concurrence via email NRR-106 OFFICE NRR/DLP/PLPB/PM NRR/DLP/PLPB/LA NRR/DRA/ARCB/BC NAME JDrake* DHarrison* KHsueh (JDozier for)
DATE 7/23/2019 7/18/2019 9/5/2019 OFFICE NRR/DLP/PLPB/BC NRR/DMLR/MVIB/BC NAME DMorey DAlley DATE 9/11/2019 9/6/2019