LR-N16-0174, Response to Second Request for Additional Information Regarding Relief Request VR-02 Associated with the Fourth 10-Year Inservice Test Interval

Response to Second Request for Additional Information Regarding Relief Request VR-02 Associated with the Fourth 10-Year Inservice Test Interval

ML16267A370
Person / Time
Site:	Hope Creek
Issue date:	09/23/2016
From:	Duke P Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N16-0174
Download: ML16267A370 (4)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 NudearLLC 10 CFR 50.55a LR-N16-0174 SEP 2 3 .216 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354

Subject:

Response to second Request for Additional Information Regarding Relief Request VR-02 Associated with the Fourth 10-Year lnservice Test Interval

References:

1. PSEG Letter LR-N15-0250, "lnservice Testing (1ST) Program- Fourth Ten Year Interval," dated December 18, 2015 (ADAMS Accession No. ML15352A127)

2. NRC Letter to PSEG, "Hope Creek Generating Station - Request for Additional Information Regarding Relief Requests GR-01, PR-01, PR-02, VR-01, and VR-02, Associated with the Fourth 10-Year lnservice Test Interval (CAC Nos. MF7200, MF7201, MF7202, MF7203, and MF7204)," dated May 5, 2016 (ADAMS Accession No. ML16089A079)

3. PSEG Letter LR-N16-01 05, "Request for Additional Information Regarding Relief Requests Associated with the Fourth 10-Year lnservice Test Interval,"

dated June 10, 2016 (ADAMS Accession No. ML16162A709)

4. NRC Letter to PSEG, "Hope Creek Generating Station - Request for Additional Information Regarding Relief Request VR-02, Associated with the Fourth 10-Year lnservice Test Interval (CAC Nos. MF7201," dated August 24, 2016 (ADAMS Accession No. ML16231A427)

In the Reference 1 letter, PSEG Nuclear LLC (PSEG) submitted relief requests to the U.S.

Nuclear Regulatory Commission (NRC) for the Hope Creek Generating Station. The requests proposed alternatives to the requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants for the fourth 10-year inservice testing (1ST) program interval.

In the Reference 2 letter, the NRC staff requested additional information for two of the proposed alternatives. PSEG's responses were provided in Reference 3.

I SEP 2 3.2016 10 CFR 50.55a Page 2 LR-N16-0174 In the Reference 4 letter, the NRC staff requested additional information for one of the proposed alternatives. PSEG's response is provided in Attachment 1.

There are no regulatory commitments contained in this letter. If you have any questions or require additional information, please contact Mr. Lee Marabella at (856) 339-1208.

Sincerely, 0 Q r{__ fl_jJ Paul R. D : , Jr.

\

Manager, Licensing Attachments

1. PSEG Response to Request for Additional Information Regarding Relief Request VR-02, Associated With the Fourth 10-Year lnservice Test Interval C D. Dorman, Regional Administrator - NRC Region I C. Parker, Project Manager - Hope Creek, USNRC NRC Senior Resident Inspector- Hope Creek P. Mulligan, Chief, NJBNE Tom MacEwen, Hope Creek Commitment Coordinator Lee Marabella, Corporate Commitment Coordinator

LR-N16-0174 Attachment 1 PSEG Response to Request for Additional Information Regarding Relief Request VR-02, Associated With the Fourth 10-Year lnservice Test Interval

LR-N16-0174 VR-02 RAI-2:

The regulations in 10 CFR 50.55a(f), "lnservice testing requirements," require, in part, that inservice testing of certain ASME Code Class 1, 2, and 3 components must meet the requirements of the ASME OM Code and applicable addenda, except where alternatives have been authorized pursuant to paragraphs 10 CFR 50.55a(z)(1) or 10 CFR 50.55a(z)(2).

1. How will the ASME OM Code sample test requirement of l-1320(a) (i.e. , 20 percent per 24 months) be applied to the main steam pressure relief valves?

2. How will the 20 percent be determined?

3. Will the two stage and three stage Target Rock valves be in separate groups (a group being defined in accordance with 1-1200)?

4. How will the change in the number of three stage versus two stage Target Rock valves affect the grouping(s)?

PSEG Response Currently PSEG Nuclear (PSEG) has 14 Target Rock Model 7567F two-stage safety relief valves installed in Hope Creek. These valves comprise the scope of relief request VR-02 and upon approval of the relief request, will be tested as described in References 1 and 3.

If, at some point in the future, PSEG decides to install one or more Target Rock 3-stage safety relief valves, they will be tested at the Mandatory Appendix I specified frequency.

PSEG intends to classify the 3-stage valves as a separate group for testing frequency purposes regardless of whether they meet the definition of a separate group per 1-1200.