ML120790050
| ML120790050 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 03/19/2012 |
| From: | Joseph Sebrosky Plant Licensing Branch IV |
| To: | Soenen P Pacific Gas & Electric Co |
| Sebrosky J,NRR/DORL/LPL4 301-415-1132 | |
| References | |
| TAC ME5713, TAC ME5714 | |
| Download: ML120790050 (1) | |
Text
From:
Sebrosky, Joseph Sent:
Monday, March 19, 2012 6:48 AM To:
'Soenen, Philippe R' Cc:
Lent, Susan; Burkhardt, Janet; 'Baldwin, Thomas (DCPP)'; Gardocki, Stanley; Billerbeck, John; Gall, Jennifer
Subject:
RE: Request for Additional information for DCPP regarding TS 3.7.1 (Tac No.
ME5713 and ME 5714)
- Philippe, By letter dated February 17, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110480870), Pacific Gas and Electric Company (PG&E) submitted PG&E Letter DCL-11-018, License Amendment Request 11-02, Revision to Technical Specification (TS) 3.7.1, Main Steam Safety Valves (MSSVs).
PG&E submitted a request for revision to TS 3.7.1, and TS Table 3.7.1-1, to remove a one-time note specific to Diablo Canyon Power Plant (DCPP), Unit No. 2 for Cycle 15, which is no longer application or needed. The licensee also proposed to revise the TS Bases, applicable to DCPP, Unit Nos. 1 and 2, to reflect a new analysis methodology for establishing the reduced power range neutron flux high setpoint for one inoperable MSSV as listed in TS Table 3.7.1-1. By letter dated April 21, 2011, the licensee clarified that the proposed revision to the TS Bases is a revision to the final safety analysis report update sections 15.12.7.03, Results, and 15.2.16, References.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your application and determined that the following additional information is required in order to complete its review. This request for additional information (RAI) was discussed with you on March 15, 2012. It was agreed that a response to this RAI would be provided by April 16, 2012.
Should the NRC determine that this RAI is no longer necessary prior to this date, the request will be withdrawn. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1132 or via e-mail at joseph.sebrosky@nrc.gov. The NRC staff has determined that no security-related or proprietary information is contained herein.
Request for Additional Information
- 1. Can PG&E provide the Crosby test data referenced in EPRI Report NP-4306-SR that supports a 5 psi max accumulation behavior for main steam safeties?
- 2. Can PG&E provide the Westinghouse evaluation that determines that the DCPP Dresser valves will perform in a similar manner?
- 3. Can PG&E provide a description of the current inservice testing methodology for the MSSVs and a summary of the inservice test results over the period that this methodology has been used? Can PG&E also provide a summary of MSSV failures or unplanned maintenance actions during this same period?
- 4. Because the EPRI report identified that a safety valves performance may vary based upon the physical plant piping configuration, the staff requests the licensee evaluate the individual plant configuration in which the safeties are installed for an effect on the valves performance.