ML121320564

Email, Request for Additional Information, Round 3, Amendment Request, Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation, and Final Safety Analysis Report Update

ML121320564
Person / Time
Site:	Diablo Canyon
Issue date:	05/11/2012
From:	Joseph Sebrosky Plant Licensing Branch IV
To:	Soenen P Pacific Gas & Electric Co
Sebrosky J,NRR/DORL/LPL4 301-415-1132
References
TAC ME7520, TAC ME7521
Download: ML121320564 (1)

Text

From:

Sebrosky, Joseph Sent:

Friday, May 11, 2012 2:22 PM To:

'Soenen, Philippe R' Cc:

Lent, Susan; Burkhardt, Janet; 'Baldwin, Thomas (DCPP)'; Gall, Jennifer

Subject:

RE: Request for Additional information for DCPP regarding TS 3.3.5 (ME7520 and ME 7521)

Philippe, By letter dated October 24, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML113010196), Pacific Gas and Electric Company (PG&E) submitted PG&E Letter DCL-11-072, License Amendment Request 11-06 Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.

PG&E submitted a request for revision to Facility Operating License Nos. DPR-80 and DPR-82, revising Technical Specification (TS) 3.3.5 and final safety analysis report update (FSARU)

Appendix 6.2D and Sections 6.3, 15.3, and 15.4, revise the loss-of-coolant accident (LOCA) control room operator and offsite dose analysis of record described in the FSARU, and provide a new process for revising input values to this analysis.

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 May 9, 2012. It was agreed that a response to this RAI would be provided by June 11, 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Should the NRC determine that this RAI is no longer necessary prior to this date, the request will be withdrawn.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. In light of Information Notice 2011-21 (Agencywide Documents Access and Management System Accession No. ML113430785) please provide information to support that the large break loss-of coolant accident (LOCA) results will remain within 10 CFR 50.46 limits when both the thermal conductivity degradation error and the safety injection delay are accounted for.

2. Please provide Reference 10 and any additional evaluation that led to the following conclusion on page 4 of the submittal, It was determined that the additional ECCS

[Emergency Core Cooling System] delay due to a 4.16 kV SLUR [second level undervoltage relay] actuation time delay would have an insignificant effect on the small break loss-of-coolant accident (SBLOCA) thermal hydraulic results.