ML13016A432

E-mail, Request for Additional Information, Round 2, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)

ML13016A432
Person / Time
Site:	Fort Calhoun
Issue date:	01/16/2013
From:	Lynnea Wilkins Plant Licensing Branch IV
To:	Hansher B Omaha Public Power District
Wilkins L
References
TAC ME7244
Download: ML13016A432 (1)

Text

Lent, Susan From: Wilkins, Lynnea Sent: Wednesday, January 16, 20133:18 PM To: 'HANSHER, BILL R' Cc: 'LIPPY, DONNA L'; 'EDWARDS, MICHAEL L'; Robinson, Jay; Fields, Leslie; Lent, Susan; Burkhardt, Janet

Subject:

DRAFT: Fort Calhoun 2nd Round RAI for NFPA 805 LAR (ME7244)

Bill, By letter dated September 28, 2011 as supplemented by letters dated December 19 and 22, 2011, March 20, July 22, August 24, and September 27,2012, Omaha Public Power District, submitted a license amendment request (LAR) to transition the fire protection licensing basis at the Fort Calhoun Station, Unit 1, from Title 10 of the Code of Federal Regulations (CFR), Section 50.48(b), to 10CFR50.48(c), National Fire Protection Association Standard NFPA 805 (NFPA 805).

The NRC staff has reviewed the information provided and has determined that additional information specified in the Request for Additional Information (RAI) below is needed for the staff to complete its evaluation:

By letter dated July 24,2012, (ADAMS Accession No. ML12208A131) the licensee responded to Probabilistic Risk Assessment (PRA) RAls 17, 18a and 18b acknowledging that the last peer review of the internal events PRA (lEPRA) was performed in 1999 and that certain model changes performed since then warrant a peer review (I.e., the Human Reliability Analysis (HRA), internal flooding, loss of off-site power (LOOP) recovery actions, and the update of the large early release frequency (LERF) model). In light of this, perform a focused scope peer review of the HRA performed for the Fire PRA and two of the PRA elements (I.e. LOOP recovery actions, and update of the LERF model) identified in response to PRA RAI 18.a and b. Provide the findings from these peer reviews and the resolutions to these findings. If the resolutions to the peer review findings require changes to the fire PRA, provide the core damage frequency (CDF), LERF, delta (l1)CDF, and l1LERF for each fire area and the total based on the updated PRA model.

In addition, please note that review efforts on this LAR are being continued and additional RAls may be forthcoming. Please contact me if a clarifying teleconference is needed for the RAt.

Lynnea Wi{f(ins, Project Manager Fort Calhoun Station, Unit 1 Cooper Nuclear Station Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: 301-415-1377 1