ML16187A066
| ML16187A066 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/07/2016 |
| From: | Martin B Plant Licensing Branch II |
| To: | Henderson K Duke Energy Carolinas |
| Martin B, NRR-DORL 301-415-1493 | |
| References | |
| CAC MF2936, CAC MF2937 | |
| Download: ML16187A066 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 7, 2016 Mr. Kelvin Henderson Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York, NC 297 45
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1AND2-REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO IMPLEMENT A RISK-INFORMED, PERFORMANCE-BASED FIRE PROTECTION PROGRAM (CAC NOS. MF2936 AND MF2937)
Dear Mr. Henderson:
By letter dated September 25, 2013 (Agencywide Documents Access and Management System Accession No. ML13276A503), Duke Energy Carolinas, LLC submitted a license amendment request to change its fire protection program to one based on the National Fire Protection Association (NFPA) Standard 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition.
The U.S. Nuclear Regulatory Commission staff is continuing its review and has determined that additional information is needed in the probabilistic risk assessment area as discussed in the enclosed Request for Additional Information.
Docket Nos. 50-413 and 50-414
Enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv Sincerely,
~Pt,...
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/)t)il fsob artin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
REQUEST FOR ADDITIONAL INFORMATION ADOPTION OF NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 DUKE ENERGY CAROLINAS, LLC CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 By letter dated September 25, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13276A503), Duke Energy Carolinas, LLC (the licensee) submitted a license amendment request to change its fire protection program to one based on the National Fire Protection Association (NFPA) 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," 2001 Edition.
By letter dated June 15, 2016 (ADAMS Accession No. ML16169A107), the licensee submitted additional information. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the June 15, 2016, letter and determined that additional information in the probabilistic risk assessment (PRA) area is required to continue the review, as follows.
PRA RAI 24 In its letter dated June 15, 2016, the licensee stated that, "A gap was identified in the NFPA 805 safe shutdown analysis related to the reactor coolant pump [RCP] seals and the time available to start the Standby Shutdown Facility's (SSF) standby make-up pump (SMUP)." The NRC staff's understanding of the licensee's PRA is that the SSF is an important contributor to keeping the risk from fires low, and that RCP seal loss-of-coolant accidents are an important contributor to fire risk. Because of the potential importance of the scenarios, the NRC staff requests additional information to determine whether the risk results following the RCP analysis update will remain acceptable or whether additional modifications or evaluations are needed.
Please provide the following:
Summarize the PRA models in which the time available to start the SSF SMUP are used.
Describe the changes to the PRA input values that may occur when the time available will change.
Provide the risk results (total core damage frequency, total large early release frequency, change-in-risk associated with transition to NFPA 805) of a sensitivity study based on a reasonable bounding estimate of the change in the time available.
If the risk results indicate that the risk acceptance guidelines would be exceeded after the RCP analysis update, please describe what actions can be taken to bring the risk results below the acceptance guidelines.
Enclosure
ML16187A066 OFFICE DORL/LPL2-1/PM DORL/LPL2-1 /LA DRA/APLA/BC NAME BMartin LRonewicz SRosenberg (S/Dinsmore for)
DATE 07/05/16 07/06/16 07/05/16 RidsNrrDorl Lpl2-1 RidsRgn2MailCenter DORL/LPL2-1/BC MMarkley 07/07/16