ML12272A016
| ML12272A016 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 09/28/2012 |
| From: | Jacqueline Thompson Plant Licensing Branch II |
| To: | Capps S Duke Energy Carolinas |
| Thompson J | |
| References | |
| TAC ME9281, TAC ME9282 | |
| Download: ML12272A016 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 September 28, 2012 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 - SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT REQUEST DATED AUGUST 9, 2012 (TAC NOS. ME9281 AND ME9282)
Dear Mr. Capps:
By letter dated August 9,2012, Duke Energy Carolinas, LLC (Duke Energy, the licensee) submitted a license amendment request (LAR) for McGuire Nuclear Station, Units 1 and 2 (McGuire 1 and 2). The proposed LAR would revise the McGuire 1 and 2 Technical Specification (TS) 3.8.4, Condition A, to allow replacement of the existing 125 Volt direct current vital batteries while at power. This proposed LAR would be applicable one-time for each of the four battery channels. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this LAR. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Title 10 of the Code of Federal Regulations (10 CFR), Section 50.90, an amendment to the license (including the TSs) must fully describe the changes requested, and follow, as far as applicable, the form prescribed for original license applications. The regulation at 10 CFR 50.34 addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features. and principal safety considerations.
The NRC staff has reviewed your LAR and concluded that the information delineated in the enclosure to this letter is necessary to enable the NRC staff to make an independent assessment regarding the acceptability of the proposed LAR in terms of regulatory requirements and the protection of public health and safety and the environment.
In order to make the application complete, the NRC staff requests that Duke Energy supplement the application to address the information requested in the enclosure by October 18, 2012. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the LAR will not be accepted for review pursuant to 10 CFR 2.101. and the NRC will cease its review actives associated with the LAR
S. Capps
- 2 application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
The information requested and associated time frame in this letter were discussed with Mr. Ken Ashe of your staff on September 25, 2012.
If you have any questions, please contact me by email or at (301) 415-1119.
Sincerely,
~IA.~*
Jon H. Thompson, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369, 50-370
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION SUPPLEMENTAL INFORMATION NEEDED LICENSE AMENDMENT REQUEST DATED AUGUST 9.2012 DUKE ENERGY CAROLINAS. LLC MCGUIRE NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370 The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed your license amendment request (LAR) and concluded that the information delineated in the enclosure to this letter is necessary to enable the NRC staff to make an independent assessment regarding the acceptability of the proposed LAR in terms of regulatory requirements and the protection of public health and safety and the environment.
- 1.
External risk quantification states that probabilistic risk assessment (PRA) results have not been provided because peer reviews have not been performed. Seismic and other external risk quantification for the application is necessary and must be addressed by a PRA if they are significant contributors. Please clarify what the estimated risk contributions are from the external hazards for this application for total core damage frequency (CDF) I large early release 'frequency (LERF) and describe their potential impact on the change in CDF/LERF.
- 2.
Fire risk quantification. Sufficient level of information on the fire PRA will be needed for performing an acceptance review of the fire PRA for the application.
This includes identification and technical justification of any unreviewed analysis methods (UAMs), as well as a description of other method differences from NUREG/CR-6850 (as supplemented) or the National Fire Protection Association Standard 805, "Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," (NFPA-805) frequently asked question (FAQ) guidance, and their significance for the application. If a position on a previous UAM has been established on a method by the NRC, please confirm that the accepted version of the UAM is used per the NRC position and, if not, then provide a revised analysis and results using an accepted approach.
- 3.
The text is not clear as to if the identification of facts and observations (F&Os) on the fire and internal events PRAs that do not meet capability Category /I of the "Standard for Level1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications, American Society of Mechanical Engineers I American Nuclear Society (ASME/ANS) RA-Sa-2009," is complete and if all such F&Os are evaluated and dispositioned for the application (i.e., capability category not met or Category I). Please clarify if the information provided in the application addresses all F&Os for which capability Category /I was not achieved. If not, please provide the complete list and the disposition of these F&Os for this application.
Enclosure
-2
- 4.
The submittal contains F&O dispositions in Attachment 4 of the LAR. However, for both the internal events PRA and the fire PRA, it is not clear that the significance of the F&Os to the application have been addressed for all the F&Os presented.
Please clarify, and revise as necessary, the disposition of the F&Os for this application. If the F&O has been resolved, please summarize what action was taken to resolve the F&O. If the F&O is not resolved, please provide the evaluation of the impact of the F&O on this application
- Via email OFFICE DORULPL2-1/PM DORULPL2-1/LA DRAlAPLAlBC*
DORULPL2-1/BC NAME JThompson SFigueroa DHarrison RPascarelli DATE 09/27/12 09/27/12 09/27/12 09/28/12