ML14295A307

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Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program
ML14295A307
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 10/27/2014
From: Geoffrey Miller
Plant Licensing Branch II
To: Capps S
Duke Energy Carolinas
Miller G
References
TAC MF2934, TAC MF2935
Download: ML14295A307 (4)


Text

, UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 O::.tober 27, 2014 Mr. Steven *D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC

  • 12700 Hagers Ferry Road Huntersville, NC 28078-8985

SUBJECT:

MCGUIRE NUCLEAR STATION, UNITS 1 AND 2: REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO IMPLEMENT A RISK-INFORMED, PERFORMANCE-BASED FIRE PROTECTION PROGRAM (TAC NOS. MF2934 AND MF2935)

Dear Mr. Capps:

By letter dated September 26, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13276A126), Duke Energy Carolinas, LLC (Duke) 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, as incorporated into Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.48(c).

The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's submittal and determined that additional information is needed in order to complete our review. describes this request for additional information (RAI). During a phone call on October 15, 2014, response dates for the questions in Enclosure 1 were discussed with Duke staff.. Duke staff agreed to a response date of 90 days from the date of this letter.

If you have any questions, please call me at 301-415-2481.

G. Edward Miller, Project Manager Plant Licensing Branch 11-1 Division of Operating* Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370

Enclosure:

As stated cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 PERFORMANCE BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR GENERATING PLANTS DUKE ENERGY CAROLINAS, LLC MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369, 50-370 By letter dated September 26, 2013, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13276A126), Duke Energy Carolinas (Duke) submitted a license amendment request (LAR) 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, as incorporated into Title 10 of the Code of Federal Regulations (1 0 CFR), Part 50, Section 50.48(c). In order for the U.S. Nuclear Regulatory Commission (NRC) staff to complete its review of the LAR, the following additional information is requested.

Radiation Release RAI 01 Describe the role and contributions of the McGuire Radiation Protection personnel in the screening process discussed in LAR Section 4.4.1, page 32.

  • Radiation Release RAI 02 LAR Attachment E, page E-11, states that Auxiliary Building "Sump C will transfer to the plant yard drains which discharge to the SNSWP [standby nuclear service water pond] and to the Waste Water Collection Basin." Is the capacity of this basin sufficient to contain liquid

. firefighting effluent such that there is no release from the site? If not, describe how the NFPA 805 release requirements will be met.

  • Radiation Release RAI 03 I

LAR AttachmenrE, page E-19, states that "The Turbine buildings are non-RCA [Radiological Controls Area] areas of the plant," but they appear to be screened-in to the evaluation. If they are screened-in, describe what, and how, administrative controls will prevent a radiological release through their unmonit6red ventilation.

Enclosure 1

'"2-Radiation Release RAI 04 LAR Attachment E, pages E-21 thru E-27, list several Compartments where administrative controls will be used to meet the NFPA 805 release requirements from fire in areas that are described as "open to atmosphere," with "no special drainage" provided. Describe what, and how, administrative controls will prevent a radiological releas.e from the facility. If these.controls meet the NFPA 805 release requirements by limiting the amount ofradioactivity available for release, provide a quantitative assessment demonstrating that the bounding case does not exceed the dose limit to a member of the public.

Enclosure 1

ML14295A307 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/DRA/ARCB NRR/LPL2-1/BC NAME GEMiller SFigueroa (SRohrer for) UShoop (RPedersen for) RPascarelli DATE 10/23/14 10/23/14 10/27/14 10/27/14