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| number = ML15225A489
| number = ML15225A489
| issue date = 08/18/2015
| issue date = 08/18/2015
| title = Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program (TAC Nos. MF2934 and MF2935)
| title = Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program
| author name = Martin R
| author name = Martin R
| author affiliation = NRC/NRR/DORL/LPLII-1
| author affiliation = NRC/NRR/DORL/LPLII-1
Line 18: Line 18:


=Text=
=Text=
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"" /J +o Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas , LLC 12700 Hagers Ferry Road Huntersville, NC 28078-8985  
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              ***~*                                              .2\ugus t 18, 2015 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078-8985


==SUBJECT:==
==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)  
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:==
==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. The U.S. Nuclear Regulatory Commission (NRC) staff is continuing its review and has determined that additional information is needed as stated below. Safe Shutdown Analysis (SSA) RAI 08 Regulatory Position C.2.4 in Regulatory Guide (RG) 1.205, "Risk-Informed, Performance Based Fire Protection for Existing Light-Water Nuclear Power Plants" states that there are two cases where operator actions taken outside the main control room may be considered as taking place at a primary control station. These two cases involve dedicated shutdown or alternative shutdown controls, which have been reviewed and approved by the NRC. On Monday, July 27, 2015 , the licensee verbally informed the NRC staff that of all the fire areas that credit the Standby Shutdown Facility (SSF) as the success path to meet the nuclear safety performance criteria (NSPC) in the McGuire Nuclear Safety Capability Analysis (NSCA), the use of the SSF to meet the safe shutdown requirements in one fire area had not been previously reviewed and approved by the NRC in the deterministic licensing basis. Utilization of the Alternative/Dedicated Shutdown strategy in a fire area that had not been previously approved by the NRC staff is a modification to the previously approved strategy.
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. The U.S. Nuclear Regulatory Commission (NRC) staff is continuing its review and has determined that additional information is needed as stated below.
a) Provide a detailed description of the modification to the dedicated or alternative shutdown strategy sufficient for the NRC staff to verify that the strategy meets the attributes provided in RG 1.205 Section C.2.4 (electrical independence, command and control, instrumentation , actions necessary to enable (if required), etc.).
Safe Shutdown Analysis (SSA) RAI 08 Regulatory Position C.2.4 in Regulatory Guide (RG) 1.205, "Risk-Informed, Performance Based Fire Protection for Existing Light-Water Nuclear Power Plants" states that there are two cases where operator actions taken outside the main control room may be considered as taking place at a primary control station. These two cases involve dedicated shutdown or alternative shutdown controls, which have been reviewed and approved by the NRC.
: s. Capps b) In addition, provide sufficient design information to provide assurance that connections/interconnections with safety-related plant systems will not cause a reduction in the capability , redundancy , diversity , or design margin for those systems. c) Since the proposed change involves the use of the previously reviewed and approved SSF, verify that the use of the SSF for the fire area in question will not invalidate any of the previously approved attributes of the alternative/dedicated shutdown strategy (electrical independence , command and control , instrumentation , actions necessary to enable , etc.). d) Verify that upon successful startup and enabling of the SSF , the credited success path is physically and electrically independent of the fire area resulting in the SSF strategy meeting the deterministic requirements of NFPA 805 Section 4.2.3. Docket Nos. 50-369 and 50-370 cc: Distribution via Listserv Sincerely , P of IM ti ,-ft'"-M'a'rfin , Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation S. Capps b) In addition , provide suffic i ent design information to provide assurance that connections/interconnections with safety-related plant systems will not cause a reduction in the capability , redundancy , diversity , or design margin for those systems. c) Since the proposed change involves the use of the previously reviewed and approved SSF , verify that the use of the SSF for the fire area in question will not invalidate any of the previously approved attributes of the alternative/dedicated shutdown strategy (electrical independence , command and control, i nstrumentation, actions necessary to enable , etc.). d) Verify that upon successful startup and enabling of the SSF , the credited success path is physically and electrically independent of the fire area resulting in the SSF strategy meeting the deterministic requirements of NFPA 805 Section 4.2.3. Docket Nos. 50-369 and 50-370 cc: Distribution via Listserv DISTRIBUTION
On Monday, July 27, 2015, the licensee verbally informed the NRC staff that of all the fire areas that credit the Standby Shutdown Facility (SSF) as the success path to meet the nuclear safety performance criteria (NSPC) in the McGuire Nuclear Safety Capability Analysis (NSCA), the use of the SSF to meet the safe shutdown requirements in one fire area had not been previously reviewed and approved by the NRC in the deterministic licensing basis.
: PUBLIC LPL2-1 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDorllpl2-1 Resource RidsNrrPMMcGuire Resource RidsNrrLASFigueroa Resource RidsRgn2MailCenter Resource ADAMS Accession No. ML15225A489 OFFICE NRR/LPL2-1  
Utilization of the Alternative/Dedicated Shutdown strategy in a fire area that had not been previously approved by the NRC staff is a modification to the previously approved strategy.
/PM NRR/LPL2-1/LA NAME BMartin SFigueroa DATE 08/17/15 08/17/15 S i ncerely , IRA/ Bob Martin , Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation TDinh , NRR/DRA HBarrett , NRR/DRA BMiller , NRR/DRA *via E-ma i l NRR/AFPB/BC NRR/LPL2-1/BC AKle i n RPascarell i 08/04/15 08/18/15 N RR/LPL2-1
a) Provide a detailed description of the modification to the dedicated or alternative shutdown strategy sufficient for the NRC staff to verify that the strategy meets the attributes provided in RG 1.205 Section C.2.4 (electrical independence, command and control, instrumentation, actions necessary to enable (if required), etc.).
/PM BMartin 08/18/15 OFFICIAL RECORD COPY}}
: s. Capps                                           b) In addition, provide sufficient design information to provide assurance that connections/interconnections with safety-related plant systems will not cause a reduction in the capability, redundancy, diversity, or design margin for those systems.
c) Since the proposed change involves the use of the previously reviewed and approved SSF, verify that the use of the SSF for the fire area in question will not invalidate any of the previously approved attributes of the alternative/dedicated shutdown strategy (electrical independence, command and control , instrumentation , actions necessary to enable, etc.).
d) Verify that upon successful startup and enabling of the SSF, the credited success path is physically and electrically independent of the fire area resulting in the SSF strategy meeting the deterministic requirements of NFPA 805 Section 4.2.3.
Sincerely, P   of IMti ,-ft'"-
                                                  ~o* b M'a'rfin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370 cc: Distribution via Listserv
 
ML15225A489                              *via E-mail OFFICE NRR/LPL2-1 /PM        NRR/LPL2-1/LA      NRR/AFPB/BC        NRR/LPL2-1/BC NRR/LPL2-1 /PM NAME     BMartin             SFigueroa         AKlein              RPascarelli      BMartin DATE     08/17/15           08/17/15           08/04/15           08/18/15         08/18/15}}

Latest revision as of 11:02, 19 March 2020

Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program
ML15225A489
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 08/18/2015
From: Martin R
Plant Licensing Branch II
To: Capps S
Duke Energy Carolinas
Martin R
References
TAC MF2934, TAC MF2935
Download: ML15225A489 (3)
v • d • e


Text

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      • ~* .2\ugus t 18, 2015 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. The U.S. Nuclear Regulatory Commission (NRC) staff is continuing its review and has determined that additional information is needed as stated below.

Safe Shutdown Analysis (SSA) RAI 08 Regulatory Position C.2.4 in Regulatory Guide (RG) 1.205, "Risk-Informed, Performance Based Fire Protection for Existing Light-Water Nuclear Power Plants" states that there are two cases where operator actions taken outside the main control room may be considered as taking place at a primary control station. These two cases involve dedicated shutdown or alternative shutdown controls, which have been reviewed and approved by the NRC.

On Monday, July 27, 2015, the licensee verbally informed the NRC staff that of all the fire areas that credit the Standby Shutdown Facility (SSF) as the success path to meet the nuclear safety performance criteria (NSPC) in the McGuire Nuclear Safety Capability Analysis (NSCA), the use of the SSF to meet the safe shutdown requirements in one fire area had not been previously reviewed and approved by the NRC in the deterministic licensing basis.

Utilization of the Alternative/Dedicated Shutdown strategy in a fire area that had not been previously approved by the NRC staff is a modification to the previously approved strategy.

a) Provide a detailed description of the modification to the dedicated or alternative shutdown strategy sufficient for the NRC staff to verify that the strategy meets the attributes provided in RG 1.205 Section C.2.4 (electrical independence, command and control, instrumentation, actions necessary to enable (if required), etc.).

s. Capps b) In addition, provide sufficient design information to provide assurance that connections/interconnections with safety-related plant systems will not cause a reduction in the capability, redundancy, diversity, or design margin for those systems.

c) Since the proposed change involves the use of the previously reviewed and approved SSF, verify that the use of the SSF for the fire area in question will not invalidate any of the previously approved attributes of the alternative/dedicated shutdown strategy (electrical independence, command and control , instrumentation , actions necessary to enable, etc.).

d) Verify that upon successful startup and enabling of the SSF, the credited success path is physically and electrically independent of the fire area resulting in the SSF strategy meeting the deterministic requirements of NFPA 805 Section 4.2.3.

Sincerely, P of IMti ,-ft'"-

~o* b M'a'rfin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370 cc: Distribution via Listserv

ML15225A489 *via E-mail OFFICE NRR/LPL2-1 /PM NRR/LPL2-1/LA NRR/AFPB/BC NRR/LPL2-1/BC NRR/LPL2-1 /PM NAME BMartin SFigueroa AKlein RPascarelli BMartin DATE 08/17/15 08/17/15 08/04/15 08/18/15 08/18/15

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