ML071170090: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:May 3, 2007Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
{{#Wiki_filter:May 3, 2007 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711


==SUBJECT:==
==SUBJECT:==
SURRY POWER STATION, UNIT NOS. 1 AND 2, REQUEST FORADDITIONAL INFORMATION (RAI) REGARDING THE PROPOSAL TO REVISE TECHNICAL SPECIFICATION FOR TEMPORARY 45-DAY AND 14-DAY ALLOWED OUTAGE TIMES TO REPLACE CHILLED WATER PIPING IN MAIN CONTROL ROOM AND EMERGENCY SWITCHGEAR ROOM AIR-CONDITIONING SYSTEM (TAC NOS. MD4622 AND MD4623)
SURRY POWER STATION, UNIT NOS. 1 AND 2, REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING THE PROPOSAL TO REVISE TECHNICAL SPECIFICATION FOR TEMPORARY 45-DAY AND 14-DAY ALLOWED OUTAGE TIMES TO REPLACE CHILLED WATER PIPING IN MAIN CONTROL ROOM AND EMERGENCY SWITCHGEAR ROOM AIR-CONDITIONING SYSTEM (TAC NOS. MD4622 AND MD4623)


==Dear Mr. Christian:==
==Dear Mr. Christian:==


By letter dated February 26, 2007, Virginia Electric and Power Company (the licensee)proposed technical specification (TS) changes for Surry Power Station, Unit Nos. 1 and 2, related to main control room and emergency switchgear room air-conditioning system. The proposed changes would revise TS 3.23 to temporarily extend the allowable outage timeassociated with an inoperable chilled water loop from 7 days up to 45 days. The temporary change has been proposed in order to permit repairs, replacement, and modifications to the chilled water piping. The NRC staff is reviewing the submittal and has determined that additional information is required to complete its evaluation.The NRC staff's RAI is enclosed. The licensee is requested to provide a response to the RAIwithin 30 days.Sincerely,/RA/Siva P. Lingam, Project ManagerPlant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-280 and 50-281
By letter dated February 26, 2007, Virginia Electric and Power Company (the licensee) proposed technical specification (TS) changes for Surry Power Station, Unit Nos. 1 and 2, related to main control room and emergency switchgear room air-conditioning system.
The proposed changes would revise TS 3.23 to temporarily extend the allowable outage time associated with an inoperable chilled water loop from 7 days up to 45 days. The temporary change has been proposed in order to permit repairs, replacement, and modifications to the chilled water piping. The NRC staff is reviewing the submittal and has determined that additional information is required to complete its evaluation.
The NRC staffs RAI is enclosed. The licensee is requested to provide a response to the RAI within 30 days.
Sincerely,
                                                      /RA/
Siva P. Lingam, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-280 and 50-281


==Enclosure:==
==Enclosure:==


RAIcc: See next page  
RAI cc: See next page
 
ML071170090                                                    NRR-088 OFFICE        NRR/LPL2-1/PM    NRR/LPD2-1/LA        NRR/DRA/APLA/BC NRR/LPL2-1/BC NAME          SLingam:nc        MOBrien            MRubin            LOlshan forEMarinos DATE              4/26/07          5 /3/07            4/19/07            5/3/07
 
REQUEST FOR ADDITIONAL INFORMATION REGARDING REVISION OF TECHNICAL SPECIFICATION FOR 45-DAY AND 14-DAY ALLOWED OUTAGE TIMES TO REPLACE MAIN CONTROL ROOM AND EMERGENCY SWITCHGEAR ROOM AIR-CONDITIONING SYSTEM CHILLED WATER PIPING SURRY POWER STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-280 AND 50-281
: 1. Virginia Electric and Power Company (the licensee) identified that the probabilistic risk assessment (PRA) internal events model includes the main control room (MCR) and emergency switchgear room (ESGR) air-conditioning (AC) system as a mitigating system, and loss of the function of ESGR cooling as an initiating event. The submittal states that a manual reactor trip is required prior to reaching 120°F in the ESGR.
However, the submittal does not provide any further details as to the failure effects of the unavailability of this system, the success criteria used for the system compared to the design bases, or any other assumptions regarding system operation and impacts in the PRA relevant to this amendment request. The licensee is requested to describe the plant impact assumed in the PRA model upon loss of the MCR/ESGR AC system, including any related assumptions, system success criteria, and any modeled alternate cooling capabilities. This should also include discussion regarding how the initiating event frequency for loss of control room AC was adjusted to account for the unavailability of a chilled water loop. If appropriate to assess any non-conservative assumptions applied, the licensee should also discuss the sensitivity of their results to this assumed plant response, including any sensitivity studies conducted using different assumed responses to a loss of the system.
: 2. The licensees submittal did not identify if the risk analyses provided point estimates of the mean or actual means, nor was there any discussion of uncertainty analyses to support the calculations. The licensee is requested to address PRA model and parametric uncertainty consistent with the guidance of Regulatory Guide 1.174, Section 2.2.5.
Enclosure


ML071170090                                    NRR-088OFFICENRR/LPL2-1/PMNRR/LPD2-1/LANRR/DRA/APLA/BCNRR/LPL2-1/BCNAMESLingam:ncMO'BrienMRubinLOlshan forEMarinosDATE    4/26/07    5 /3/07  4/19/07    5/3/07 EnclosureREQUEST FOR ADDITIONAL INFORMATIONREGARDING REVISION OF TECHNICAL SPECIFICATION FOR 45-DAY AND 14-DAY ALLOWED OUTAGE TIMESTO REPLACE MAIN CONTROL ROOM AND EMERGENCY SWITCHGEAR ROOM AIR-CONDITIONING SYSTEMCHILLED WATER PIPINGSURRY POWER STATION, UNIT NOS. 1 AND 2DOCKET NOS. 50-280 AND 50-2811.Virginia Electric and Power Company (the licensee) identified that the probabilistic riskassessment (PRA) internal events model includes the main control room (MCR) and emergency switchgear room (ESGR) air-conditioning (AC) system as a mitigating system, and loss of the function of ESGR cooling as an initiating event. The submittal states that a manual reactor trip is required prior to reaching 120°F in the ESGR.
However, the submittal does not provide any further details as to the failure effects of the unavailability of this system, the success criteria used for the system compared to the design bases, or any other assumptions regarding system operation and impacts in the PRA relevant to this amendment request. The licensee is requested to describe the plant impact assumed in the PRA model upon loss of the MCR/ESGR AC system, including any related assumptions, system success criteria, and any modeled alternate cooling capabilities. This should also include discussion regarding how the initiating event frequency for loss of control room AC was adjusted to account for the unavailability of a chilled water loop. If appropriate to assess any non-conservative assumptions applied, the licensee should also discuss the sensitivity of their results to this assumed plant response, including any sensitivity studies conducted using different assumed responses to a loss of the system.2.The licensee's submittal did not identify if the risk analyses provided point estimates ofthe mean or actual means, nor was there any discussion of uncertainty analyses to support the calculations. The licensee is requested to address PRA model and parametric uncertainty consistent with the guidance of Regulatory Guide 1.174, Section 2.2.5.
Surry Power Station, Units 1 & 2 cc:
Surry Power Station, Units 1 & 2 cc:
Mr. David A. ChristianSenior Vice President and Chief Nuclear Officer Virginia Electrical and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711Ms. Lillian M. Cuoco, Esq.Senior Counsel Dominion Resources Services, Inc.
Mr. David A. Christian                Office of the Attorney General Senior Vice President                 Commonwealth of Virginia and Chief Nuclear Officer           900 East Main Street Virginia Electrical and Power Company Richmond, Virginia 23219 Innsbrook Technical Center 5000 Dominion Boulevard               Mr. Chris L. Funderburk, Director Glen Allen, VA 23060-6711            Nuclear Licensing & Operations Support Dominion Resources Services, Inc.
Building 475, 5th Floor Rope Ferry Road Waterford, Connecticut 06385Mr. Donald E. JerniganSite Vice President Surry Power Station Virginia Electric and Power Company 5570 Hog Island Road Surry, Virginia 23883-0315Senior Resident InspectorSurry Power Station U. S. Nuclear Regulatory Commission 5850 Hog Island Road Surry, Virginia 23883ChairmanBoard of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683Dr. W. T. LoughVirginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23218Dr. Robert B. Stroube, MD, MPHState Health Commissioner Office of the Commissioner Virginia Department of Health Post Office Box 2448 Richmond, Virginia 23218Office of the Attorney GeneralCommonwealth of Virginia 900 East Main Street Richmond, Virginia  23219Mr. Chris L. Funderburk, DirectorNuclear Licensing & Operations Support Dominion Resources Services, Inc.
Ms. Lillian M. Cuoco, Esq.           Innsbrook Technical Center Senior Counsel                       5000 Dominion Blvd.
Innsbrook Technical Center 5000 Dominion Blvd.
Dominion Resources Services, Inc. Glen Allen, Virginia 23060-6711 Building 475, 5th Floor Rope Ferry Road Waterford, Connecticut 06385 Mr. Donald E. Jernigan Site Vice President Surry Power Station Virginia Electric and Power Company 5570 Hog Island Road Surry, Virginia 23883-0315 Senior Resident Inspector Surry Power Station U. S. Nuclear Regulatory Commission 5850 Hog Island Road Surry, Virginia 23883 Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23218 Dr. Robert B. Stroube, MD, MPH State Health Commissioner Office of the Commissioner Virginia Department of Health Post Office Box 2448 Richmond, Virginia 23218}}
Glen Allen, Virginia  23060-6711}}

Revision as of 07:00, 23 November 2019

Request for Additional Information Regarding the Proposal to Revise Technical Specifications for Temporary 45-Day and 14-Day Allowed Outage Times (TAC Nos. MD46222 and MD4623)
ML071170090
Person / Time
Site: Surry  
Issue date: 05/03/2007
From: Siva Lingam
NRC/NRR/ADRO/DORL/LPLII-1
To: Christian D
Virginia Electric & Power Co (VEPCO)
Lingam, Siva NRR/DORL 415-1564
References
TAC MD4622, TAC MD4623
Download: ML071170090 (6)


Text

May 3, 2007 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

SURRY POWER STATION, UNIT NOS. 1 AND 2, REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING THE PROPOSAL TO REVISE TECHNICAL SPECIFICATION FOR TEMPORARY 45-DAY AND 14-DAY ALLOWED OUTAGE TIMES TO REPLACE CHILLED WATER PIPING IN MAIN CONTROL ROOM AND EMERGENCY SWITCHGEAR ROOM AIR-CONDITIONING SYSTEM (TAC NOS. MD4622 AND MD4623)

Dear Mr. Christian:

By letter dated February 26, 2007, Virginia Electric and Power Company (the licensee) proposed technical specification (TS) changes for Surry Power Station, Unit Nos. 1 and 2, related to main control room and emergency switchgear room air-conditioning system.

The proposed changes would revise TS 3.23 to temporarily extend the allowable outage time associated with an inoperable chilled water loop from 7 days up to 45 days. The temporary change has been proposed in order to permit repairs, replacement, and modifications to the chilled water piping. The NRC staff is reviewing the submittal and has determined that additional information is required to complete its evaluation.

The NRC staffs RAI is enclosed. The licensee is requested to provide a response to the RAI within 30 days.

Sincerely,

/RA/

Siva P. Lingam, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-280 and 50-281

Enclosure:

RAI cc: See next page

ML071170090 NRR-088 OFFICE NRR/LPL2-1/PM NRR/LPD2-1/LA NRR/DRA/APLA/BC NRR/LPL2-1/BC NAME SLingam:nc MOBrien MRubin LOlshan forEMarinos DATE 4/26/07 5 /3/07 4/19/07 5/3/07

REQUEST FOR ADDITIONAL INFORMATION REGARDING REVISION OF TECHNICAL SPECIFICATION FOR 45-DAY AND 14-DAY ALLOWED OUTAGE TIMES TO REPLACE MAIN CONTROL ROOM AND EMERGENCY SWITCHGEAR ROOM AIR-CONDITIONING SYSTEM CHILLED WATER PIPING SURRY POWER STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-280 AND 50-281

1. Virginia Electric and Power Company (the licensee) identified that the probabilistic risk assessment (PRA) internal events model includes the main control room (MCR) and emergency switchgear room (ESGR) air-conditioning (AC) system as a mitigating system, and loss of the function of ESGR cooling as an initiating event. The submittal states that a manual reactor trip is required prior to reaching 120°F in the ESGR.

However, the submittal does not provide any further details as to the failure effects of the unavailability of this system, the success criteria used for the system compared to the design bases, or any other assumptions regarding system operation and impacts in the PRA relevant to this amendment request. The licensee is requested to describe the plant impact assumed in the PRA model upon loss of the MCR/ESGR AC system, including any related assumptions, system success criteria, and any modeled alternate cooling capabilities. This should also include discussion regarding how the initiating event frequency for loss of control room AC was adjusted to account for the unavailability of a chilled water loop. If appropriate to assess any non-conservative assumptions applied, the licensee should also discuss the sensitivity of their results to this assumed plant response, including any sensitivity studies conducted using different assumed responses to a loss of the system.

2. The licensees submittal did not identify if the risk analyses provided point estimates of the mean or actual means, nor was there any discussion of uncertainty analyses to support the calculations. The licensee is requested to address PRA model and parametric uncertainty consistent with the guidance of Regulatory Guide 1.174, Section 2.2.5.

Enclosure

Surry Power Station, Units 1 & 2 cc:

Mr. David A. Christian Office of the Attorney General Senior Vice President Commonwealth of Virginia and Chief Nuclear Officer 900 East Main Street Virginia Electrical and Power Company Richmond, Virginia 23219 Innsbrook Technical Center 5000 Dominion Boulevard Mr. Chris L. Funderburk, Director Glen Allen, VA 23060-6711 Nuclear Licensing & Operations Support Dominion Resources Services, Inc.

Ms. Lillian M. Cuoco, Esq. Innsbrook Technical Center Senior Counsel 5000 Dominion Blvd.

Dominion Resources Services, Inc. Glen Allen, Virginia 23060-6711 Building 475, 5th Floor Rope Ferry Road Waterford, Connecticut 06385 Mr. Donald E. Jernigan Site Vice President Surry Power Station Virginia Electric and Power Company 5570 Hog Island Road Surry, Virginia 23883-0315 Senior Resident Inspector Surry Power Station U. S. Nuclear Regulatory Commission 5850 Hog Island Road Surry, Virginia 23883 Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23218 Dr. Robert B. Stroube, MD, MPH State Health Commissioner Office of the Commissioner Virginia Department of Health Post Office Box 2448 Richmond, Virginia 23218