ML20205C030
| ML20205C030 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/26/1999 |
| From: | Dan Collins NRC (Affiliation Not Assigned) |
| To: | Cross J DUQUESNE LIGHT CO. |
| References | |
| GL-97-04, GL-97-4, TAC-M99959, NUDOCS 9904010059 | |
| Download: ML20205C030 (5) | |
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UNITED STATES w-
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NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20555-0001 March 26, 1999'
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Mr. ~J. E. Cross
' President-Generation Group Duquesne Light Company, '
Post Office Box 4 Shippingport, PA 15077
SUBJECT:
COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 97-04,
" ASSURANCE OF SUFFICIENT NET POSITIVE SUCTION HEAD FOR EMERGENCY CORE COOLING AND CONTAINMENT HEAT REMOVAL PUMPS," FOR BEAVER VALLEY POWER STATION, UNIT NO 1 (TAC NO.
- M99959).
Dear Mr. Cross:
The U. S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 97-04,
" Assurance of Sufficient Net Positive Suction liead for Emergency Core Cooling and
. Containment Heat Removal Pumps," to all holders of operating licenses or construction permits on October 7,1997. The NRC issued GL 97-04 to confirm the adequacy of the net positive suction head (NPSH) available for emergency core cooling (including core spray and decay heat removal) and containment heat removal pumps under all design-basis accident l
- scenados, in GL 97-04, the NRC staff specifically requested that licensees provide the information g
outlined below for each of their facilities.
1r 1.
Specify the general methodology used to calculate the head loss associated with the bgf ECCS suction strainers.
j 2.
Identify the required NPSH and the available NPSH.
3.
Specify whether the current design-basis NPSH analysis differs from the most recent analysis reviewed and approved by the NRC for which a safety evaluation was issued.
4.
Specify whether containment overpressure (i.e., containment pressure above the vapor pressure of the sump or suppression pool fluid) was credited in the calculation of availatne NPSH. Specify the amount of overpressure needed and the minimum overpressure available.
5.
When containment overpressure is credited in the calculation of available NPSH,
. confirm that an appropriate containment pressure analysis was done to establish the minimum containment pressure.
i in response to GL 97-04, Duquesne Light Company (DLC) provided letters dated November 6 and November 24,1997, and January 6,1998, for Beaver Valley Power Station, Unit Nos.1 and 2 (BVPS-1 and BVPS-2). Based on review of your response, the staff questioned whether l
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9904010059 990326 PDR ADOCK 05000334 i
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J. E. Cross BVPS-1 was within licensing basis with regard to use of containment overpressure to assure adequate NPSH to the low head safety injection pumps. By letter dated August 17,1998, the staff sent a request for additional information (RAl) regarding how the GL 97-04 response compares with the current licensing basis at BVPS-1. DLC recoonded to the RAI by letter dated September 16,1998. Subsequently, the staff met with representatives of DLC (BVPS-1), V5PCO (representing Suny Units 1 and 2, and North Anna Units 1 and 2), and Stone &
Webster to discuss the containment pressure and NPSH evaluations. During the meeting, the staff was presented with references to past licensing documentation and current methodology of containment analysis code and how it is used to calculate the svailable NPSH.
The NRC staff has reviewed the referenced and current documentation of the BVPS-1 licensing basis with regard to use of containment overpres:ure. The combined documentation clearly defines the methodology and analytical process which has been used both in the past as well as the present. The process has remained essentbily unchanged since the last major staff review. Based on this finding, and review of DLC's responses to GL 97-04, the NRC staff concludes that the requested information has been provided. Therefore, the staff considers GL 97-04 closed for BVPS-1. The NRC previously closed GL 07-04 for BVPS-2 by letter dated June 4,1998.
l if you have any questions regarding this matter, please contact me at (301) 415-1427.
Sincerely,
/asc I 50H Daniel S. Collins, Project Manager Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-334 cc: See next page
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. March 26,1999 J. E. Cross adequate NPSH to the low head safety !njection pumps. By letter dated August 17,1998, the
' staff sent a request for additional inforrnation (RAl) regarding how the GL 97-04 response compares with the current licensing basis at BVPS-1. DLC responded to tina RAl by letter dated September 16,1998. Subsequently, the staff met with representatives of DLC (BVPS-1), VEPCO (representing Surry Units 1 and 2, and North Anna Units 1 and 2), and Stone &
Webster to discuss the containment pressure and NPSH evaluations. During the meeting, the staff was presented with references to past licensing documentation and current methodology of containment analysis code and how it is used to calculate the available NPSH.
The NRC staff has reviewed the referenced and current documentation of the BVPS-1 licensing basis with regard to use of containment overpressure. The combined documenta6on cleady defines the methodology and analytical process which has been used both i' the past as well as the present. The process has remained essentially unchanged since the inst major staff review. Based on this fi,1 ding, and review of DLC's responses to GL 97-04, the NRC staff concludes that the requested information has been provided. Therefore, the staff considers GL 97-04 closed for BVPS-1. - The NRC previously closed GL 97-04 for BVPS-2 by letter dated June 4,1998.
If you have any quesuons regarding this matter, please contact me at (301) 415-1427.
t Sincerely, Original signed by:
Daniel S. Collins, Project Manager Project Directorate I-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-334
. cc: See next page SBajwa MO'Brien PUBLIC DCollins MEvans, RGN-1
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March 26,1999 J. E; Cross adequate NPSH to the low head safety injection pumps. By letter dated August 17,1998, the staff sent a request for additional information (RAI) regarding how the GL 97-04 response compares with the current licensing basis at BVPS-1. DLC responded to the RAI by letter dated September 16,1998. Subsequently, the staff met with representatives of DLC (BVPS-1), VEPCO (representing Surry Units 1 and 2, and North Anna Units 1 and 2), and Stone & -
Webster to discuss the containment pressure'and NPSH evaluations. During the meeting, the staff was presented with references to past licensing documentation and current methodology of containment analysis code and how it is used to calculate the available NPSH.
The NRC staff has reviewed the referenced and current documentation of the BVPS-1 licensing basis with regard to use of containment overpressure. The combined documentation clearly defines the methodology and analytical process which has been used both in the past as well as tne present. The process has remained essentially unchanged since the last major staff review. Based on this finding, and review of DLC's responses to GL 97-04, the NRC staff concludes that the requested information has been provided. Therefore, the staff considers GL 97-04 closed for BVPS-1. The NRC previously closed GL 97-04 for BVPS-2 by letter dated June 4,1998.
If you have any questions regarding this matter, please contact me at (301) 415-1427.
Sincerely, Original ' signed by:
Daniel S. Collins, Project Manager Project Directorate I-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-334 cc: See next page DISTRIBUTION' Docket File SBajwa MO'Brien PUBLIC DCollins MEvans, RGN-l PDl-1 Reading OGC JKudrick JZwolinski/SBlack ACRS KKavanagh DOCUMENT NAME: G:\\ BEAVER \\GL9704.WPD OFFICE PDl-j/PM PDI-2/LA PDI-1/D 2 NAME Dbol ns:lec M he k SBajwa (DATE 3/ M99 0 M/99 5 /$9 OFFICIAL RECORD COPY -
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i Mr. J. E. Cross Beaver Valley Power Station, Units 1 & 2 '
' Duquesne Ught Company cc:
Jay E. Silberg, Esquire Bureau of Radiation Protection Shaw, Pittman, Potts & Trowbridge Pennsylvania Department of 2300 N Street, NW.
Environmental Protection
' Washington, DC 20037 ATTN: Michael P. Murphy l
Post Office Box 2063 Di ector-Safety and Ucensing Harrisburg, PA 17120 Department (BV-A)
_ Duquesne Light Company Mayor of the Borough of Beaver Valley Power Station Shippingport PO Box 4 Post Office Box 3 Shippingport, PA 15077 Shippingport, PA 15077 Commissioner Roy M. Smith Regional Administrator, Region I West Virginia Department of Labor U.S. Nuclear Regulatory Commission Building 3 Room 319 475 Allendale Road Capitol Complex King of Prussia, PA 19406 Charleston, WV 25305 Resident inspector-Director, Utilities Department U.S. Nuclear Regulatory Commission Public Utilities Commission Post Office Box 298 180 East Broad Street Shippingport, PA 15077 Columbus, OH 43266-0573 Director, Pennsylvania Emergency Duquesne Light Company Management Agency Beaver Valley Power Station Post Office Box 3321 PO Box 4 Harrisburg, PA 17105-3321 Shippingport, PA 15077 ATTN: S. C. Jain, Senior Vice President Ohio EPA-DERR Nuclear Services (BV A)
ATTN: Zack A. Clayton Post Office Box 1049 Columbus, OH 43266-0149 Mr. J. A. Hultz, Manager Projects & Support Services Dr. Judith Johnsrud First Energy National Energy Committee 76 South Main Street Sierra Club Akron, OH 44308 433 Oriando Avenue State College, PA 18803 Duquesne Light Company Beaver Valley Power Station PO Box 4 Shippingport, PA 15077 ATTN: Kevin L. Ostrowski, Division Vice President, Nuclear Operations Group and Plant Manager (BV-SOSB-7) i-L L.