ML20248J977
| ML20248J977 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/04/1998 |
| From: | Brinkman D NRC (Affiliation Not Assigned) |
| To: | Cross J DUQUESNE LIGHT CO. |
| References | |
| GL-97-04, GL-97-4, TAC-M99960, NUDOCS 9806090382 | |
| Download: ML20248J977 (4) | |
Text
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June 4, 1998 Mr. J. E. Cross President-Generation Group Duquesne Light Company Post Office Box 4 Shippingport, PA 15077
SUBJECT:
COMPLETION OF LICENSING ACTION i J 't GENERIC LETTER 97 BEAVER VALLEY POWER STATION, UNIT NO. 2 (TAC NO M99960)
Dear Mr. Cross:
The U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 97-04, " Assurance of Sufficient Net Positive Suction Head 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 not 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 scenarios.
In GL 97-04, the NRC staff specifically requested that licensees provide the information outlined below for each of their facilities.
- 1. Specify the general methodology used to calculate the head loss associated with the ECCS suction strainers.
- 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 available
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NPSH. Specify the amount of overpressure needed and the minimum overpressure
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available.
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- 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.
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-2' in response to GL 97-04, you provided letters dated November 6,1997, November 24,1997, and January 6,1998, for Beaver Valley Power Station, Unit Nos.1 and 2 (BVPS-1 and BVPS-2).
l These submittals, in conjunction with the information provided by your staff during a May 26, 1998, conference call, provided the information requested by GL 97-04 for BVPS-2. Your staff informed us during the May 26,1998, conference call that the NPSH requirement for BVPS-2 containment recirculation spray pumps did not take credit for the hot factor referred to on page 6.2-53 of BVPS-2 UFSAR Section 6.2.2.3.2. The NRC staff has reviewed the.Mformation provided for BVPS-2 and has concluded that all information required by GL 97-04 for BVPS-2
. has been provided; therefore, we consider GL 97-04 to be closed for BVPS-2 (TAC No.
M99960). Thank you for your prompt and complete response. The NRC staff is continuing to review the information provided for BVPS-1.
If you have any questions regarding this matter, please contact me at (301) 415-1409.
Sincerely,
/S/
Donald S. Brinkman, Senior Project Manager Project Directorate 1-2 Division of Reactor Projects - t/11 Office of Nuclear Reactor Regulation Docket No. 50-412 cc: See next page DISTRIBUTION:
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J. E, Cross in rrn ponse to GL 97-04, you provided letters dated November 6,1997, November 24,1997, and January 6,1998, for Beaver Valley Power Station, Unit Nos.1 and 2 (BVPS-1 and BVPS-2).
These submittals, in conjunction with the information provided by your staff during a May 26,'
1998, conference call, provided the information requested by GL 97-04 for BVPS 2. Your staff informed us dunng the May 26,1998, conference call that the NPSH requirement for BVPS-2 containment recirculation spray pumps did not take credit for the hot factor referred to on page 6.2-63 of BVPS 2 UFSAR Section 6.2.2.3.2. The NRC staff has reviewed the information provided for BVPS 2 and has concluded that all information required by GL 97-04 for BVPS-2 has been provided; therefore, we consider GL 97-04 to be closed for BVPS-2 (TAC No.
M99960). Thank you for your prompt and complete response. The NRC staff is continuing to review the information provided for BVPS-1.
If you have any questions regarding this matter, please contact me at (301) 415-1409.
Sincerely, i
Al / DD.
Donald S. Lt.akman, Senior Project Manager Project Directorate 1-2 Division of Reactor Projects - t/11
- Office of Nuclear Reactor Regulation cc: See next page
O 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 Resources Washington, DC 20037 ATTN: Michael P. Murphy Post Office Box 2063 Director-Safety and Ucensing Harrisburg, PA 17120 Department (BV-A)
Duquesne Ught Company Mayor of the Borrough of Beaver Vriley Power Station Shippingport PO Box /
Post Offee Box 3 Shippin(Art, PA 15077 Shippingport, PA 15077 Commissioner Roy M. Smith Regional Administrator, Region l West Virginia Department of Labor U.S. Nuclear Regulatory Commission Buildirig 3, Room 319 475 Allendale Road Capitol Complex King of Prussia, PA 19406 Charlesto 1, WVA 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 Columbur, OH 43266-0573 Director, Pennsylvania Emergency Duquesne Ught Company Management Agency Beaver Valley Power Station Post Office Box 3321 PO Box 4 1
Harrisburg, PA 17105-3321 Shippingport, PA 15077
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ATTN: S. C. Jain, Vice President Ohio EPA-DERR Nuclear Services (BV-A)
ATTN: Zack A. Clayton Post Office Box 1049 J
Columbus, OH 43266-0149 I
Dr. JuCith Johnsrud National Energy Commihae Sierra Club 433 Orlando Avenue State College, PA 16803 Duquesne Ught Company Beaver Valley Power Station PO Box 4 Shippingport, PA 15077 ATTN: R. L Grand, Division Vice l
Prof Wnt, Nuclear Operations Group and Mant Manager (BV-SOSB-7)
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