ML20199H563
| ML20199H563 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/06/1997 |
| From: | Jeffery Wood CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2499, GL-97-04, GL-97-4, NUDOCS 9711260152 | |
| Download: ML20199H563 (3) | |
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$501 N State Route 2 419-249-2300 John K. Wood
- oak Harter.OH 43449 FAX: 419-3214337 Vce Prescent Nuclear
, Davis Beste Docket Number 50-346 License Number NPF-3 Serial Number L499 November 6, 1997
. United States Nuclear Regulatory Commission Document Control Desk Was'dngton, D. C. 20555-0001
Subject:
Initial Response to NRC Generic Letter 97-04: Assurance of Suflicient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps
- Ladies and Gentlemen:
On October 7,1997, the Nuclear Regulatory Commission (NRC) issued Gener a Letter (GL) 97-04, requesting that nuclear power plant licensees review their current design basis analyses used to determine the available net positive suction head (NPSH) for the emergency core cooling (including core spray and decay heat removal) and containment heat removal pumps that meet either of the following criteria:
(1) pumps that take suction from the containment sump or suppression pool
. following a design basia Loss of Coolant Accident (LOCA) or secondary line break, or (2) pumps used in " piggyback" operation that are necessary for recirculation cooling of the reactor core and containment (that is, pumps that are supplied by pumps which take suction directly from the sump or suppression pool)...
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Based on this review, licensees are requested to provide the information outlined below to the NRC by January 5,1998:
9711260152 971106 PDR ADOCK 05000346 P
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. Serial Number 2499
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- 1. Specify the general methodology used to calculate the head loss associated.
with the ECCS suction strainers.
- 3. Specify whbther 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 paol fluid) was credited in the calculation of available 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.
Generic Letter 97-04 required that licensees submit an initial response to the NRC by November 6,1997, indicating whether or not the above requested information will be submitted within the requested time period. Toledo
. Edison plans to submit the requested information regarding the Davis Besse Nuclear Power Station, Unit Number 1 to the NRC by January 5,1998.
Should you have any questions or require additional information, please contact Mr. James L. Frects, Manager-Regulatory Affairs, at (419) 321-8466.
Very truly yours, a pse.
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A. B. Beach, Regional' Administrator, NRC Region HI
- S; J. Campbell, DB-1 NRC Senior Resident Inspector A G. Hansen, DB-1 NRC/NRR Project Manager Utility Radiological Safety Board E
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Dock;t Number 50-346 License Number NPF-3 :
Serial Number 2499
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RESPONSE
TO
.NRC GENERIC LE' ITER 97-04 FOR THE DAVIS-BESSE NUCLEAR POWER STATION UNIT NUMBER 1 This letter is submitted pursuant to 10 CFR 50.54(f) and contains information pursuant to NRC Generic Letter 97-04," Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps" for the Davis-Besse Nuclear Power Station, Unit Number 1.
For: John K. Wood, Vic e President - Nuclear By:
lu T. J. Myers i ctor-DB Nuclear Support Services
-Sworn to and subscribed before me this 6th day-of November,1997 O
Noiary Public, State of Ohio -
LAURA A. JEf*NSON My% PuWic, State of OW.
Commission Empires 8-15 2001
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