ML20134F253
| ML20134F253 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/28/1996 |
| From: | Jeffery Wood CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2409, GL-96-06, GL-96-6, NUDOCS 9611050098 | |
| Download: ML20134F253 (3) | |
Text
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Ih 4lg> CENTERDOR ENERGY 6200 00k Tree Boulevard Mc:t Add ess independence OH PO Box 94661 216 447 3100 Cleveland OH 441014661 Docket Number 50-346 License Number N"F-3 Serial Number 2409 October 28, 1996 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001
Subject:
Response to NRC Generic Letter 96-06: Assurance of Equipment j
Operability and Containment Integrity During Design-Basis Accident i
Conditions Ladies and Gentlemen:
)
i Nuclear Regulatory Commission (NRC) Generic Letter 96-06, dated September 30, 1996, requtists that nuclear power plants determine:
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(1) If their containment air cooler cooling water systems are suscep-tible to either waterhammer or two-phase flow conditions during postulated accident conditions,and (2) If tSeir piping systems that penetrate the containment are suscep-tible to thermal expansion of fluid so that overpressurization of piping could occur.
In addition to the individual nuclear power plant's postulated accident conditions, Generic Letter 96-06 states the above two items should also be reviewed with respect to the specific scenarios described in the Generic Letter.
By January 28, 1997, a written summary report must be submitted to the NRC stating:
(1) actions taken in response to the requested actions above, (2) conclusions that were reached relative to susceptibility for waterham-4 mer and two-phase flow in the containment air cooler cooling water system, and overpressurization of piping that penetrates containment, (3) the basis for continued operability of affected systems and components as applicable, and (4) corrective actions that were implemented or are planned to be implemented.
Each nuclear power plant is required to inform the NRC by October 30, 1996, whether it will complete the above requested actions by January 28, 1997.
Based on information available at this time, the Davis-Besse Nuclear Power 9611050098 961028 g6
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Docket Number 50-346
.. License Number NPF-3 Serial Number 2409 Page 2 Station Unit Number 1 (DBNPS) plans to complete the above requested actions and submit the requested information to the NRC by January 28, 1997.
How-ever, as the NRC is aware, an industry meeting to discuss Generic Letter 96-06 is scheduled for October 29, 1996, at which NRC Staff will discuss and clarify the requested actions.
Should the results of this meeting affect the DBNPS's plans, the NRC will be notified by letter.
Should you have any questions or require additional information, please contact Mr. James L. Freels, Manager-Regulatory Affairs, at (419) 321-8466.
Very truly yours, John K. Wood Vice President - Nuclear Davis-Besse Nuclear Power Station DRW/laj attachment cc:
A.
G. Hansen, NRC/NRR Project Manager A.
B. Beach, Regional Administer, NRC Region III S.
- Stasek, NRC Region III, DB-1 Senior Resident Inspector J.
R. Williams, Chief of Staff, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
Utility Radiological Safety Board
1 Dockat Number 50-346 Licensa Numbar NPF-3 Sarial Numbsr 2409 a
Attachment Page 1
RESPONSE
TO l
NRC GENERIC LETTER 96-06 FOR THE DAVIS-BESSE NUCLEAR POWER STATION UNIT NUMBER 1 This letter is submitted pursuant to 10 CFR 50.54(f). Attached is the requested response to NRC Generic Letter 96-06, " Assurance of Equipment Operability and Containment Integrity During Design - Basis Accident Conditions" for the Davis-Besse Nuclear Power Station, Unit Number 1.
I By:
N J. K. Wood, Vice President - Nuclear Sworn to and subscribed before me this 28th day of October, 1996.
N /L dda w L tu Notary Public, Q/ ate of Ohio Nora Lynn Flood My commission expires September 3, 1997.
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