ML20138E655
| ML20138E655 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/23/1997 |
| From: | Jeffery Wood CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2439, GL-97-01, GL-97-1, NUDOCS 9705050086 | |
| Download: ML20138E655 (2) | |
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CENTE~ EOR ENERGY 6501 N State Route 2 419 249-2300 John K. Wood Oak Harbor. OH 43449 FAX: 419 321-8337 Vice Presdent. Nuclear Davis Besse Docket Number 50-346 License Number NPF-3 Serial Number 2439 April 23, 1997 United States Nuclear Regulatory Commission Document Control Desk washington, D.
C.
20555-0001
Subject:
Initial Response to NRC Generic Letter 97-01:
Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations Ladies and Gentlemen:
On April 1, 1997, the Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 97-01 (Toledo Edison letter Log Number 5027), requesting that the licensees for the Davis-Besse Nuclear Power Station (DBNPS), Unit Number 1 provide a description of their program for ensuring the timely inspection of the reactor's control rod drive mechanism (CRDM) nozzles and other vessel closure head j
penetrations (VHP).
The generic letter requested specific information regarding CRDM nozzle and other VHP inspection activities, and also a description of any ion exchange resin bed intrusions and their effect on the primary water chemistry.
Toledo Edison plans to submit the requested information to the NRC by July 29, 1997.
In the meantime, should you have any questions or require additional
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information, please contact Mr. Ja';.es L.
Freels, Manager - Regulatory Affairs, l
at (419) 321-8466.
Very truly yours, FWK/1a' cc:
A.
B.
Beach, Regional Administrator, NRC Region III A. G. Hansen, DB-1 NRC/NRR Project Manager S.
Stasek, DB-1 NRC Senior Resident Inspector Utility Radiological Safety Board 9705050006 970423 PDR ADOCK 05000346 P
l Docket Number 50-346
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Licensa Number NPF-3 Serial Number 2439 Attachme'nt
RESPONSE
l TO l
NRC GENERIC LETTER 97-01 FOR THE i
DAVIS-BESSE NUCLEAR POWER S7ATION UNIT NUMBER 1 This letter is submitted pursuant to the provisions of Section 182a, Atomic
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Energy Act of 1954 as amended, and 10 CFR S0.54 (f). Attached is the 1
requested response to NRC Generic Letter 97-01, " Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations" for the Davis-Besse Nuclear Power Station, Unit Number 1.
i By:
g K.j ood, Vice President - Nuclear J.
1 1
Sworn to and subscribed before me this 23rd day of April, 1997.
Y
'Ot+(-f A)>2/vu f W.
Notary Public,#5 tate of Ohio Nora Lynn Flood My Commission expires September 3, 1997.
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