ML053070350
| ML053070350 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  (NPF-003) |
| Issue date: | 04/23/1997 |
| From: | Jeffery Wood Centerior Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2439a, GL-97-001 | |
| Download: ML053070350 (3) | |
Text
5501 N. Stale Route 2 Oak Harbor. OH 43449 4 19-249-2300 FAX: 419-321-8337 John K. Wood Vice President -Nuclear Caws-Besse Docket Number 50-346 License Number NPF-3 Serial Number 2439a 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 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.
information, please contact Mr. James L. ??reels, Manager - Regulatory Affairs, at (419) 321-8466.
In the meantime, should you have any questions or require additional very truly yours, a x
- cc: A. B. Beach, Regional Administrator, NRC Region I11 A. G. Hansen, DB-1 NRC/NRR Project Manager S. Stasek, DB-1 NRC Senior Resident Inspector Utility Radiological Safety Board
Dokket Number 50-346 License Number NPF-3 Serial Number 2439%
Attachment
RESPONSE
TO NRC GENERIC LETTER 97-01 FOR THE DAVIS-BESSE NUCLEAR POWER STATION UNIT NUMBER 1 This letter is submitted pursuant to the provisions of Section 182a, Atomic Energy Act of 1954 as amended, and 10 CFR 50.54(f). Attached is the 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.
By :
Sworn to and subscribed before me this 23rd day of A p r i l, 1997.
-v^
r Lje9-t L,A&,,-)+&?2L--4' Notary Public,yState of Ohio Nora Lynn Flood My Commission e x p i r e s September 3, 1997.
RAS-97-00504 Docket Number 50-346 License Number NPF-3 Serial Number 2439 Date: April 23. 1997
Subject:
Initial Response to NRC Generic Letter 97-01: Degradation of Control Rod Drive Mechanism Nozzle and other Vessel Closure Head Penetrations W. J. Molpus P. K. Goyal D. W. Schreiner R. J. Slyker T. S. Swim D. R. Wuokko Company Nuclear Review Board Correspondence Control Public Relations Safety Analysis Report Update Station Review Board 5175 3210 1046 3065 3210 3065 3030 3020 3025 3065 1021