ML053070355
| ML053070355 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/28/1997 |
| From: | Jeffery Wood Centerior Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2472, GL-97-001 | |
| Download: ML053070355 (3) | |
Text
CNrRIOR
- ENERGY 5501 N. Stale Roule 2 0akHarbor.OH 43449 419-249-2300 John K.Wood FAX: 419-321-8337 Vie Presidenl - Nuclear Davis-Besse Docket Number 50-346 License Number NPF-3 Serial Number 2472 July 2 8, 1997 United States Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555-0001
Subject:
Response to 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 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 reactors control rod drive mechanism (CRDM) nozzles and other vessel closure head penetrations ().
The generic letter requested specific information regarding CRDM nozzle and other VKP inspection activi-ties, and also a description of any ion exchange resin bead intrusions and their effect on the primary water chemistry. Toledo Edison (TE) initially responded to the generic letter by letter dated April 23,1997 and committed to providing a final response by July 29,1997.
Toledo Edison is a member of the Babcock & Wilcox Owners Group (B&WOG) which has developed an integrated response. The B&WOG response is documented in B&WOG Topical Report, titled B&WOG Integrated Response to Generic Letter 97-0 I :
Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations, BAW-2301, dated July 1997 which has been submitted to the NRC. The information contained in BAW-2301 applies to the DBNPS and TE endorses BAW-2301.
Topical Report BAW-2301 provides the justification and schedule for an integrated VHP inspection program representative of the B&WOG plants. Inspections will be performed based on the B&WOG plants determined to be most susceptible to CRDM n o d e e
Docket Number 50-346 License Number NPF-3 Serial Number 2472 Page 2 cracking. The Topical Report also concludes that there have been no conductivity excursions indicative of resin intrusions at any of the B&WOG plants.
Should you have any questions or require additional information regarding the applicability of this B&WOG response to the DBNPS, please contact Mr. James L. Freels, Manager - Regulatory Affairs, at (419) 321-8466. Specific questions regarding Topical Report BAW-2301 may be directed to the contacts referenced in the B&WOG cover letter transmitting Topical Report BAW-2301.
1 Very truly yours, attachment cc:
A. B. Beach, Regional Administrator, NRC Region I11 A. G. Hansen, DB-1 NRCMRR Project Manager S. Stasek, DB-1 NRC Senior Resident Inspector Utility Radiological Safety Board
Docket Number 50-346 License Number NPF-3 Serial Number 2472 a
Attachment
RESPONSE
TO NRC GENERIC LETTER 97-01 FOR THE DAVIS-BESSE NUCLEAR POWER STATION UNITNUMBER 1 This letter is submitted pursuant to the provisions of Section 182% Atomic Energy Act of 1954 as amended, and 10 CFR 50.54(f) and provides the requested response to NRC Generic Letter 97-0 1, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations for the Davis-Besse Nuclear Power Station, Unit Number 1.
0
/
By:
od, Vice President - fiuclear By:
Sworn to and subscribed before me this 28th day of July, 1997.
%&ry Public, Stad! of Ohio Nora Lynn Flood My commission expires September 3, 1997.