ML20217C482
| ML20217C482 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/20/1998 |
| From: | Jeffery Wood CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20217C487 | List: |
| References | |
| 2523, NUDOCS 9803270039 | |
| Download: ML20217C482 (2) | |
Text
' ), j <.e 9=
n2=
s.
Davis-Besse Nuclear Power Statm ynyV 5501 North State Route 2 Oak Harbor.Ohc43449-9760 m
l.
Jahrt K. N.
419-249-2300 Vice President-Nuclear Fax:419-321 8337 Docket Number 50-346 1
License Number NPF-3 Serial Number 2523 March 20, 1998 United States Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555-0001 l.
Subject:
Transmittal of a Revised Technical Specification Page for License Amendment l
Application Letter Serial Number 2512 Ladies and Gentlemen:
Toledo Edison (TE) submitted a License Amendment application (Letter Setial Number 2512, dated February 26,1998) that proposed an amendment to the Davis-Besse Nuclear Power Station (DBNPS) Unit Number 1, Facility Operating License NPF-3, Appendix A, Technical Specifications. The proposed changes involved a new repair process called " repair roll." These l
proposed changes involved Technical Specification (TS) 3/4.4.5, Reactor Coolant System -
L Steam Generators, TS 3/4.4.6.2, Reactor Coolant System - Operational Leakage, and their L
associated Bases.
-l In accordance with a telephone call conducted on March 11,1998, between TE and the NRC, TE is submitting the attached revised TS page. The attached revised TS page contains the following additional text: "of the new roll areas." This text is inserted in the previously proposed wording to Surveillance Requirement (SR) 4.4.5.3.c.1 after "... additional inspections..." and before "...in j
- the unaffected steam generator."
l This change to SR 4.4.5.3.c.1 provides greater specificity as to the location of the additional inspectior.s in the unaffected steam generator. This additional text does not affect the Leonclusions previow!y provided to the NRC in the Safety Assessment and Significant Hazards Consideration in TE letter Serial Number 2512.
-9903270039 990320 0
F PDR--ADOCK 05000346 p!r P
PDR; f l---
I
. L a
Docket Number 50-346 License Number NPF-3 Serial Number 2523
. Page,2 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, FWK/laj Attachment cc:
A. B. Beach, Regional Administrator, NRC Region III l
S. J. Campbell, DB-1 NRC Senior Resident Inspector A. G. Hansen, DB-1 NRC/NRR Project Manager J. R. Williams, Chief of Staff, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
Utility Radiological Safety Board t,
4
\\
L.--__.~.
_ _ _ _ - _ _ _. - _ _ _ - _ - _ _ _ -