ML20203L071

Forwards Application for Amend to License NPF-3 to Revise TS to Incorporate New Repair Roll Process for SG Tubes. Proprietary Version of Topical Rept BAW-2303P, OTSG Repair Roll Qualification Rept, Encl.Proprietary Encl Withheld

ML20203L071
Person / Time
Site:	Davis Besse
Issue date:	02/26/1998
From:	Jeffery Wood CENTERIOR ENERGY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19317C931	List: ML20203L071 ML20203L086 ML20203L111
References
2512, NUDOCS 9803050335
Download: ML20203L071 (2)

Text

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.lohn K. Wood 419 249 2300 VwePrewmt Nucer Fas 4193218337 Note: The enclosure to this letter contains proprietary information  ;

Docket Number 50-346 License Number NPF-3 Serial Number 2512 February 26,1998 United States Nuclear Regulatory Commission Document Control Desk Waslungton, D. C. 20555-0001 3

Subject:

Proposed Modification to the Davis-Besse Nuclear Power Station Operating License NPF-3, Appendix A Technical Specifications to

Incorporate a New Repair Roll Process for the Steam Generator Tubes With Defects Within the Upper Tube Sheet Ladies and Gentlemen

Enclosed is an application for 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 involve a new repair process called

" repair roll." The repair roll process is used for the repair of steam generator tubes with defects within the upper tube sheet. This application additionally proposes a reduction in the primary to seconda'v steam generator leakage limit from 1 Gallon /

Per Minute, total primary to secondary leakage (1440 Gallons Per Day) to 150 /

Gallons Per Day, primary to secondary leakage through the tubes of any one steam generator. These proposed changes involve Technical Specification (TS) 3/4.4.5, Reactor Coolant System - Steam Generators, TS 3/4.4.6.2, Reactor Coolant System -

Operational Leakage, and their associated Bases.

A

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This application proposes to revise the TS Surveillance Requirements (SR) for steam generator tube sample selection and inspection to include the recently qualified repair roll method of Once Through Steam Generator (OTSG) tube-to-tubesheet expansion joint repair. The associated SR that support steam generator tube sample selection and inspection are proposed for change where necessary to incorporate the proposed repair roll method. This method is described in the 9803050335 900;226 PDR ADOCK 05000346 1W W - g'

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enclosed proprietary Framatome Txhnologies Incorporated Topical Report BAW.

2303P, Revision 3, "OTSO Repair Ro!i Qualification Report." A non-proprietary version of the topical report will be prepsred and submitted to the NRC by March 13,1998. A reduced leakage limit for primary to secondary steam generator

leakage is proposed for the Operational Leakage Limiting Condition for Operation (LCO). A new surveillance method to enable occurate detection of the relativelylow allowed leakage is proposed for the associated SR.

The Eleventh Refueling Outage (11RFO) for the DSNPS is presently scheduled to commence on April 11,1998, which will include insenice inspection of the steam generators. Toledo Edison would like to have this steam geneutor tube repair ,

method available for use as an NRC-approved method. Accordingly, Toledo Edison requests that the NRC approve and issue these TS changes by April 17,1998.

Should you have any questions or require additional informatma, please contact Mr.

James L. Freels, Manager - Regulatory Affairs, at (419) 321-8460.

Very truly yours, f 4~- /$1 F Kilaj Enclosure cc: A. B. Beach, Regional Administrator, NRC Region III S. J. Campbell, DB-1 NRC Senior Resident Inspector A. G. Hansen, DB-1 NRC/NRR Project Manager J. R. Williams, Chief of StafT, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)

Utility Radiological Safety Board -

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