ML20114D897

Forwards Application for Amend to License NPF-3,revising TS 3.4.5 (SGs LCO) & Bases 3/4.4.5 (Sgs.)

ML20114D897
Person / Time
Site:	Davis Besse
Issue date:	09/03/1992
From:	Shelton D CENTERIOR ENERGY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20114D898	List: ML20114D897 ML20114D902 ML20114D903
References
2050, NUDOCS 9209100139
Download: ML20114D897 (2)

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GN1tR00R '

ENERGY Donald C. SheNon 300 Mdson Avenue '

Vce Prescent.Nudear Toledo;0H 43652RX)1 Davis Bene -(419)2G2300 -

Docket Number 50-346 License Number NPF-3 Serial Wumber 2050 September 3, 1992 United States Nuclear Regulatory Commission Document' Control Desk Vashington, DC 20555

Subject:

License Amendm e t Application to Revise Techr. cal Specification 3.4.5 (Steam Generators Limit' g Condition for.

Operation) and Bases 3/4.4.5 (Steam Generasors)

Gentlemen 1 Enclosed is an application for an amendment to the. Davis-Besse. Nuclear i Power Station--(DBNPS), Unit 1 Opera (;ing License. Number NPF-3, Appendix A, Technical Specifications ~(TS) to.: reflect the< changes attached. The proposed changes' involve TS 3.4.5L(Steam Generators Limiting Condition for Operation) and TS Bases 3/4.4.5-.(Steam Generators).

This request proposes that the Limiting Condition for Operation of the-Steam Generators (TS 3.4.5) be revised to permitithe' maximum allovable steamofgenerator mode operation. (SG): level- to be- a variable-limit 1 based on,the: plant's 4 A graph of' Acceptable SG Operate Range: Level versus-Main Steam Superheat--during-Modes-1 andi2 is~ proposed'for incorporation- g into the Technical Specifications as new Figure 3.4;5. 1Thel-Limiting; Condition for-Operation vill also specify the1 maximum acceptable steam-generator level when the plant is in-Mooe 3~ based.on the statu's ofi the '

a Main Feedvater.. Pumps and the Steam and-Feedvate'r-Rupture Control System; O (SFRCS) and specify the maximum acceptableLsteam generator [levelivhen the plant is'in Mode 4.

The proposed administrative'_changerto;TS' ' .

Bases 3/4.5.4 is-to_specify;that the steam generator _vatet9_ level > limits are consistent with the assumptions'in>the' Updated Safety' Analysis.

Analysis1(USAR)

Report rather than the initial assumptionstinLthe FinalHSafety _ .

Report _(FSAR).'

under this proposed T.S.' Examples.of1 3.4.5 are also provided-inLthe_ Base's -

incapable Main Feedvater Pumps 1 These changes to T.S. 3/4.4.5 are being proposed:to allow;the plant to

" continue to produce-full'pover as' Steam Generator fouling' occurs, while ensuring'_ the_ plant response to accident conditions remains a;ceptable 9209100139 92d903 'trv limits-are maintained.

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Docket Number 50-346 .

. License Numb <ir NPF-3 Serial Number 2050 e Pag'e 2 A description and explanation of the operation of the plant's once Through Steam Generator (OTSG) is provided for informational purposes in Enclosure 2.

Toledo Edison requests that this amendrient be issued by the NRC by February 28, 1993, for use during the DBNPS eighth refueling outage (currently scheduled to commence March 1, 1993).

If you have any questicns regarding this amendment application, please contact Mr. R. W. Scheauder, Managar - Nuclear Iicensing, at (419) 249-2366.

'.'ery n; tly yours ,

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[ /W Q RAS /dle Enclosures cc: A. B. Davis, Regional Adininistrator, NRC Region III J. B. Ilopkins, NRC/NRR DB-1 Senior Project Manager V. Levis, NRC Senior Resident Inspector General J. Villiams, Chief of Staff, Ohio Adjutant General's Office, State of Ohio Utility Radiological Safety Board l

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