ML20072J534

Forwards Application for Amend to License Npf,Revising TS 3.1.1.1 Re Shutdown Margin,Ts 3.4.5 Re Steam Generators LCO & TS Bases 3/4.4.5

ML20072J534
Person / Time
Site:	Davis Besse
Issue date:	08/22/1994
From:	Stetz J CENTERIOR ENERGY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20072J536	List: ML20072J534 ML20072J587 ML20072J614
References
NUDOCS 9408290084
Download: ML20072J534 (2)

Text

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Docket Number 50-346 l License Number NPF-3 Serial Number 2231 1

i August 22, 1994 United States Nuclear Regulatory Commission  !

Document Control Desk Washington, DC 20555

Subject:

License Amendment Application to Revise Technical Specification 3.1.1.1 (Shutdown Margin); 3.4.5 (Steam Generators Limiting Condition for Operation) and Bases 3/4.4.5 (Steam Generators)

Gentlemen:

Enclosed is a revised application for an amendment to the Davis-Besse Nuclear Power Station (DBNPS), Unit 1 Operating License Number NPF-3, Appendix A, Technical Specifications (TS) to reflect the changes attached. The proposed changes involve TS 3.1.1.1 (Shutdown Margin),

TS 3.4.5 (Steam Generators Limiting Condition for Operation) and TS Bases 3/4.4.5 (Steam Generators). This application supersedes the

-application previously submitted on September 3, 1992 (Serial Number 2050) in order to include changes to TS 3.1.1.1 and 3.4.5 which have been discussed between the NRC Staff and Toledo Edison.

This revised request proposes that a footnote be added to the MODE applicability section of TS 3.1.1.1 which refers to additional requirements for SHUTDOVN MARGIN which are also being added to TS 3.4.5, Steam Generators.

As in Toledo Edison's submittal of September 3, 1992, this request also proposes that the Limiting Condition for Operation of the Steam Generators (TS 3.4.5) be revised to permit the maximum allowable steam generator (SG) vater level to be a variable limit based on the plant's mode of operation. A graph of Acceptable SG Operate Range Level versus Main Steam Superheat during Modes 1 and 2 is proposed for incorporation into the Technical Specifications as new Figure 3.4-5. The Limiting Condition for Operation vill also specify the maximum accertable steam generator water level when the plant is in Mode 3 based on the status of the Main Feedvater Pumps and the Steam and Feedvater Rupture Control 9408290084 940822 o PDR ADOCK 05000346 o P PDR operonna companies Cleveland Electnc muminowng

@' g Toledo Edison e

Docket Number 50-346 License Number NPF-3 Serial Number 2231 Page 2 System (SFRCS) and specify the maximum acceptable steam generator water level when the plant is in Mode 4. A footnote is to be added to require maintaining an adequate SHUTD0VN MARGIN while in Mode 3.

The proposed administrative change to TS Bases 3/4.4.5 specifies that the steam generator water level limits are consistent with the assumptions in the Updated Safety Analysis Report (USAR) rather than the initial assumptions in the Final Safety Analysis Report (FSAR).

Examples of incapable Main Feedwater Pumps under this proposed TS 3.4.5 are also provided in the Bases. The Bases will.also note that the SHUTDOVN MARGIN requirements are provided in plant operating procedures.

These changes to TS 3/4.4.5 are being proposed to allow the plant to continue to produce full power as future Steam Generator fouling occurs, while ensuring the plant response to accident conditions remains acceptable and adequate margins to safety limits are maintained.

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 amendment be issued by the NRC by September 30, 1994, for use during the DBNPS ninth refueling outage (currently scheduled to commence October 1, 1994).

If you have any questions regarding this amendment application, please contact Mr. V. T. O'Connor, Manager - Regulatory Af fairs, at (419) 249-2366.

Very truly yours, J hn P. Stetz Vice President - Nuclear  !

l Davis-Besse Nuclear Power Station 1

KMN/laj Enclosures f I

cc: L. L. Gundrum, NRC/NRR DB-1 Project Manager J. B. Martin, Regional Administrator, NRC Region III S. Stasek, NRC Region III, DB-1 Senior Resident Inspector i J. R. Villiams, Chief of Staff, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)

Utility Radiological Safety Board

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