ML20053D970

Application for Amend to License NPF-3,revising Reactor Protection Sys Trip Setpoints

ML20053D970
Person / Time
Site:	Davis Besse
Issue date:	06/01/1982
From:	Crouse R TOLEDO EDISON CO.
To:
Shared Package
ML20053D585	List: ML20053D584 ML20053D970 ML20053D973
References
TAC-48044, NUDOCS 8206070490
Download: ML20053D970 (3)

Text

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APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE NO. NPF-3 FOR DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Enclosed are forty-three (43) copies of the requested changes to the Davis-Besse Nuclear Power Station Unit No. 1 Facility Operating License No. NPF-3. together with the Safety Evalution for the requested change.

The proposed changes contained in Cycle 3 Reload Report (BAW - 1707).

By /s/ R. P. Crouse Vice President, Nuclear 1

Sworn and subscribed befor' .e this 1st day of June, 1982.

c 0 .

N'otary Public ,

G LAURIE A. BRUDZ'INSKI Notary Public. State of Chis My Commission Expires Way 16.1986 0306070490 6 PDR ADOCK 0 PDR P -

Docket No. 50-366 License No. NPF-3 Serial No. 822 June 1, 1982 Attachment I. Changes to Davis-Besse Nuclear Power Station Unit 1, Appendix A Technical Specifications contained in the Cycle 3 reload report (BAW

- 1707 submitted on March 5, 1982 Serial No. 787).

A. Time required to Implement.

This change is to be effective upon NRC approval.

B. Reason for Change (Facility Change Request 80-268 Supplement 4).

To eliminate the dual inclusion of the calibration related errors in the Reactor Protection Trip Setpoints.

C. Safety Evaluation This amendment request is to revise several of the Reactor Protection System (RPS) Technical Specifications trip setpoints contained in the Cycle 3 reload report (BAW - 1707 submitted March 5, 1982 Serial No. 787).

The safety function of the RPS trip setpoints is to ensure the reactor is properly protected against DNB or KW/ft safety limits determined by the accident analysis. The actual setpoints in the field should account for possible errors associated with instrumentation (hardware related as well as calibration related),

heat balance, drifts transient overshoots, steady state noise, etc. In order to ensure that the Technical Specification trip setpoints are not violated, an additional margin for safety is established by Toledo Edison is always maintained between the Technical Specification trip setpolni' and the actual setpoint in the field. This margin, in part is determined liy the instru-ment calibration error. B&W already included the calibration error in the Cycle 3 RPS Technical Specification trip setpoints as listed in Tabic 2.2-1 of the reload report submitted in Toledo Edison letter dated March 5, 1982 (Serial No. 787). To avoid violation of Technical Specifications, the instrument calibration error would have to be accounted for again. (See attached drawings). The dual inclusion of calibration related errors presents an unnecessary restriction on plant operation.

The Technical Specification trip setpoints are being revised to eliminate this dual inclusion of calibration related error without compromising any intended safety function of the RPS.

Pursuant to the above, it is concluded that the change as proposed do not constitute any unreviewed safety question, ks b/5

UbW TOLEDO EDISON CYCLE 3 REPORT REPORT l / l So f 3 W5 r

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1. Accident Analysis

2. Technical Specific 5 tion frpm Accident Analysis i

3. Instrument Calibration Error Added by B&W

4. Technical Specification Limits Submitted to NRC for Approval

5. Instrument Calibration Error Added by Toledo Edison.

6. Margin of Safety Added by Toledo Edison

7. Trip Setpoint e

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