ML20054J874

Application to Amend License NPF-3,changing Tech Spec Table 3.3-2 Re Reactor Protection Sys Instrumentation Response Times.Table Inadvertently Omitted from 820305 Application to Amend OL

ML20054J874
Person / Time
Site:	Davis Besse
Issue date:	06/21/1982
From:	Crouse R TOLEDO EDISON CO.
To:
Shared Package
ML20054J873	List: ML20054J872 ML20054J874 ML20054J875
References
829, NUDOCS 8206300132
Download: ML20054J874 (2)

Text

r 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 relating to Cycle 3 reload report (BAW-1707 February, 1982.)

By // hg_ -

Vice ' President, Nuclear Sworn and subscribed before ee this 21st day of June, 1982.

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Notary Public LINDA U. COSTELU Notary Pubisc. State of Ohio My commission expires feb. 15, 1937 r206300132 820621 PDR ADOCK 05000346 P PDR

Docket No. 50-346 License No. NPF-3 Serial No. 829 .

June 21, 1982 Attachment I. Changes to Davis-Besse Nuclear Power Station Unit 1, Appendix A Technical Specifications relating to Cycle 3 reload report Table 3.3-2.

A. Time required to Implement .

This change is to be effective upon NRC approval.

B. Reason for Change (Facility Change Request 80-268, Supplement 7)

Table 3.3-2 was inadvertently omitted in the Cycle 3 reload report.

C. Safety Evaluation The amendment request is to incorporate the Reactor Protection System (RPS) instrument response time (Table 3.3-2) in Davis-Besse Cycle 3 reload report. The safety function of the RPS is to insure that the reactor will trip before DNB and fuel center

- line temperature limits are reached. B&W has used the revised RPS response time in the Cycle 3 reload accident analysis to determine the Cycle 3 RPS trip setpoints for Technical Specifica-tions. This amendment request will make the Cycle 3 Technical Specifications consistent with the response times used. e The total trip delay time used in the accident analysis contains 3 components; the sensor and the RPS instrument delay, the breaker delay and the CRD release delay. The Technical Specifi-cations response times are the sum of sensor RPS delay and the breaker delay since these are the only equipment tested in the RPS response time surveillance testings. By limiting the surveillance testing acceptance criteria to the response time values, operation within the accident analysis will be ensured.

Pursuant to the above, it is concluded that the changes as proposed do not involve any unreviewed safety questions.

bt a/11

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