ML20076J247

Application for Amend to License NPF-3,revising Tech Spec Surveillance Test Requirements to Include Flow Test to Verify Normal Path Availability of Auxiliary Feedwater to Steam Generator.Class III Amend Fee Encl

ML20076J247
Person / Time
Site:	Davis Besse
Issue date:	06/15/1983
From:	Crouse R TOLEDO EDISON CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML20076J250	List: ML20076J247 ML20076J251
References
956, TAC-51964, NUDOCS 8306200393
Download: ML20076J247 (4)

Text

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TOLEDO

%m= EDISON Rom P. CAOUSE Docket No. 50-346 vce p.esent feuctear License No. NPF-3 S'259-522' Serial No. 956 June 15, 1983 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz Operating Reactor Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Stol=:

Under separate cover, we are transmitting three (3) original and forty (40) conformed copies of an application for Amendment to Facility Operating License No. NPF-3 for the Davis-Besse Nuclear Power Station Unit No. 1.

This application requests that the Davis-Besse Nuclear Power Station Unit 1 Technical Specifications, Appendix A, be revised to reflect the changes attached. The proposed changes involve Section 4.7.1.2.

The attachment identifies the proposed change and its Safety Evaluation concerning Auxiliary Feedwater System (AFW) to ensure the availability has not been affected following any modifications or repairs to the AFW system piping and during the refueling outage.

This amendment request involves a change of Class III type. Enclosed is a check for $4,000 as requested by 10CFR170.22.

Very truly yours, RPC: GAB:lah Attachment l

cc: DB-1 NRC Resident Inspector I d 8306200393 830615 PDR ADOCK 05000346 IlI P PDR THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO d'3652 i

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APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE NO. NPF-3 FOR DAVlS-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 Evaluation for the requested change.

The proposed changes include Section 4.7.1.2.

By /s/ R. P. Crouse Vice President, Nuclear Sworn and subscribed before me this 15th day of June, 1983.

Laurie A. Hinkle, nee (Brudzinski)

Notary Public , State of Ohio My Commission Expires May 16, 1986 SEAL

Docket No. 50-346 License No. NPF-3 Serial No. 956 June 15, 1983 Attachment I. Changes to Davis-Besse Nuclear Power Station Unit 1, Appendix A Technical Specifications 4.7.1.2.

A. Time required to Implement. This change is to be effective upon NRC approval.

B. Reason for Change (Facility Change Request 83-032 Rev. A).

In response to Mr. J.F. Stolz letter dated December 1, 1982 (Log No. 1144) concerning Auxiliary Feedwater System (AFW) to ensure the availability following any modification or repairs to the AFW system piping and during the refueling outage.

C. Safety Evaluation (see attached)

D. Significant Hazards Considerations Toledo Edison has reviewed the above Amendment Request in accordance with 10 CFR 50.92(c) and has determined the proposed amendment would not:

(1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.

The above determination is based on the attached Safety Evaluation.

I SAFETY EVALUATION This amendment request is to revise Technical Specification Surveillance Test Requirements Section 4.7.1.2 to include a flow test to verify normal path availability of the Auxiliary Feedwater (AFW) to the Steam Generators following any modifications or repairs to the AFW system piping and during the refueling outage.

The safety function of the AFW system is to provide feedwater to the steam generators for the removal of reactor decay heat in the absence of main feedwater and to promote natural circulation of the reactor coolant system in the event of a loss of all four reactor coolant pumps.

NRC has requested Toledo Edison (December 1, 1982 Log No. 1144) to propose a technical specification change to perform a flow test following a refueling outage or any maintenance / modifications to the AFWS which might degrade system performance or flow path availability. Per letter Log No. 1144, NRC agreed that introduction of non-deaerated water to the steam generator can produce adverse effects and share Toledo Edison's concerns that such injection should be held to a minimum. This technical specification change is proposed in light of these understandings to specifically exclude the verification of flow rates and minimize the introduction of non-deaerated water to the steam generator.

We propose to perform the tests in Mode 5 (RCS temp (200*F) as follows:

(1) During refueling outage verification of AFW flow path between each auxiliary feedwater pump and each steam generator will be made by pumping water to the steam generator. Flow to the steam generator will be verified by either steam generator level change or AFW flow indication.

(2) If the modifications / repairs are made upstream of the flow test line, no water will be injected to the steam generator, and the existing test flow path will be used to verify the affected flow path availability. If the modifications or repairs are made downstream of the test flow path, a minimum amount of water will be pumped from the appropriate auxiliary feedwater pumps to the steam generator to verify the affected flow path availability. This flow path will be verified by observing steam generator level change or by AFW flow indication.

The proposed flow path test verifies that the AFW flow path is available

, to the steam generators which ensures the safety function of the AFW system.

Therefore, it is concluded that the requested change is not an unreviewed safety question.

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