ML20041G379

Transmits Application for Amend to License NPF-3,extending Length of Fuel Cycle 3

ML20041G379
Person / Time
Site:	Davis Besse
Issue date:	03/05/1982
From:	Crouse R TOLEDO EDISON CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML20041G380	List: ML20041G379 ML20041G381 ML20041G382 ML20041G383
References
TASK-2.K.2.10, TASK-TM TAC-45184, TAC-48044, NUDOCS 8203220169
Download: ML20041G379 (2)

Text

TOLEDO

%s EDISON Rmano P. CAoust Docket No. 50-346 License No. NPF-3 U7 Serial No. 787 m 2 m 22' March 5, 1982 q

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Director of Nuclear Reactor Regulation g

g Attention:

Mr. John F. Stolz NEO 2

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Operating Reactor Branch No. 4

'8; g,Q g.O I982 h Division of Operating Reactors 3

United States Nuclear Regulatory Comaission 1

J Washington, DC 20555 y

Dear Mr. Stolz:

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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 (DB-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:

1.

Technical Specifications contained in the Cycle 3 reload report (BAW-1707 February 1982) and 2.

Tables 3.3-15 and 4.3-15 The two attachments identify the proposed changes and their safety evaluation.

Item 1 concerns the Cycle 3 reload report, and the supporting accident / transient analysis evaluation are included in the reload report (BAW-1707 February, 1982).

Item 2 concerns revision to Toledo Edison's Amendment request (Item No. 2) submitted November 25, 1981 (Serial No. 757) on Anticipatory Reactor Trip System (ARTS).

The nominal base design cycle length for Cycle 3 is 230 effective full power days (EFPD). However, the attached reload report is designed to provide flexibility in the overall cycle length depending on the perform-ance of Davis-Besse up to the first 200 EFPD of operation of Cycle 3, and the date for commencement of the third refueling outage (tentatively scheduled for Spring 1983). This flexibility in cycle length is achieved by a complete withdrawal of the axial power shaping rods at 200 110 EFPD and coastdown of power level towards the end of cycle. This would facili-tate an extension of cycle length to 268 110 EFPD. The analyses and 0(

0 8203220169 820305 PDR ADOCK 05000346

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P PDR THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MAOISON AVENUE TOLEDO. OHIO 43652 h

_ _ _ _ _ _..__ _ _ _ _ _ _ _ Docket No. 50-346 License No. NPF-3 l

Serial No. 787 I

March 5, 1982 Technical Specifications included in the attached report support this flexibility in mode of operation in the latter part of Cycle 3.

The Technical Specification changes included in BAW-1707 incorporate the impact of the accident induced neutron flux error issue as applied to the Cycle 3 parameters (also see Toledo Edison letter Serial No. 693 dated March 13, 1981).

In addition, the reactor protection system trip set-points and allowable values have been appropriately modified to address the revised instrument inaccuracies as comitted to in License Event Report NP-33-81-89.

This amendment request contains one revision of a previous submittal requiring no fee and one change of Class IV Type.

It is therefore deter-mined to be a Class IV amendment. Enclosed is a check for $12,300 as requested by 10 CFR 170.22.

Very truly yours,

.Q^

RPC:SCJ: GAB Attachment cc:

DB-1 NRC Resident Inspector bt d/3

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