ML20196C421

Amend 102 to License DPR-36,revising Tech Spec 3.10.C.3.1.1 to Reflect Revised LOCA Monitoring Limits to Be Used When in-core Monitoring Sys Inoperable

ML20196C421
Person / Time
Site:	Maine Yankee
Issue date:	02/09/1988
From:	Wessman R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20196C390	List: ML20196C385 ML20196C421 ML20196C430
References
NUDOCS 8802160095
Download: ML20196C421 (5)

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.s p asu f( UNITED STATES NUCLEAR REGULATORY COMMISSION y g 3 WASHINGTON, D. C. 20555

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MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 MAINE YANXEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Arnendment No.102 License No. DPR-36

1. The Nuclear Regulatory Commission (the Comission) has found that-A. The application for amendment by Maine Yankee Atomic Power Company (the licensee), dated July 30, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity wit.h the application, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (i) that the activities authorized  !

by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in conpliance with the Comission's regulations; D. The issuance of this anondment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

8802160095 880209 PDR ADOCK 05000309 P PDR 1

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.B(6)(b) of Facility Operatina License No. DPR-36 is hereby amended to read as follows:

(b) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.102, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective 60 days from the date of this letter.

FOR THE NUCLEAR REGULATORY COMMISSION Richard H. Wessman, Actino Director Proiect Directorate I-3 Division of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications Date of Issuance: February 9, 1988

ATTACHMENT TO LICENSE AtiENDMENT NO.102 FACILITY OPERATING LICENSE NO. DPR-36, DOCKET NO. 50-309 Revise Appendix A as follows:

Remove Pages Insert Pages 3.10-4 3.10-4 3.10-4a 3.10-4a*

• Repositioned on page - no change i

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'3. Incore detector alarms shall be set at least weekly.

Alarms will be based on the latest power distribution obtained, so that U.e linear heat rate does not exceed the linear heat rate limit defined in Specification 3.10.C.1. If four or more coincident alarms are received, the validity of the alarms shall be imediately determined and, if valid, power shall be immediately decreased below the alarm setpoint.

3.1 If the incore monitoring system becomes inoperable, perform one of the following within 4 effective full power hours:

1. Initiate a power reduction at a rate of at least 1% per hour to a power level less than or equal to the power level given by the following expression for the limiting location:

P - (R-0.5 S) (LHR (limit)/ LHR (measured)], where:

P - % of rated power, R - 85 for symmetric offset between 0.00 and +0.10, or 92 for symmetric offset between 0.00 and -0.10, S - Number of steps the CEAs deviates from the CEA position existing when the linear heat rate measurement was taken, LHR (limit) - Linear heat rate permitted by Specification 3.10.C.1, and LHR (measured) - Linear heat rate last measured corrected to 100% power.

The CEAs shall be maintained above the 100% power dependent insertion limit and symmetric offset shall be monitored once per shift to ensure that it remains within the above range.

This method may be used for up to 14 effective full power  ;

days from the time when the linear heat rate measurement j was taken; or i  ;

2. Comply with the LCO given in Figure 3.10-2 while maintaining l the CEAs above the 100% power insertion limit. If a power l reduction is required, reduce power at a rate of at least '

1% per hour; or

3. Comply with the LCO in Figure 3.10-3. If a power reduction j is required, reduce power at a rate of at least 1% per hour. I l

3.10-4  ;

Amendment No. 38, 40, 65, 68, 78, 98, 102 _ . . _-

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4. The azimuthal power tilt, Tg, shall be determined prior to operation above

. 50% of full rated power after each refueling and at least once per day during operation above 50% of full rated power.

Tq is given by the following expression:

T g- 2 (Da-Dc)2 + (Db-Dd)2 (Da+0b + Dc+0d)2 where Di is the signal from excore detector channel i. If an excore channel is inoperable, Di are the relative quadrant powers determined from the incore system for all quadrants, i.

Tq shall not exceed 0.03.

4.1 If the measured value of T g is greater than 0.03 but less than or equal to 0.10, or an excore channel is inoperable, assure that the total radial peaking factor (FRT) is within the provisions of Specification 3.10.C.P. once per shif t.

Amendment No. 98, 102 3.10-4a