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Amend 98 to License DPR-36,modifying Tech Specs to Reflect Revised LOCA Limits Using Revised Delta P Injection Penalty Factor During Reflood Phase of LOCA & Limiting Axial Power Shapes
	ML20215E921
Person / Time
Site:	Maine Yankee
Issue date:	06/15/1987
From:	Nerses V; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20215E910	List: ML20215E908; ML20215E921; ML20215E930;
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	NUDOCS 8706220158
	Download: ML20215E921 (8)
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DOCKET N0. 50-309 ] MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 98 License No.'DPR-36

1. The Nuclear Regulatory Commission (the Commission) has found that: 1 A. The application for amendment by Maine Yankee Atomic Power Company (the licensee), dated February 24, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Coranission; ,

C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health i and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common t 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 Commission's regulations and all applicable requirements have been satisfied.

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 Operating 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. 98, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

8706220158 870615 PDR ADOCK 05000309 p PDR

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       .     ,                                                    3.. This license amendment is effective'as of Ne'date of.its issuance.               j FOR THE NUCLEAR REGULATORY C(WHISSION Victor. Nerses Acting Director Project Directorate I-3 Division of Reactor Projects I/II

Attachment:

              . Changes to the Technical Specifications Date of Issuance: June 15,1987 l

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       -                                                                 1 ATTACHMENT TO LICENSE AMENDMENT NO. 98
                              ' FACILITY OPERATING LICENSE NO. DPR-36 DOCKET NO. 50-309 Revise Appendix A as follows:

Remove Pages Insert Pages 3.10-2 3.10-2 3.10-3 3.10 3.10-4 3.10-4 3.10-4a* 3.10-20* j u

Denotes New Page

4. If the CEA deviation alarms from both the computer pulse counting system and the reed. switch indication system are not available, individual CEA positions'shall be logged and misalignment' checked every 4' hours.

5. Operation of the CEA's in the automatic mode is not permitted.

B. Shutdown Margin Limits

1. When the reactor is critical, the shutdown margin will not be less than that shown in Figure 3.10-7, except during-low power physics-tests when the shutdown margin will not be less than 2% in reactivity.

2. .A trippable CEA is considered inoperable if it cannot be tripped. ..

f A CEA that cannot be driven shall be assumed not able to be tripped until it is' proven that it can bel tripped. Operation with an in-operable CEA is permitted provided:

a. The shutdown margin specified in 3.10.B.1 is' satisfied without the reactivity associated with the inoperable CEA within 2 hours of identification of the inoperable CEA.

b. Except for low power physics. tests and CEA exercises,.only one CEA is inoperable. ')

3. A'trippable CEA is considered to be a slow CEA if the drop time from I de-energizing its holding coil to reaching.90% of.its full insertion !

exceeds 2.7 seconds at operating temperature and 3 pump flow. Opera- -l tion with a slow CEA is permitted provided: '

a. The shutdown margin specified in 3.10.B.1 is satisfied without 1.5 times the reactivity associated with the slow CEA after 2.5

                               -seconds of drop time.

C. Power Distribution Limits

1. The peak linear heat rate with appropriate consideration of normal flux peaking, measurement-calculational uncertainty (8%), engineering factor (3%), increase in linear heat rate due to axial fuel.densifica-tion and thermal expansion (0.3% for Type E only) and power measure-ment uncertainty (2%) shall not exceed the -limits shown in Figure 3.10-12 as a function of core height.

Should any of these limits be exceeded, immediate action will be taken-to restore the . linear heat rate to within the appropriate limit specified in Figure 3.10-12. I Amendment No. 38, 40, 65, dd , 98 3.10-2

3 , 2. the total radial' peaking factor, . defined as Ff=Fh(1+T) q shall be evaluated at least once a month during power operation above 50% of rated l full power. 2.1 F is the latest ~availabie:unrodded radial peak determined from

                      'the,incore monitoring system for a condition where all CEAs'are at or.above the.1000 power insertion limit. T9:is given by the following expression:

T =2 (Pa-Pc)' + (Pb-Pd)' 9 (Pa+Pb .+ Pc+Pd)' where Pi is'the relative quadrant' power determined from the incore system for quadrant i, when .the incore system is operable. -If' the incore system is not operable, the' Pi are the signals .from excore detector channels 1. 2.2 If the measured value of Ff exceeds the value given in Figure 3.10-4, perform one of the following.within 24. hours: 1.' Reduce symmetric offset LC0 (Figures 3.10-9 and 3.10-10). and trip band (Figure 2.1-2), thermal margin / low pressure-trip limit (Figures 2.1-1 a and b and. Technical Specification 2.1), and excore LOCA monitoring limits (Figures 3.10-2 and 3.10-3) by a factor greater than.or equalito: [Ff measured] / [Ff Figure' 3.10-4] OR:

2. Reduce thermal power at a rate of at least 1%/ hour to bring thecombinationof-thermalpowerand.%increaseinFfto '

within the limits of. Figure 3.10-5, while maintaining CEAs at or above;the 100% power incertion limit- If incores are not operable and Fig. 3.10-2 is'in use,.then'also reduce 1 excore LOCA monitoring limit (Figure 3.10-2) by. a factor greater than or equal to: [Ffmeasured]1[FfFigure'3.10-4] _O R :-

3. Be in'a't least HOT SHUTDOWN.

       . gndmentNo.28,.N6,65,68,78, 3.10-3

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3. Incore detector alarms shall be set at least weekly. J I

Alarms will be based on.the latest power distribution obtained, so that I the linear heat rate does not exceed the linear heat rate limit defined I in Specification 3.10.C.1. If four or more coincident alarms are received, the validity of the alarms.shall be immediately determined-and, if valid, power shall be immediately-decreased below the alarm setpoint. > i 1 3.1 If the incore monitoring system becomes inopersble, perform one of tne following within 4 EFPH: q

1. Initiate a power reduction to less than or equal to P at a rate of at least 1%/ hour where P (% of rated Power) is ,

given by: l P = 0.85 x R, where R is the-minimum ratio -{ of (Linear heat. rate permitted by Specification 3.10.C.1 x 100) (Latest measured peak linear heat rate corrected to 100% Power) at any core height, while maintaining CEAs above the'100% power insertion limit ~ and monitor symmetric offset once a shift to insure that it remains within 0.05 of the value measured at the time when the above equation is evaluated. This procedure may be employed for up to 2 effective full power weeks; or

2. Comply with the LC0 given in Figure 3.10-2Lwhile maintaining the CEAs above the 100% power insertion limit. If a power reduction-is required, reduce power at a rate of at least 1%/ hour; or -

3. Comply with the LC0 in Figure 3.10-3. If a power reduction is j required, reduce power at a rate of at least 1%/ hour. )

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4. The azimuthal power tilt, Tq , 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: T4= 2 (Da-Dc)e + (Db-Dd)" (Da + Db + Dc + Dd)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. i i Amendment No. 38,#0,65,68,/S, 3.10-4 1 98 0

r 4.1 If the measured value of Tq is greater than 0.03 but less than or equal to 0.10, or an excore channel is inoperable, assure that the totalradialpeakingfactor(Ff)iswithintheprovisionsof Specification 3.10.C.2 once per shift. J 1 J l 1 l I I 1 i l J Amendment lio. 98 3.10-4 a

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Technical Versus _g Specificotton Core Height Amendment No. 98 3.10 -20 i}}

ML20215E921

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