ML20039C210

Amend 60 to License DPR-36,revising Tech Specs in Support of Cycle 6 Steamline Break Analyses & by Restructuring Certain Sections for Clarification Purposes

ML20039C210
Person / Time
Site:	Maine Yankee
Issue date:	12/11/1981
From:	Clark R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20039C209	List: ML20039C208 ML20039C210 ML20039C211 ML20039C212
References
NUDOCS 8112290061
Download: ML20039C210 (10)

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[,i.r..,g/ j U.' :T D STATES NUCLEAR REGULATORY COMMISSION

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wAsmscTom. o. c. 20sss MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309

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MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendmentho.60 License No. OPR-36 1.

The Nuclear Regulatory Comission (the Commission) has found that:

A.

The soplication for amendment by Maine Yankee Atomic Power Company (the licensee) dated November 18, 1981, 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; 3.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulaticns of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amencment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in comoliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common 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 apolicable requirements have been satisfied.

8112290061 811211 PDR ADOCK 05000309 P

PDR

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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 Operating License No. OPR-36 is hereby amended to read as follows:

(b) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 60, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective upon issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 5

Rober: A. Clark, Chief Operating Reactors Branch #3 Division of Licensing Attachments:

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Changes to the Technical Specifications Date of Issuance:

December 11, 1981 6

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ATTACHMENT TO LICENSE AMEN 0 MENT NO. 60 TO FACILITY OPERATING LICENSE NO. DPR-36 DOCVET NO. 50-309 Revise Appendix A as follows:

Remove Pages Insert Pages Table of Contents - 1 Table of Contents - 1 3.6-1 3.6-1 3.6-2 3.6-2 3

3.6-3 3.10-1 s-9 3.10-9 3.10-15 4

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TECHNICAL SPECIFICATIONS Table of Contents 1-2 I

Definitions

Page, 1.1 Fuel Storage 1.1-1 1.2 Site Description 1.2-1 1.3 Reactor 1.3-1 1.4 Containment 1.4-1 2.0 Safety Limits and Maximum Safety Settirgs 2.1 Limiting Safety Settings Reactor Protection System 2.1-1 2.2 Safety Limits - Reactor Core 2.2-1 2.3 Safety Limits - Reactor Coolant System Pressure 2.3-1 3.0 Limiting Conditions for Operation 3.0-1 3.1 Incore Instrumentatte:

3.1-1 1

3.2 Reactor Coolant System Activity 3.2-1 3.3 Reactor Coolant System Operational Components 3.3-1 3.4 Combined Heat-up, Cooldoen and Press-Temp. Limits 3.4-1 3.5 Chemical and Volame Control System 3.5-1 3.6 Emergency Core Cooling and Containment Spray Systems 3.6-1 l

3.7 Boron and Sodium Hydroxide Available for Containment i

Spray System 3.7-1 l

3.8 Reactor Core Energy Removal 3.8-1 3.9 Operational Safety Instrumentation and Control Systems 3.9-1 3

1 3.10 CEA Group and Power Distribution Limits 3.10-1 3.11 Containment 3.11-1 3.12 Station Service Power 3.12-1 1

3.13 Refueling Operations 3.13-1 3.14 Primary System Leakage 3.14-1 3.15 Reactivity Anomalies 3.15-1 3.16 Radioactive Liquid Waste Release 3.16-1 j

3.17

_ Radioactive Gaseous Waste Release 3.17-1 3.18 Chemistry 3.18-1 3.19 Safety Injection Valving 3.19-1 3.20 Shock Suppressors 3.20-1 3.21 Steam Generators 3.21-1 3.22 (Reserved) 3.22-1 3.23 Fire Protection Systems 3.23-1 3.24 Secondary Coolant Activity 3.24-1 j

4.0 Surveillance Requirements 4.u-l j

4.1 Instrumentation and Control 4.1-1 4.2 Equipment and Sampling Tests 4.2-1 4.3 Reactor Coolant System Leak Tests 4.3-1 4.4 Containment Testing, 4.4-1 l

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Amendment No. 60

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3.6 EMERCEPCY CCRE COCLIPC ANO CCNTAIf4ENT SPRAY SYSTENS Acolicability:

Applies to the ccerating status of the emergency ccre ecoling and contal.- snt spray systems.

Obiective:

To cefine the conditions under which ccmponents of the emergency core cooling and containment spray systems must be operable.

Scecification:

A.

The following eouipment must be operable whenever the reactor coolant system temperature and pressure exceed 2100F and 400 psig:

1.

Two safety injection tanks set for automatic initiation. Each tank shall contain 11,200 + 500 gallons of water borated to at least 1720 ppm and pressurized with nitrogen to 230 psig + 10 psi,

- 25 csi.

2.

One operable ECCS train consisting of the following subsystems of the train. Each subsystem includes the manual valves that are aligned and locked in the position recuired for safeguards operation, the automatically cperated valves set for automatic cperation or aligned and locked in the position recuired for safeguards operation, the controls set for automatic initiaticn where appropriate, and a pump powered from an engineered safeguards bus.

a.

One service water pump subsystem b.

Cne component cooling pump subsystem c.

One low pressure safety injection pump subsystem d.

One high pressure safety injection pump subsystem f.

One containment spray pump and RHR heat exchanger subsystem 3.

Station service power in accordance with Technical Specification 3.12 supplying the same cperable ECCS train as in (2) acove.

4 The refueling water storage tank filled and available in accordance with Technical Specification 3.7-.

5.

The fill header motor operated rcot valves to two Iceps.

Excectien: The recuirements may be modified with regard to the position of controls and valves during periods of hycrostatic testing. l Femedial Action: Restore recuired limiting ccndition within fcur hcurs or place the plant in a Hot Shutdown coedition within the next 6 hcurs and in a Cold Shutdown ccndition witnin the folicwing 24 l

hcurs.

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l Araendment No-. 60

• 3.6-1 l

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B.

Whenever the reactor coolant system baron ccncentration is less than that recuired for hot shutdown condition, two high pressure safety i

'njection pump subsystems shall be operable.

C.

The follcwirg eculpment must ce cperable whenever the reacter is in a j

ocwer cperation condition.

1.

Three safety injection tanks set for automatie initiation and subject to the conditions specified in A.1 above.

j 2.

Two operable and redundant ECCS trains, each train censisting of the subsystems specified in A.2 above.

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3.

Station service power in accordance with Technical Specificatien l

3.12.

4 The refueling water storage tank and the spray chemical addition tank filled and available in accordance with Technical j

Specification 3.7.

5.

The fill header motor cperated root valves to three 1 cops.

.Exceotiens:

1.

If any of the component subsystems specified in B and C.2 above i

becomes incperable continued power operations is permitted for a maximum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided the ccmponent subsystem performing i

the name function in' the other train are operable.

In this I

situation the operable subsystem and its diesel generator snall be tested within two hours after discovery of the cutage.

2.

If any of the fill header motor coerated root valves becomes inoperable continued power cperation is permitted for a maximum of 72 hcurs provided both of the remaining rcot valves are tested ccerable within two hours after discovery of the outage.

l 3.

One safety injection tank may be isolated for a period not to 1

exceed one hour.

4 If one of the safety injection tanks is found not to be within scecificatiens it shall be restored to specification within four hcurs.

Remedial Action: Restore recuired limiting ccndition within grace perica specified or place the plant in a Hot Shutdown ccndition within the next 6 hcurs and in a Cold Shutdown condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i Basis:

Adecuate core ecolirg and containment scray is provided for the entire j

break scectrum uo to and incruding the design basis accident. This 1

protection covers all moces of coeraticn frcm shutcown to full ccwer.

At full ocwer minimum recuired safety injection includes three (3) r l

ccerable safety injecticn tanks,..and_t%o complete ECCS trains censisting l.

of the ecuicment specified in A.2,.A.3 and A.4 abcve. The accicent analysis censiders that caly 2/3 of the cacacity of the ccerable 'ecu'i;; ment is effective for core ccolirge

' Amendment No. 60

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Containment peak accident pressure is maintained below design pressure and subsequent containment cooling requirements are adequate if one of the two containment spray pumps is operable.

Specification A provides a pressure and temperature limit above which ECCS must be operable.

It recognizes the greatly decreased probability of a loss of coolant accident and the negligible amount of energy stored in the primary coolant.

Specification B ensures that a sufficient quantity of boron can be injected by the ECCS to maintain the reactor suberitical following the most limiting main steam line break accident with the concurrent failures of the highest worth CEA stuck out of the core and the failure of one HPSI pump subsystem to function.

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3.10 CEA CROUP. POWER DISTRIEUTICN. 90CERATOR TOwPERATURE COEFFICIENT LIMITS AND COOLANT CONDITICNS Acolicabilitv:

acclies to inserti:n c' CEA greucs and peak lii'.est heat rata during cceration.

Objective:

To ensure (1) core subcriticality after a reactor trip, (2) limited potential reactivity insertions from a hypothetical CEA ejection, and (3) an acceptable core power distribution, moderator temcerature coefficient, core inlet temperature, and reactor coolant system pressure during power oceration.

Scecification:

A.

CEA Insertion Limits 1.

When the reactor is critical, except for physi:s tests and CEA exercises, the shutdown CEA's (Groups A, 8 ar,d C) shall be fully withdrawn and the regulating CEAS (groups 1 through 5) shall be no further inserted than the limits shown in Figure 3.10-1 for 3 lecp operation.

2.

CEA's shall be censidered fully withdrawn when positioned such that:

a.

the rods are inserted within A steps from their upper electrical limit when the RCS boren concentration is greater than 100 ppm or b.

the rods are at their upcer electrical limit when the RCS baron cencentration is less than or ecual to 1C0 ppm.

3.

When the reactor is critical, the shutdown margin with one CEA stuck out will not be less than that shcwn in Figure 3.10-7.

During low power chysics testing at the beginning of a cycle, CEA insertien is permitted such that the minimum shutdown margin is no less than 2% in reactivity.

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

8.

Power Distribution Limits 1.

The peak linear heat rate with apprcpriate censideraticn of normal flux peaking, measurement-calculational uncertainty (8%),

engineerirg factor (3%), increase in lirear heat rate due to axial fuel densificaticn and thermal excansion. (0.3% for Types E, G, H &

I cnly) and pewer measurement uncertainty (2%) shall not exceed:

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Technical Versus 3.10-7 Specification RCS Boron Concentration 3.10-15 Amen'dment No. 60

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