ML20136B797

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Amend 90 to License DPR-3, Modifying Tech Specs to Define Limiting Conditions for Operation & Surveillance Requirements to Limit ECCS Leakage to 50 Gallons Per Day
ML20136B797
Person / Time
Site: Yankee Rowe
Issue date: 12/16/1985
From: Lear G
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20136B795 List:
References
NUDOCS 8601020921
Download: ML20136B797 (7)
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Text

  1. UNITED STATES 8  % NUCLEAR REGULATORY COMMISSION g E WASHINGTON, D. C. 20555

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YANKEE ATOMIC ELECTRIC COMPANY YANVEE NUCLEAR POWER STATION DOCKET N0. 50-29 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 90 License No. DPR-3

l. 1. The Nuclear Regulatory Comission (the Comission) has found that:

l A. The application for amendment by Yankee Atomic Electric Company (the licensee) dated May 7,1985 complies with the standards and requirements of the Atomic Energy Act of 1954,

, as amended (the Act), and the Comission's rules and regulations 8

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 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 compliance 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 i 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.

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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.C.(2) of Facility Operating License No. OPR-3 is hereby amended to read as follows:

(2) Technical Specifications

! The Technical Specifications contained in Appendix A as revised through Amendmert No. 90, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 2,

f Geor Lear, Director PWR Project Directorate #1 Division of PWR Licensing-A Attachrer.t:

Changes to the Technical Specifications Date of Issuance: December 16, 1985 Il t-(

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ATTACHMENT TO LICENSE AMENDMENT N0.90 FACILITY OPERATING LICENSE NO. OPR-3 ,

DOCKET NO. 50-29 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area

, of change. Overleaf pages (*) have been provided to maintain document completeness.

l REMOVE INSERT ,

3 V V IX

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X X 3/4 5-13 B3/4 5-3

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9 INDEX LIMIT 1hG CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE MAIN COOLANT *hYSTEM_ (Continued) '

3/4.4.6 CHEMISTRY.............................................. 3/4 4-12 .

3/4.4.7 SPECIFIC ACTIVITY......................................

3/4 4-15 3/4.4.8 PRESSURE / TEMPERATURE LIMITS -

Main Coolant System.................................... 3/4 4-19 Pressurizer........................................,... 3/4 4-26 3/4.4.9 JTRUCTURAL INTEGRITY................................... 3/4 4-26 3/4.4.10 STEAM GENERATORS....................................... 3/4 4-32 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 A C C UMUL ATOR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .3/4 . . . 5-1

.....- 1 3/4.5.2. ECCS SUBSYSTEMS........................................ 3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS........................................ 3/4 5-9 3/4.5.4 SAFETY INJECTION TANK.................................. 3/4 5-12

3/4.5.5 ECCE SUBSYSTEM LEAKAGE................................. 3/4 5-13' 3/4.6 CONT INMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT 1

Con ta i nme n t I n teg ri ty. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-1

' Cont'a f nment Lea ka ge . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-2 i

. Containment Air Lock................................... 3/4 6-4 s Internal Pressure...................................... 3/4 6-5

, ( i r T em pe ra t u re . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-6 acontainment Vessel Structural Integrity................ '

l 3/4 6-7 l

Continuous Leak Monitoring Syster....................... 3/4 6-8 l 3.'4. 6. 2 CONTAINMENT ISOLATION VALVES........................... '

! 3/4 6-9 n ,

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YANKEE-ROWE

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V AmendmentNo.'Af6.54.A7.

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i INDEX .'

BASES SECTION PAGE 3/4.0 APPLICABILITY............................................. B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTR0L........................................ B 3/4 1-1 3 / 4.1. 2 .BO RAT I ON SYST EMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 1-3 3/4.1.3 MOVABLE CONTROL R0DS.................................... B 3/4 1-4 1

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 PEAK LINEAR HEAT GENERATION RATE. . . . . . . . . . . . . . . . . . . . . . . . B 3/4 2-1 3/4.2.2 and 3/4.2.3 NUCL' EAR HEAT FLUX AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACT 0RS............................... B 3/4 2-2 3/4.2.4 DNB PARAMETERS.......................................... B 3/4 2-3

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3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE SYSTEM INSTRUMENTATION............... B 3/4 3-1 3/4.3.2 ENGINEERED SAFEGUARDS SYSTEM INSTRUMENTATION............ B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION.............................. B 3/4 3-1 YANKEE-ROWE IX

INDEX BASES SECTION PAGE 3/4.4 MAIN COOLANT SYSTEM 3/4.4.1 MA I N C OO L ANT L 00 PS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-1 3/4.4.2 and 3/4.4. 3 S AFETY YALV ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-1 3/4.4.4 PRESSURIZER............................................. B 3/4 4-2 3/4.4.5 MAIN COOL ANT SYST EM L EAKAGE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4.-3 3/4.4.6 CHEMISTRY............................................... B 3/4 +-5 3/4.4.7 SPECIFIC ACTIVITY....................................... B 3/4 4-5 3/4.4.8 PRESSURE /T EMPERATURE LIMITS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-6 3/4.4.9 STRUCTU RAL I NTEGRI TY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-11 3/4 .4 .10 STEAM GENE RATORS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/t. 4-12 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATOR............................................. B 3/4 5-1 3/4.5.2 a nd 3/4. 5.3 ECCS SUBSYST EMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 5-1

'3/4.5.4 S AF ETY IN J ECTION TANK . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 5-2 l 3/4.5.5 ECCS SUBSYSTEM LEAKAGE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 5'-3 1

I YANKEE-ROWE X AmendmentNo.#f.90 i

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EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEM LEAKAGE LIMITINC CONDITION FOR OPERATION 3.5.5 The ECCS subsystem leakage outside containment shall be limited to 50 spd.

APPLTCABILITY Modes 1. 2, 3, and 4.

ACTION With ICCS subsystem leakage greater than the above limit, reduce the leakage rate to less than the limit within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

$URVIILLANCE RKOUIREMENTS 4.5.5 Verify BCCS subsystem leakage outside containment is below the limit concurrent with specification 4.5.2.a. including the following subsystems:

a. The operating HPSI pump.
b. The operating LPSI pump.
c. The non-operating safety injection pumps.

l d. The accessible recirculation subsystem flow path from the containment l ' sump through the safety injection pumps to the safety injection 1

header.

e. The accessible long-tern hot les injection flow path from the safety injection pumps to the boron injectica flow path,
f. The accessible flow path taking suction from the safety injection tank.

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1 YANKEE-ROWE  % '. 5-13 Amenttrent N, . 90 i.

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3/4.5.5 ECCS SUBSYSTEM LEAKAGE BASIS The limiting condition on CCCS subsystem leakage outside containment insures that the off-site doses for the design basis LOCA. including ECCS leakage contribution, will be less than the limits of IOCFR100.

YANKEE-ROWE B 3/4 5-3 Amendment No. 90

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