ML19317F693
| ML19317F693 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/20/1977 |
| From: | Vassalla D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19317F691 | List: |
| References | |
| NUDOCS 8001230590 | |
| Download: ML19317F693 (5) | |
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Q THE TOLEDO EDIS0f! CO'tPANY AND 9
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THE CLEVELAND ELECTRIC ILLLHINATING C0"PMlY
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DAVIS-EESSE MUCLEAR POWER STATION, UNIT No. 1 ss
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AMEND"E!!T TO FACILITY OPERATING LICE"SE
\\s Amendment No. 1 License No. MPF-3 1.
The Nuclear Regulatory Comission (the Comission) havina found that:
A.
The facility will operate in confornity with the a>nlication, the provisions of the Act, and the rules and regulations of the Cotznission; 3.
There is reasonable assurance (i) that the activities authorize!
by this anondment can be conducted without endangering the health and safety of the public, and (ii) that such activities will he conducted in compliance with the Comission's regulations; C.
The issuance of this anendment will not be ininical to the ccmon defense and security or to the health and safety of the public; and D.
The issuance of this amendment is in acccrdance with in CF'1 Part 51 of the Connission's regulations and all a?olicable require-ments have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachnent to this license anend-ment, and paragraph 2.C(2) of facility Operating License No. !1PF-3 is hereby amended to read as follows:
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- 2.C(2) Technical Soecifications The Technical Specifications contained in Aonendices A and B, as revised through faendnant No.1, are hereby incor-porated in the license. Toledo Edison Company shall coerate the facility in accordance with the Technical S,ecifications.
3.
This license amend =ent is effective as of the date of its issuance.
FOR THE NUCLCAR REGULATORY C0" MISSION Oris!=15ia:4 'n D. B. Vassallo, Assistant Director for Light Water Reactors Division of Project anag<nent Attach: rent:
Changes to the Technical Specifications Cate of Issuance: MAY 2 01977 9
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ATTAC!aE!!T TO LICENSE AMENDHEHT NO.1 iACILITY OPERATI?!G LICENSE NO. NPF-3 DCCKET NO. 50-346 Replace the following pages of the Appendix "A" TecSnical Specifications with the enclosed cages. The revised pages are identified by Amendnent ntsaber and contain vertical lines indicating the area cf change. The corresponding overleaf pages are also provided to nt r ;in document i
completeness.
Pages 3/4 4-2 3/4 4-3 9
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3/4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT LOOPS LIMITING CONDITION FOR OPERATION 3.4.1 Both reactor coolant loops and both reactor coolant pumps in each -
loop shall be in operation.
APPLICABILITY: As noted below, but excluding MODE 6.*
ACTION:
MODES 1-and 2:
With one reactor coolant pump not in operation, STARTUP and a.
POWER OPERATION may be initiated and may proceed provided THERMAL POWER is restricted to less than 80.7", of RATED THERMAL POWER and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the setpoints for the following trips have been reduced to the values specified in Specification 2.2.1 for operation with three reactor coolant pumps operating:
1.
High Flux 2.
Flux-aFlux-Flow b.
With one reactor coolar.t pump in each loop not in operaticn, STARTUP and POWER OPERATION may be initiated and may proceed provided THERMAL POWER is restricted to less than 53.0". of RATED THERMAL POWER and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the setpoints for the following trips have been reduced to the values specified in Specification 2.2.1 for operation with one reactor coolant pump operating in each loop:
1.
High Flux 2.
Fl ux-tJ' ux-Fl ow
- See Special Test Exception 3.10.3.
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V DAVIS-BESSE, UNIT 1 3/4 4-1
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REACTOR C'0LANT SYSTEM 0
LIMITING CONDITION FOR OPERATION (Continued)
MODES 3, 4 and 5:
Operation may proceed provided at least one reactor coolant loop a.
lM is in operation with an associated reactor coolant pump or decay heat removal pump.*
15 b.
The provisions of Specifications 3.0.3 and 3.0.4 are not aoplicable. W 4
D.
SURVEILLANCE REQUIREMENTS 4.4.1 The Reactor Protective Instrumentation channels specified in the applicable ACTION statement above shall be verified to have had thei-trip setpoints changed to the values specified in Specification 2.2.1 for the applicable number of reactor coolant pumps operating either:
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> af ter switchirg to a different pump combination a.
if the switch is made while operating, or Prior to reactor cri icality if the switch is made while shutdown.
t b.
- All reactor coolant pumps and decay heat removal train pumps may be de-energized for up to one (1) hour to accommodate decay heat removal pump switching operations, provided no operations are permitted which could cause dilution of the reactor coolant system boron concentrations.
CaVis-Rih 1E. UN!T 1 3/4 4-2
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