ML17346A920

Corrected Tech Spec Pages 3.10-1,3.10-2 & 3.10-4 Re Refueling Operations

ML17346A920
Person / Time
Site:	Turkey Point
Issue date:	03/28/1985
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17346A919	List: ML17346A918 ML17346A920
References
NUDOCS 8504020297
Download: ML17346A920 (6)

Text

3.10 REFUELING OPERATIONS 3.10.1 CONTAINMENTBUILDINGPENETRATIONS The containment building penetrations shall be in the following status:

a) The equipment door closed and held in place by a minimum of four bolts, b) A minimum of one door in each air lock is closed, and c) Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either+:

1) Closed by an isolation valve, blind flange, or manual valve, or

2) Be capable of being closed by an OPERABLE automatic containment ventilation isolation valve.

+Exception may be taken under Administrative Controls for opening of certain valves and airlocks necessary to perform surveillance or testing requir ements.

APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building.

3.10.2 CONTAINMENTVENTILATIONISOLATION SYSTEM The Containment Ventilation Isolation System shall be OPERABLE.

APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.

ACTION:

a) With the Containment Ventilation Isolation System inoperable, close each of the Containment Ventilation System penetrations providing direct access from the containment atmosphere to the outside atmosphere.

b) The provisions of Specifications 3.0.1 and 3.0.0 are not applicable.

3.10.3 INSTRUMENTATION As a minimum, two Source Range Neutron Flux Monitors shall be OPERABLE, each with continuous visual indication in the control room and one with audible indication in the containment.

APPLICABILITY: MODE 6 8504020297 850328 PDR ADOCK 05000250 P PDR 3.10-1 Amendment Nos. and

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ACTION:

a) With one of the above required monitors inoperable or not operating, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

b) With both of the above required monitors inoperable or not operating, determine'the boron concentration of the Reactor Coolant System at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3.10'ADIATION MONITORING The containment radiation monitors which initiate containment and control room ventilation isolation shall be OPERABLE.

APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.

ACTION:

a) With one or both radiation monitors inoperable, operation may continue provided the containment ventilation isolation valves are maintained closed.

b) With one or both radiation monitors inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> isolate the Control Room Ventilation System and initiate operation of the Control Room Ventilation System in the recirculation mode.

3.10.5 DECAY TIME The reactor shall be subcritical for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.

APPLICABILITY: During movement of irradiated fuel in the reactor vessel.

ACTION:

With the reactor subcritical for less than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, suspend all operations involving movement of irradiated fuel in the reactor vessel.

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3.10.6 COMMUNICATIONS Direct communications shall be maintained between the control room and personnel at the refueling station.

APPLICABILITY: During CORE ALTERATIONS.

ACTION:

When direct communications between the control room and personnel at the refueling station cannot be maintained, suspend all CORE ALTERATIONS.

3.10-2 Amendment Nos. and

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a) A Keff of 0.90 or less, or b) A boron concentration of greater than or equal to 1950 ppm.++

APPLICABILITY: MODE 6+

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 05 gpm of a solution containing greater than or equal to 1950 ppm boron or its equivalent until jeff is reduced to less than or equal to 0.90 or the boron concentration is restored to greater than or equal to 1950 ppm, whichever is the more restrictive.

+The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

+ "The boron concentration of the reactor Coolant System and the refueling canal shall be determined by chemical analysis at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.10.9 CRANE TRAVEL-SPENT FUEL STORAGE AREAS HEAVY LOADS shall be prohibited from travel over fuel assemblies in the storage pool.+

"Exception may be taken for the temporary construction crane to be used for the re-rack operation which may be carried over irradiated fuel to facilitate installation of the crane. Lift rigs which meet the design and operational requirements of NUREG 0612 "Control of Heavy Loads at Nuclear Power Plants" will be used while performing this installation.

APPLICABILITY: With fuel assemblies in the storage pool.

ACTION:

a) With the. requirements of the above specification not satisfied, place the crane load in a safe condition.

b) The provisions of Specification 3.0.1 and 3.0.0 are not applicable.

3.10-0 Amendment Nos. and

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