ML20138B912

Proposed Tech Specs,Revising TS 3/4.9.4 Containment Bldg Penetrations & Associated Bases Section to Allow Selected Containment Isolation Valves to Be Opened Under Administrative Controls During Periods of Core Alterations

ML20138B912
Person / Time
Site:	Wolf Creek
Issue date:	04/23/1997
From:	WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20138B905	List: ML20138B901 ML20138B912
References
NUDOCS 9704290304
Download: ML20138B912 (3)

Text

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. 1 Attachment IV to ET 97-0028 Page 1 of 3

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ATTACHMENT IV

! PROPOSED TECHNICAL SPECIFICATION CHANGES l

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. 9704290304 970423

PDR ADOCK 05000482

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Attachment IV to ET 97-0028 Page 2 of 3 REF!UELING OPERATIONS 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 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 the emergency airlock is closed *, and one door in the personnel airlock is capable of being 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 approved functional equivalent, or

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

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d. Penetration P-63 (Service Air valves KA V-039 and KA V-118) and Penetration P-98 (Breathing Air valves KB V 001 and KB V-002) may be opened under administrative controls.

APPLICABILITY: During CORE ALTERATIONS or movement ofirradiated 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 _ _ _ _ . __ _ _ _ _ _ _ _ _ _

fuelin the containment building.

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SURVEILLANCE REQUIREMENTS 4.9.4 Each of the above required containment building penetrations shall be determined to be either in its required condition or capable of being closed by an OPERABLE automatic containment purge isolation valve within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment building by:

a. Verifying the penetrations are in their required condition, or

b. Testing the containment purge isolation valves per the applicable portions of Specification 4.6.3.2.

t *An emergency escape hatch temporary closure device is an acceptable j replacement for the airlock door.

1 WOLF CREEK - UNIT 1 3/4 9-4 Amendment No. M PC %

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e Attachment IV to ET 97-0028 i Page 3 of 3 l REEUELING OPERATIONS BASES l

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS a

Both containment personnel airlock doors may be open during movement of irradiated fuel or CORE ALTERATIONS, provided one airlock door is capable of

{ being closed and the water level in the refueling pool is maintained as required. Service Air valves KA V-039 and KA V 118 (Containment penetration P-63) and Breathing Air valves KB V-001 and KB V-002 (Containment penetration P-98) may be opened under administrative controls during movement of irradiated fuel or j CORE ALTERATIONS to provide air services to the reactor building to support outage

activities. Administrative controls ensure that 1) appropriate personnel are j aware of the open status of the containment during movement of irradiated fuel l or CORE ALTERATIONS,2) specified individuals are designated and readily aveilnble to close the airlock or the service air and breathing air valves following i an evacuation that would occur in the event of a fuel handling accident, and j 3) any obstructions (e.g., cables and hoses) that could prevent rapid closure of j an open airlock can be quickly removed.

l l Equivalent isolation methods for the emergency personnel escape lock and containment wall penetrations ensure releases from containment are prevented for credible accident scenarios. The isolation techniques must be approved by an engineering evaluation and may include use of a material that can provide a temporary, pressure tight seal capable of maintaining the integrity of the penetrations and airlock to restrict the release of radioactive material from a fuel element rupture.

3/4.9.5 DELETED 3/4.9.6 DELETED 3/4 9.7 DELETED 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor vessel below 140*F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the core to minimize the effect of a boron dilution incident and prevent boron stratification. The minimum of 1000 gpm allows flow rates which provide additional margin against vortexing at the RHR pump suction while in a reduced RCS inventory condition.

Addition of borated water with a concentration greater than or equal to the minimum required RWST concentration but less than the actual RCS boron concentration shall not be considered a reduction in boron concentration.

The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of RHR capability, With the reactor vessel head removed and at least 23 feet of water above the reactor vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR bop, adequate time is provided to initiate emergency procedures to cool the core.

WOLF CREEK - UNIT 1 B 3/4 9-2 Amendment No. 35, SG,96 l