ML20087J402

Proposed Tech Specs 1.7 & 3/4.6.3,reflecting Relocation of TS Table 3.6-1 to WCGS Plant Procedure,Per GL 91-08

ML20087J402
Person / Time
Site:	Wolf Creek
Issue date:	08/16/1995
From:	WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20087J395	List: ML20087J391 ML20087J402
References
GL-91-08, GL-91-8, NUDOCS 9508210135
Download: ML20087J402 (3)

Text

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Attrchment III.to ET 95-0065 Page 1 of 3 ATTACHMENT I REVISED PROPOSED TECHNICAL SPECIFICATION CHANGES l

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4 9508210135 950916 PDR ADDCK 05000482 P

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i i-i Attnchment III to ET 95-0065 l

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CONTAINMENT SYSTEMS h

J 3/4 8.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION

' 3.6.3 Each The-containment isolation valvec eg&d !- Tebb 3.S 1 shall be OPERABLE.1 wits ! chtha tWd e ehee-t- T255 3.s 4 I

APPLICABILITY: MODES 1,2,3, and 4.

ACTION':

l' With one or more ohntainment isolation valve (s) SW5-d != T255 3.s A inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and:

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a. Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />,

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b. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position,2 or

c. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange, or

d. 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 />.

e. The provisions of Specification 3.0.4 do not apply.

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SURVEILLANCE REQUIREMENTS l

4.6.3.1 Each The-power-operated or automatic containment isolation valvec eperSd != Tebb 3.6-1 shall be demonstrated OPERABLE prior to retuming the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, codrol or power circuit by performance of a cycling test, and verification of isolation time.

l 1 'For valves with excessive leakage, refer to Technical Specification 3.6.1.2. Locked or sealed closed valves may be opened on an intermittent basis under administrative control.

2.' After satisfying this action statement, the motor operated valves associated with reactor coolant pump seal cooling, EG HV-58,59,60,61,62,127,130,131,132, and 133, may be energized and cycled for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to conduct a ny actuator diagnostic evaluations which may be required to restore the valve to an OPERABLE cotidition.

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WOLF CREEK-UNIT 1 3/4 6-16 Amendment No. 33

AttOchment III to ET 95-0065 Page 3 of 3 DEFINITIONS CONTAINMENT INTEGRITY 47 CONTAINMENT INTEGRITY shall exist when:

a.

All penetrations required to be closed during accident conditions are either-1)

Capable of being closed by an OPERABLE containment automatic isolation valve system, or 2)

Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except = pic';!'M !a Te5 3.6 -1 cf ?#9^- 313. for valves that are open under

i administrative control as permitted by Specification 3.6.3.

b.

All equipment hatches are closed and sealed, c.

Each air lock is in compliance with the requirements of Specification 3.6.1.3, I

d.

The containment leakage rates are within the limits of Specification 3.6.1.2, and e.

The sealing mechanism associated with each penetration (e.g., welds, bellows, or O-rings) is OPERABLE.

CONTROLLED LEAKAGE

'i 1.8 CONTROLLED LEAKAGE shall be that seal water flow from the reactor coolant pump seals.

CORE ALTERATION 1.9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.

CORE OPERATING LIMITS REPORT 1.10 The CORE OPERATING LIMITS REPORT (COLR)is the unit-specific document that provides core operating limits for the current operatir:g reload cycle. These cycle-specific core operating limits shall be l

determined for each reload cycle in accordance with Specification 6.9.1.9. Plant operation within these i

operating limits is addressed in individual Specifications.

_s WOLF CREEK-UNIT 1 1-2 Amendment No. 64 i

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