ML20086S057

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Revised Tech Specs 3.4.6.3 Re Limiting Condition for Operation for Containment Isolation Valves & 3/4.7.1 Re Limiting Condition for Operation for Safety Valves
ML20086S057
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 12/20/1991
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20086S050 List:
References
NUDOCS 9201030029
Download: ML20086S057 (4)
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Text

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REVISED TECHNICAL SPECIFICATION CllANGES-

-9201030029 911220

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CONTAINMENT SYSTEMS-3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3.1 The containment isolation valves specified in Table 3.6-1 shall be OPERABLE with isolation times as shown in Table 3.6-1.

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

ACTION:

With one or more of the isolation valve (s) specified in Table 3.6-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either 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 />, or 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, or c.

Isolate the 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 11 angel 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 />.

I SURVEILLANCE REQUIREMENTS 4.6.3.1.1 The isolation valves specified in, Table 3.6-1 shall-be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator. control or power circuit by performance of a cycling test and verification of isolation time.

ARKANSAS - UNIT 2 3/4,6-16 Amendment. No. 121, 3

3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITINO CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves shall be OPERABLE with lift settings as specified in Table 3.7-5.

APPLICABILITY:

MODES 1, 2 and 3*.

ACTION:

a.

With both reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2, and 3 may proceed provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Linear Power Levol-High trip setpoint is reduced per Table 3.7-1; otherwise, 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 />, b.

With one reactor coolant loop and associated steam generator in operation and with one or more main steam line code safety valves associated with the operating steam generator inoperable, operation in MODES 1, 2 and 3 may proceed provided:

.1.

That at least 2 main steam line code safety valves on the non-operating steam generator are OPERABLE, and 2.

That within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is-restored to OPERABLE status or the Linear Power Level-High trip setpoint is reduced per Table 3.7-2: otherwise 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 />.

SURVEILLANCE REQUIREMENTS 4.7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.5.

  • Except that during hydrostatic testing in Mode 3 eight of the main steam line code safety valves may be gagged and two (one on each header) may be reset for the duration of the test to allow the required-pressure for the test to be attained. The Reactor Trip Breakers shall be open for the duration of the test.

ARKANSAS - UNIT 2 3/4 7-1 Amendment No. 83, j

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4 ELECTRICAL POWER SYSTEMS CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEV{CES LIMITING CONDITION FOR OPERATION 3.8.2.5 All containment penetration conductor overcurrent protective devices shown in Tabic 3.8-1 shall be OPERABLE.

APPLICABILITY:

MODES 1, 2. 3 and 4.

ACTION:

With one or more of1the containment penetration conductor overcurrent protective devices-shown in Table 3.8-1' inoperable:

De-energize the circult(s) by tripping the associated backup a.

circuit breaker within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and; verifying the_ backup circuitL l

breaker to be tripped at least once per 7_ days thereafter, or.

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b.

Be in at' least 110T. 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 />.

SURVEILLANCE REQUIREMENTS 4.8.2.5 All containment penetration conductor overcurrent protective devices shown in Table 3.8-1 shall be demonstrated OPERABLE in accordance with the manufacturers': recommendations:

LAt least once per 18 months:

a.

1.

For-at least.one 6.9 kV reactor coolant pump circuit, such

Sat all reactor coolant pump circuits are demonstrated

' OPERABLE-at least once-per 72 months,--by performance of -

(a)

A CRANNEL CAL 1BRATION of the asso iated protective relays,'and-(b); An integrated system functici.a1 test which; includes-

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simulated automatic _actuatior:'af;the system-and verifying that'each relay and associated circuit-

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breakers and control circuits function ~as_ designed.

i f5 l

ARKANSAS - UNIT 2-3/4 8-11

-Amendment No. :8C m.

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