ML17331A979

Proposed Tech Specs Replacement Page 3/4 5-5 of AEP:NRC:1181 Attachments 1 & 3 Re Surveillance Interval Extension Withdrawal for Unit 2 Cycle 9

ML17331A979
Person / Time
Site:	Cook
Issue date:	09/28/1993
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17331A978	List: ML17331A977 ML17331A979
References
NUDOCS 9310010214
Download: ML17331A979 (5)

Text

Replace Page 3/4 5-5 of AEP:NRC:1181, Attachment 2 (proposed T/Ss) with the following page:

9310010214 930928 PDR ADOCK 05000316 PDR,,

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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued d0 At least once per 18 months by:

Verifying automatic isolation and interlock action of the RHR system from the Reactor Coolant System when the Reactor Coolant System pressure is above 600 psig.

2. A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.t

e. At least once per 18 months, during shutdown, by:t

1. Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection test signal.

2. Verifying that each of the following pumps start auto-matically upon receipt of a safety injection test signal:

a) Centrifugal charging pump b) Safety injection pump c) Residual heat removal pump By verifying that each of the following pumps develops the indicated discharge pressure on recirculation flow when tested pursuant to Specification 4.0.5:

1. Centrifugal charging pump Greater than or equal to 2405 psig

2. Safety Injection pump Greater than or equal to 1409 psig

3. Residual heat removal pump Greater than or equal to 190 psig go By verifying the correct position of each mechanical stop for the following Emergency Core Cooling System throttle valves:

1. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS sub-systems are required to be OPERABLE.

t The provisions of Technical Specification 4.0.8 are applicable.

COOK NUCLEAR PLANT UNIT 2 3/4 5-5 AMENDMENT NO. &7 i 99, 43k, 434

Replace Page 3/4 5-5 of AEP:NRC:1181, Attachment 3 (marked up T/Ss) with the following page:

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued

d. At least once per 18 months by:

1. Verifying automatic isolation and interlock action of the RHR system from the Reactor Coolant System when the Reacto'r Coolant Sy'tem pressure is above 600 psig.

2. A visual inspection of the containment \ sump and verifying that the subsystem suction inlets are.not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.f

e. At least. once per 18 months, during shutdown, by: $

1. Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection test signal.

2. Verifying that each of the following pumps start auto-matically upon receipt of a safety injection test signal:

a) Centrifugal charging pump .

b) Safety injection pump c) Residual heat removal pump By verifying that each of the following pumps develops the indicated discharge pressure on recirculation flow when tested pursuant to Specification 4.0.5:

1. Centrifugal charging pump Greater than or equal to 2405 psig

2. Safety Injection pump Greater than or equal to 1409 psig

3. Residual heat removal pump Greater than or equal to 190 psig g By verifying the correct position of each mechanical stop for the following Emergency Core Cooling System throttle valves:

1. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion'f each valve stroking operation or maintenance on the valve when the ECCS sub-systems are required to be OPERABLE.

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COOK NUCLEAR PLANT - UNIT 2 3/4 5-5 AMENDMENT NO.97~

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