ML20137B914
| ML20137B914 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek |
| Issue date: | 03/18/1997 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20137B901 | List: |
| References | |
| NUDOCS 9703240101 | |
| Download: ML20137B914 (2) | |
Text
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f Attachment. IV to ET 97-00* 3 Paga 1 of 2 h
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' ATTACHMENT IV PROPCSED TECHNICAL SPECIFICATION CHANGES 1
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9703240101 970318 PDR. ADOCK 05000482' p-PDR g
1 Attachm:mt IV to ET 97-0013 Ptga 2 of 2 a
EMERGENCY CORE COOLING SYSTEMS
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SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
- a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated positions with power to the valve operators removed:
Valve Number Valve Function Valve Position BN-HV-8813 Safety injection to Open RWST Isolation Viv EM-HV-8802A(B) S1 Pump Discharge Closed Hot Leg iso Vivs EM-HV-8835 Safety injection Open Cold Leg Iso Valve EJ-HV-8840 RHR/SI Hot Leg Closed Recirc Iso Valve EJ-HV-8809A RHR to Accum inj Open Loops 1 & 2 Iso V:v EJ-HV-88098 RHR to Accum inj Open Loops 3 & 4 iso Viv
- b. At least once per 31 days by:
- 1) Verifying that the ECCS piping is full of water by venting the ECCS pump casings and accessible discharge piping high points, and
- 2) Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
- c. By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visualinspection shall be performed:
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- 1) For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and
- 2) At least once daily Gof the areas affected within containment et the co-'p! tion of each by containment entry and during the final entry when CONTAINMENT INTEGRITY is established.
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- d. At least once per 18 months by:
- 1) Verifying automatic interlock action of the RHR System from the Reactor Coolant System by ensuring that with a simulated or actual Reactor Coolant System pressure signal greater than or equal to 425 psig, the interlocks prevent the valves from being opened.
WOLF CREEK - UNIT 1 3/4 5-4 Amendment No. 49