ENS 41650
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ENS Event | |
|---|---|
06:27 Apr 29, 2005 | |
| Title | Reactor Core Isolation Cooling Full Flow Test Line May Not Isolate |
| Event Description | On 4/28/05 Grand Gulf provided a call in on an issue with [two] secondary containment isolation valves on the Main Steam Line drain system. [See EN-41645]
A preliminary detailed review of similar valves has been completed. An additional concern with the Reactor Core Isolation Cooling (RCIC) full flow test line was noted. Specifically preliminary engineering evaluation indicates that during full flow test with flow to the Condensate Storage Tank concurrent with a high drywell pressure secondary containment isolation signal the differential pressure across the valves may prevent adequate design bases closure. Pending further evaluation this issue is conservatively considered reportable under 10CFR50.72(B)(3)(v)(d). Testing of Reactor Core Isolation Cooling with return to the Condensate Storage Tank has been suspended until resolution of this issue. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
| Grand Gulf Mississippi (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
| Time - Person (Reporting Time:+3.47 h0.145 days <br />0.0207 weeks <br />0.00475 months <br />) | |
| Opened: | Brian Blanche 09:55 Apr 29, 2005 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Apr 29, 2005 |
| 41650 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
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