ENS 51201
ENS Event | |
|---|---|
21:20 Jul 6, 2015 | |
| Title | Postulated Multiple Spurious Operations Scenario That Could Adversely Impact Post-Fire Safe Shutdown |
| Event Description | A recent review of Fire Protection and Post Fire Safe Shutdown (PFSS) Programs at Columbia Generating Station (CGS) identified a potential unanalyzed condition with Multiple Spurious Operation (MSO) Scenario 2x.
Review of the circuit design for High Pressure Core Spray (HPCS) HPCS-V-10, HPCS-V-11 and HPCS-V-15 identified that fire-induced circuit failure (hot shorts) on the OPEN function control circuits for each valve would create the flow path to potentially drain inventory from the suppression pool (SP). The normal operation of HPCS-P-3 (keep-fill pump) would allow additional inventory from the SP to be transferred to the CSTs [Condensate Storage Tank]. If a fourth hot short is postulated, HPCS-P-1 would transfer inventory from the SP to the CST at a much faster rate. HPCS-V-11 was deactivated on 6/12/2015 due to a maintenance repair issue and will be left in the fully closed position. This plant alignment resolves current concern for MSO scenario 2x as fire-induced circuit damage cannot cause spurious opening of HPCS-V-11. However, with an incomplete analysis for MSO scenario 2x, compliance with PFSS MSO requirements would have been challenged from the completion of the MSO project (October 2012) up to June 2015. CGS is reporting this event as an unanalyzed condition in conformance with 10 CFR 50.72(b)(3)(ii)(B). Further analyses are being implemented to confirm the condition and to develop appropriate remedial actions. The licensee will notify the NRC Resident Inspector. |
| Where | |
|---|---|
| Columbia Washington (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| LER: | 05000397/LER-2015-006 Regarding Postulated Multiple Spurious Operations Scenario That Could Adversely Impact Post-Fire Safe Shutdown |
| Time - Person (Reporting Time:+-0.65 h-0.0271 days <br />-0.00387 weeks <br />-8.9037e-4 months <br />) | |
| Opened: | David Porter 20:41 Jul 6, 2015 |
| NRC Officer: | Jeff Herrera |
| Last Updated: | Jul 6, 2015 |
| 51201 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (64 %) |
| After | Power Operation (64 %) |
WEEKMONTHYEARENS 569282024-01-18T20:04:00018 January 2024 20:04:00
[Table view]10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Residual Heat Removal Degraded Due to Service Water Leakage ENS 512012015-07-06T21:20:0006 July 2015 21:20:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Multiple Spurious Operations Scenario That Could Adversely Impact Post-Fire Safe Shutdown ENS 498982014-03-11T17:01:00011 March 2014 17:01:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot Short Fire Event That Could Adversely Impact Safe Shutdown Equipment 2024-01-18T20:04:00 | |