ENS 43603
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ENS Event | |
|---|---|
20:45 Aug 27, 2007 | |
| Title | Grating Inside Containment Found Unsecured |
| Event Description | At 1645 hours0.019 days <br />0.457 hours <br />0.00272 weeks <br />6.259225e-4 months <br /> on 8/27/07 it was determined that a section of grating in the containment pool swell region was not properly restrained. During a postulated large break Loss of Coolant Accident, the grating could become dislodged and subsequently impact the ECCS suction strainer located in the suppression pool below the grating. An engineering review determined that the force of the impact could be larger than the impingement forces that had been previously evaluated. The forces were postulated to impact one of two concentric suction strainers. The resulting damage could cause either Residual Heat Removal B and C loops or High Pressure Core Spray (not both) to be inoperable. This condition was determined to meet the reporting requirements for 10 CFR 50.72(b)(3)(ii)(B), 'Any event or condition that results in: (B) The nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.' Since one of the strainers was for High Pressure Core Spray, a single train safety system, this event was also determined to meet the reporting criteria for 10 CFR 50.72(b)(3)(v)(D), 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of systems needed to (D) mitigate the consequences of an accident.'
Technical Specification 3.5.1, ECCS - Operating, was entered and Required Actions taken within the specified completion time. The grating was subsequently restored to design configuration and the Technical Specification LCO was exited. Time of restoring grating to design was 1838 8/27/07, exited Tech Spec 3.5.1. Location of grating is in the Containment Building on the 599' elevation near the lower air lock. The section is a 3 X 7 foot piece of grating that is located on the level just above the suppression pool. We still are investigating when the grating hold down plates were removed, potentially removed during our recent recirc motor replacement in July 07. The grating hold down plates were discovered by an Operations Roving Operator during his tour on rounds. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Perry  Ohio (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| LER: | 05000440/LER-2007-003 |
| Time - Person (Reporting Time:+0 h0 days <br />0 weeks <br />0 months <br />) | |
| Opened: | Al Rabenold 20:45 Aug 27, 2007 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Aug 27, 2007 |
| 43603 - 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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