ENS 41417
ENS Event | |
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22:30 Feb 17, 2005 | |
Title | |
Event Description | The following information was provided by the licensee via facsimile:
During testing of the Division 2 Diesel Generator Testable Rupture Disc (TRD), it was discovered that excessive force was needed to open its damper. The function of the TRD is to open to relieve exhaust pressure should the diesel generator's non-safety exhaust silencer become blocked. Upon inspection of the TRD, some deformation was noted on the TRD damper. Since the possibility that the condition might exist on the other two divisional diesel generators could not be ruled out, they were also declared inoperable and LCO 3.0.3 entered. An unanalyzed condition potentially exists because a change in engineering design potentially affected multiple trains. Since all three diesel generators are inoperable, a loss of off-site power would challenge safe shutdown capability, the ability to remove decay heat and accident mitigation. A plant shutdown required by Technical Specifications (LCO 3.0.3) was required due to declaring all 3 divisional diesel generators inoperable. LCO 3.0.3 was entered at 1730 hrs on 2/17/05. No power reduction was required as the Division 2 Diesel Generator was declared operable at 2011 after unlatching its Testable Rupture Disc (TRD) [and LCO 3.0.3 was exited]. The resident NRC inspector was informed of the LCO 3.0.3 entry and exit [and this event notification]. No other notifications of governmental agencies or the press are planned. At the time of the notification to NRC Headquarters, the Division 1 EDG TRD had been unlatched and declared operable. The Division 3 EDG TRD was expected to be unlatched within the next hour. |
Where | |
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Perry Ohio (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
LER: | 05000440/LER-2005-002 |
Time - Person (Reporting Time:+-0.42 h-0.0175 days <br />-0.0025 weeks <br />-5.75316e-4 months <br />) | |
Opened: | Frederick Smith 22:05 Feb 17, 2005 |
NRC Officer: | Jeff Rotton |
Last Updated: | Feb 17, 2005 |
41417 - NRC Website
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Unit 1 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (93 %) |
After | Power Operation (93 %) |