ENS 43581
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ENS Event | |
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15:53 Aug 20, 2007 | |
Title | Electrical Breaker B4305 Unable to Function |
Event Description | During panel walk downs in the Main Control Room, an Operator discovered no light indication for V-AC-4, B RHR ROOM AIR COOLING UNIT. Operator was dispatched to Breaker B4305 and 'B' RHR room to determine cause of loss of indicating light. The Operator determined that breaker B4305 (V-AC-4, 'B' RHR ROOM AIR COOLING UNIT 480V SUPPLY) was unable to function. Division II RHR pumps, Division II CS pump, and associated low pressure injection systems were declared inoperable. Tech Spec Actions 3.5.1.A, 3.5.1.B, and 3.5.1.M were entered resulting in entry into LCO 3.0.3 at 1053 on August 20, 2007. At 1151 on August 20, 2007 power reduction was commenced using normal shutdown procedures.
Site Electricians determined that a line fuse had blown. The fan motor was meggared and all three line fuses were replaced. At 1230 on August 20, 2007, V-AC-4 was tested and returned to service. Division II RHR pumps, Division II CS pump and associated low pressure injection systems were declared operable. LCO 3.0.3 and T.S. Actions 3.5.1.A, 3.5.1.B, and 3.5.1.M were exited. Power reduction was terminated at 98%. At the completion of the call the power level had returned to 100%. The licensee notified the NRC Resident Inspector. |
Where | |
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Monticello Minnesota (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown | |
Time - Person (Reporting Time:+-1.3 h-0.0542 days <br />-0.00774 weeks <br />-0.00178 months <br />) | |
Opened: | Randy Sandy 14:35 Aug 20, 2007 |
NRC Officer: | John Knoke |
Last Updated: | Aug 20, 2007 |
43581 - NRC Website
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Unit 1 | |
---|---|
Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (98 %) |
WEEKMONTHYEARENS 497392014-01-17T23:36:00017 January 2014 23:36:00
[Table view]10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Required Shutdown Due to Reactor Pressure Boundary Leakage ENS 435812007-08-20T15:53:00020 August 2007 15:53:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Electrical Breaker B4305 Unable to Function 2014-01-17T23:36:00 | |
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