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With the plant in Mode 1 at (approximately … With the plant in Mode 1 at (approximately) 75% power, the Auxiliary boiler and water treatment building 480 volt switchgear (NJS-SWG1J) faulted. The fault resulted in the loss of the NPS A bus (13.8 Kv normal supply), causing condensate and feed pumps to trip. Operators in the control room immediately responded and the plant was manually scrammed at 0306. Both the high pressure core spray (HPCS) and the reactor core isolation cooling (RCIC) systems responded automatically and injected into the vessel (valid ECCS signal). Safety systems responded as expected, including level 2 isolations.</br>The licensee believes a transformer fault may have transferred up the line and caused the loss of normal power supply.</br>RCIC is controlling reactor water level with primary plant pressure approximately 325 psia. Decay heat is being controlled through modulating the SRV's. The licensee has all systems available to place the unit in safe shutdown and cooldown. The licensee has one inoperable EDG and is not in any technical specification action statement at this time. </br>The licensee notified the NRC Resident Inspector.</br>* * * UPDATE AT 2214 ON 11/7/2007 FROM BRYAN KELLEY TO MARK ABRAMOVITZ * * *</br>The high pressure core spray system was returned to its standby lineup at 0318 (all times are CST). Standby service water was being placed in service at 0701 to raise service water header pressure when standby service water pump 'C' started automatically. NPS 13.8kv switchgear 'A' was restored to service at 1245. The reactor core isolation cooling system, which automatically started at the time of the event, was shutdown at 1645. The Division 3 diesel generator, which automatically started at the time of the event, was restored to its standby lineup at 1429. Shutdown cooling was placed in service with residual heat removal pump 'A', at 1626. The plant entered Mode 4 (cold shutdown) at 1942. </br>The electrical fault that initiated the event has been isolated to a 13.8kv/480v transformer in the turbine building. An investigation is ongoing.</br>The licensee notified the NRC Resident Inspector.</br>Notified the R4DO (Spitzberg) and NRR (Lubinski).d the R4DO (Spitzberg) and NRR (Lubinski).
09:06:00, 7 November 2007 +
43,773 +
07:58:00, 7 November 2007 +
09:06:00, 7 November 2007 +
With the plant in Mode 1 at (approximately … With the plant in Mode 1 at (approximately) 75% power, the Auxiliary boiler and water treatment building 480 volt switchgear (NJS-SWG1J) faulted. The fault resulted in the loss of the NPS A bus (13.8 Kv normal supply), causing condensate and feed pumps to trip. Operators in the control room immediately responded and the plant was manually scrammed at 0306. Both the high pressure core spray (HPCS) and the reactor core isolation cooling (RCIC) systems responded automatically and injected into the vessel (valid ECCS signal). Safety systems responded as expected, including level 2 isolations.</br>The licensee believes a transformer fault may have transferred up the line and caused the loss of normal power supply.</br>RCIC is controlling reactor water level with primary plant pressure approximately 325 psia. Decay heat is being controlled through modulating the SRV's. The licensee has all systems available to place the unit in safe shutdown and cooldown. The licensee has one inoperable EDG and is not in any technical specification action statement at this time. </br>The licensee notified the NRC Resident Inspector.</br>* * * UPDATE AT 2214 ON 11/7/2007 FROM BRYAN KELLEY TO MARK ABRAMOVITZ * * *</br>The high pressure core spray system was returned to its standby lineup at 0318 (all times are CST). Standby service water was being placed in service at 0701 to raise service water header pressure when standby service water pump 'C' started automatically. NPS 13.8kv switchgear 'A' was restored to service at 1245. The reactor core isolation cooling system, which automatically started at the time of the event, was shutdown at 1645. The Division 3 diesel generator, which automatically started at the time of the event, was restored to its standby lineup at 1429. Shutdown cooling was placed in service with residual heat removal pump 'A', at 1626. The plant entered Mode 4 (cold shutdown) at 1942. </br>The electrical fault that initiated the event has been isolated to a 13.8kv/480v transformer in the turbine building. An investigation is ongoing.</br>The licensee notified the NRC Resident Inspector.</br>Notified the R4DO (Spitzberg) and NRR (Lubinski).d the R4DO (Spitzberg) and NRR (Lubinski).
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