ENS 42161
ENS Event | |
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16:42 Nov 21, 2005 | |
Title | Division 3 Emergency Diesel Generator Declared Inoperable |
Event Description | The Division 3 Emergency Diesel Generator (EDG) was declared INOPERABLE following a trip during a routine monthly surveillance run. As soon as the Division 3 EDG was at full load it tripped off line (output breaker tripped). The Division 3 EDG supplies electrical power to the High Pressure Core Spray System in the event of a loss of offsite power.
No problems occurred on the Division 3, 4160 volt, safety related bus. This event is being reported in accordance with 10CFR50.72(b)(3)(v)(B), Event or Condition That Could Have Prevented Fulfillment of a Safety Function for a single-train system failure. The NRC Resident inspector has been notified.
Subsequent trouble-shooting and testing determined that the cause of the engine trip on 11/21/05 was an invalid high coolant temperature trip signal. This trip is bypassed during a Loss of Coolant (LOCA) initiation of the system, therefore, it was determined that the EDG would have been able to perform its safety function during a LOCA. Following a Loss of Offsite Power (LOOP), reactor water level is expected to reach Reactor Pressure Vessel (RPV) Water Level Low Low (Level 2) within 30 seconds of the initiating signal. Once Level 2 is reached, both the EDG and the LOCA Trip bypass signals are actuated. It was determined that the bypass would have occurred prior to the high coolant temperature trip. Based on the above, it was determined that the Division 3 EDG would have been fully capable of performing its safety function under both LOCA and LOOP. The Division 3 EDG was restored to an operable condition at 0214 on 11/22/05. The NRC Senior Resident Inspector has been notified. Notified R3DO (H. Peterson). |
Where | |
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Clinton Illinois (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat | |
Time - Person (Reporting Time:+1 h0.0417 days <br />0.00595 weeks <br />0.00137 months <br />) | |
Opened: | Steven Meng 17:42 Nov 21, 2005 |
NRC Officer: | Bill Huffman |
Last Updated: | Dec 20, 2005 |
42161 - NRC Website | |
Unit 1 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (96 %) |
After | Power Operation (96 %) |
WEEKMONTHYEARENS 482692012-09-03T03:04:0003 September 2012 03:04:00
[Table view]10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Transfer of Emergency Reserve Auxiliary Transformer Isolating Fuel Pool Cooling and Cleanup System, and Fuel Building Ventilation System ENS 475332011-12-18T15:30:00018 December 2011 15:30:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Rhr Cooling Due to Incorrect Reactor Water Level Indication ENS 467712011-04-20T14:15:00020 April 2011 14:15:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Watertight Doors Left Ajar Simultaneously During Room Checks ENS 421612005-11-21T16:42:00021 November 2005 16:42:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Division 3 Emergency Diesel Generator Declared Inoperable 2012-09-03T03:04:00 | |