U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/17/2003 - 11/18/2003 ** EVENT NUMBERS ** | Power Reactor | Event Number: 40325 | Facility: LASALLE Region: 3 State: IL Unit: [1] [ ] [ ] RX Type: [1] GE-5,[2] GE-5 NRC Notified By: JEFF SMITH HQ OPS Officer: BILL GOTT | Notification Date: 11/17/2003 Notification Time: 09:35 [ET] Event Date: 11/17/2003 Event Time: 01:10 [CST] Last Update Date: 11/17/2003 | Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION | Person (Organization): ANNE MARIE STONE (R3) | Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text EVENT OR CONDITION THAT COULD HAVE PREVENTED FULFILLMENT OF A SAFETY FUNCTION "This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), Event or Condition that could have prevented fulfillment of a Safety Function needed to mitigate the consequences of an Accident. During performance of scheduled surveillance test LIS-HP-310, Reactor Vessel High Water Level 8 [High Pressure Core Spray] HPCS Injection Valve Closure Instrument Channels A and B Functional Test, Instrument Maintenance personnel discovered one end of fuse 1B21A-F8 not fully seated. The other end of the fuse was fully seated, and was maintaining the un-clipped end in sufficient contact with the fuse holder to complete the circuit. Had the circuit been deenergized, a Control Room annunciator (1H13-P601 A404) would have alarmed, and High Pressure Core Spray (HPCS) automatic low level initiation circuits would have been disabled. The fuse was fully seated without incident. "Upon discovery of the unseated fuse, the initial operability determination concluded that adequate contact was maintained to keep the circuit OPERABLE. After followup evaluation by Engineering, it was determined that continued OPERABILITY could not be assured during a seismic event. Failure of this fuse would prevent automatic actuation of HPCS on reactor vessel level low 2; and would prevent automatic closure of the HPCS discharge valve 1E22-F004 on reactor vessel level high 8. This would prevent the HPCS system, a single train safety system, from performing its design function during a Loss of Coolant Accident subsequent to a seismic event. This is reportable as an 8 hour ENS notification." The licensee informed the NRC Resident Inspector. | Power Reactor | Event Number: 40326 | Facility: PERRY Region: 3 State: OH Unit: [1] [ ] [ ] RX Type: [1] GE-6 NRC Notified By: ROBERT KIDDER HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 11/17/2003 Notification Time: 15:26 [ET] Event Date: 11/17/2003 Event Time: 12:10 [EST] Last Update Date: 11/17/2003 | Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(v)(B) - POT RHR INOP 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION | Person (Organization): CHRISTINE LIPA (R3) | Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text DIVISION 1 AND 2 DIESEL GENERATORS AND ALL ECCS SYSTEMS WERE DECLARED INOPERABLE While aligning the Emergency Service Water (ESW) to the swale, the sluice gates were opened without the ESW being aligned to the swale. This condition made both Div 1&2 Diesel Generators and all ECCS systems inoperable. The probable cause of this event is that the wrong procedure was used in this evolution. Procedure SOI-P45/49 sec 7.3.1 "ESW Pumphouse Forebay Emergency Supply Initiation" was used instead of the correct procedure SOI-P45/49 section 7.3.3. "Alignment of ESW to Pumphouse Forebay Emergency Supply". The condition was discovered at 1215 and corrected at 1220 after section 7.3.1 was exited and section 7.3.3 was used to complete the lineup to the swale. The Nrc Resident Inspector was notified. | Power Reactor | Event Number: 40327 | Facility: WOLF CREEK Region: 4 State: KS Unit: [1] [ ] [ ] RX Type: [1] W-4-LP NRC Notified By: DAVID DEES HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 11/17/2003 Notification Time: 16:08 [ET] Event Date: 11/17/2003 Event Time: 09:00 [CST] Last Update Date: 11/17/2003 | Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(ii)(A) - DEGRADED CONDITION | Person (Organization): KRISS KENNEDY (R4) | Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text REACTOR COOLANT SYSTEM LEAKAGE DUE TO A CRACKED SOCKET WELD During routine operations activities a leak was identified in the area of EPV0109 (combined SI/RHR to Accumulator "D" outlet line vent). At 0900 it was determined that the leak was due to a cracked weld on the socket up stream of EPV0109. The leak rate is 25-30 drops/per minute . This condition is being reported as a degraded condition in the primary coolant system under 10CFR50.72(b)(3)(ii)(A). The plant is currently in Mode 5 with RCS pressure at approximately 345 psig and temperature at approximately 125F. Shutdown cooling is being supplied by the "A" train Residual Heat Removal System. The Resident Inspector has been notified. | |