U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/23/2011 - 06/24/2011 ** EVENT NUMBERS ** | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | Power Reactor | Event Number: 46786 | Facility: COMANCHE PEAK Region: 4 State: TX Unit: [ ] [2] [ ] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: RAUL MARTINEZ HQ OPS Officer: JOHN KNOKE | Notification Date: 04/26/2011 Notification Time: 03:58 [ET] Event Date: 04/26/2011 Event Time: 00:20 [CDT] Last Update Date: 06/23/2011 | Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION | Person (Organization): MICHAEL HAY (R4DO) | Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | 2 | N | Y | 1 | Startup | 1 | Startup | Event Text SAFETY RELATED PIPING HAD UNACCEPTABLE AIR VOID "Engineering reported that an ultrasonic [test] had identified an unacceptable air void in the horizontal run of suction piping from the Refueling Water Storage Tank (RWST) to the Safety Injection pumps, Residual Heat Removal pumps, and Containment Spray pumps. Technical Specification 3.0.3 was entered at 0020 CDT [on] 04/26/2011, and actions were started to remove the [air] void by venting of the suction pipe. Unit 2 was in progress of low power physics testing following refueling outage 2RF12. Inspection for [air] voids is in response to NRC generic letter on voiding in ECCS piping. "The void was removed from the system by venting. Engineering confirmed with ultrasonic [test] that the void was removed, and Technical Specification 3.0.3 was exited at 0143 CDT [on] 04/26/2011." The licensee has notified the NRC Resident Inspector. * * * RETRACTION FROM MIKE NIEMEYER TO DONALD NORWOOD AT 1628 EDT ON 6/23/2011 * * * "Further analysis demonstrated that the declaration of inoperability was a conservative action, and RHR and SI would have fulfilled their respective safety functions and been operable. This analysis is based on a detailed study of the void transport and piping design. The analysis confirmed that one (1) train of containment spray was inoperable, however the containment spray safety function would have been fulfilled with the remaining operable [containment spray] train. Based on the above, it is concluded that the health and safety of the public were unaffected by this condition and this event has been evaluated to not meet the definition of a safety system functional failure per 10CFR50.72(b)(3)(v)(D). The NRC Resident Inspector has been notified of this retraction." Notified R4DO (Deese). | Power Reactor | Event Number: 46979 | Facility: LIMERICK Region: 1 State: PA Unit: [1] [ ] [ ] RX Type: [1] GE-4,[2] GE-4 NRC Notified By: JOHN WEISSINGER HQ OPS Officer: DONALD NORWOOD | Notification Date: 06/23/2011 Notification Time: 17:39 [ET] Event Date: 06/23/2011 Event Time: 11:00 [EDT] Last Update Date: 06/23/2011 | Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION | Person (Organization): CHRISTOPHER CAHILL (R1DO) | 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 HIGH PRESSURE COOLANT INJECTION SYSTEM DECLARED INOPERABLE "During performance of scheduled surveillance testing, the Unit 1 High Pressure Coolant Injection (HPCI) turbine control valve did not fully close when the system was secured. The HPCI system was removed from service and the control valve was inspected. The inspection identified a broken steam supply valve internal to the control valve. This condition would have prevented HPCI from fulfilling its safety function and is being reported for the inability of a single train system to mitigate the consequences of an accident." | |