U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/16/2013 - 01/17/2013 ** EVENT NUMBERS ** | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | Power Reactor | Event Number: 48527 | Facility: QUAD CITIES Region: 3 State: IL Unit: [1] [ ] [ ] RX Type: [1] GE-3,[2] GE-3 NRC Notified By: FRED SWIHART HQ OPS Officer: BILL HUFFMAN | Notification Date: 11/20/2012 Notification Time: 18:27 [ET] Event Date: 11/20/2012 Event Time: 13:21 [CST] Last Update Date: 01/16/2013 | Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL | Person (Organization): BILLY DICKSON (R3DO) | 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 DRYWELL RADIATION MONITOR INOPERABLE "At 1321 [CST] hours on November 20, 2012, the 1B Drywell Radiation Monitor exhibited degraded performance at the conclusion of surveillance testing. This monitor provides the input into one division of the primary containment isolation logic for a Group II isolation. As a result, the channel was placed in a tripped condition in accordance with Technical Specification 3.3.6.1, Condition B. "Given both divisions are required to complete the Group II isolation logic, this condition is reportable in accordance with 10 CFR 50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function. "The station is currently taking action to troubleshoot and restore the 1B Drywell Radiation Monitor to an operable condition." "The NRC Resident Inspector has been notified." * * * UPDATE AT 1303 EST ON 01/16/13 FROM DEREK DROCKELMAN TO S. SANDIN * * * "ENS Retraction - Drywell Radiation Monitor Inoperable "The purpose of this notification is to retract the ENS Report made on November 20, 2012, at 1827 EST hours (ENS Report # 48527). "Further evaluation performed by Quad Cities Station confirms the 1B Drywell Radiation Monitor would have performed its safety function when required. Based on this subsequent evaluation, ENS Report # 48527 is being retracted. "Note: On November 21, 2012, the 1B Drywell Radiation Monitor was successfully repaired and returned to Operable status." The licensee informed the NRC Resident Inspector. Notified R3DO (Bloomer). | Power Reactor | Event Number: 48676 | Facility: FITZPATRICK Region: 1 State: NY Unit: [1] [ ] [ ] RX Type: [1] GE-4 NRC Notified By: STEVE DeFILLIPPO HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 01/16/2013 Notification Time: 04:43 [ET] Event Date: 01/15/2013 Event Time: 21:12 [EST] Last Update Date: 01/16/2013 | Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION | Person (Organization): JOHN ROGGE (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 LOSS OF A 4160 VOLT BUS WHILE PERFORMING TESTING "On January 15, 2013 at 2112 EST while performing testing associated with the remote shutdown system at the James A. FitzPatrick Nuclear Power Plant, an unexpected loss of the 10600 bus 'B' division AC vital power system occurred. This loss of power to the 10600 bus resulted in an automatic actuation of the 'B' and 'D' Emergency Diesel Generators. The diesel generators started as expected, but did not close in to energize the 10600 Bus due to the configuration at the time of the event. As a result of the loss of the 10600 bus, the 'B' Reactor Protection System (RPS) lost power resulting in a half scram signal and a Group II Primary Containment Isolation System (PCIS) actuation. This actuation resulted in closing containment isolation valves in multiple systems and isolating Reactor Water Clean-Up (RWCU). Based on these system actuations, the event is reportable under criterion 10 CFR 50.72(b)(3)(iv). "Power to the 10600 Bus was restored January 16, 2013 at 0400 EST, and the half scram and isolation signals have been reset. Additional actions to restore systems to a normal operating line-up are on-going. Investigation into the cause of the unexpected power loss is on-going and will be addressed through the corrective action program. "The NRC Resident Inspector has been notified." | |