Event Notification Report for January 14, 2002
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/11/2002 - 01/14/2002 ** EVENT NUMBERS ** 38622 38623 38625 38626 38627 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38622 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 01/11/2002| | UNIT: [] [2] [] STATE: NJ |NOTIFICATION TIME: 05:12[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/11/2002| +------------------------------------------------+EVENT TIME: 04:00[EST]| | NRC NOTIFIED BY: JOHN GARECHT |LAST UPDATE DATE: 01/11/2002| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |RONALD BELLAMY R1 | |10 CFR SECTION: | | |ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 N Y 100 Power Operation |65 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION SHUTDOWN DUE TO # 2A EMERGENCY DIESEL GENERATOR NOT | | OPERATING PROPERLY. | | | | "A unit shutdown was initiated at 0400 on 01/11/02 as required by Technical | | Specifications. Technical Specification Action Statement 3.8.1.1.b action b | | was entered at 0303 on 01/08/02 for scheduled maintenance on the 2A | | emergency diesel generator. During post maintenance testing, oscillations | | associated with the generator voltage control system were observed. The | | cause of the voltage oscillations has not been identified or corrected. | | Troubleshooting activities are on-going in an attempt to identify the | | cause. | | | | "The 2B and 2C emergency diesel generator surveillance tests were performed | | within 24 hours to evaluate for common cause failures. A Common Cause | | Failure was not identified and the 2B and 2C surveillance tests were | | performed satisfactorily. | | | | "Salem Unit Two will be in Mode 3 by 0930 on 01/11/02 and in Mode 5 by 1503 | | on 01/12/02 as required by Technical Specifications. | | | | "Salem Unit one is not affected by this event and remains in Mode 1 at | | 100%" | | | | The NRC Resident Inspector was notified of this event notification by the | | licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38623 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 01/11/2002| | UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 11:23[EST]| | RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 01/11/2002| +------------------------------------------------+EVENT TIME: 09:15[EST]| | NRC NOTIFIED BY: J. SCHORK |LAST UPDATE DATE: 01/11/2002| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |RONALD BELLAMY R1 | |10 CFR SECTION: | | |ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFF-SITE SIRENS INOPERABLE IN YORK COUNTY | | | | "TMI is notifying the NRC Operations Center in accordance with 10 CFR | | 50.72(b)(3)(xiii) that a major loss of emergency preparedness capabilities | | for TMI has occurred. At 9:15 AM on Friday, January 11, 2001 during a test | | of all of the emergency sirens for the five (5) risk counties around TMI, it | | was determined that the public emergency sirens for York County did not | | activate. Attempts to return the sirens to an operable status within 1 hour | | were unsuccessful. The sirens are currently inoperable. | | | | "The apparent cause of the siren failure was a serial port failure on the | | computer that activates the York County signal transmitter. Therefore, no | | signal was transmitted to the 34 sirens for York County. Troubleshooting is | | in process to determine the exact cause of the failure. | | | | "The siren test covered all of the five (5) risk counties around TMI. All of | | the public emergency sirens for the other four risk counties for TMI | | (Cumberland, Dauphin, Lancaster and Lebanon) activated with the exception of | | a single siren in Lancaster County. The inoperability of sirens for one-(1) | | of the five (5) risk counties around TMI impacts a large segment of the | | population. (continued on next page) | | | | "This event meets the criteria set forth in NUREG 1022 for a major loss of | | emergency offsite communications capability. The site Sr. Resident Inspector | | has been informed of the event and the 8-hour report. The Pennsylvania | | Emergency Management Agency (PEMA) has been notified of the event. York | | County Emergency Management is aware of the event and has contacted the | | siren vendor. The siren failure event is being entered into the TMI-1 | | corrective action program." | | | | The licensee notified the NRC Resident Inspector as well as state and local | | authorities. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 38625 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: U.S. AIR FORCE |NOTIFICATION DATE: 01/11/2002| |LICENSEE: U.S. AIR FORCE |NOTIFICATION TIME: 15:50[EST]| | CITY: SANTA FE REGION: 4 |EVENT DATE: 01/10/2002| | COUNTY: STATE: NM |EVENT TIME: [MST]| |LICENSE#: NM-00624 AFB AGREEMENT: Y |LAST UPDATE DATE: 01/11/2002| | DOCKET: 90000624 |+----------------------------+ | |PERSON ORGANIZATION | | |BLAIR SPITZBERG R4 | | |E. WILLIAM BRACH NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: DAVID PUGH | | | HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNKNOWN CONDITION OF SOURCES ON HELICOPTER THAT CRASHED | | | | On 1/10/02 a H-60 US Air Force helicopter crashed north of Santa Fe, NM | | during a rescue effort. The helicopter has 6 IBIS (In-flight Blade | | Inspection System) indicators, each containing 500 microcuries of Sr-90. | | The condition and actual location of the sources is unknown at this time. | | Teams will be out this weekend to access the crash site and try to locate | | the sources as part of the recovery efforts. | | | | The NRC Region 4 contact (Tony Gains) will be notified by the US Air Force. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38626 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 01/11/2002| | UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 18:14[EST]| | RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 01/04/2002| +------------------------------------------------+EVENT TIME: 09:32[CST]| | NRC NOTIFIED BY: MARK HANNEMAN |LAST UPDATE DATE: 01/11/2002| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |DAVID HILLS R3 | |10 CFR SECTION: | | |AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 N Y 95 Power Operation |95 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INVALID ACTUATION OF PARTIAL GROUP II ISOLATION | | | | "While performing Post Maintenance Testing (PMT) on Primary Containment | | Isolation Valve (PCIV) 2-9208A (Unit 2 Drywell Air Sample Valve) a fuse in | | the control circuit blew when the 2-9208A valve was given an open signal. | | This caused a partial Group II Isolation (Invalid Actuation) consisting of a | | loss of indication to 14 PCIVs and the automatic closure of 11 PCIVs. | | Additionally the Traversing In-Core Probes (TIP) automatically retracted and | | the 5 associated ball valves closed. | | | | "All plant systems responded as expected for the fuse opening. The fuse was | | replaced and the PCIVs that repositioned were returned to their normal | | position. The 2-9208A was removed from service. TIP runs were restarted. | | This event did not have any adverse effect on plant operation. | | | | "Troubleshooting found a shorted wire connection in the junction box for the | | 2-9208A solenoid. The wire connection was repaired and the 2-9208A valve PMT | | was performed satisfactorily." | | | | The licensee notified the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 38627 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 01/11/2002| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 23:03[EST]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 01/11/2002| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 18:07[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/11/2002| | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION | |LICENSE#: GDP-1 AGREEMENT: Y |DAVID HILLS R3 | | DOCKET: 0707001 |E. WILLIAM BRACH NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: KEVIN BEASLEY | | | HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24 HOUR REPORT - VALID ACTIVATION OF A TSR REQUIRED SAFETY SYSTEM | | | | "At 1807 CST, on 1-11-02 the Plant Shift Superintendent (PSS) was notified | | of an activation of the Water Inventory Control System (WICS) on #4 | | autoclave In the C-360 building. Approximately seven minutes into the heat | | cycle the Hi Primary and HI Secondary Condensate alarms were received, and | | the autoclave went into containment as designed. The operators investigated | | the alarm with assistance from the Shift Engineer. Due to the alarm being | | received on the redundant Primary and Secondary probes at a point in the | | heat cycle when there is a high steam demand. Engineering determined this to | | be a valid activation of the system. The autoclave was removed from service | | and the WICS was declared inoperable. Further investigation will be | | performed by the System Engineer and Instrument Maintenance to determine the | | exact cause of the alarm. The purpose of the WICS is to limit the amount of | | water In the autoclave and is a safety system required by TSR 2.1.4.3. | | | | "The PSS determined that this event is a 24 Hour Event Report due to the | | valid activation of a TSR required safety system. | | | | "The NRC Senior Resident Inspector has been notified of this event." | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021