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." |
+------------------------------------------------------------------------------+