Event Notification Report for January 22, 2002
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/18/2002 - 01/22/2002 ** EVENT NUMBERS ** 38601 38631 38638 38639 38640 38642 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38601 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 01/01/2002| | UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 09:41[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 01/01/2002| +------------------------------------------------+EVENT TIME: 00:42[CST]| | NRC NOTIFIED BY: STEVE WHEELER |LAST UPDATE DATE: 01/21/2002| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |BLAIR SPITZBERG R4 | |10 CFR SECTION: | | |AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 10 Power Operation |10 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) TURBINE DETERMINED TO BE INOPERABLE | | | | The licensee determined during surveillance testing that the HPCI turbine | | was inoperable due to the minimum flow valve cycling open and closed due to | | problem with the associated flow switch. The problem is being worked on. | | | | The licensee intends to notify the NRC Resident Inspector. | | | | * * * RETRACTED AT 1736 EST ON 1/21/02 BY DAVID MADSEN TO FANGIE JONES * * | | * | | | | "Event Number 38601 reported a condition at Cooper Nuclear Station (CNS) | | where the High Pressure Coolant Injection (HPCI) was declared inoperable due | | the minimum flow valve cycling open and closed. This condition occurred | | during surveillance testing of the HPCI turbine. | | | | "This event was reported per 10CFR50.72(b)(3)(v)(D), Accident Mitigation, | | on the basis that the cycling of the minimum flow valve (when HPCI injection | | is required) could have resulted in injection flow below that required to | | maintain fuel integrity during certain transients or accidents. Subsequent | | investigation found the instrumentation initiating a signal to open the MOV | | would not reset. The requirement for the minimum flow to open for pump | | protection was always met. Existing analyses have determined that sufficient | | margin exists to achieve adequate system flow even if the minimum flow valve | | is in the full-open position. Also, the additional flow demands on the HPCI | | pump would not have resulted in a large enough increase in turbine speed | | that would have resulted in a turbine trip. For the scenario where the valve | | may have cycled between open and closed position, the HPCI pump control | | system is capable of handling the change in flow without resulting in a | | turbine trip. Should HPCI have received a isolation signal or if the turbine | | was manually tripped, the minimum flow valve would have closed. | | | | "Therefore, the above described condition did not result in a loss of safety | | function for HPCI. Nebraska Public Power District has determined that this | | event is not reportable under the requirements of 10CFR50.72(b)(3)(v)(D), | | and as such, Event 38601 is retracted." | | | | The licensee intends to notify the NRC Resident Inspection. The R4DO (Dale | | Powers) has been notified. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 38631 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: STORA ENSO NORTH AMERICA CORP. |NOTIFICATION DATE: 01/16/2002| |LICENSEE: STORA ENSO NORTH AMERICA CORP. |NOTIFICATION TIME: 09:56[EST]| | CITY: WISCONSIN RAPIDS REGION: 3 |EVENT DATE: 01/15/2002| | COUNTY: WOOD STATE: WI |EVENT TIME: 15:00[CST]| |LICENSE#: 48-01117-01 AGREEMENT: N |LAST UPDATE DATE: 01/18/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |ANTON VEGEL R3 | | |DON COOL NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: CHARLES CHAPMAN | | | HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF A MISSING CESIUM-137 SOURCE AT A PAPER MILL (STORA ENSO NORTH | | AMERICA CORP.) LOCATED IN WISCONSIN RAPIDS, WISCONSIN | | | | During performance of a quarterly inventory on 01/15/02, the licensee | | discovered that a 200-millicurie cesium-137 source was missing. It was used | | as part of a fixed volume/density gauge which was mounted on a pipe. | | Apparently, the unit had been stored in the locked position on the pipe. | | The licensee reported that a paper machine dismantling project was ongoing | | near the previous location of the unit. It is currently believed that the | | unit may either have been moved or dismantled and shipped somewhere. The | | licensee's investigation is still in progress. | | | | (Call the NRC operations officer for a licensee contact telephone number.) | | | | | | * * * UPDATE ON 1/17/02 @ 1711 BY CHAPMAN TO GOULD * * * | | | | After further investigation the licensee has determined the source may have | | been stolen from the site. The licensee has notified the police and Region | | 3. The device manufacturer will be notified. | | Notified RDO 3 (Vegel), NMSS EO(Frant) | | | | * * * UPDATE ON 1/17/02 @ 1843 BY BREWSTER TO GOULD * * * | | | | The licensee reported that they had been advised that an individual working | | for a contractor took the missing device. They are further investigating | | the incident. | | | | Notified RDO 3 (Vegel), NMSS EO(Frant) | | | | * * * UPDATE ON 1/18/02 @ 1513 BY CHAPMAN TO GOULD * * * | | | | The licensee after further investigation and coordination with the local | | police have determined the the missing device was stolen. Continuing | | investigation is ongoing. | | | | Notified Reg 3 RDO (Vegel) and NMSS EO(Hickey) | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 38638 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: LOUISIANA RADIATION PROTECTION DIV |NOTIFICATION DATE: 01/18/2002| |LICENSEE: OWENSBY AND KRITIKOS |NOTIFICATION TIME: 12:39[EST]| | CITY: SULPHUR REGION: 4 |EVENT DATE: 01/18/2002| | COUNTY: STATE: LA |EVENT TIME: 11:00[CST]| |LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 01/18/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |DALE POWERS R4 | | |JOHN HICKEY NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: HENRY | | | HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INDUSTRIAL RADIOGRAPHY ACCIDENT WITH POSSIBLE CONTAMINATION | | | | Louisiana state licensee Owensby and Kritikos had an industrial radiography | | accident at the Citgo refinery in Lake Charles , La. It appears that the | | source drive cable crossed an electric line and a spark exploded the | | Iridium-192 source. They believe the source is in a safe condition, but | | there was considerable contamination outside the device. They also believe | | some people may have contamination on their clothing which may have been | | tracked to other areas. A health physicist has been dispatched to the | | scene. The state also told the licensee to isolate the area. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38639 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 01/19/2002| | UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 00:47[EST]| | RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 01/18/2002| +------------------------------------------------+EVENT TIME: 21:23[CST]| | NRC NOTIFIED BY: M. HANNEMAN |LAST UPDATE DATE: 01/19/2002| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |ANTON VEGEL R3 | |10 CFR SECTION: | | |AINB 50.72(b)(3)(v)(B) POT RHR INOP | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THREE OUT OF FOUR TIME DELAY SETTINGS FOR THE REACTOR HIGH PRESSURE | | ISOLATION CONDENSER INITIATION SWITCHES FOUND OUT OF CALIBRATION. | | | | | | During performance of DIS 1300-01, Sustained High Reactor Pressure | | Calibration, three of the four time delay settings for the reactor high | | pressure Isolation Condenser initiation switches were found to be out of | | Technical Specification tolerance. The maximum time delay allowed per | | Technical Specification Surveillance Requirement 3.3.5.2.3 is 15 seconds. | | The time delays for high pressure switches 2-263-53A, 53A, and 53C were | | 15.6, 15.4, and 15.4 seconds respectively. The 2-263-53D switch was found | | in tolerance at 14.8 seconds. Each time delay was adjusted to be back in | | tolerance. This combination of three out-of-tolerance time delays could | | have prevented the Isolation Condenser from receiving an initiation signal | | within the 15 second Technical Specification required time limit. | | | | The NRC Resident Inspector was notified of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38640 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 01/19/2002| | UNIT: [] [2] [] STATE: MI |NOTIFICATION TIME: 07:56[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/19/2002| +------------------------------------------------+EVENT TIME: 00:05[EST]| | NRC NOTIFIED BY: S. KOSHAY |LAST UPDATE DATE: 01/19/2002| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |ANTON VEGEL R3 | |10 CFR SECTION: | | |AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 N N 0 Hot Standby |0 Hot Standby | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNEXPECTED AUTOMATIC START OF TURBINE DRIVEN AUXILIARY FEEDWATER PUMP | | (TDAFW) AFTER PLANT SHUTDOWN. | | | | After the scheduled reactor trip from 20% power in preparation for a | | refueling outage the steam generator water level lowered to approximately | | 17%. This was lower than anticipated on the trip resulting in the Turbine | | Driven Auxiliary Feedwater Pump autostarting as a function of the steam | | generator's water level. Both Motor Driven Auxiliary Feedwater (MDAFW) | | pumps had already been started. Steam generator water levels rapidly | | recovered and the reactor coolant system cooled below 547 degrees F, which | | is the normal no load temperature, to 540 degrees F. The 7 degree cooldown | | below the Tave No Load Condition resulted in Pressurizer Water Level shrink | | and a letdown isolation. The operators secured the TDAFW pump and throttled | | the flows from the MDAFW pumps and restored reactor coolant system | | temperature and pressurizer inventory. The reactor coolant system cooldown | | and depressurization proceeded normally from that point on. | | | | | | The NRC Resident Inspector was notified of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38642 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 01/21/2002| | UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 19:50[EST]| | RXTYPE: [1] GE-3 |EVENT DATE: 01/21/2002| +------------------------------------------------+EVENT TIME: 17:35[CST]| | NRC NOTIFIED BY: DUSTIN WRIGHT |LAST UPDATE DATE: 01/21/2002| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: |ANTON VEGEL R3 | |10 CFR SECTION: | | |ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 A/R Y 100 Power Operation |0 Hot Shutdown | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM ON TURBINE GENERATOR LOAD REJECT | | | | The licensee reported receiving a turbine generator load reject scram, cause | | unknown at this time. Generator lockout started the event. A Group 2 | | isolation occurred at +9" reactor water level. All systems functioned as | | designed. The scram and Group 2 have been reset and the plant will remain | | shutdown until further investigation is complete. | | | | The licensee notified the NRC Resident Inspector, as well as the State and | | Local Governments. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021