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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 38601 |
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| 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
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| 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. |
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|Other Nuclear Material |Event Number: 38631 |
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| 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 | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 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) |
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|General Information or Other |Event Number: 38638 |
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| 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. |
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|Power Reactor |Event Number: 38639 |
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| 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
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| 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. |
+------------------------------------------------------------------------------+
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|Power Reactor |Event Number: 38640 |
+------------------------------------------------------------------------------+
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| 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. |
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|Power Reactor |Event Number: 38642 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
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| 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. |
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