Event Notification Report for October 10, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/09/2002 - 10/10/2002
** EVENT NUMBERS **
39260 39262 39263 39264 39265
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|Power Reactor |Event Number: 39260 |
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| FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 10/09/2002|
| UNIT: [1] [] [] STATE: NH |NOTIFICATION TIME: 03:31[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 10/09/2002|
+------------------------------------------------+EVENT TIME: 03:07[EDT]|
| NRC NOTIFIED BY: LOU GAREAU |LAST UPDATE DATE: 10/09/2002|
| HQ OPS OFFICER: MIKE NORRIS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNUSUAL EVENT |JOHN WHITE R1 |
|10 CFR SECTION: |WILLIAM BECKNER NRR |
|AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |NADER MAMISH IRO |
| |JIM DUNKER FEMA |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| UNUSUAL EVENT DECLARED DUE TO FIRE IN PROTECTED AREA LASTING GREATER THAN 10 |
| MINUTES |
| |
| "Unusual event was classified based on a fire in the protected area lasting |
| > 10 minutes. The fire started in the motor of the 'B' circulating water |
| pump. It was 'contained' to that location (the CW pump motor). Motor |
| [is]still smoldering, [but] it is controlled and contained. Steam Generator |
| Blowdown system isolated due to high flash tank level. Multiple rad |
| monitors went into alarm due to voltage surge." |
| |
| The NRC Resident Inspector will be notified. |
| |
| The Licensee reported that no offsite assistance was requested and that the |
| State (NH) was notified. |
| |
| ***UPDATE JIM HILL TO JOHN MacKINNON 0614 EDT 10/9/02*** |
| |
| The Unusual Event was Terminated at 0547 EDT. |
| |
| The Licensee has notified the NRC Resident Inspector and the State(NH). |
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|Power Reactor |Event Number: 39262 |
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| FACILITY: COLUMBIA GENERATING STATIREGION: 4 |NOTIFICATION DATE: 10/09/2002|
| UNIT: [2] [] [] STATE: WA |NOTIFICATION TIME: 15:30[EDT]|
| RXTYPE: [2] GE-5 |EVENT DATE: 08/16/2002|
+------------------------------------------------+EVENT TIME: 02:54[PDT]|
| NRC NOTIFIED BY: CRAIG SLY |LAST UPDATE DATE: 10/09/2002|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |WILLIAM JONES R4 |
|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 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INVALID SYSTEM ACTUATION DUE TO LOSS OF RPS BUS "A" |
| |
| "On August 16, 2002 at approximately 0254 hours, a loss of Reactor |
| Protection System (RPS) Bus A occurred while operators were attempting to |
| reset a half-scram on the A2 logic channel of the RPS. The A2 logic reset |
| attempt was required in accordance with a surveillance test procedure that |
| was in progress, PPM OSP-RPS-Q402, MSIV Closure Scram Functional. Upon loss |
| of RPS Bus A, control room operators entered Abnormal Procedure ABN-RPS, |
| Loss of RPS, and an operator was dispatched to investigate the problem. |
| |
| "The operator investigating the problem discovered that the Motor Generator |
| Set (RPS-MG-A) that supplies RPS Bus A was running with both of its |
| electrical protection assemblies (EPAs) in the tripped position. In |
| accordance with procedure ABN-RPS, operators transferred RPS Bus A to its |
| alternate power supply and then reset the half-scram and associated |
| containment outboard isolations. The operators then exited PPM OSP-RPS-Q402. |
| The follow-up investigation found that the loss of the RPS Bus A was due to |
| a trip of the RPS-MG-A output breaker (RPS-MG-CB1) on over-voltage. The |
| output breaker trip caused both downstream Electrical Protection Assemblies |
| (RPS-EPA-3A and RPS-EPA-3C) to trip. This is the expected and required |
| response for RPS-EPA-3A and RPS-EPA-3C." |
| |
| The loss of power to RPS Bus A had the following effects on the plant: An |
| actuation of RPS trip system A (Half-Scram), Main Steam Line Radiation |
| Monitors A and C lost power; a trip of the Balance of Plant isolation logic |
| in control room relay Cabinet RC-1; an outboard primary containment |
| isolation signal was received by the following (valves closed or were |
| already closed): Main Steam Line Drain Valves, Reactor Water Sample Valve, |
| Drywell Floor and Equipment Drain Isolation Valves, Residual Heat Removal |
| (RHR) Discharge to Radwaste and Heat Exchanger Sample Isolation Valves, RHR |
| Shutdown Cooling (SDC) Reactor Head Spray Isolation Valve, SDC Return |
| Valves, Reactor Water Cleanup (RWCU) Suction Valve. All of these plant |
| equipment responses were as expected and per plant design. |
| |
| The licensee notified the NRC Resident Inspector. |
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|Hospital |Event Number: 39263 |
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| REP ORG: ST PATRICK HOSPITAL |NOTIFICATION DATE: 10/09/2002|
|LICENSEE: ST PATRICK HOSPITAL |NOTIFICATION TIME: 16:38[EDT]|
| CITY: MISSOULA REGION: 4 |EVENT DATE: 08/30/2002|
| COUNTY: STATE: MT |EVENT TIME: [MDT]|
|LICENSE#: 121677302 AGREEMENT: N |LAST UPDATE DATE: 10/09/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |WILLIAM JONES R4 |
| |ERIC LEEDS NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: BREWER | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|LADM 35.33 MED MISADMINISTRATION | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| MEDICAL MISADMINISTRATION |
| |
| A patient was receiving a gynecological implant of Cs-137 which had the |
| incorrect activity entered into the computer. The calibrated activity was |
| inadvertently entered instead of the current activity. The patient was |
| also receiving external beam therapy from a linear accelerator along with |
| the Cs-137 implant. With the incorrect data being entered into the |
| computer, the patient received a total dose(external and implant) which |
| deviated below the prescribed dose by approximately 16%. The implant |
| dosage, however had greater than a 20% deviation less than the prescribed |
| dose. This medical misadministration was discovered on 10/09/02 @ 1620 MT. |
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|Power Reactor |Event Number: 39264 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 10/09/2002|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 17:12[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 10/09/2002|
+------------------------------------------------+EVENT TIME: 13:59[EDT]|
| NRC NOTIFIED BY: LEONE |LAST UPDATE DATE: 10/09/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOHN WHITE R1 |
|10 CFR SECTION: |WILLIAM BECKNER NRR |
|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 |97 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE |
| |
| "At 1518 hours on October 9, 2002 Indian Point Unit 2 commenced a controlled |
| shutdown per T/S 3.0.1. T/S 3.0.1 was entered because Emergency Diesel |
| Generators (EDG) 21 and 23 were declared inoperable. EDG 23 was declared |
| inoperable at 2152 hours on October 8, 2002 due to failure of monthly test. |
| EDG 21 was declared inoperable at 1359 hours on October 9, 2002 due to |
| indications of jacket water in the lube oil system. EDG 23 was declared |
| operable at 1635 hours on October 9, 2002 following corrective actions and |
| testing at which time T/S 3.0.1 was exited. They think EDG 21 may have a |
| cracked engine head. The reactor power reduction was stopped at 97 percent, |
| but the are planning to return to 100%. The to the Public Service |
| Commission was informed of the reason for the downpower at 1610 hours on |
| October 9, 2002." |
| |
| The NRC Resident Inspector was notified. |
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|Power Reactor |Event Number: 39265 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 10/10/2002|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 00:20[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/10/2002|
+------------------------------------------------+EVENT TIME: 00:08[EDT]|
| NRC NOTIFIED BY: ROBERT BOESCH |LAST UPDATE DATE: 10/10/2002|
| HQ OPS OFFICER: MIKE NORRIS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOHN WHITE 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| TECH SPEC REQUIRED SHUTDOWN DUE TO FAILURE TO MEET 2 OFFSITE POWER SUPPLIES |
| |
| "Susquehanna Unit 1 initiated a Technical Specification required shutdown |
| due to failure to meet LCO 3.8.1 Action A.3 and the Notice of Enforcement |
| Discretion (Docket No. 50-387), for operating with one inoperable offsite |
| power supply. The offsite power supply was originally lost due to a |
| Transformer failure on 10/3/02 at 0230 est. The NOED allowed Unit One to |
| continue operation until 10/1 0/02 at 0230. The shutdown requirements of LCO |
| 3.8.1 Action F (Mode 3 within 12 hours and Mode 4 within 36 hours) are being |
| implemented. It has been determined that replacement activities of the |
| transformer will not be completed in time to meet the NOED, and therefore |
| shutdown of unit 1 has been initiated as of 0008. |
| |
| "This event is a Technical Specification required shutdown, and is |
| reportable as a four hour ENS Notification under 10 CFR 50.72(b)(2)(I)." |
| |
| The Licensee has notified the NRC Resident Inspector. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021