Event Notification Report for August 23, 2002
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/22/2002 - 08/23/2002 ** EVENT NUMBERS ** 39067 39136 39137 39138 39143 39144 39145 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39067 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 07/16/2002| | UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 18:15[EDT]| | RXTYPE: [1] GE-4 |EVENT DATE: 07/16/2002| +------------------------------------------------+EVENT TIME: 13:19[EDT]| | NRC NOTIFIED BY: DANIEL J. BOYLE |LAST UPDATE DATE: 08/22/2002| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |JAMES LINVILLE R1 | |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 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECH SPEC 3.0.3 ENTERED AFTER DECLARING BOTH TRAINS OF CONTROL ROOM | | VENTILATION INOPERABLE | | | | "On 7/16/02 at 1319 hours, the Hope Creek Generating Station experienced a | | trip of the in-service 'B' train of Control Room Ventilation and it's | | associated Chiller. The standby 'A' Train attempted to start, but it's | | chilled water pump tripped precluding a successful start. This condition | | rendered both trains of Control Room Emergency Filtration INOPERABLE. In | | accordance with Technical Specifications 3.7.2, both trains were declared | | Inoperable and Technical Specification 3.0.3 was entered. At 1400 hours the | | 'B' Control Room Ventilation train was successfully restored to service and | | Operable status and Technical Specification 3.0.3 was exited. This event is | | being reported in accordance with 10CFR50.72(b)(3)(v) because both trains of | | Control Room Emergency filtration were unavailable for approximately 40 | | minutes. There was no power reduction associated with this event. No | | additional safety related equipment was inoperable at the time of the | | event. | | | | "The initiating condition is still under investigation, but is believed to | | have been induced as the result of an associated cooling coil fill evolution | | that caused a low head tank level and potential air induction that resulted | | in the trip of the in-service cooling train and subsequently the standby | | train. As of the time of this report the 'A' Control Room Emergency | | Filtration Train is still inoperable pending completion of fill and vent of | | the supporting chilled water system." | | | | The licensee will inform the Lower Alloways Creek Township and has informed | | the NRC Resident Inspector. | | | | ***RETRACTION ON 08/22/02 AT 1021 ET BY ERV PARKER TAKEN BY MACKINNON**** | | | | "Subsequent evaluation determined that if a postulated accident had occurred | | during the time that both trains of the Control Room Emergency Ventilation | | system were INOPERABLE, control room dose would be less than the acceptance | | criteria specified in 10CFR50.67 and Regulatory Guide 1.183 and bounded by | | our current analysis. The site boundary doses are not affected. The dose | | impact of the condition as it existed would be bounded by the current | | analysis. Thus, the safety function would have been fulfilled, and the | | notification event number 39067 is retracted" R1DO (Cliff Anderson) | | notified. | | | | The NRC Resident Inspector will be notified of this event by the licensee. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39136 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 08/19/2002| | UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 10:36[EDT]| | RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 08/19/2002| +------------------------------------------------+EVENT TIME: 02:32[EDT]| | NRC NOTIFIED BY: ELI DRAGOMER |LAST UPDATE DATE: 08/22/2002| | HQ OPS OFFICER: RICH LAURA +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |CLIFFORD ANDERSON R1 | |10 CFR SECTION: | | |AINC 50.72(b)(3)(v)(C) POT UNCNTRL RAD REL | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | REACTOR BUILDING EMERGENCY RECIRCULATION UNIT COOLER ANOMALY IDENTIFIED | | DURING ROUTINE SURVEILLANCE TEST | | | | "On August 19, 2002 at 0232, Reactor Building Emergency Recirculation Unit | | Cooler, 2HVR*413A, was declared inoperable due to Reactor Building Emergency | | Recirculation Unit Cooler Inlet Damper, 2HVR*AOD6A, not reaching its full | | open position during testing. Failure of 2HVR*AOD6A to fully open may affect | | the flow-rate through the Reactor Building Emergency Recirculation Unit | | Cooler and may prevent the Standby Gas Treatment System from performing its | | Post-LOCA Secondary Containment drawdown function. The manual operating | | mechanism was returned to its withdrawn position and 2HVR*AOD6A was verified | | to be capable of being fully opened. Opposite train components were | | inspected to confirm that a similar condition does not exist on Train "B". | | This notification is being made as a conservative measure. Evaluation | | coritinues into the actual affect on Post-LOCA drawdown function." | | | | The NRC Resident Inspector was notified. | | | | * * * 1410EDT on 8/22/02 from Dave Richardson to S. Sandin * * * | | | | The licensee is retracting this report based on the following: | | | | "The purpose of this communication is to retract event report number 39136 | | which was initiated at 1030 hours on 08-19-2002, by Nine Mile Point Unit 2. | | This event, reported under 10CFR50.72 (b)(3)(v)(C), involved unplanned | | inoperability of a Reactor Building Emergency recirculation unit cooler due | | to its inlet damper being found partially overridden shut. | | | | "Evaluation revealed that, when called upon to reposition to its emergency | | position, the damper was approximately 97% open. Based on Engineering | | analysis, with the damper in this position, there is 'no appreciable | | increase in system resistance' that would adversely impact the HVR (reactor | | building ventilation) or GTS (standby gas treatment) system flowrates. As a | | result, this condition would not have precluded the aforementioned systems | | from performing their respective safety functions." | | | | The licensee informed the NRC Resident Inspector. Notified R1DO(Anderson). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 39137 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: WA DIVISION OF RADIATION PROTECTION |NOTIFICATION DATE: 08/19/2002| |LICENSEE: URS CORPORATION |NOTIFICATION TIME: 16:33[EDT]| | CITY: CENTRALIA REGION: 4 |EVENT DATE: 08/19/2002| | COUNTY: STATE: WA |EVENT TIME: [PDT]| |LICENSE#: WN-I0172-1 AGREEMENT: Y |LAST UPDATE DATE: 08/19/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |WILLIAM JOHNSON R4 | | |THOMAS ESSIG NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: TERRY C. FRAZEE (e-mail) | | | HQ OPS OFFICER: MIKE NORRIS | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT INVOLVING THEFT OF MOISTURE/DENSITY GAUGE | | | | "The licensee reported the theft of a Campbell Pacific Nuclear | | moisture/density gauge (model MC-1DRP, serial number MD01005902). The gauge | | contained a 1.85 GBq (50 [millicuries]) Am-Be source and a 0.37 GBq (10 | | [millicuries]) Cs-137 source. An authorized user had been working at a | | temporary job site for two weeks. On Sunday, August 18 at 8:00 p.m. the | | authorized user parked his pick-up truck in the parking lot of a local motel | | in Centralia. The gauge was in back under the locked canopy, but visible. | | The gauge box was locked but not secured within the bed of the truck. When | | the authorized user went out to his truck at 6:00 a.m. on Monday the 19th | | the gauge was gone. The back window of the canopy had been forced open. | | Nothing else was missing from the truck (not much else of value was in the | | truck). The theft was reported to the Centralia police and to the licensee's | | RSO. The RSO notified the Department." | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 39138 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: ALABAMA RADIATION CONTROL |NOTIFICATION DATE: 08/19/2002| |LICENSEE: UNIVERSITY OF SOUTHERN ALABAMA |NOTIFICATION TIME: 16:47[EDT]| | CITY: MOBILE REGION: 2 |EVENT DATE: 06/28/2002| | COUNTY: STATE: AL |EVENT TIME: [CDT]| |LICENSE#: 582 AGREEMENT: Y |LAST UPDATE DATE: 08/19/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |MARK LESSER R2 | | |THOMAS ESSIG NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: JIM McNEES (fax) | | | HQ OPS OFFICER: MIKE NORRIS | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT INVOLVING 2 MEDICAL MISADMINISTRATIONS | | | | "Alabama licensee identifies two misadministrations from previous year. | | | | "By telephone notification on June 28, 2002 the University of South Alabama | | (Alabama Radioactive Material License No. 582) notified the State of Alabama | | that during their annual Quality Management Program review they identified | | two possible misadministrations of Iodine-131 from the previous year. | | | | "By letter dated July 8, 2002, and received by the State of Alabama on July | | 11, 2002, the University of South Alabama confirmed that a review of the | | records revealed that: | | | | "A. On April 3,2002, a patient was given 3.9 [millicuries] of iodine-131 for | | a total body diagnostic scan when 3.0 [millicuries] had been prescribed by | | the authorized user. The administered dose exceeded the prescribed dose by | | 30%; and | | | | "B. On August 7,2001, a patient was administered 0.702 [millicuries] of | | iodine-131 for a whole body diagnostic scan when 0.500 [millicuries] had | | been prescribed by the authorized user. The administered dose exceeded the | | prescribed dose by 40%. | | | | "In both cases the patients attending physician concluded that these doses | | had 'no clinical significance to either patient and therefore no untoward | | effects.' He ordered that this not be reported to the patients. | | | | "According to the licensee, these events occurred because the nuclear | | medicine staff was operating under a window wider than the 20% maximum | | deviation allowed in the 420-3-26-.07(2)(m)1.b of the Alabama Rules for | | Control of Radiation. The licensee stated that the nuclear medicine | | department had been using criteria from an article published in the Journal | | of Nuclear Medicine which 'quoted NRC regulations with a greater | | tolerance.' | | | | "The licensees corrective action was to notify nuclear medicine staff | | members both verbally and in writing of the current Alabama regulations. The | | State of Alabama considers the licensee's actions to be appropriate and the | | matter closed." | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Hospital |Event Number: 39143 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: VA NATIONAL HEALTH PHYSICS PRGM |NOTIFICATION DATE: 08/22/2002| |LICENSEE: VA MEDICAL CENTER |NOTIFICATION TIME: 12:34[EDT]| | CITY: NORTH PORT REGION: 1 |EVENT DATE: 08/20/2002| | COUNTY: STATE: NY |EVENT TIME: [EDT]| |LICENSE#: 31-13511-05 AGREEMENT: Y |LAST UPDATE DATE: 08/22/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |CLIFFORD ANDERSON R1 | | |FRED BROWN NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: GARY WILLIAMS | | | HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |LADM 35.33 MED MISADMINISTRATION | | |ISAF 30.50(b)(2) SAFETY EQUIPMENT FAILUR| | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REPORT OF POSSIBLE MISADMINISTRATION AND/OR SAFETY EQUIPMENT FAILURE | | | | On 8/20/02 a patient was being prepared for treatment in a Co-60 teletherapy | | unit by two technicians when the beam turned on with no operator action. | | The beam was on for about 50 seconds. The event is being investigated and | | the unit has been placed out-of-service. It is unknown at this time whether | | the patient was in position or not and received an exposure to the right or | | wrong site. The investigation will determine if there was an actual | | misadministration, exposure to the wrong area. The two technicians' | | dosimeters were processed and the results showed no exposure in excess of | | limits, actual reading was 20 millirem for both badges. | | | | The licensee will update this report when more information is determined. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39144 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 08/22/2002| | UNIT: [] [] [3] STATE: CT |NOTIFICATION TIME: 17:06[EDT]| | RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 08/22/2002| +------------------------------------------------+EVENT TIME: 16:33[EDT]| | NRC NOTIFIED BY: MICHAEL MARTELL |LAST UPDATE DATE: 08/22/2002| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |CLIFFORD ANDERSON R1 | |10 CFR SECTION: | | |AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | |3 N Y 95 Power Operation |95 Power Operation | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNANALYZED CONDITION CONCERNING STEAM GENERATOR ATMOSPHERIC RELIEF VALVE | | BYPASS VALVES | | | | Historical analysis deficiencies associated with the steam generator | | atmospheric dump bypass valves, a condition that during a fire could cause | | seriously degrade the safety of the plant. | | | | "The system affected is main steam, there are no actuation signals. The | | cause is historical analysis deficiencies. There are no affects on the | | plant. There are no actions taken or planned at this time and there is no | | additional information. The NRC Resident Inspector was notified. The State | | and Local Authorities have been notified." | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39145 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 08/22/2002| | UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 17:25[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/22/2002| +------------------------------------------------+EVENT TIME: 16:50[EDT]| | NRC NOTIFIED BY: DENNIS MOORE |LAST UPDATE DATE: 08/22/2002| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: UNUSUAL EVENT |KEN BARR R2 | |10 CFR SECTION: |JOHN HANNON NRR | |AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |JOSEPH HOLONICH IRO | |APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION |KEN CIBOCH FEMA | |ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | |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 M/R Y 100 Power Operation |0 Hot Standby | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 DECLARED AN UNUSUAL EVENT DUE TO A FIRE IN THE TURBINE BUILDING | | | | "Fire in Turbine Building at H2 Dryer lasting for greater than 15 minutes. | | Fire out at 1655 [hours]. Fire reported at 1633 [hours]." | | | | The Fire Brigade responded and extinguished the fire. The Hydrogen Dryer | | has been isolated. Offsite assistance was not requested. There were no | | injuries reported. A preliminary assessment revealed extensive damage to | | the Hydrogen Dryer as a result of the fire. The cause of the fire is under | | investigation. There were no maintenance activities, e.g., welding, in | | progress at the time. | | | | Operators manually tripped Unit 2. All rods fully inserted. The plant | | responded as expected. No secondary reliefs lifted. Auxiliary Feedwater | | autostarted to maintain Steam Generator water levels. The Main Condenser is | | in-service removing decay heat via the main steam dumps. Cooldown limits | | were not exceeded during the transient. Unit 2 will remain in mode 3 | | pending completion of the investigation. | | | | The licensee informed state/local agencies and the NRC Resident Inspector. | | | | * * * UPDATED AT 1855 EDT ON 8/22/02 BY DENNIS MOORE TO FANGIE JONES * * * | | | | Unusual Event terminated at 1830 EDT. The fire extinguished when the | | hydrogen isolation valve was closed, automatic sprinkler system actuated | | which allowed personnel access to the isolation valve. | | | | The licensee notified the NRC Resident Inspector. Notified the R2DO (Ken | | Barr), NRR EO (John Hannon), IRO (Joe Holonich), and FEMA (David Barden). | | | | * * * UPDATED AT 2023EDT ON 8/22/02 BY WAYNE HOYLE TO S. SANDIN * * * | | | | The licensee furnished the following additional information: | | | | "On August 22, 2002 at 1636 hours, a manual reactor trip was initiated on | | McGuire Unit 2 in response to a fire in a hydrogen dryer in the hydrogen | | supply to the Unit 2 Turbine Generator. As a result of the fire, the | | hydrogen supply to the turbine generator experienced a low pressure | | condition and plant operators manually tripped the reactor (RPS Actuation) | | to prevent damage to the turbine generator. Following the trip, the Unit 2 | | Auxiliary Feedwater Pumps started due to loss of Unit 2 Main Feedwater Pumps | | (Auxiliary Feedwater System Actuation). Subsequent to the start of the Unit | | 2 Auxiliary Feedwater Pumps, the 2C Steam Generator experienced a HI-HI | | water level. Level was restored and the water level in all four Steam | | Generators is currently in the normal band for existing plant conditions. | | | | "The fire in the Unit 2 hydrogen dryer has been extinguished. Plant | | equipment necessary to safely shutdown Unit 2 operated correctly and the | | Unit is stable and in Mode 3. The Unit 2 Auxiliary Feedwater Pumps are still | | running supplying the Steam Generators. An investigation into the cause of | | the fire is in progress. | | | | "The NRC Resident Inspector has been notified." | | | | Notified R2DO(Barr). | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021