Event Notification Report for June 17, 2002
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/14/2002 - 06/17/2002 ** EVENT NUMBERS ** 38979 38985 38991 38992 38993 38995 +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 38979 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE: 06/11/2002| |LICENSEE: THE BOEING COMPANY |NOTIFICATION TIME: 19:50[EDT]| | CITY: ANAHEIM REGION: 4 |EVENT DATE: 06/11/2002| | COUNTY: STATE: CA |EVENT TIME: [PDT]| |LICENSE#: 0065-30 AGREEMENT: Y |LAST UPDATE DATE: 06/11/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |ANTHONY GODY R4 | | |THOMAS ESSIG NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: ROBERT GREGER | | | HQ OPS OFFICER: RICH LAURA | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT FROM CA REGARDING POTENTIAL PERSONNEL OVEREXPOSURE | | | | The California state radiation safety officer called in a potential 20.2202 | | personnel overexposure incident that occurred at The Boeing Company in | | Anaheim, California. The licensee utilizes irradiator facilities large | | enough for an individual to enter. The individual's dosimeter was read by | | the personnel monitoring vendor (i.e., Landauer) as 94 Rem DDE, 94 Rem LDE | | and 112 Rem SDE. The dosimetry was worn during the period of April 1 to | | April 30, 2002. The licensee commenced an investigation to determine the | | validity of the high and unexpected reading. The licensee will conduct an | | interview with the individual and also the State indicated a blood test will | | most likely be performed. The State indicated the badge received a "static" | | exposure, and it will probably turn out to be a dosimeter-only exposure. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 38985 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 06/12/2002| |LICENSEE: FURGO SOUTH INC. |NOTIFICATION TIME: 17:30[EDT]| | CITY: HOUSTON REGION: 4 |EVENT DATE: 06/12/2002| | COUNTY: HARRIS STATE: TX |EVENT TIME: 12:00[CDT]| |LICENSE#: L00058 AGREEMENT: Y |LAST UPDATE DATE: 06/12/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |ANTHONY GODY R4 | | |LARRY CAMPER NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: HELEN WATKINS (via fax) | | | HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT INVOLVING A STOLEN TROXLER GAUGE | | | | "A technician was transporting a gauge that was chained, locked, and secured | | on the back of a pickup truck. He stopped at a restaurant for a take out | | lunch. Upon returning to the truck, he noticed the gauge was missing. The | | chain was cut. | | Some other items, including test equipment and a sand cone, were taken. | | Gauge: Troxler Model 3430, ser#26992 Sources: 8 mCi Cs-137 ser#750-171 [and] | | 40 mCi Am-241 ser#47-23560." | | | | The local police, Troxler Electronics and the TXDOT were informed. Texas | | Incident No.: I-7907 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38991 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 06/14/2002| | UNIT: [] [2] [] STATE: TX |NOTIFICATION TIME: 07:14[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/14/2002| +------------------------------------------------+EVENT TIME: 04:35[CDT]| | NRC NOTIFIED BY: KLAY KLIMPLE |LAST UPDATE DATE: 06/14/2002| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |ANTHONY GODY R4 | |10 CFR SECTION: | | |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 +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP FOLLOWING CLOSURE OF A FEEDWATER ISOLATION VALVE DURING | | SURVEILLANCE TESTING | | | | The following text is a portion of a facsimile received from the licensee: | | | | "At 04:35 [CDT] on 06/14/2002, operators manually tripped the reactor | | following closure of feedwater isolation valve 2C during surveillance | | testing. The cause of the feedwater isolation valve failure is unknown at | | this time. Also, both source range nuclear instruments failed to energize | | following the reactor trip, but both extended range nuclear instruments are | | available. The auxiliary feedwater system actuated as expected on steam | | generator low-low level." | | | | "Did the rods fully insert? yes | | Did steam bypass to the condenser or to atmosphere? condenser | | Did any primary/secondary relief valves lift? no | | Any electrical bus transfer problems? no | | State normal operating temperature and pressure (NOT/NOP)[:] 590 degrees | | 2235 psig | | Any significant TS LCOs entered? no" | | | | The licensee stated that there was nothing unusual or misunderstood with the | | exception of the cause of the feedwater isolation valve failure and the | | cause of the failure of both source range nuclear instruments to energize | | following the reactor trip. All systems functioned as required with the | | same exceptions. | | | | The licensee also stated that the unit is currently stable in Mode 3 (Hot | | Standby). Normal charging and letdown, pressurizer heaters and sprays, and | | the reactor coolant pumps are currently being utilized for primary system | | level, pressure, and transport control. Secondary steam is being dumped to | | the condenser, and auxiliary feedwater is supplying water to the steam | | generators. Operators are in the process of transferring from auxiliary | | feedwater to main feedwater. All engineered safety feature equipment and | | emergency core cooling systems are operable and available if needed. | | | | The licensee notified the NRC resident inspector. | | | | * * * UPDATE ON 6/14/02 @ 2243 BY REDDIX TO GOULD * * * | | | | Licensee reported that after further investigation it was determined that | | both source range instruments did energize as expected, however, after | | indicating some counts erratically, they decayed away to zero. Both source | | range detectors are inoperable at this time. | | | | The NRC Resident Inspector was notified. | | | | Notified Reg 4 RDO(Gody) | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38992 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 06/14/2002| | UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 11:24[EDT]| | RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 06/13/2002| +------------------------------------------------+EVENT TIME: 11:30[EDT]| | NRC NOTIFIED BY: DOUG RICHARDSON |LAST UPDATE DATE: 06/14/2002| | HQ OPS OFFICER: RICH LAURA +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |LAWRENCE DOERFLEIN R1 | |10 CFR SECTION: |JOHN DAVIDSON IAT | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 24 HOUR REPORT ON LICENSE CONDITION 2F | | | | " At 1130 hours on 6/13/02 it was discovered that the Safety Relief Valve | | (SRV) Position Indication Channel for one of the SRVs controlled from the | | Remote Shutdown Panel was inoperable. The inoperability was due to both | | alarm card inhibit switches for associated acoustic monitoring channel being | | found to be in the inhibit position. These switches are normally in the | | "alarm" position. With the switches in the "inhibit" position the SRV | | position indication from a high vibration condition would not provide an | | open position indication for the SRV in the Control Room or at the Remote | | Shutdown Panel. Immediate Action was to return the switches to the alarm | | position and all other SRV acoustic monitoring switches were verified to be | | in the correct "alarm" position. | | | | "Technical Specification LCO 3.3.3.2 requires that the Remote Shutdown | | System Functions shall be OPERABLE. With this channel inoperable, Required | | Actions require restoration to OPERABLE status within 30 days OR placing the | | Unit in Mode 3 within the following 12 hours. Since the potential exists | | that this condition has existed in excess of the 30-day requirement this | | event may be considered a Condition Prohibited by Technical Specifications. | | | | "This report is being made in accordance with Section 2F of Operating | | License NPF-69 for Nine-Mile Point Unit 2. Section 2F requires that the | | initial notification of a violation of any requirement contained in Section | | 2C to the Operating License (License Conditions) be reported to the NRC | | Operations Center via the Emergency Notification System within 24 hours with | | written follow-up with 30 days. License Condition 2C requires that Nine Mile | | Point Nuclear Station, LLC shall operate the facility in accordance with the | | Technical Specifications." | | | | The NRC Resident Inspector has been notified. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38993 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 06/14/2002| | UNIT: [1] [] [] STATE: MI |NOTIFICATION TIME: 17:14[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/14/2002| +------------------------------------------------+EVENT TIME: 14:43[EDT]| | NRC NOTIFIED BY: MAY |LAST UPDATE DATE: 06/14/2002| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |JAMES CREED 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 M/R Y 88 Power Operation |0 Hot Standby | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR MANUALLY TRIPPED FROM 88% POWER DUE TO LOSS OF THE EAST MAIN FEED | | PUMP ON LOW CONDENSER VACUUM | | | | At 1443 the unit one reactor was manually tripped from 88% reactor power due | | to the loss of the East Main Feedwater pump on low condenser vacuum. Loss | | of East Main Feedwater Pump Condenser Vacuum occurred during the start of | | #13 Main Circulating Water Pump. It is believed that this was caused by | | high differential pressure across the feed pump condenser and it appeared | | that the circulating water pump transferred some debris from the forebay | | into the condenser resulting in the loss of condenser vacuum, but this | | incident is still under investigation. | | | | All rods fully inserted, no ECCS injection and no safety relief valves | | lifted. | | | | Plant is currently stable in Mode 3. All plant equipment functioned as | | designed. Event Investigation is currently in progress. | | | | The NRC Resident Inspector was notified. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38995 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 06/15/2002| | UNIT: [1] [2] [] STATE: GA |NOTIFICATION TIME: 14:54[EDT]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/15/2002| +------------------------------------------------+EVENT TIME: 08:30[EDT]| | NRC NOTIFIED BY: WATTS |LAST UPDATE DATE: 06/15/2002| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |KERRY LANDIS R2 | |10 CFR SECTION: | | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FITNESS-FOR-DUTY QUESTIONED DUE TO FAILURE OF ALCOHOL TEST | | | | COMPENSATORY MEASURES TAKEN | | | | THE RESIDENT INSPECTOR WAS NOTIFIED | | | | Refer to HOO for additional details | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021