Event Notification Report for July 8, 2003
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/07/2003 - 07/08/2003 ** EVENT NUMBERS ** 39631 39975 39976 39980 39981 39982 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39631 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 03/02/2003| | UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 16:00[EST]| | RXTYPE: [1] CE,[2] CE |EVENT DATE: 03/02/2003| +------------------------------------------------+EVENT TIME: 14:30[EST]| | NRC NOTIFIED BY: CHARLES PIKE |LAST UPDATE DATE: 07/07/2003| | HQ OPS OFFICER: GERRY WAIG +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |WALTER RODGERS R2 | |10 CFR SECTION: |DAVID AYRES R2 | |APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION TO STATE AGENCY OF EXPIRED GREEN SEA TURTLE FOUND AT | | BARRIER NET | | | | "NRC notification [is] being made due to state notification to [the] Florida | | Wildlife Commission regarding a Green Sea Turtle found dead at barrier net | | pursuant to 10 CFR 50.72(b)(2)(xi)." | | | | The turtle was found on the surface at the barrier net with no injuries or | | abnormalities except for fresh cuts common for turtles coming through pipes. | | The cause of death is unknown at this time. A necropsy is planned. | | | | The NRC Resident Inspector will be notified by the licensee. | | | | * * * UPDATE ON 3/15/03 @ 1033 EST FROM TEREZAKIS TO CROUCH * * * | | | | "On 3-15-03, a green sea turtle was retrieved from the plant's intake canal. | | The turtle was determined to be in need of rehabilitation. The injuries to | | the turtle are not causal to plant operation. Per the plant's turtle permit, | | the Florida Fish and Wildlife Conservation Commission (FWCC) was notified at | | 0920 EST. This non-emergency notification is being made pursuant to 10 CFR | | 50.72(b)(2)(xi) due to the notification of FWCC." | | | | The NRC Resident Inspector will be notified by the licensee. | | | | * * * UPDATE ON 3/19/03 AT 1222 EST FROM E. SUMNER TO RIPLEY * * * | | | | "On 03/19/03 @ 1105 hrs., one loggerhead turtle was retrieved from the | | plant's intake canal. The turtle was determined to be in need of | | rehabilitation. The injury to the turtle is not causal to plant operation. | | Per the plant's turtle permit, the Florida Fish and Wildlife Conservation | | Commission (FWCC) was notified at 1115 EST." | | | | The NRC Resident Inspector was notified. | | | | * * * UPDATED ON 3/31/03 AT 1159 EST FROM W.L. PARK TO A. COSTA * * * | | | | "On 3-31-03 [1105 EST], a loggerhead sea turtle was retrieved from the | | plant's intake canal. The turtle was determined to be in need of | | rehabilitation. The injuries to the turtle are not causal to plant | | operation. Per the plant's turtle permit, the Florida Fish and Wildlife | | Conservation Commission (FWCC) was notified at 1105 EST. This non-emergency | | notification is being made pursuant to 10 CFR 50.72(b)(2)(xi) due to the | | notification of FWCC." | | | | The NRC Resident Inspector will be notified. | | | | * * * UPDATE 1235EST ON 4/9/03 FROM ANDY TEREZAKIS TO S.SANDIN * * * | | | | "On 4-9-03, a loggerhead sea turtle was retrieved from the plant's Intake | | canal. The turtle was determined to be in need of rehabilitation. The | | injuries to the turtle are not causal to plant operation. Per the plant's | | turtle permit, the Florida Fish and Wildlife Conservation Commission (FWCC) | | was notified at 1100 EST. This non-emergency notification is being made | | pursuant to 10CFR50.72(b)(2)(xi) due to the notification of FWCC." | | | | The licensee informed the NRC resident inspector. Notified R2DO(Landis). | | | | *** UPDATE ON 5/2/03 AT 1826 FROM S. OEHRLE TO A. COSTA *** | | | | "On 5/2/03, a green sea turtle was retrieved from the intake canal. The | | turtle required rehabilitation. The injuries were not causal to plant | | operation. Per the plant's turtle permit, the Florida Fish and Wildlife | | Conservation Commission was notified at 1445 EDT. This non-emergency | | notification is being made pursuant to 10 CFR 50.72 (b)(2)(xi) due to | | offsite notification." | | | | The Licensee will notify the NRC Resident Inspector. Notified R2DO | | (Munday). | | | | **** update on 05/24/03 at 1417 EDT FROM JOE HESSLING TO JOHN MACKINNON | | **** | | | | "On 5-24-03, a loggerhead sea turtle was retrieved from the plant's intake | | canal. The turtle was determined to be in need of rehabilitation. The | | turtle was very underweight and lethargic, no injuries or anomalies noted. | | Turtle's condition is not causal to plant operation. Per the plant's turtle | | permit the Florida Fish and Wildlife Conservation Commission (FWCC) was | | notified at 1345 EDT. This non-emergency notification is being made | | pursuant to 10 CFR 50.72(b)(2)(xi) due to the notification of FWCC. NRC R2DO | | (TOM DECKER) notified. | | | | The NRC Resident Inspector was by notified of this event by the licensee. | | | | ****UPDATE ON 5/27/03 AT 10:49 FROM HESSLING TO LAURA**** | | | | "On 5-27-03, a loggerhead sea turtle was retrieved from the plant's intake | | canal. The turtle was determined to be in need of rehabilitation. The turtle | | was underweight, and missing lower posterior marginals on left side. | | Turtle's injuries are not causal to plant operation. Per the plant's turtle | | permit, the Florida Fish and Wildlife Conservation Commission (FWCC) was | | notified at 0850 EDT. This non-emergency notification is being made pursuant | | to 10 CFR 50.72(b)(2)(xi) due to the notification of FWCC." | | | | Notified R2DO (T. Decker) | | | | * * * UPDATE ON 06/17/03 AT 12:45 EDT FROM CALVIN WARD TO ARLON COSTA * * * | | | | "At approximately 12:45 p.m. on 6/17/03 a loggerhead turtle was rescued from | | the St. Lucie Plant intake canal. The turtle was injured and will be | | transported to the State authorized sea turtle rehabilitation facility. The | | Florida Dept. of Environmental Protection (FDEP) was notified at 1:09 p.m. | | as required by the St. Lucie Plant Sea Turtle Permit - see the attached sea | | turtle stranding report (1 page). | | | | "Notification to the state government agency requires a four (4) Hr. | | Non-Emergency Notification to the NRC per 10 CFR 50.72(b)(2)(xi). There were | | no unusual plant evolutions in progress which may have contributed to this | | event." | | | | The licensee notified the NRC Resident Inspector. | | | | Notified R2DO (L. Wert). | | | | * * * UPDATE 0605 EDT ON 6/26/03 FROM STEVE MERRILL TO S. SANDIN * * * | | | | The licensee was informed by the FWCC that the green sea turtle requiring | | rehabilitation which was retrieved from the plant's intake canal on 3/15/03 | | had expired within 10 days of removal. Consequently, the licensee is | | updating their 3/15/03 report to include this additional information. The | | licensee will inform the NRC Resident Inspector. Notified R2DO(C. Ogle). | | | | * * * UPDATE 1506 EDT ON 07/01/03 FROM CALVIN WARD TO GOTT * * * | | | | On 04/02/03, a green sea turtle was retrieved from the intake canal. The | | turtle required rehabilitation. The injuries were not causal to plant | | operation. Per the plant's turtle permit, the Florida Fish and Wildlife | | Conservation Commission was notified. This non-emergency notification is | | being made pursuant to 10 CFR 50.72 (b)(2)(xi) due to offsite notification. | | On 07/01/03 licensee QA discovered that the injury had occurred and that the | | NRC had not been notified within the 4 hours. The failure to report the | | event within the regulatory time is being investigated and has been entered | | into the stations corrective action program. | | | | The licensee notified the NRC Resident Inspector. | | | | Notified R2DO (Munday) | | | | * * * UPDATE 1750 EDT ON 07/07/03 FROM JOE HESSLING TO MACKINNON * * * | | | | On 07/07/03, a Loggerhead sea turtle was retrieved from the plants' intake | | canal. The turtle was determined to be in need of rehabilitation. The | | injuries to the turtle are not causal to plant operation. Per the plant's | | Turtle permit, the Florida Fish and Wildlife Conversation Commission (FWCC) | | was notified at 1715 EDT. This non-emergency is being made pursuant to 10 | | CFR 50.72(b)(2)(xi) due to the notification of FWCC. | | | | The licensee notified the NRC Resident Inspector. | | | | Notified R2DO (Munday). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 39975 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 07/03/2003| |LICENSEE: H&G INSPECTION |NOTIFICATION TIME: 17:59[EDT]| | CITY: Texas City REGION: 4 |EVENT DATE: 05/20/2003| | COUNTY: STATE: TX |EVENT TIME: 14:30[CDT]| |LICENSE#: L02181 AGREEMENT: Y |LAST UPDATE DATE: 07/03/2003| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |CHARLES MARSCHALL R4 | | |THOMAS ESSIG NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: HELEN WATKINS | | | HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OVEREXPOSURE | | | | Event occurred on May 20, 2003 between the hours of 0200 and 0230 hours CDT | | at the Amoco Refinery in Texas City, TX. Overexposure was reported to the | | Texas Dept. of Health on July 3, 2003. | | | | "A radiography source was not cranked into the fully shielded position | | resulting in a 6.403 R whole body exposure to a radiographer. The | | radiographer was making wall thickness exposures using a 100 curie cobalt 60 | | source with a directional collimator. The radiographer made the last | | exposure for the night, then proceeded to retrieve the film and take it for | | development in the darkroom. The radiographer believed the pigtail had been | | fully retracted, however, his initial survey was not conclusive because his | | survey meter was not turned on. Although the ratemeter was alarming, | | because of the noise level and the ear plugs, he did not initially hear | | ratemeter alarming. When he did hear the faint ringing he checked the meter | | and it was off. When the radiographer turned the meter on and resurveyed the | | guide tubes, the needle went off-scale. He checked his pocket dosimeter and | | it was off scale. The radiographer then retracted the pigtail into the | | fully shielded position. The radiographers reported the event to their | | management by telephone, then returned to the company shop. | | | | "The following day the personnel monitoring badge was sent for emergency | | processing. The radiographer believes he was exposed for about one minute. | | | | "We will provide additional information as it is collected" | | | | Source Production & Equipment Company. | | Source Information: | | Model G-70 sn# C60-02 | | 101 Curies cobalt-60 on May 29, 2002 (3737GBq) | | | | Texas Incident No: I-8033 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 39976 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 07/03/2003| |LICENSEE: SUNOCO CHEMICALS |NOTIFICATION TIME: 18:41[EDT]| | CITY: LaPorte REGION: 4 |EVENT DATE: 06/19/2003| | COUNTY: STATE: TX |EVENT TIME: 06:45[CDT]| |LICENSE#: L02778 AGREEMENT: Y |LAST UPDATE DATE: 07/03/2003| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |CHARLES MARSCHALL R4 | | |THOMAS ESSIG NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: HELEN WATKINS | | | HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DAMAGED TEXAS NUCLEAR MODEL 5180A LEVEL GAUGE | | | | "An explosion and fire occurred in a distillation unit. The operating units | | were shut down and the fire was extinguished. A visual inspection of a | | level gauge installed on a vessel located in the area showed the device was | | intact with no apparent physical damage except heat discoloration was | | visible on the device. A preliminary survey found no readings above the | | regulatory limits. However, an attempt to close the shutter was made and | | debris and molten materials made the closing difficult. A wipe test was | | performed with no leakage found. The device and area was barricaded to | | prevent unauthorized entry. | | | | "Consultant Assistance: | | A radiation technician from Alpha Process Sales inspected the device and the | | area. Occupancy surveys were made and showed no persons who entered the | | area received exposures over the allowable limits. | | | | "Thermo-Measuretech of Round Rock, TX, an authorized company, removed the | | device and took possession for disposal. | | | | "TX Nuclear Level Gauge | | TN model 5180A | | source sn# B380, 500mCi [millicuries] Cs-137" | | | | Texas Incident No: I-8032 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39980 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 07/07/2003| | UNIT: [] [2] [3] STATE: AL |NOTIFICATION TIME: 19:32[EDT]| | RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 07/07/2003| +------------------------------------------------+EVENT TIME: 15:00[CDT]| | NRC NOTIFIED BY: DONALD SMITH |LAST UPDATE DATE: 07/07/2003| | HQ OPS OFFICER: ERIC THOMAS +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |JOEL MUNDAY R2 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 N Y 100 Power Operation |100 Power Operation | |3 N Y 100 Power Operation |100 Power Operation | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNANALYZED CONDITION | | | | "At 1500 on 07/07/2003, Operations received a revised Functional Evaluation | | concerning a Unit 1 Appendix R Analysis which affected both Units 2 & 3. It | | was identified that a Reactor Building fire could fault a Recirc Pump Motor | | Generator (MG) Set supply cable/control power cable and cause a loss of the | | control power required to trip the breaker. Upon further review, it was | | determined that the 250v dc control power associated circuit for the Recirc | | Pump Board breaker trip circuit does not have adequate separation from the | | 4KV feeder cable to the Recirc Pump MG Set (Unit 3) or the Variable | | Frequency Drive (Unit 2). A fire propagating to the Cable Spreading Room | | from the Reactor Building may affect safe shutdown circuits and remains | | unanalyzed. Roving Fire watches were established in the affected areas on | | both Units 2 & 3. | | | | "This event is reportable as an 8-hour Notification and a 60-day written | | report in accordance with 10 CFR 50.72 (b)(3)(ii)(B) & 10 CFR | | 50.73(a)(2)(ii) as 'Any event or condition that results in the Nuclear Power | | Plant being in an unanalyzed condition that significantly degrades plant | | safety.'" | | | | The licensee notified the NRC Resident Inspector | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 39981 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 07/07/2003| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 23:44[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 07/07/2003| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 07/07/2003| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |CHRIS MILLER R3 | | DOCKET: 0707002 |THOMAS ESSIG NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: SPAETH | | | HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL ACTUATION OF A SAFETY SYSTEM DUE TO UF6 CYLINDER LEAKAGE | | | | "On 07/07/03 at 1100 hrs the Plant Shift Superintendent's (PSS) office was | | notified by operations personnel at the X344 facility, that during the | | initiation of UF6 transfer from Autoclave #3 to the daughter cylinder, smoke | | was observed emitting from between the cylinder valve stem and packing | | gland. The operator attempted to shut the cylinder valve, but discovered | | that the stem would continue to turn in the closing direction well beyond | | its normal expected shut position. Out gassing continued to be observed | | emitting from between the cylinder valve stem and packing gland. The First | | Line Manager, observing the evolution directed the Operator to press the | | Emergency Closure Button placing autoclave #3 into containment. This was | | manual actuation of Safety Equipment used to mitigate (prevent) a release of | | UF6. Emergency Response was initiated and the Gas Release Alarm was | | activated to evacuate the building, which placed the other in service | | autoclave into containment. All Air monitoring was less than detectable for | | HF and below Plant Allowable Limits for Beta and Gamma." | | | | Operations notified both the DOE site representative and the NRC resident | | inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39982 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 07/08/2003| | UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 02:52[EDT]| | RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 07/07/2003| +------------------------------------------------+EVENT TIME: 23:19[CDT]| | NRC NOTIFIED BY: LARRY BLUNK |LAST UPDATE DATE: 07/08/2003| | HQ OPS OFFICER: GERRY WAIG +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |CHRIS MILLER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 A/R Y 100 Power Operation |0 Hot Shutdown | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM AT LaSALLE UNIT 2 DUE TO TRIP OF THE MAIN TURBINE | | | | "At 2319 CDT on July 7, 2003 LaSalle Unit 2 Automatically scrammed due to a | | trip of the main turbine. The main turbine trip was caused by a main lockout | | due generator to a fault on the "B" phase of the main power disconnect. All | | rods inserted on the scram. Three safety relief valves actuated in the | | relief mode on the turbine trip. Both reactor recirc pumps tripped off and | | all three circulation water pumps tripped off. The main steam line isolation | | valves and main steam line drains were closed due to the loss of the | | circulating water pumps. Tech Spec 3.0.3 was entered due to simultaneous | | inoperability of A, B, and C residual heat removal pumps. "A" residual heat | | removal pump was declared inoperable due to use in suppression pool cooling. | | "B" and "C" residual heat removal pumps were inoperable at the beginning of | | the event for planned preventative maintenance on the essential core cooling | | system ventilation. There were no automatic actuations of ECCS systems and | | no primary or secondary containment isolation system actuations. There was | | no ECCS injections into the reactor vessel. There were 3 subsequent auto | | scram signals on low reactor level due to level shrink on SRV closure in | | pressure control." | | | | Unit 2 is currently stable with reactor feedwater being provided by the | | condensate system and reactor heat removal using SRV steam discharge to the | | suppression pool. Residual heat removal pumps "A" and "B" are operating to | | provide suppression pool cooling. "C" residual heat removal pump has been | | returned to operable status. All emergency diesel generators are available. | | | | The licensee also reported that the electrical system transient resulted in | | the need to reduce power on LaSalle Unit 1 from 100% to ~92% to stabilize | | condensate booster pump suction pressure. | | | | The licensee has notified the NRC Resident Inspector | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021