Event Notification Report for October 4, 2002
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/03/2002 - 10/04/2002 ** EVENT NUMBERS ** 37995 39114 39241 39242 39243 39245 +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 37995 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: FLORIDA BUREAU OF RADIATION CONTROL |NOTIFICATION DATE: 05/16/2001| |LICENSEE: WINGERTER LABORATORIES, INC. |NOTIFICATION TIME: 16:12[EDT]| | CITY: MIAMI REGION: 2 |EVENT DATE: 05/15/2001| | COUNTY: DADE STATE: FL |EVENT TIME: 16:00[EDT]| |LICENSE#: 0673-1 AGREEMENT: Y |LAST UPDATE DATE: 10/03/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |CHARLES R. OGLE R2 | | |SUSAN FRANT NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: JEAROLD EAKINS (fax) | | | HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT REGARDING THE THEFT OF A TROXLER GAUGE FROM THE | | RESIDENCE OF A WINGERTER LABORATORIES, INC. EMPLOYEE IN MIAMI, FLORIDA | | | | The following text is a portion of a facsimile received from the Florida | | Bureau of Radiation Control: | | | | "Incident Number[:] FL01-057" | | | | "Incident Date[:] 15-May-01" | | | | "Licensee or Owner[:] WINGERTER LABORATORIES, INC." | | | | "City, State, and Zip Code[:] Miami, FL 33181" | | | | "License #[:] 0673-1" | | | | "License Type; Category[:] Specific; 3L(1)" | | | | "Isotope(s)[:] Cs-137, Am-241" | | | | "Activity(s)[:] N/A" | | | | "Material Form; Chemical Form; Physical Form[:] N/A" | | | | "Portable Disposition of Material[:] Unknown" | | | | "Exposure? No" | | | | "Incident Category[:] Loss of Control - Lost , Abandoned, or Stolen | | Materials" | | | | "Location Classification[:] Unrestricted Area" | | | | "Incident Description[: A licensee] operator[, ...,] was transporting [the] | | gauge from [a] jobsite to [the] office and stopped off at [a] personal | | residence (@ [approximately] 1600 hrs.). [The employee] left [the] truck | | running while he went into [the] residence. When [the] employee returned, | | [the] truck and gauge were missing. [The key] ring for [the] truck also | | contained keys to [the] gauge[,] employees residence[,] and personal | | vehicles. Company has issued [a] press release in the Miami Herald | | newspaper offering $1,000 for information on [the] return of [the] | | truck/gauge. [The truck] was reported recovered at 1500 on 16 May. [The | | gauge] is still missing." | | | | "Device Type (Quantity)[:] Soil moisture/Density Gauge" | | | | "Manufacturer[:] Troxler" | | | | "Model Number[:] 3411-B" | | | | "Serial Number(s)[:] 7400" | | | | "Emergency Groups at Scene[:] USNRC, State Warning Point" | | | | "Organizations Notified[:] Metro Dade PD" | | | | "Media Contacted[:] None" | | | | (Call the NRC operations officer for state and licensee contact information, | | the incident location, and licensee operator name.) | | | | ***UPDATE 10/3/02 0809 EDT JERRY EAKINS TO MIKE NORRIS*** | | | | "Pick-up truck, driven by [ ],scrap metal collector, tripped the monitor | | alarm. [ ]identified the isotope as Cs- | | 137 with an Exploraniun instrument. After consultation with this office, [ ] | | unloaded the truck, identified the gauge, and placed it in a secure locked | | box until the inspector picked it up. The gauge had been reported stolen on | | 15 May 01, incident report FL01-057. Incident tag # K-31 was issued. Gauge | | was returned to licensee." | | | | The source was secured and locked. Surveys indicated no leakage from the | | source. | | | | Notified R2DO (Henson) and NMSS EO (Brown). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39114 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 08/06/2002| | UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 16:08[EDT]| | RXTYPE: [1] W-4-LP |EVENT DATE: 08/06/2002| +------------------------------------------------+EVENT TIME: 10:00[CDT]| | NRC NOTIFIED BY: STEVE GIFFORD |LAST UPDATE DATE: 10/03/2002| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |CHUCK CAIN R4 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE DISCOVERED A POST-FIRE SAFE SHUTDOWN FUNCTION THAT MAY NOT BE MET | | | | "On August 6, 2002, conditions were discovered where a postulated fire could | | cause the pressurizer to blow down to the pressurizer relief tank (PRT). | | Wolf Creek is in Mode 1, at 100% power. | | | | "During reviews associated with post-fire safe shutdown reanalysis work, | | Wolf Creek personnel discovered that power and control cables for a | | pressurizer power operated relief valve (PORV) and its associated motor | | operated block valve are routed in electrical raceways with no horizontal | | separation. The two valves are in the same electrical separation group but | | are redundant in their post-fire safe shutdown function to prevent reactor | | coolant system (RCS) blowdown to the PRT. Further investigation determined | | that the power and control cables in the opposite separation group have the | | same configuration. This does not meet our commitments to 10 CFR 50 Appendix | | R.lll.G as reflected in our approved Fire Protection Plan. | | | | "During a fire in the plant, it is the function of PORV valves and block | | valves to provide a barrier to blowing down the RCS into the PRT. A fire in | | any of the affected fire areas in which the circuits are routed has the | | potential to damage cables in a manner that cause a the PORV to spuriously | | open (due to a hot short), and to damage cables in a manner that causes the | | block valve to not respond to a close signal (due to an open circuit or a | | hot short). This would cause a non-isolable RCS blowdown to the PRT. | | | | "Based on the guidance provided in NUREG 1022 Revision 2, this situation | | meets the criterion of 10 CFR 50.72(b)(3)(ii)(B) for an 8-hour ENS | | notification, as it relates to being in an unanalyzed condition. | | | | "The licensee has implemented a 1-hour fire watch and is developing | | compensatory measures. | | | | "The licensee notified the NRC Resident Inspector." | | | | * * * RETRACTED AT 1544 EDT ON 10/3/02 BY STEVEN HENRY TO FANGIE JONES * * | | * | | | | "Wolf Creek has reevaluated the routing of the cables for the PORV and its | | associated block valve using the guidance contained in Generic Letter 86-10 | | and in NUREG 1022 Revision 2, and has determined that this condition is not | | reportable. The reevaluation shows that the reactor core will never be | | uncovered even if the PORV were to remain open and that a diverse means is | | available via the deenergization of a dc bus to close the PORV in the event | | of a fire. A fire initiated spurious opening of the PORV will not result in | | a condition that significantly degrades plant safety. This is based on the | | plant design, low probability of occurrence and actions to mitigate this | | event. Therefore, per NUREG 1022, this condition is not an unanalyzed | | condition that significantly degrades plant safety and is not required to be | | reported in accordance with 10CFR50.72(b)(3)(ii)(B)." | | | | The licensee notified the NRC Resident Inspector. Notified R4DO (Kriss | | Kennedy). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39241 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 10/03/2002| | UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 03:33[EDT]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/03/2002| +------------------------------------------------+EVENT TIME: 03:15[EDT]| | NRC NOTIFIED BY: BOESCH/DIDOMENICO |LAST UPDATE DATE: 10/03/2002| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: UNUSUAL EVENT |PETE ESELGROTH R1 | |10 CFR SECTION: |MOHAMED SHANBAKY R1 | |AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |WILLIAM DEAN NRR | | |TIM MCGINTY IRO | | |SWEETSER 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 | |2 M/R Y 1 Startup |0 Hot Shutdown | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED PER EAL 14.1- FIRE LASTING GREATER THAN 15 MINUTES & | | ACTIVATION OF THE FIRE BRIGADE. | | | | "At 0230 on 10/3/02, the control room was notified that there was a fire at | | Startup Transformer T-20. Unit 2 was in the process of starting up and was | | at a pressure of 435 psig and range 8 on the IRMs. T-20 lost power which | | caused the recirc pumps on Unit 2 to trip. With no recirculation, operators | | placed the mode switch to shutdown. All rods were inserted. Unit 1 was at | | 100% power at the time and continued to operate. The Station Fire Brigade | | was activated. The deluge system extinguished the fire in 10 minutes" | | | | Non-Vital power is being supplied to T-20 Startup Transformer Bus from | | Startup Transformer T-10 via cross tie breaker. Offsite fire department was | | called but was not needed. All Emergency Core Cooling systems and the | | Emergency Diesel Generators are fully operable if needed. | | | | The Unusual event will be terminated after an assessment of what caused the | | Startup Transformer T-20 fire/failure. | | | | | | The licensee notified the State of PA, surrounding counties and the NRC | | Resident Inspector of the declaration of an Unusual Event. | | | | ***UPDATE ON 10/03/02 AT 0605ET BY SID MORGAN TAKEN BY MACKINNON *** | | | | EAL 14.1 was exited and the Unusual Event terminated at 05:52 ET. Unusual | | event was terminated after damage assessment of Startup Transformer T-20 | | was completed. R1DO (Pete Esselgroth), NRR EO (Bill Dean) & FEMA (Sweetser) | | notified. | | | | The NRC Resident Inspector was notified of the termination of the Unusual | | event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39242 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 10/03/2002| | UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 05:15[EDT]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/03/2002| +------------------------------------------------+EVENT TIME: 02:30[EDT]| | NRC NOTIFIED BY: ROBERT BOESCH |LAST UPDATE DATE: 10/03/2002| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |PETE ESELGROTH R1 | |10 CFR SECTION: | | |ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | | |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 M/R Y 1 Startup |0 Hot Shutdown | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR SCRAM DUE TO LOSS OF POWER TO RECIRC PUMPS. | | | | "At 0230 on 01/3/02, the control room was notified that there was a fire at | | Startup Transformer T-20. Unit 2 was in the process of starting up and was | | at a pressure of 435 psig and range 8 on the IRMs. T-20 lost power which | | caused the recirc pumps on Unit 2 to trip. With no recalculation while in | | Mode 2, Tech Specs requires the unit to be in Mode 3 within 12 hours. | | Operations placed the mode switch to shutdown. All rods were inserted. | | Unit 1 was at 100% power at the time and continued to operate. The Station | | Fire Brigade was activated. The deluge system extinguished the fire in 10 | | minutes. An Unusual Event was declared under EAL 14.1 at 03:15. | | | | "This is a 4 hr Non-Emergency notification under 10 CFR 50.72(b)(2)(I) for a | | Tech Spec required shutdown and a 4 hr Non-Emergency notification under 10 | | CFR 50.72(b)(2)(iv)(B) for an RPS actuation." | | | | A press release will be made. | | | | The NRC Resident Inspector was notified of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39243 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 10/03/2002| | UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 08:12[EDT]| | RXTYPE: [1] GE-3 |EVENT DATE: 10/03/2002| +------------------------------------------------+EVENT TIME: 01:50[EDT]| | NRC NOTIFIED BY: DAVID NOYES |LAST UPDATE DATE: 10/03/2002| | HQ OPS OFFICER: MIKE NORRIS +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |PETE ESELGROTH R1 | |10 CFR SECTION: | | |AINA 50.72(b)(3)(v)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | POTENTIAL UNABLE TO SAFE SHUTDOWN DUE TO CORE FLOW INDICATION OUT OF | | TOLERANCE | | | | "During performance of procedure PNPS 9.17 Core Flow Evaluation a | | discrepancy in the 'A' Loop core flow between EPIC and RPS indication was | | noted. This caused Pilgrim to investigate and perform a calibration of the | | 'A' RPS Flow converter. The initial 'as found' set points were out of | | tolerance per the procedure. Adjustments were attempted but we were unable | | to calibrate the flow converter. The 'A' Flow Converter was declared inop | | and a half-scram signal was maintained on the 'A' RPS channel. Pilgrim is | | continuing its efforts to replace and/or repair the 'A' Flow converter. It | | is unknown at this time if the as found flow indications were acceptable to | | fulfill its safety function." | | | | The Licensee has notified the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39245 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 10/03/2002| | UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 14:40[EDT]| | RXTYPE: [1] W-2-LP |EVENT DATE: 10/02/2002| +------------------------------------------------+EVENT TIME: 13:00[CDT]| | NRC NOTIFIED BY: ANTHONY BOLYEN |LAST UPDATE DATE: 10/03/2002| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |SONIA BURGESS R3 | |10 CFR SECTION: | | |BSUR 20.1906(d)(1) SURFACE CONTAM LEVELS >| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | REMOVABLE CONTAMINATION EXCEEDING LIMITS FOUND ON EMPTY CONTAINERS DELIVERED | | TO SITE | | | | "On Wednesday, October 2, 2002, Nuclear Management Company, LLC (NMC) | | received a shipment of two empty sea-land containers from U.S. Ecology at | | the Kewaunee Nuclear Plant. These containers were shipped by R&R Trucking of | | Duenweg, MO. Although these containers were empty, NMC conservatively | | surveyed the outside of the containers. During this survey of the | | containers, a masslin contamination check identified some external | | contamination. Further and more specific sampling techniques resulted in | | identifying contamination levels of 24,700 DPM/100 sq. cm. in one location | | on the underside of the container. Department of Transportation acceptance | | limits identified in 49 CFR 173.433 for this type of container are 22,000 | | DPM/100 sq. cm. Because these containers were considered empty, they were | | unlabeled. Nevertheless, because NMC identified removable radioactive | | surface contamination in excess of the limits of 10 CFR 71.81(i) which refer | | to the DOT limits of 49 CFR 173.433, this event is immediately reportable to | | the NRC Operations Center in accordance with 10 CFR 20.1906(d). In | | accordance with 10 CFR 20.1906(d), the radiation safety officer at U.S. | | Ecology was notified of the conditions found when the shipment was | | received. | | | | "Because, the area of contamination was on the underside of the container, | | it was not accessible during transportation. The container was secured and | | posted as necessary to control the contaminated areas within an RCA at the | | plant. NMC surveyed the flatbed trailer upon which the containers were | | shipped, and no contamination was found. Based on this, the trailer was | | released. | | | | "Additionally, the NRC senior resident inspector and the regional RP | | inspector were notified." | | | | UPDATE: | | | | "The correct time of discovery was 1300 CST. The U.S. Ecology contact was [ | | . . .]. The dose rate instrument was an RO-20 (handheld, portable, | | ionization chamber capable of detecting both beta end gamma radiation). The | | initial contamination survey equipment was a frisker (thin-end window GM | | detector). The contamination levels of 24,700 DPM/100 sq. cm. was found | | using a Baird alpha, beta, fixed geometry scalar/counter." | +------------------------------------------------------------------------------+
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Page Last Reviewed/Updated Thursday, March 25, 2021