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
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|General Information or Other |Event Number: 37995 |
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| 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 | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 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). |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 39114 |
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| 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 |
| | |
| | |
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EVENT TEXT
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| 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). |
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|Power Reactor |Event Number: 39241 |
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| 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 |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 39242 |
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| 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 |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 39243 |
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| 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
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| 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. |
+------------------------------------------------------------------------------+
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|Power Reactor |Event Number: 39245 |
+------------------------------------------------------------------------------+
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| 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
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| 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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