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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).                                  |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|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       |
+------------------------------------------------------------------------------+
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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     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   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."                   |
+------------------------------------------------------------------------------+