Event Notification Report for June 7, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/06/2002 - 06/07/2002
** EVENT NUMBERS **
38955 38967 38968 38969
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|General Information or Other |Event Number: 38955 |
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| REP ORG: ARIZONA RADIATION REGULATORY AGENCY |NOTIFICATION DATE:
05/31/2002|
|LICENSEE: CONSTRUCTION INSPECTION AND TESTING |NOTIFICATION TIME:
13:42[EDT]|
| CITY: TEMPE REGION: 4 |EVENT DATE: 05/31/2002|
| COUNTY: STATE: AZ |EVENT TIME: 09:30[MST]|
|LICENSE#: 7-98 AGREEMENT: Y |LAST UPDATE DATE: 06/04/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GARY SANBORN R4 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: WILLIAM A. WRIGHT (fax) | |
| HQ OPS OFFICER: MIKE NORRIS | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| STOLEN TROXLER MOISTURE/DENSITY GAUGE |
| |
| "Description of event: The licensee reported the loss of a Troxler |
| moisture/density gauge and company truck when a technician failed to report |
| to a designated job site. The gauge is a Troxler Model 3440, serial number |
| 21935. It contains approximately 8 millicuries of Cesium 137 (source serial |
| number 75-3524) and approximately 40 millicuries of Americium-Beryllium |
| (source serial number 47-17271). The company vehicle is a 1999 white Ford |
| F-150 extended cab pickup, company number 50, Arizona license [ ]. The Tempe |
| police have been notified and are investigating. The company is offering a |
| $250 reward for information leading to the return of the gauge and truck. |
| |
| "The U.S. NRC, FBI, Mexico, and the states of Colorado, Nevada, Utah, New |
| Mexico and California are being informed of this incident." |
| |
| * * * UPDATE ON 6/4/02 BY WRIGHT (BY FAX) TO GOULD * * * |
| |
| The gauge and truck have been recovered. |
| |
| The FBI, Mexico and the states of Colorado, Nevada, Utah, New Mexico and |
| California were informed. |
| |
| Notified Reg 4 RDO (Pellet), NMSS (Brown), IAT (Davidson) |
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|Power Reactor |Event Number: 38967 |
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| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 06/06/2002|
| UNIT: [1] [] [] STATE: MI |NOTIFICATION TIME: 02:51[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/05/2002|
+------------------------------------------------+EVENT TIME: 23:00[EDT]|
| NRC NOTIFIED BY: DUANE COBB |LAST UPDATE DATE: 06/06/2002|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNUSUAL EVENT |JAMES CREED R3 |
|10 CFR SECTION: |STUART RICHARDS NRR |
|AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |JOSEPH HOLONICH IRO |
| |DEPUY FEMA |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
| | |
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EVENT TEXT
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| UNIT 1 DECLARED AN UNUSUAL EVENT DUE TO RCS LEAKAGE > 25 GPM DURING
|
| SURVEILLANCE TESTING |
| |
| "D.C. Cook Unit One declares entry and exit of an Unusual Event due to |
| Reactor Coolant System leakage of greater than 25 gallons per minute. On |
| June 5 @ 23:00 while performing an 18 month surveillance [1-IHP-4030-102-017 |
| 'Pressurizer PORV/Actuation Channel Calibration with Valve Operation'] on |
| the Pressurizer Power Operated Relief Valves (PORVs) an unblocked PORV |
| lifted and discharged to the Pressure Relief Tank (PRT) for approximately 15 |
| seconds. This lifting discharged approximately 100 gallons to the PRT. The |
| Initiating Condition for this Unusual Event is Reactor Coolant System |
| leakage greater than 25 gallons per minute. |
| |
| "The plant is and was in Mode 4. Conditions remain stable after manual |
| isolation of the PORV with the Control Switch of the Block Valve by the |
| assisting Reactor Operator." |
| |
| The licensee attributed this occurrence to the recently revised procedure |
| identified above which did not address blocking the other PORVs during |
| testing. The licensee informed state and local agencies and the NRC |
| Resident Inspector. |
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|Other Nuclear Material |Event Number: 38968 |
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| REP ORG: BJ SERVICES COMPANY |NOTIFICATION DATE: 06/06/2002|
|LICENSEE: BJ SERVICES COMPANY |NOTIFICATION TIME: 10:57[EDT]|
| CITY: TOMBALL REGION: 4 |EVENT DATE: 06/06/2002|
| COUNTY: STATE: TX |EVENT TIME: [CDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 06/06/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ELMO COLLINS R4 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: CHARLOTTE BELLON | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BLO1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| GENERAL LICENSE CESIUM-137 SOURCE COULD NOT BE ACCOUNTED FOR |
| |
| BJ Services, an oil field service company, determined that a general |
| licensed source could not be located. The source, 250 mCi Cs-137 sealed in |
| special form manufactured circa 1984, was installed in a Kay Ray Model 7063 |
| instrument, S/N 28820, used for slurry density measurements. The last |
| recorded location was Rock Springs, WY, on September 8, 1990 for a leak |
| test. The instrument was then owned by Western Company which was acquired |
| by BJ Services in 1995. BJ Services has discussed this incident with |
| R4(Donovan) and will continue their investigation. |
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|Power Reactor |Event Number: 38969 |
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| FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 06/06/2002|
| UNIT: [] [2] [] STATE: TX |NOTIFICATION TIME: 22:21[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/06/2002|
+------------------------------------------------+EVENT TIME: 19:24[CDT]|
| NRC NOTIFIED BY: LEON NEAT |LAST UPDATE DATE: 06/06/2002|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ELMO COLLINS R4 |
|10 CFR SECTION: |NADER MAMISH R4 |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Standby |
| | |
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EVENT TEXT
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| REACTOR TRIP CAUSED BY TURBINE TRIP |
| |
| The reactor tripped due to a turbine trip due to a main generator trip |
| caused by a high vibration on the main generator primary water pump shaft. |
| All systems functioned properly. The plant is stable in Mode 3 with steam |
| generator level being maintained with auxiliary feedwater (started |
| automatically on low steam generator level) and excess heat being removed |
| via the steam bypassed to the main condenser. |
| |
| Primary water pump vibration trip is a 2 out of 2 channel coincidence. |
| There was no indication of high vibration on the plant recorder. At the |
| time of the trip, an investigation was ongoing on one of the channels that |
| was in alarm. An investigation continues into the sensors and circuits |
| associated with the high vibration trip. The plant will remain in Mode 3 |
| until the problem is identified and corrected. |
| |
| The licensee notified the NRC Resident Inspector. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021