Event Notification Report for May 31, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/30/2000 - 05/31/2000
** EVENT NUMBERS **
37029 37032 37043 37044
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|General Information or Other |Event Number: 37029 |
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| REP ORG: WASHINGTON DEPARTMENT OF HEALTH |NOTIFICATION DATE: 05/24/2000|
|LICENSEE: SPEARS ENGINEERING & TECHNICAL SERVIC|NOTIFICATION TIME: 18:26[EDT]|
| CITY: SOUTH SEATTLE REGION: 4 |EVENT DATE: 05/22/2000|
| COUNTY: STATE: WA |EVENT TIME: 18:00[PDT]|
|LICENSE#: WN-I0357-1 AGREEMENT: Y |LAST UPDATE DATE: 05/30/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CLAUDE JOHNSON R4 |
| |WAYNE HODGES NMSS |
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| NRC NOTIFIED BY: FRAZEE | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| LICENSEE REPORTED A STOLEN PORTABLE GAUGE. |
| |
| The licensee reported on May 23 that at approximately 6:00 PM the previous |
| evening a Seaman Nuclear C-200 gauge, serial number A-872, with 4.5 |
| milligrams of Ra-226 was stolen. The licensee's technician had stopped by a |
| friend's house in South Seattle on his way home. While there, his pickup |
| truck was stolen from in front of the house. The gauge was locked, in a |
| locked transport box, and the box was chained and locked in the bed of the |
| truck. The licensee believes the thief wanted only the truck and will |
| probably abandon the gauge. The police were notified and the licensee was |
| advised to notify the local papers and post a reward. |
| |
| Overexposures? Unknown. |
| |
| Disposition/recovery: Unknown at this time. |
| |
| * * * UPDATE ON 05/30/00 @ 1400 BY FRAZEE TO GOULD * * * |
| |
| On May 27, 2000, the gauge was found intact and abandoned along a side |
| street in South Seattle, Washington. (The abandoned pickup truck was |
| eventually found elsewhere.) Police and Fire Department personnel responded |
| to the scene and called 206-NUCLEAR (the Washington State radiation |
| emergency line). The Division's Emergency Response Duty Officer determined |
| that the gauge was not leaking, surveyed the exterior, and impounded it. |
| The retrieval was covered by all the major Seattle television stations. The |
| gauge will be returned to the licensee. |
| |
| The R4DO (Sanborn) and NMSS EO ( Hickey) were notified by the NRC Operations |
| Officer. |
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|Power Reactor |Event Number: 37032 |
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| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 05/25/2000|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 21:47[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/25/2000|
+------------------------------------------------+EVENT TIME: 20:46[EDT]|
| NRC NOTIFIED BY: H. M. HARRIS |LAST UPDATE DATE: 05/30/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MARK LESSER R2 |
|10 CFR SECTION: |JOHN HANNON NRR |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION |JOSEPH GIITTER IRO |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
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EVENT TEXT
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| TURBINE RUNBACK TO 50% DUE TO LOSS OF A MAIN FEEDWATER PUMP FOLLOWED BY A |
| REACTOR TRIP ON LOW LOW STEAM GENERATOR WATER LEVEL. ONE AUXILIARY |
| FEEDWATER PUMP HAD TO BE MANUALLY STARTED. |
| |
| Reactor automatic trip occurred at 2046 ET. Initiating event was steam |
| generator low low water level on "C" steam generator. Prior to the trip |
| Channel 1 vital 120 volt AC power was lost due to the tripping open of EVIA |
| (DC/AC ) inverter AC output breaker. No testing was in progress at this |
| time and the cause of the AC breaker trip is under investigation. When the |
| AC output breaker opened it caused a loss of Channel 1 power. Main |
| feedwater pump "1A" control circuitry interfaces with Channel 1 120 volt AC |
| power and when Main Feedwater pump "1A" control circuitry power was lost |
| main feedwater pump "1A" turbine tripped. The loss of Main Feedwater pump |
| "1A" turbine initiated an automatic main turbine runback to 50% power. |
| After the main turbine runback to 50% power the reactor tripped on steam |
| generator "1C" low low water level. Only one of two motor driven auxiliary |
| feedwater pumps automatically started on steam generator "1C" low low water |
| level. Auxiliary feedwater pump "1A" was manually started approximately 2 |
| minutes after the automatic reactor trip. The licensee is investigating why |
| the "1A" auxiliary feedwater pump did not automatically start. All rods |
| fully inserted into the core and reactor coolant temperature is being |
| maintained at Tave no load condition of 557 degrees F. No PORVs or code |
| safety valves on either the primary or secondary side of the plant opened. |
| All the Emergency Core Cooling Systems and the Emergency Diesel Generators |
| are fully operable if needed. Offsite electrical grid is stable. The |
| licensee's investigation into the initiating event is continuing. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * UPDATE ON 05/26/00 AT 1640 EDT BY HEAFNER TAKEN BY MACKINNON * * * |
| |
| Only the Turbine Driven Auxiliary Feedwater Pump and the Motor Driven |
| Auxiliary Feedwater Pump "1B" automatically started. The "1A" Motor Driven |
| Auxiliary Feedwater Pump did not automatically start since its control |
| circuitry is supplied electrical power from Channel 1 vital 120 volt AC |
| power, which was lost. As stated in the original event report, Auxiliary |
| Feedwater Pump "1A" was manually started approximately 2 minutes after the |
| automatic reactor trip. |
| |
| Two of three Primary side Power Operated Relief Valves (PORV) opened and |
| subsequently closed. No secondary side PORVs or code safety valves on |
| either the Primary or Secondary side of the plant opened. Investigation |
| into the event is continuing. |
| R2DO (Tom Decker) notified. |
| |
| The NRC Resident Inspector was notified of this update by the licensee. |
| |
| * * * UPDATE ON 05/30/00 @ 1634 BY DIAL TO GOULD * * * |
| |
| An ongoing evaluation has determined that Main Feedwater Pump "1A" tripped |
| as a result of high discharge pressure which occurred due to the response of |
| the Feedwater Regulating Valves control circuitry. This circuitry was |
| associated with the failed power supply. |
| |
| The NRC Resident Inspector will be informed by the licensee. The R2DO |
| (McAlpine) was notified by the NRC Headquarters Operations Officer. |
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|Power Reactor |Event Number: 37043 |
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| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/30/2000|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 09:07[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/26/2000|
+------------------------------------------------+EVENT TIME: 14:42[EDT]|
| NRC NOTIFIED BY: NICK LIZZO |LAST UPDATE DATE: 05/30/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RICHARD BARKLEY R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 N Y 100 Power Operation |100 Power Operation |
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EVENT TEXT
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| MAY 26, 2000, DISCOVERY OF A VIOLATION OF ELECTRICAL SEPARATION CRITERIA |
| (DETERMINED TO BE REPORTABLE ON MAY 30, 2000 AT 0835) |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At approximately 0835 hours on May 30, 2000, operations [personnel] |
| determined that plant cable separation criteria had been violated placing |
| the plant outside the design basis. A cable routed from a Channel 'C' |
| instrument bus had been retired in place by terminating the cable from the |
| equipment it was routed to, taping the cable end, and placing the rolled |
| cable in a cable tray. The rolled cable, still power by the instrument bus, |
| was placed in a Channel 'B' cable tray. This resulted in a condition |
| outside the plant's design basis since channel electrical separation |
| criteria is defined by the [Final Safety Analysis Report (FSAR)]. The event |
| was originally identified on May 26, 2000, at approximately 1442 hours, but |
| [it was] not recognized as reportable at the time. Corrective action was |
| taken when the event was identified by removing the Channel 'C' cable from |
| the Channel 'B' cable tray." |
| |
| The licensee plans to notify the NRC resident inspector. |
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|General Information or Other |Event Number: 37044 |
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| REP ORG: FLORIDA BUREAU OF RADIATION CONTROL |NOTIFICATION DATE: 05/30/2000|
|LICENSEE: SPRINGSTEAD ENGINEERING, INC., d/b/a |NOTIFICATION TIME: 10:24[EDT]|
| CITY: FLORAL CITY REGION: 2 |EVENT DATE: 05/26/2000|
| COUNTY: STATE: FL |EVENT TIME: [EDT]|
|LICENSE#: 1347-1 AGREEMENT: Y |LAST UPDATE DATE: 05/30/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |EDWARD MCALPINE R2 |
| |JOHN HICKEY NMSS |
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| NRC NOTIFIED BY: CHARLEY E. ADAMS | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
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EVENT TEXT
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| AGREEMENT STATE REPORT INVOLVING A DAMAGED TROXLER GAUGE OWNED BY |
| SPRINGSTEAD ENGINEERING, INC., d/b/a CENTRAL TESTING LABORATORY LOCATED IN |
| FLORAL CITY, FLORIDA |
| |
| The following text is a portion of a facsimile received from the Florida |
| Bureau of Radiation Control: |
| |
| "Licensee: Springstead Engineering, Inc., d/b/a Central Testing |
| Laboratory" |
| |
| "City, State, and Zip Code: Floral City, FL 34436" |
| |
| "Isotope(s): Cs-137; Am-241:Be" |
| |
| "Activity(s): 6.0, 39.2 mCi, respectively" |
| |
| "Material Form; Chemical Form; Physical Form: By-product: Special Form" |
| |
| "Probable Disposition of Material: Transferred to Another Licensee" |
| |
| "Exposure? No" |
| |
| "Number: N/A" |
| |
| "Type of Individual(s): N/A" |
| |
| "Exposure Source: N/A" |
| |
| "Dose Delivered to: N/A" |
| |
| "Maximum Dose Received: N/A" |
| |
| "Incident Category: Equipment Problems (Licensed Material)" |
| |
| "Incident Location: Intersection of CR 226 and US 27, just west of I-75 |
| exit 70" |
| |
| "Incident Description: While gauge was in use (calibration position, with |
| sources retracted), a front loader ran over the gauge. The housing and case |
| were destroyed, but the lead case around the source was intact with the |
| source retracted. The licensee asked for assistance in surveying the area, |
| the loader, and the source housing. Survey of the area and the front loader |
| were background. Wipes of the source housing were background. Troxler has |
| been notified and will pick up the gauge for repair. Cause of the accident |
| was front loader driver inattention." |
| |
| "Device Type (Quantity): Soil/Moisture Density Gauge (1)" |
| |
| "Manufacturer: Troxler" |
| |
| "Model Number: 3440" |
| |
| "Serial Number: 14821" |
| |
| "Emergency Groups at Scene: None" |
| |
| "Organizations Notified: NRC" |
| |
| "Media Contacted: None" |
| |
| "Investigator's Name; Title: Reno Fabii, Environmental Specialist II" |
| |
| "Office: Environmental Radiation Control" |
| |
| "Date; Time Investigated: 26-May-00; 1115" |
| |
| Call the NRC operations officer for contact information. |
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