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Event Notification Report for June 4, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/03/2002 - 06/04/2002

                              ** EVENT NUMBERS **

38950  38960  38961  38962  

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|General Information or Other                     |Event Number:   38950       |
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| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 05/30/2002|
|LICENSEE:  HUNTER INDUSTRIES, LTD               |NOTIFICATION TIME: 10:08[EDT]|
|    CITY:  SAN ANTONIO              REGION:  4  |EVENT DATE:        05/30/2002|
|  COUNTY:                            STATE:  TX |EVENT TIME:             [CDT]|
|LICENSE#:  L04175-000            AGREEMENT:  Y  |LAST UPDATE DATE:  05/30/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GARY SANBORN         R4      |
|                                                |F. BROWN             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JAMES OGDEN, JR              |                             |
|  HQ OPS OFFICER:  RICH LAURA                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| AGREEMENT STATE REPORT - TEXAS REPORTS STOLEN NUCLEAR GAUGE                  |
|                                                                              |
| "Gauge had been in use at a job site in San Antonio. The gauge was secured   |
| in the bed of a company pickup and was discovered missing at 8 a.m. on May   |
| 20, 2002. The gauge, a Troxler Thin-Lift Asphalt Gauge Model 4640B, Serial   |
| No. 1825, with an 8 millicurie Cs-137 source, Serial No. 75-8669, was        |
| removed from the case which was pried open in the back of the pickup. A      |
| police report was filed with the San Antonio Police Department. Transport    |
| case was left secure in the rear of the pickup. Only the gauge was stolen.   |
| Other details are lacking and will be reported by the Licensee to this       |
| Agency within 30 days."                                                      |
|                                                                              |
| This is tracked under Texas Incident No. I-7901.                             |
|                                                                              |
| The R4DO (G. Sanborn) and NMSS (F. Brown )  was notified.  The local police  |
| department was notified.                                                     |
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|Power Reactor                                    |Event Number:   38960       |
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| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 06/03/2002|
|    UNIT:  [2] [3] []                STATE:  NY |NOTIFICATION TIME: 11:14[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        06/03/2002|
+------------------------------------------------+EVENT TIME:        08:00[EDT]|
| NRC NOTIFIED BY:  PRUSSMAN                     |LAST UPDATE DATE:  06/03/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |PETE ESELGROTH       R1      |
|10 CFR SECTION:                                 |WILLIAM BECKNER      NRR     |
|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| REMOVAL OF EMERGENCY SIRENS FROM SERVICE DUE TO MAINTENANCE                  |
|                                                                              |
| Planned maintenance of the offsite siren system will result in each of the   |
| sirens in Putnam County being removed from service.  There are 10 sirens in  |
| Putnam County and Indian Point Energy Center considers a loss of 10% of the  |
| sirens in a county to be a major loss of emergency assessment capability.    |
| The removal of sirens from service in Putnam County will continue on an      |
| intermittent basis from June 3, 2002 until June 21, 2002.  The first siren   |
| was removed from service at 8 a.m. on June 3, 2002.                          |
|                                                                              |
| The planned maintenance is intended to replace the siren                     |
| actuation/verification system in order to improve reliability and            |
| maintainability.  The replacement process will install the new               |
| actuation/verification system, connect the actuation/verification system,    |
| and terminate the connection of the old controls.  This work is currently    |
| scheduled on one siren per day.  Testing of the new actuation/verification   |
| system will not occur until the next day at the request of Putnam County.    |
| If this plan is followed, a 10% loss of the offsite communications occurs    |
| when the old controls are terminated until the new actuation/verification    |
| system is tested.  This increases to 20% if the testing does not occur prior |
| to the next siren being taken out of service.                                |
|                                                                              |
| Putnam County will use route alerting to notify the public in lieu of the    |
| non-operational sirens.  County officials are aware of the scheduled         |
| activities, and newspaper ads have been placed regarding testing.            |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
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|Power Reactor                                    |Event Number:   38961       |
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| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 06/03/2002|
|    UNIT:  [1] [] []                 STATE:  CA |NOTIFICATION TIME: 16:38[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/03/2002|
+------------------------------------------------+EVENT TIME:        13:02[PDT]|
| NRC NOTIFIED BY:  STEVEN A. DAVID              |LAST UPDATE DATE:  06/03/2002|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JOHN PELLET          R4      |
|10 CFR SECTION:                                 |                             |
|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  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       86       Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| AUTOMATIC REACTOR TRIP DUE TO LOW STEAM GENERATOR LEVEL BECAUSE A
MAIN       |
| FEEDWATER REGULATING VALVE FAILED CLOSED                                     |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "The unit was at approximately 86% power, ramping to 92% power following     |
| [the eleventh Unit 1 refueling outage (1R11)].  The main feedwater           |
| regulating valve for steam generator 1 failed closed.  Attempts to open the  |
| valve manually failed.  The [Shift Foreman] ordered a manual reactor trip,   |
| but an automatic trip occurred before operators could trip the reactor.  The |
| unit is currently stable in Mode 3."                                         |
|                                                                              |
| The licensee stated that the automatic reactor trip signal was two out of    |
| three steam generator 1-1 low level.  All control rods fully inserted, and   |
| auxiliary feedwater automatically initiated as designed.  There were no      |
| emergency core cooling system (ECCS) injections or engineered safety feature |
| (ESF) actuations, and none were required.  Other than the cause of the main  |
| feedwater regulating valve failure, there was nothing unusual or             |
| misunderstood, and all systems functioned as required.  There were no        |
| related maintenance or surveillance activities ongoing at the time of the    |
| automatic reactor trip.                                                      |
|                                                                              |
| The licensee also stated that normal charging and letdown, pressurizer       |
| heaters and sprays, and the reactor coolant pumps are currently being        |
| utilized for primary system level, pressure, and transport control.          |
| Auxiliary feedwater being utilized to supply water to the steam generators,  |
| and secondary steam is being dumped to the condenser.  Containment           |
| parameters are normal, and all ECCS and ESF systems are available if needed. |
| The unit is currently on offsite power, and the emergency diesel generators  |
| are available if needed.                                                     |
|                                                                              |
| The licensee notified the NRC resident inspector, who is currently in the    |
| control room, and may issue a press release.                                 |
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|Power Reactor                                    |Event Number:   38962       |
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| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 06/03/2002|
|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 17:02[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        06/03/2002|
+------------------------------------------------+EVENT TIME:        15:00[EDT]|
| NRC NOTIFIED BY:  DAVID PITSLEY                |LAST UPDATE DATE:  06/03/2002|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JOHN WHITE           R1      |
|10 CFR SECTION:                                 |TERRY REIS           NRR     |
|AINC 50.72(b)(3)(v)(C)   POT UNCNTRL RAD REL    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| DISCOVERY OF AN OPEN MANUALLY-OPERATED HEADER VENT VALVE RESULTING IN 
      |
| INOPERABILITY OF THE ISOLATION VALVE SEAL WATER SYSTEM                       |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "Indian Point Unit 3 is making an [8-hour] non-emergency notification that   |
| the Isolation Valve Seal Water System (IVSWS) was found in an inoperable     |
| condition on June 2, 2002.  A manually operated header vent valve (IV-1428)  |
| was found mispositioned in an open position.  [The] IVSWS is designed to     |
| provide a water seal for certain containment isolation valves by injecting   |
| water between the seats and stem packing of globe and double disc type       |
| isolations valves and piping between other closed containment isolation      |
| valves.  Water under pressure is supplied from a single seal water tank to   |
| five IVSWS headers for valve sealing.  IVSWS is designed to provide the      |
| water seal for 24 hours, without operator action, after a postulated loss of |
| coolant accident, in order to mitigate bypass leakage.  The open vent valve  |
| could have prevented pressurization and drained the seal water in the IVSWS  |
| tank, requiring operator action to refill it, in less than 2 hours.  The     |
| inoperable IVSWS is not expected to result in any significant effect on      |
| public health and safety since the containment isolation valves remain       |
| operable.  The containment Isolation valves are not pneumatically 10 CFR     |
| [Part] 50, Appendix J, Type C tested because they are supplied with seal     |
| water but they have been leak tested with water.  The inoperable IVSWS is    |
| required to be operable by Technical Specification 3.6.9."                   |
|                                                                              |
| "On discovery, the operator closed the vent valve and restored the IVSWS to  |
| operability.  The condition report issued at that time called for a past     |
| operability report.  The inoperable IVSWS was identified while performing    |
| this evaluation.  The duration of the mispositioned valve is still under     |
| investigation."                                                              |
|                                                                              |
| The licensee stated that this event was determined to be reportable at       |
| approximately 1500 EDT today (06/03/02).                                     |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
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