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| |
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| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| | |
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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 | |
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| | |
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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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| 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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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021