| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/13/2003 - 11/14/2003 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 40306 | Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [ ] [ ]
RX Type: [3] CE
NRC Notified By: KEVIN CHESTER
HQ OPS Officer: JEFF ROTTON | Notification Date: 11/10/2003
Notification Time: 06:41 [ET]
Event Date: 11/10/2003
Event Time: 05:00 [CST]
Last Update Date: 11/13/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
| Person (Organization):
MARK SHAFFER (R4)
DONNA-MARIE PEREZ (TAS)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Refueling | 0 | Refueling | Event Text SAFEGUARD VULNERABILITY - PHYSICAL SECURITY
Discovered vulnerability in a safeguard system that could allow access to a controlled access area for which compensatory measures were not employed.
The licensee notified the NRC Resident Inspector.
TAS notified Region IAT member who will followup for NRC.
Contact the Headquarters Operations Officer for additional details.
* * * UPDATE ON 11/13/03 @ 1340 BY T. MANZELLA/ R. MURILLO TO GOULD * * * RETRACTION
After further review it was determined that there was no vulnerability that would allow access to a controlled access area, therefore the licensee is retracting this event.
The NRC Resident Inspector was notified. |
| General Information or Other | Event Number: 40307 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: SOUTHWEST RESEARCH INSTITUTE
Region: 4
City: SAN ANTONIO State: TX
County:
License #: L00775-000
Agreement: Y
Docket:
NRC Notified By: JIM OGDEN
HQ OPS Officer: ARLON COSTA | Notification Date: 11/10/2003
Notification Time: 09:32 [ET]
Event Date: 11/10/2003
Event Time: [CST]
Last Update Date: 11/10/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MARK SHAFFER (R4)
DOUG BROADDUS (NMSS)
CNSNS (Via Fax) ()
| Event Text AGREEMENT STATE REPORT FOR LOST/STOLEN SOURCE
"On October 30, 2003, during a routine inventory of sources, it was discovered that a Nickel-63 electron capture source that had been in storage since January 23, 1996, was missing. An exhaustive search of source storage areas did not locate the source. However, upon questioning employees that had access to the source storage area, one employee recalled that the source in question had been picked up by a Health Physics Technician from the manufacturer, it was believed during the year 1998. The manufacturer denies having the source picked. A search of paperwork is ongoing to locate a transfer document, if one exists." |
| General Information or Other | Event Number: 40312 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: CONSTRUCTION TESTING & ENGINEERING , INC.
Region: 4
City: SACRAMENTO State: CA
County:
License #: 5927-34
Agreement: Y
Docket:
NRC Notified By: BARBARA HAMRICK
HQ OPS Officer: MIKE RIPLEY | Notification Date: 11/10/2003
Notification Time: 17:51 [ET]
Event Date: 11/10/2003
Event Time: [PST]
Last Update Date: 11/10/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WILLIAM JONES (R4)
LARRY CAMPER (NMSS)
| Event Text AGREEMENT STATE REPORT - STOLEN AND RECOVERED TROXLER MOISTURE DENSITY GAUGE
The State of California was informed at 1900, November 9, 2003 that Construction Testing & Engineering had reported the theft of one of their Troxler gauges (Model 3440, S/N 24168). The theft occurred on Friday November 7, 2003, and was reported to Sacramento County Sheriff. The sheriff detectives indicated that they would be questioning the operator who had possession of the gauge at the time it was stolen. An onsite inspection/investigation will be conducted.
The licensee RSO indicated that the theft had been on the local television news Monday morning along with photographs of the stolen device, and a reward for its recovery.
Subsequent to the initial report, the gauge was reported by an unknown party to be in a ditch in an area north of Sacramento. Sheriffs, Hazmat, and other agencies responded and the gauge was recovered without incident.
California Incident Report # 111003. |
| Power Reactor | Event Number: 40318 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: P. DUBROUILLET
HQ OPS Officer: GERRY WAIG | Notification Date: 11/13/2003
Notification Time: 05:27 [ET]
Event Date: 11/12/2003
Event Time: 22:22 [EST]
Last Update Date: 11/13/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
JOHN PELCHAT (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 96 | Power Operation | 96 | Power Operation | Event Text HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION DURING TESTING
"During quarterly surveillance testing of the High Pressure Coolant Injection (HPCI) System the HPCI system isolated. The cause of the isolation is believed to be high turbine exhaust diaphragm pressure. HPCI is currently inoperable. The outboard steam line isolation valve closed automatically and the inboard steam line isolation valve was manually closed. The HPCI room carbon dioxide fire protection system actuated due to the high temperature spike. No fire was present. The Reactor Core Isolation Cooling (RCIC) System, Auto Depressurization System (ADS), Low Pressure Core Spray System and Low Pressure Coolant Injection System are operable.
"Initial Safety Evaluation - Low initial safety significance due to availability of alternate high and low pressure injection systems.
"Corrective Actions - HPCI will remain inoperable pending investigation. Determine and correct the cause of HPCI isolation. Determine if the inboard steam isolation valve should have automatically closed."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 40319 | Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: MCCOY
HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 11/13/2003
Notification Time: 12:37 [ET]
Event Date: 11/13/2003
Event Time: 09:54 [EST]
Last Update Date: 11/13/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
KENNETH JENISON (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text AUTO START AND LOADING OF THE "B" EMERGENCY DIESEL GENERATOR
While the plant was in "ER-SC.1", Adverse Weather Plan, due to high winds and offsite power in a 50/50 alternate lineup, a momentary loss of offsite power circuit "751" occurred. This resulted in an undervoltage condition on safeguard busses "16" and "17". The "B" emergency diesel Generator automatically started and energized buses "16" and "17" . Entry was made into AP.Elec.1, Loss of 12A and/or 12B busses. The offsite electrical lineup was changed to 100/0 on circuit "767". Safeguard busses were re-energized from offsite power and the "B" diesel generator was secured and returned to automatic. This sequence of events took 22 minutes.
The NRC Resident Inspector was notified. |
| Power Reactor | Event Number: 40320 | Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: KEN TIEFENTHAL
HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 11/13/2003
Notification Time: 13:48 [ET]
Event Date: 11/13/2003
Event Time: 11:35 [EST]
Last Update Date: 11/13/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
KENNETH JENISON (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP FROM 100% POWER WITH CAUSE BEING INVESTIGATED
"Unit 1 was at 100% power when an automatic reactor trip occurred. The Auxiliary Feedwater systems automatically started due to low post trip steam generator levels. This includes the steam driven Auxiliary feedwater pump. The steam discharge of this pump is considered to [be] a gaseous release due to trace amounts of tritium in the secondary system. These trace amounts are well below limits. The pump was shutdown after 31 minutes of operation, terminating the discharge. The Rad Waste & Effluents Section will assess the impact during the event response review.
The plant is currently stable in mode 3 with steam generator levels restored to post shutdown values. The steam dumps and main unit condenser are available for heat removal. All normal and emergency busses are energized from offsite power."
All rods fully inserted, no ECCS actuation and no primary or secondary relief valves lifted.
The NRC Resident Inspector was notified. |
| Power Reactor | Event Number: 40321 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: FRED NYGARD
HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 11/13/2003
Notification Time: 19:25 [ET]
Event Date: 11/13/2003
Event Time: 17:15 [EST]
Last Update Date: 11/13/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
KENNETH JENISON (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LICENSEE CALLED THE WATERFORD, CT. FIRE DEPARTMENT TO ASSIST IN EXTINGUSHING A FIRE OUTSIDE THE PROTECTED AREA
The licensee notified the Waterford, CT Fire Department to assist in extinguishing a fire affecting their offsite domestic water supply in the owner controlled area outside of the protected area. The fire caused damage to the offsite domestic water system limited to the heat tracing circuit for piping, an influent water filter and a trailer that provided shelter for the equipment. The fire, which was approximately 75-100 yards outside the protected area fence, was extinguished within 11 mins. The domestic water influent filter has been bypassed to allow normal domestic water supply capacity to the plant. The cause is being investigated.
The NRC Resident Inspector was notified. |
| Power Reactor | Event Number: 40322 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: LAURIE RAYLE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 11/13/2003
Notification Time: 23:39 [ET]
Event Date: 11/13/2003
Event Time: 21:49 [EST]
Last Update Date: 11/13/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
KENNETH JENISON (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 80 | Power Operation | Event Text LOSS OF 115 KV LINE RESULTS IN EMERGENCY DIESEL GENERATOR AUTO-START
"Auto initiation of Emergency Diesel Generator (EDG) 103 and re-energizing of PB 103 from EDG due to loss of off-site 115 KV line #4. Line #4 was momentarily lost, then re-energized. The loss of power also resulted in a trip of Reactor Recirculating Pump 13. Power reduced to approximately 80% rated. Recovery operations are in progress."
All systems functioned as required and there was not anything unusual or not understood.
The NRC Resident Inspector was notified. | |