Event Notification Report for October 31, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/30/2003 - 10/31/2003
EVENT NUMBERS
40338403714028640285
Other Nuclear Material
Event Number: 40338
Rep Org: MALLINCKRODT
Licensee: MALLINCKRODT
Region: 3
City: ST. LOUIS State: MO
County:
License #: 24-04206-01
Agreement: N
Docket:
NRC Notified By: RULAND SAWYER
HQ OPS Officer: MIKE RIPLEY
Licensee: MALLINCKRODT
Region: 3
City: ST. LOUIS State: MO
County:
License #: 24-04206-01
Agreement: N
Docket:
NRC Notified By: RULAND SAWYER
HQ OPS Officer: MIKE RIPLEY
Notification Date: 11/19/2003
Notification Time: 08:15 [ET]
Event Date: 10/31/2003
Event Time: 00:00 [CST]
Last Update Date: 11/19/2003
Notification Time: 08:15 [ET]
Event Date: 10/31/2003
Event Time: 00:00 [CST]
Last Update Date: 11/19/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
CHRISTINE LIPA (R3)
THOMAS ESSIG (NMSS)
CHRISTINE LIPA (R3)
THOMAS ESSIG (NMSS)
MISSING CESIUM-137 CHECK SOURCE
During an inventory on 10/31/03, it was discovered that a sealed Cs-137 instrument check source was missing from its storage location. The source strength is 232.5 microcuries as of 11/18/03. The source was last seen during the previous inventory on 05/08/03.
During an inventory on 10/31/03, it was discovered that a sealed Cs-137 instrument check source was missing from its storage location. The source strength is 232.5 microcuries as of 11/18/03. The source was last seen during the previous inventory on 05/08/03.
Power Reactor
Event Number: 40371
Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: KELLY ROBINSON
HQ OPS Officer: JEFF ROTTON
Region: 1 State: VT
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: KELLY ROBINSON
HQ OPS Officer: JEFF ROTTON
Notification Date: 12/03/2003
Notification Time: 14:38 [ET]
Event Date: 10/31/2003
Event Time: 00:00 [EST]
Last Update Date: 12/03/2003
Notification Time: 14:38 [ET]
Event Date: 10/31/2003
Event Time: 00:00 [EST]
Last Update Date: 12/03/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
RICHARD CONTE (R1)
RICHARD CONTE (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 |
INVALID GROUP III PRIMARY CONTAINMENT ISOLATION SYSTEM ACTUATION
"This notification is being made in accordance with 10CFR50.73(a)(2)(iv)(A) to provide the NRC with information pertaining to the Primary Containment Isolation System (PCIS) Group III invalid actuation signals that affected containment isolation valves in more than one system on two separate occasions.
"On October 31, 2003 and November 9, 2003, with the reactor at full power, an invalid actuation of the 'B' Reactor Building Ventilation Monitor caused Group III isolations of PCIS. A spike that was caused by electronic noise within the detector invoked a spurious High Level Trip to this monitor (RM 17-452B), that resulted in a trip to PCIS logic Channel B1.
"The PCIS functioned successfully providing a complete Group III isolation. The train actuation was complete. Both trains of the Standby Gas Treatment System started as designed. The PCIS Group III isolation occurred which involves isolation of valves in the following systems:
Drywell Air Purge and Vent, Drywell and Suppression Chamber Main Exhaust, Suppression Chamber Purge and Vent, Containment Air Compressor Suction Valve, Exhaust to Standby Gas Treatment, Containment Purge Supply and Makeup, Containment Air Sampling, Air dilution Subsystem Valves, Vent Subsystem Valves, and Containment Air Dilution Vent System MOV VG-22 A/B.
"It was determined that both of these Group III isolations were invalid, due to the Reactor Building Vent Monitor Radiation Level Trip occurring at 25 millirem/hr on 10/31/03 and 15 millirem/hr on 11/09/03. General area radiation levels in these areas at the time of the event were approximately 2.5 millirem/hr to 6 millirem/hr."
The licensee will notify the NRC Resident Inspector.
"This notification is being made in accordance with 10CFR50.73(a)(2)(iv)(A) to provide the NRC with information pertaining to the Primary Containment Isolation System (PCIS) Group III invalid actuation signals that affected containment isolation valves in more than one system on two separate occasions.
"On October 31, 2003 and November 9, 2003, with the reactor at full power, an invalid actuation of the 'B' Reactor Building Ventilation Monitor caused Group III isolations of PCIS. A spike that was caused by electronic noise within the detector invoked a spurious High Level Trip to this monitor (RM 17-452B), that resulted in a trip to PCIS logic Channel B1.
"The PCIS functioned successfully providing a complete Group III isolation. The train actuation was complete. Both trains of the Standby Gas Treatment System started as designed. The PCIS Group III isolation occurred which involves isolation of valves in the following systems:
Drywell Air Purge and Vent, Drywell and Suppression Chamber Main Exhaust, Suppression Chamber Purge and Vent, Containment Air Compressor Suction Valve, Exhaust to Standby Gas Treatment, Containment Purge Supply and Makeup, Containment Air Sampling, Air dilution Subsystem Valves, Vent Subsystem Valves, and Containment Air Dilution Vent System MOV VG-22 A/B.
"It was determined that both of these Group III isolations were invalid, due to the Reactor Building Vent Monitor Radiation Level Trip occurring at 25 millirem/hr on 10/31/03 and 15 millirem/hr on 11/09/03. General area radiation levels in these areas at the time of the event were approximately 2.5 millirem/hr to 6 millirem/hr."
The licensee will notify the NRC Resident Inspector.
Power Reactor
Event Number: 40286
Facility: SEABROOK
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: TOM WAECHTER
HQ OPS Officer: MIKE RIPLEY
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: TOM WAECHTER
HQ OPS Officer: MIKE RIPLEY
Notification Date: 10/31/2003
Notification Time: 21:15 [ET]
Event Date: 10/31/2003
Event Time: 19:48 [EST]
Last Update Date: 10/31/2003
Notification Time: 21:15 [ET]
Event Date: 10/31/2003
Event Time: 19:48 [EST]
Last Update Date: 10/31/2003
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
DAVID SILK (R1)
DAVID SILK (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 |
REACTOR TRIP ON LOW STEAM GENERATOR WATER LEVEL
"Automatic Reactor Trip due to low Steam Generator levels. All systems responded normally. Plant is stable at NOT/NOP [normal operating temperature and pressure] in Mode 3. Emergency Feedwater system actuated as designed due to reactor trip."
Lowest Steam Generator level reached was just below the trip setpoint of 25%. Low level caused by trip of one of two Main Feed Pumps. All control rods fully inserted. No primary or secondary relief valves lifted. The electrical system is stable and the EDG's remain in standby. Decay heat is being removed via steam dumps.
The licensee has notified the NRC Resident Inspector.
"Automatic Reactor Trip due to low Steam Generator levels. All systems responded normally. Plant is stable at NOT/NOP [normal operating temperature and pressure] in Mode 3. Emergency Feedwater system actuated as designed due to reactor trip."
Lowest Steam Generator level reached was just below the trip setpoint of 25%. Low level caused by trip of one of two Main Feed Pumps. All control rods fully inserted. No primary or secondary relief valves lifted. The electrical system is stable and the EDG's remain in standby. Decay heat is being removed via steam dumps.
The licensee has notified the NRC Resident Inspector.
Other Nuclear Material
Event Number: 40285
Rep Org: ESMER & ASSOCIATES
Licensee: ESMER & ASSOCIATES
Region: 1
City: Boomer State: WV
County:
License #: 47-17478-01
Agreement: N
Docket:
NRC Notified By: DON PHILLIPS
HQ OPS Officer: MIKE RIPLEY
Licensee: ESMER & ASSOCIATES
Region: 1
City: Boomer State: WV
County:
License #: 47-17478-01
Agreement: N
Docket:
NRC Notified By: DON PHILLIPS
HQ OPS Officer: MIKE RIPLEY
Notification Date: 10/31/2003
Notification Time: 14:31 [ET]
Event Date: 10/31/2003
Event Time: 07:00 [EST]
Last Update Date: 11/03/2003
Notification Time: 14:31 [ET]
Event Date: 10/31/2003
Event Time: 07:00 [EST]
Last Update Date: 11/03/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
DAVID SILK (R1)
TOM ESSIG (NMSS)
DAVID SILK (R1)
TOM ESSIG (NMSS)
STOLEN TROXLER MOISTURE DENSITY GAUGE
A Troxler moisture density gauge Model # 3411B, Serial # 9905 containing 8.1 millicuries Cs-137 and 40 millicuries Am-241:Be was stolen from a company field technician's SUV while parked at a motel in Kanawha City, WV sometime between 10:00 pm 10/30/03 and 7:00 am 10/31/03. The gauge was locked inside its case at the time of the theft. The licensee notified the Kanawha City police department and will be notifying NRC Region 1.
* * * UPDATE ON 11/03/03 @ 0957 BY DOD PHILLIPS TO GOULD * * *
Missing Troxler gauge was found along some railroad tracks near where it was stolen, undamaged and intact. It was taken to a volunteer fire department in Boone, Cty. WV. The licensee was notified by the fire department on 11/03/03 and they have sent someone to get it.
A Troxler moisture density gauge Model # 3411B, Serial # 9905 containing 8.1 millicuries Cs-137 and 40 millicuries Am-241:Be was stolen from a company field technician's SUV while parked at a motel in Kanawha City, WV sometime between 10:00 pm 10/30/03 and 7:00 am 10/31/03. The gauge was locked inside its case at the time of the theft. The licensee notified the Kanawha City police department and will be notifying NRC Region 1.
* * * UPDATE ON 11/03/03 @ 0957 BY DOD PHILLIPS TO GOULD * * *
Missing Troxler gauge was found along some railroad tracks near where it was stolen, undamaged and intact. It was taken to a volunteer fire department in Boone, Cty. WV. The licensee was notified by the fire department on 11/03/03 and they have sent someone to get it.