Event Notification Report for March 30, 2004
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/29/2004 - 03/30/2004
EVENT NUMBERS
4062840629406264062540674
Power Reactor
Event Number: 40628
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: ROBERT SWEET
HQ OPS Officer: ARLON COSTA
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: ROBERT SWEET
HQ OPS Officer: ARLON COSTA
Notification Date: 03/30/2004
Notification Time: 17:38 [ET]
Event Date: 03/30/2004
Event Time: 11:29 [EST]
Last Update Date: 03/30/2004
Notification Time: 17:38 [ET]
Event Date: 03/30/2004
Event Time: 11:29 [EST]
Last Update Date: 03/30/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(ii)(A) - DEGRADED CONDITION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(ii)(A) - DEGRADED CONDITION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JOEL MUNDAY (R2)
JOEL MUNDAY (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 10 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO LO-LO STEAM GENERATOR LEVEL
"On March 30, 2004, while at power, VCSNS [V.C. Summer Nuclear Station] personnel were performing a reactor building inspection to identify the source of reactor coolant system unidentified leakage that was within Technical Specification (TS) limits.
"At 1129 hours, a pressure boundary leak was identified at the seal injection line to reactor coolant pump 'C'.
"Pursuant to TS 3.4.6.2, Action a., VCSNS commenced a controlled reactor shutdown at 1410 on March 30, 2004.
"During the shutdown, the main turbine experienced higher than normal vibration. At 1516, the turbine was manually tripped at approximately 43% reactor power. Subsequent to the turbine trip, feedwater regulating valve IFV-498 failed in the closed position while in automatic with a full open demand signal. The cause of this failure is not known. The reactor automatically tripped at 1520 due to lo-lo level in the 'C' steam generator at 10% reactor power.
"All control rods fully inserted and all safety systems responded normally. Both motor driven emergency feedwater pumps started as required. The plant stabilized in mode 3."
The licensee notified the NRC Resident Inspector.
"On March 30, 2004, while at power, VCSNS [V.C. Summer Nuclear Station] personnel were performing a reactor building inspection to identify the source of reactor coolant system unidentified leakage that was within Technical Specification (TS) limits.
"At 1129 hours, a pressure boundary leak was identified at the seal injection line to reactor coolant pump 'C'.
"Pursuant to TS 3.4.6.2, Action a., VCSNS commenced a controlled reactor shutdown at 1410 on March 30, 2004.
"During the shutdown, the main turbine experienced higher than normal vibration. At 1516, the turbine was manually tripped at approximately 43% reactor power. Subsequent to the turbine trip, feedwater regulating valve IFV-498 failed in the closed position while in automatic with a full open demand signal. The cause of this failure is not known. The reactor automatically tripped at 1520 due to lo-lo level in the 'C' steam generator at 10% reactor power.
"All control rods fully inserted and all safety systems responded normally. Both motor driven emergency feedwater pumps started as required. The plant stabilized in mode 3."
The licensee notified the NRC Resident Inspector.
General Information or Other
Event Number: 40629
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: LOR GEO TECHNICAL
Region: 4
City: VICTORVILLE State: CA
County:
License #: 5459
Agreement: Y
Docket:
NRC Notified By: DONELLE KROJEWSKI
HQ OPS Officer: CHAUNCEY GOULD
Licensee: LOR GEO TECHNICAL
Region: 4
City: VICTORVILLE State: CA
County:
License #: 5459
Agreement: Y
Docket:
NRC Notified By: DONELLE KROJEWSKI
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 03/30/2004
Notification Time: 23:54 [ET]
Event Date: 03/30/2004
Event Time: 17:00 [PST]
Last Update Date: 04/02/2004
Notification Time: 23:54 [ET]
Event Date: 03/30/2004
Event Time: 17:00 [PST]
Last Update Date: 04/02/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DALE POWERS (R4)
SCOTT MOORE (NMSS)
VICTOR GONZALEZ (MEX)
DALE POWERS (R4)
SCOTT MOORE (NMSS)
VICTOR GONZALEZ (MEX)
STATE LICENSEE REPORTED A CPN GAUGE WAS STOLEN FROM THEIR TECHNICIAN'S TRUCK
Lor Geo Technical of Riverside, CA reported to the state of California that a CPN nuclear gauge model MC1DR serial # MD10506147 was stolen from the back of a technician's pickup truck when it was parked at a fast food restaurant in Victorville, CA. The gauge contained 10 millicuries of Cs-137 and 50 millicuries of Am-241. The local police department was notified and a reward is being offered.
* * * UPDATE 1550 EST ON 4/2/04 FROM DONELLE KRAJEWSKI TO S. SANDIN VIA EMAIL * * *
The State of California was notified on 3/31/04 that the gauge was recovered intact in a utility trench at a jobsite near the one the user had been working in on 3/30/04. The lock on the gauge handle was missing. The recovery of the gauge was also reported to the police by the user.
Notified R4DO (Powers), NMSS (Essig) and Mexico (Gonzalez) via fax.
Lor Geo Technical of Riverside, CA reported to the state of California that a CPN nuclear gauge model MC1DR serial # MD10506147 was stolen from the back of a technician's pickup truck when it was parked at a fast food restaurant in Victorville, CA. The gauge contained 10 millicuries of Cs-137 and 50 millicuries of Am-241. The local police department was notified and a reward is being offered.
* * * UPDATE 1550 EST ON 4/2/04 FROM DONELLE KRAJEWSKI TO S. SANDIN VIA EMAIL * * *
The State of California was notified on 3/31/04 that the gauge was recovered intact in a utility trench at a jobsite near the one the user had been working in on 3/30/04. The lock on the gauge handle was missing. The recovery of the gauge was also reported to the police by the user.
Notified R4DO (Powers), NMSS (Essig) and Mexico (Gonzalez) via fax.
Power Reactor
Event Number: 40626
Facility: POINT BEACH
Region: 3 State: WI
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: CHARLES STALZER
HQ OPS Officer: MIKE RIPLEY
Region: 3 State: WI
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: CHARLES STALZER
HQ OPS Officer: MIKE RIPLEY
Notification Date: 03/30/2004
Notification Time: 15:26 [ET]
Event Date: 03/30/2004
Event Time: 12:15 [CST]
Last Update Date: 03/30/2004
Notification Time: 15:26 [ET]
Event Date: 03/30/2004
Event Time: 12:15 [CST]
Last Update Date: 03/30/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
MICHAEL PARKER (R3)
TERRY REIS (NRR)
MICHAEL PARKER (R3)
TERRY REIS (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 82 | Power Operation |
SAFETY INJECTION ACCUMULATOR LEVEL GREATER THAN ALLOWED BY TECHNICAL SPECIFICATION
"Unit 2 'A' Safety Injection Accumulator level was determined to be greater than level band allowed by technical specification 3.5.1 for Safety Injection Accumulators at 1127 [CST]. A power reduction in preparation for a normal reactor shutdown was commenced at 1215 in accordance with normal plant procedures.
"The Safety Injection Accumulator level instruments were in question due to one indicator being within the normal range and the other being off-scale high. During troubleshooting efforts, an ultra-sonic detector was used to verify 'A' Safety Accumulator tank level. The ultra-sonic detector indicated that level was above the high scale indication, and the accumulator was declared OOS due to being above the maximum accumulator volume allowed by SR 3.5.1.2 (<1136 cubic feet). The Unit 2 'B' Safety Injection Accumulator was unaffected by the event and remains operable.
"The Unit 2 'A' Safety Injection Accumulator level and pressure was returned to technical specification parameters at 1403. The Unit 2 shutdown was stopped with the unit at 82% power and actions are in progress to return to full power operation."
The licensee notified the NRC Resident Inspector.
"Unit 2 'A' Safety Injection Accumulator level was determined to be greater than level band allowed by technical specification 3.5.1 for Safety Injection Accumulators at 1127 [CST]. A power reduction in preparation for a normal reactor shutdown was commenced at 1215 in accordance with normal plant procedures.
"The Safety Injection Accumulator level instruments were in question due to one indicator being within the normal range and the other being off-scale high. During troubleshooting efforts, an ultra-sonic detector was used to verify 'A' Safety Accumulator tank level. The ultra-sonic detector indicated that level was above the high scale indication, and the accumulator was declared OOS due to being above the maximum accumulator volume allowed by SR 3.5.1.2 (<1136 cubic feet). The Unit 2 'B' Safety Injection Accumulator was unaffected by the event and remains operable.
"The Unit 2 'A' Safety Injection Accumulator level and pressure was returned to technical specification parameters at 1403. The Unit 2 shutdown was stopped with the unit at 82% power and actions are in progress to return to full power operation."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 40625
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: JIM STORTZ
HQ OPS Officer: BILL GOTT
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: JIM STORTZ
HQ OPS Officer: BILL GOTT
Notification Date: 03/30/2004
Notification Time: 10:40 [ET]
Event Date: 03/30/2004
Event Time: 07:40 [CST]
Last Update Date: 03/30/2004
Notification Time: 10:40 [ET]
Event Date: 03/30/2004
Event Time: 07:40 [CST]
Last Update Date: 03/30/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
MICHAEL PARKER (R3)
TERRY REIS (NRR)
MICHAEL PARKER (R3)
TERRY REIS (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 72 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM DURING TURBINE THRUST BEARING WEAR DETECTOR TESTING
"At 0740 hours [CST] during testing of the turbine thrust bearing wear detector, a main turbine trip occurred. This resulted in an automatic reactor scram due to turbine stop valve closure. Following the scram all Group II (Primary Containment) and Group III (Reactor Water Cleanup) isolations occurred as expected. All essential equipment functioned as required. Unit 2 remains in Mode 3 with reactor water level in the normal level band. An investigation into the Unit 2 turbine trip is in progress.
"Unit 1 was unaffected by the event and remains at 85% power."
All control rods fully inserted. Decay heat is being removed via steam to the main condenser using the bypass valves.
The Licensee notified the NRC Resident inspector.
"At 0740 hours [CST] during testing of the turbine thrust bearing wear detector, a main turbine trip occurred. This resulted in an automatic reactor scram due to turbine stop valve closure. Following the scram all Group II (Primary Containment) and Group III (Reactor Water Cleanup) isolations occurred as expected. All essential equipment functioned as required. Unit 2 remains in Mode 3 with reactor water level in the normal level band. An investigation into the Unit 2 turbine trip is in progress.
"Unit 1 was unaffected by the event and remains at 85% power."
All control rods fully inserted. Decay heat is being removed via steam to the main condenser using the bypass valves.
The Licensee notified the NRC Resident inspector.
Other Nuclear Material
Event Number: 40674
Rep Org: PENNSYLVANIA STATE UNIVERSITY
Licensee: PENNSYLVANIA STATE UNIVERSITY
Region: 1
City: UNIVERSITY PARK State: PA
County:
License #: 37185-04
Agreement: N
Docket:
NRC Notified By: ERIC BOELDT
HQ OPS Officer: BILL GOTT
Licensee: PENNSYLVANIA STATE UNIVERSITY
Region: 1
City: UNIVERSITY PARK State: PA
County:
License #: 37185-04
Agreement: N
Docket:
NRC Notified By: ERIC BOELDT
HQ OPS Officer: BILL GOTT
Notification Date: 04/14/2004
Notification Time: 15:25 [ET]
Event Date: 03/30/2004
Event Time: 00:00 [EDT]
Last Update Date: 04/14/2004
Notification Time: 15:25 [ET]
Event Date: 03/30/2004
Event Time: 00:00 [EDT]
Last Update Date: 04/14/2004
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):
BRIAN MCDERMOTT (R1)
ROBERTO TORRES (NMSS)
BRIAN MCDERMOTT (R1)
ROBERTO TORRES (NMSS)
MISSING GAS CHROMATOGRAPH
"During a routine sealed source inventory and leak test in March 2004, a technician from the Pennsylvania State University's Office of Environmental Health and Safety (EHS) found that a 14 millicurie source of nickel-63 was missing. The source was from a Varian Associates, Inc. gas chromatograph (GC):
Model number: 3400CX
Serial number : 17561
Source serial number: A10017
NRC Device Key #: 478731
Penn State # 1993-1019
Source Description: Plated nickel-63 source
Current activity: 14 millicuries
"EHS contacted faculty and staff associated with the laboratory while trying to locate the instrument. After repeated inquiries, it was determined that the GC had been sent to University Salvage in September 2003, and from there it was sold as scrap. According to NUREG-1717, Systematic Radiological Assessment of Exemptions for Source and Byproduct Materials, the dose to any individual from a scrapped Ni-63 gas chromatograph source would be less than 0.01 mSv (1 millirem)."
"During a routine sealed source inventory and leak test in March 2004, a technician from the Pennsylvania State University's Office of Environmental Health and Safety (EHS) found that a 14 millicurie source of nickel-63 was missing. The source was from a Varian Associates, Inc. gas chromatograph (GC):
Model number: 3400CX
Serial number : 17561
Source serial number: A10017
NRC Device Key #: 478731
Penn State # 1993-1019
Source Description: Plated nickel-63 source
Current activity: 14 millicuries
"EHS contacted faculty and staff associated with the laboratory while trying to locate the instrument. After repeated inquiries, it was determined that the GC had been sent to University Salvage in September 2003, and from there it was sold as scrap. According to NUREG-1717, Systematic Radiological Assessment of Exemptions for Source and Byproduct Materials, the dose to any individual from a scrapped Ni-63 gas chromatograph source would be less than 0.01 mSv (1 millirem)."