Event Notification Report for May 27, 2004
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/26/2004 - 05/27/2004
EVENT NUMBERS
40782407784077940780
Fuel Cycle Facility
Event Number: 40782
Facility: BWX TECHNOLOGIES
Region: 2 State: VA
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
NRC Notified By: LES DUNCAN
HQ OPS Officer: MIKE RIPLEY
Region: 2 State: VA
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
NRC Notified By: LES DUNCAN
HQ OPS Officer: MIKE RIPLEY
Notification Date: 05/28/2004
Notification Time: 12:48 [ET]
Event Date: 05/27/2004
Event Time: 19:00 [EDT]
Last Update Date: 05/11/2008
Notification Time: 12:48 [ET]
Event Date: 05/27/2004
Event Time: 19:00 [EDT]
Last Update Date: 05/11/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
70.50(b)(2) - SAFETY EQUIPMENT FAILURE
10 CFR Section:
70.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
DAVID AYRES (R2)
LINDA PSYK-GERSEY (NMSS)
DAVID AYRES (R2)
LINDA PSYK-GERSEY (NMSS)
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THIS IS NOT A NEW REPORT.
This event report was originally withheld from public release under the NRC's policy for protecting sensitive unclassified information. The NRC has reevaluated this policy and is now making this event report available to the public with suitable redactions.
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24-HOUR NOTIFICATION - [DELETED] CRITICALITY DETECTOR FAILED ROUTINE TEST
"At approximately 19:00 P.M. on May 27th, one of two criticality detectors for [DELETED] failed a routine source check. The failure resulted in the detector not being able to give a High alarm, which resulted in a loss of criticality detector coverage for [DELETED] at the [DELETED] at BWX Technologies. This situation presents no risk to the public or workers, since the [DELETED] have not had any fuel since February 20, 2001. The last time the [DELETED] criticality detectors were source checked (successfully) was on April 11, 2004. However, [DELETED] was authorized for fuel operations, therefore, criticality detectors were required to be functional. This loss of criticality detector coverage is required to be reported to the NRC within 24 hours per 10CFR70.24 and 10CFR70.50(b)(2)."
The licensee notified the NRC Resident Inspector.
* * * UPDATE ON 05/11/08 BY H. Crouch * * *
THIS IS NOT A NEW REPORT.
This event report was originally withheld from public release under the NRC's policy for protecting sensitive unclassified information. The NRC has reevaluated this policy and is now making this event report available to the public with suitable redactions.
THIS IS NOT A NEW REPORT.
This event report was originally withheld from public release under the NRC's policy for protecting sensitive unclassified information. The NRC has reevaluated this policy and is now making this event report available to the public with suitable redactions.
* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
24-HOUR NOTIFICATION - [DELETED] CRITICALITY DETECTOR FAILED ROUTINE TEST
"At approximately 19:00 P.M. on May 27th, one of two criticality detectors for [DELETED] failed a routine source check. The failure resulted in the detector not being able to give a High alarm, which resulted in a loss of criticality detector coverage for [DELETED] at the [DELETED] at BWX Technologies. This situation presents no risk to the public or workers, since the [DELETED] have not had any fuel since February 20, 2001. The last time the [DELETED] criticality detectors were source checked (successfully) was on April 11, 2004. However, [DELETED] was authorized for fuel operations, therefore, criticality detectors were required to be functional. This loss of criticality detector coverage is required to be reported to the NRC within 24 hours per 10CFR70.24 and 10CFR70.50(b)(2)."
The licensee notified the NRC Resident Inspector.
* * * UPDATE ON 05/11/08 BY H. Crouch * * *
THIS IS NOT A NEW REPORT.
This event report was originally withheld from public release under the NRC's policy for protecting sensitive unclassified information. The NRC has reevaluated this policy and is now making this event report available to the public with suitable redactions.
Power Reactor
Event Number: 40778
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: GLENN HUTTON
HQ OPS Officer: ARLON COSTA
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: GLENN HUTTON
HQ OPS Officer: ARLON COSTA
Notification Date: 05/27/2004
Notification Time: 01:21 [ET]
Event Date: 05/27/2004
Event Time: 00:33 [EDT]
Last Update Date: 05/27/2004
Notification Time: 01:21 [ET]
Event Date: 05/27/2004
Event Time: 00:33 [EDT]
Last Update Date: 05/27/2004
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):
RICHARD CONTE (R1)
RICHARD CONTE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 2 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM WHILE PERFORMING SCHEDULED SHUTDOWN
"During a reactor shutdown for scheduled maintenance, a full reactor scram was generated from the Nuclear Instrumentation System.
"IRMs [Intermediate Range Monitoring detectors] 13, 14 and 18 spiked causing scram signals in both RPS [Reactor Protection Systems].
"All systems functioned properly post scram, all operator actions were correct. Holding reactor pressure at 900 psig to perform leakage inspection. Following [the leakage] inspection [operations intend] to proceed to cold shutdown."
All control rods inserted fully into the core and excess decay heat is currently being diverted to the main condenser, as necessary.
The licensee notified the NRC Resident Inspector.
"During a reactor shutdown for scheduled maintenance, a full reactor scram was generated from the Nuclear Instrumentation System.
"IRMs [Intermediate Range Monitoring detectors] 13, 14 and 18 spiked causing scram signals in both RPS [Reactor Protection Systems].
"All systems functioned properly post scram, all operator actions were correct. Holding reactor pressure at 900 psig to perform leakage inspection. Following [the leakage] inspection [operations intend] to proceed to cold shutdown."
All control rods inserted fully into the core and excess decay heat is currently being diverted to the main condenser, as necessary.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 40779
Facility: HADDAM NECK
Region: 1 State: CT
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: BRIAN CAMPBELL
HQ OPS Officer: HOWIE CROUCH
Region: 1 State: CT
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: BRIAN CAMPBELL
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/27/2004
Notification Time: 10:57 [ET]
Event Date: 05/27/2004
Event Time: 10:20 [EDT]
Last Update Date: 05/27/2004
Notification Time: 10:57 [ET]
Event Date: 05/27/2004
Event Time: 10:20 [EDT]
Last Update Date: 05/27/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION 20.1906(d)(1) - SURFACE CONTAM LEVELS > LIMITS
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION 20.1906(d)(1) - SURFACE CONTAM LEVELS > LIMITS
Person (Organization):
RICHARD CONTE (R1)
ROBERTO TORRES (NMSS)
RICHARD CONTE (R1)
ROBERTO TORRES (NMSS)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Decommissioned | 0 | Decommissioned |
OFFSITE NOTIFICATION MADE DUE TO EXTERNAL CONTAMINATION FOUND ON CONTAINER SHIPPED BY LICENSEE
The following information was received by the licensee via facsimile:
"Contamination levels in excess of USDOT [U.S. Department of Transportation] and Barnwell [South Carolina] limits found on a shipment when it reached its destination. (Sea Land Container).
"No personnel contaminations were reported."
The licensee was informed by Barnwell of the contamination event. Apparently, the temperature difference between Connecticut and South Carolina caused condensation to form inside the Sea Land container. The condensation puddled inside the container and then leaked out onto the trailer bed. Contamination was found by Barnwell personnel upon receipt of the trailer.
The licensee informed the State of Connecticut Department of Environmental Protection representative on site and NRC Region 1 (John Wray).
The following information was received by the licensee via facsimile:
"Contamination levels in excess of USDOT [U.S. Department of Transportation] and Barnwell [South Carolina] limits found on a shipment when it reached its destination. (Sea Land Container).
"No personnel contaminations were reported."
The licensee was informed by Barnwell of the contamination event. Apparently, the temperature difference between Connecticut and South Carolina caused condensation to form inside the Sea Land container. The condensation puddled inside the container and then leaked out onto the trailer bed. Contamination was found by Barnwell personnel upon receipt of the trailer.
The licensee informed the State of Connecticut Department of Environmental Protection representative on site and NRC Region 1 (John Wray).
Power Reactor
Event Number: 40780
Facility: SALEM
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICH DESANCTIS
HQ OPS Officer: MIKE RIPLEY
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICH DESANCTIS
HQ OPS Officer: MIKE RIPLEY
Notification Date: 05/27/2004
Notification Time: 13:15 [ET]
Event Date: 05/27/2004
Event Time: 06:30 [EDT]
Last Update Date: 05/27/2004
Notification Time: 13:15 [ET]
Event Date: 05/27/2004
Event Time: 06:30 [EDT]
Last Update Date: 05/27/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RICHARD CONTE (R1)
RICHARD CONTE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
AUTOMATIC SAFETY INJECTION FUNCTION INADVERTANTLY BLOCKED
"This 8-hour notification is being made to report that in Mode 4, during the start-up of Salem Unit 2, the Automatic Safety Injection function was identified blocked. At 0140 hours on 5/27/04, Salem Unit 2 transitioned from Mode 5 to Mode 4. In Mode 4, Automatic Safety Injection is required per Technical Specification 3.3.2.1. At 0630 hours on 5/27/04, it was discovered that both trains of the Automatic Safety Injection logic were blocked. Technical Specification 3.0.3 was entered. At 0635, Automatic Safety Injection was reinstated to both trains of Safety Injection and Technical Specification 3.0.3 was exited. Salem Unit 2 is currently in Mode 4 with reactor coolant temperature at 320 degrees and reactor coolant pressure at 320 psig. The Reactor Coolant System is being cooled by the 21 Residual Heat Removal loop. During the time period that Automatic Safety Injection was blocked, the required ECCS Pump was available in compliance with Technical Specification 3.5.3. Additionally, the following equipment status existed: 21 Reactor Coolant Pump was cleared and tagged for an oil leak repair, and 22BF19 Main Feed Regulating Valve was cleared and tagged closed for positioner repairs.
"There were no personnel injuries or radiological occurrences associated with this event."
The licensee has notified the NRC Resident Inspector.
"This 8-hour notification is being made to report that in Mode 4, during the start-up of Salem Unit 2, the Automatic Safety Injection function was identified blocked. At 0140 hours on 5/27/04, Salem Unit 2 transitioned from Mode 5 to Mode 4. In Mode 4, Automatic Safety Injection is required per Technical Specification 3.3.2.1. At 0630 hours on 5/27/04, it was discovered that both trains of the Automatic Safety Injection logic were blocked. Technical Specification 3.0.3 was entered. At 0635, Automatic Safety Injection was reinstated to both trains of Safety Injection and Technical Specification 3.0.3 was exited. Salem Unit 2 is currently in Mode 4 with reactor coolant temperature at 320 degrees and reactor coolant pressure at 320 psig. The Reactor Coolant System is being cooled by the 21 Residual Heat Removal loop. During the time period that Automatic Safety Injection was blocked, the required ECCS Pump was available in compliance with Technical Specification 3.5.3. Additionally, the following equipment status existed: 21 Reactor Coolant Pump was cleared and tagged for an oil leak repair, and 22BF19 Main Feed Regulating Valve was cleared and tagged closed for positioner repairs.
"There were no personnel injuries or radiological occurrences associated with this event."
The licensee has notified the NRC Resident Inspector.