Event Notification Report for May 21, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/20/2003 - 05/21/2003
EVENT NUMBERS
398713987239873398743987539910
Power Reactor
Event Number: 39871
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: COSENZA
HQ OPS Officer: CHAUNCEY GOULD
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: COSENZA
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 05/21/2003
Notification Time: 09:15 [ET]
Event Date: 05/21/2003
Event Time: 02:20 [MST]
Last Update Date: 05/21/2003
Notification Time: 09:15 [ET]
Event Date: 05/21/2003
Event Time: 02:20 [MST]
Last Update Date: 05/21/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
TROY PRUETT (R4)
TROY PRUETT (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 98 | Power Operation | 98 | Power Operation |
| 2 | N | Y | 98 | Power Operation | 98 | Power Operation |
| 3 | N | Y | 98 | Power Operation | 98 | Power Operation |
FAILURE OF THE SECURITY FORCES HAND HELD RADIOS
Security at the site had a partial loss of their radio system. Their Bay station and telephone communications systems were up, but the hand held radios could not transmit out. These radios, however could receive. This problem has occurred in the past. Their communications people were able to reboot the system and go back to the secondary and returned the radios back to service. There was no evidence that equipment had been tampered with.
The NRC Resident will be notified.
Security at the site had a partial loss of their radio system. Their Bay station and telephone communications systems were up, but the hand held radios could not transmit out. These radios, however could receive. This problem has occurred in the past. Their communications people were able to reboot the system and go back to the secondary and returned the radios back to service. There was no evidence that equipment had been tampered with.
The NRC Resident will be notified.
Power Reactor
Event Number: 39872
Facility: DRESDEN
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: DENNIS FRANCIS
HQ OPS Officer: HOWIE CROUCH
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: DENNIS FRANCIS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/21/2003
Notification Time: 11:31 [ET]
Event Date: 05/21/2003
Event Time: 04:18 [CDT]
Last Update Date: 05/21/2003
Notification Time: 11:31 [ET]
Event Date: 05/21/2003
Event Time: 04:18 [CDT]
Last Update Date: 05/21/2003
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):
ANNE MARIE STONE (R3)
ANNE MARIE STONE (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 85 | Power Operation | 85 | Power Operation |
ACCIDENT MITIGATION DEGRADED DUE TO PRESSURE SWITCHES OUTSIDE TECHNICAL SPECIFICATION ALLOWANCES
"During calibration of Dresden Unit 2 Electromatic Relief Valve/Target Rock Valve Pressure Switches, two of the five pressure switches were found outside the Technical Specification (TS) Allowable Range and outside the Analytical Limit (1.5 psig above the TS Allowable). Setpoints for the B and C Electromatic Relief Valves (ERVs) were found at 3.1 and 2.4 psig above the TS allowable respectively. The TS Bases state that four ERVs are required to accomplish the safety function for pressure mitigation. This event is reportable because two of five ERV pressure switches were outside TS allowables, which could have prevented fulfillment of the safety function for pressure mitigation (10 CFR 50.73(a)(2)(v)]. The pressure switch setpoints have been subsequently calibrated and returned to within TS allowable values."
The licensee notified NRC Resident Inspector.
"During calibration of Dresden Unit 2 Electromatic Relief Valve/Target Rock Valve Pressure Switches, two of the five pressure switches were found outside the Technical Specification (TS) Allowable Range and outside the Analytical Limit (1.5 psig above the TS Allowable). Setpoints for the B and C Electromatic Relief Valves (ERVs) were found at 3.1 and 2.4 psig above the TS allowable respectively. The TS Bases state that four ERVs are required to accomplish the safety function for pressure mitigation. This event is reportable because two of five ERV pressure switches were outside TS allowables, which could have prevented fulfillment of the safety function for pressure mitigation (10 CFR 50.73(a)(2)(v)]. The pressure switch setpoints have been subsequently calibrated and returned to within TS allowable values."
The licensee notified NRC Resident Inspector.
Other Nuclear Material
Event Number: 39873
Rep Org: S.K. GEOTECHNICAL CORPORATION
Licensee: S.K. GEOTECHNICAL CORPORATION
Region: 4
City: HELENA State: MT
County:
License #: 25-27594-01
Agreement: N
Docket:
NRC Notified By: LOWELL KLOCKE
HQ OPS Officer: ARLON COSTA
Licensee: S.K. GEOTECHNICAL CORPORATION
Region: 4
City: HELENA State: MT
County:
License #: 25-27594-01
Agreement: N
Docket:
NRC Notified By: LOWELL KLOCKE
HQ OPS Officer: ARLON COSTA
Notification Date: 05/21/2003
Notification Time: 13:06 [ET]
Event Date: 05/21/2003
Event Time: 07:00 [MDT]
Last Update Date: 02/09/2005
Notification Time: 13:06 [ET]
Event Date: 05/21/2003
Event Time: 07:00 [MDT]
Last Update Date: 02/09/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
TROY PRUETT (R4)
JIM WHITNEY (TAS)
LARRY CAMPER (NMSS)
TROY PRUETT (R4)
JIM WHITNEY (TAS)
LARRY CAMPER (NMSS)
STOLEN MOISTURE DENSITY GAUGE
A Campbell Pacific Nuclear portable moisture density gauge Model MC-3, Serial Number MC 39058846 was stolen from the licensee's storage trailer. The gauge contains a cesium-americium-beryllium radioactive source (10 millicuries Cs-137 and 50 millicuries Am-241/Be). The licensee's trailer containing the stolen gauge was located at a Home Depot construction site, 1801 Custer Ave, Helena, MT 59601. Helena City police is investigating this and other thefts that occurred overnight at several trailers located at this same site.
The licensee contacted Region IV (M. Shaffer) and will contact the Montana Department of Health.
* * * UPDATE ON 02/09/05 @ 1819 BY GREG STAFFILENO TO CHAUNCEY GOULD * * *
The licensee was contacted by another company which also uses moisture density gauges to inform them they had in their possession the stolen gauge. The individual that had the device spotted it for sale on the street in Los Angeles CA for $20 and bought it. The devise appeared to be in good shape but has been taken to a local gauge service company where it will be checked out before it is returned to the original licensee.
Notified Reg 4 RDO (Whitten) and NMSS EO(Reamer)
A Campbell Pacific Nuclear portable moisture density gauge Model MC-3, Serial Number MC 39058846 was stolen from the licensee's storage trailer. The gauge contains a cesium-americium-beryllium radioactive source (10 millicuries Cs-137 and 50 millicuries Am-241/Be). The licensee's trailer containing the stolen gauge was located at a Home Depot construction site, 1801 Custer Ave, Helena, MT 59601. Helena City police is investigating this and other thefts that occurred overnight at several trailers located at this same site.
The licensee contacted Region IV (M. Shaffer) and will contact the Montana Department of Health.
* * * UPDATE ON 02/09/05 @ 1819 BY GREG STAFFILENO TO CHAUNCEY GOULD * * *
The licensee was contacted by another company which also uses moisture density gauges to inform them they had in their possession the stolen gauge. The individual that had the device spotted it for sale on the street in Los Angeles CA for $20 and bought it. The devise appeared to be in good shape but has been taken to a local gauge service company where it will be checked out before it is returned to the original licensee.
Notified Reg 4 RDO (Whitten) and NMSS EO(Reamer)
Power Reactor
Event Number: 39874
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: RICHARD ALEXANDER
HQ OPS Officer: ARLON COSTA
Region: 1 State: NY
Unit: [2] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: RICHARD ALEXANDER
HQ OPS Officer: ARLON COSTA
Notification Date: 05/21/2003
Notification Time: 17:32 [ET]
Event Date: 05/21/2003
Event Time: 13:55 [EDT]
Last Update Date: 05/21/2003
Notification Time: 17:32 [ET]
Event Date: 05/21/2003
Event Time: 13:55 [EDT]
Last Update Date: 05/21/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ANTHONY DIMITRIADIS (R1)
ANTHONY DIMITRIADIS (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
LOSS COMMUNICATION DUE TO MORE THAN 10% AVAILABILITY OF SIRENS
"On May 21, 2003 at 1355 hours, during on site monitoring of the offsite emergency notification system, three (3) sirens out of a total of 10 in Putnam County indicated a communications failure. The cause for the failure was subsequently determined, based on information obtained by the crew, to have been attributed to communication failure due to fuse failure at the sirens. Communication was fully restored to the affected sirens at approximately 1549 hours on May 21, 2003. Route alerting was available during the loss of sirens.
"The NRC resident inspectors, State and Putnam county were notified of this event."
"On May 21, 2003 at 1355 hours, during on site monitoring of the offsite emergency notification system, three (3) sirens out of a total of 10 in Putnam County indicated a communications failure. The cause for the failure was subsequently determined, based on information obtained by the crew, to have been attributed to communication failure due to fuse failure at the sirens. Communication was fully restored to the affected sirens at approximately 1549 hours on May 21, 2003. Route alerting was available during the loss of sirens.
"The NRC resident inspectors, State and Putnam county were notified of this event."
Other Nuclear Material
Event Number: 39875
Rep Org: TERRACON CORPORATION
Licensee: TERRACON CORPORATION
Region: 3
City: Raymore State: MO
County:
License #: 15-27070-01
Agreement: N
Docket:
NRC Notified By: Bob Weber
HQ OPS Officer: MIKE RIPLEY
Licensee: TERRACON CORPORATION
Region: 3
City: Raymore State: MO
County:
License #: 15-27070-01
Agreement: N
Docket:
NRC Notified By: Bob Weber
HQ OPS Officer: MIKE RIPLEY
Notification Date: 05/21/2003
Notification Time: 18:08 [ET]
Event Date: 05/21/2003
Event Time: 00:00 [CDT]
Last Update Date: 05/21/2003
Notification Time: 18:08 [ET]
Event Date: 05/21/2003
Event Time: 00:00 [CDT]
Last Update Date: 05/21/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
TROY PRUETT (R4)
MARK SHAFFER (R4)
LARRY CAMPER (NMSS)
ANNE MARIE STONE (R3)
TROY PRUETT (R4)
MARK SHAFFER (R4)
LARRY CAMPER (NMSS)
ANNE MARIE STONE (R3)
DAMAGED MOISTURE DENSITY GUAGE
A moisture density gauge owned by the licensee was damaged when it was run over at a construction site in Raymore, Missouri (Hwy. 58 at Lauris Dr.). The gauge is a Campbell Pacific model CPN1DR containing a 10 millicurie Cs-137 source and a 50 millicurie Am-241:Be source. The gauge has been isolated and it has been determined that the sources appear intact. The licensee is the process of retrieving the gauge for return to the manufacturer.
Notified R3DO (A. Stone), R4DO (T. Pruett), R4 (Mark Shaffer), NMSS EO (L. Camper)
A moisture density gauge owned by the licensee was damaged when it was run over at a construction site in Raymore, Missouri (Hwy. 58 at Lauris Dr.). The gauge is a Campbell Pacific model CPN1DR containing a 10 millicurie Cs-137 source and a 50 millicurie Am-241:Be source. The gauge has been isolated and it has been determined that the sources appear intact. The licensee is the process of retrieving the gauge for return to the manufacturer.
Notified R3DO (A. Stone), R4DO (T. Pruett), R4 (Mark Shaffer), NMSS EO (L. Camper)
Power Reactor
Event Number: 39910
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: DAVE BROWN
HQ OPS Officer: ARLON COSTA
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: DAVE BROWN
HQ OPS Officer: ARLON COSTA
Notification Date: 06/09/2003
Notification Time: 21:18 [ET]
Event Date: 05/21/2003
Event Time: 11:55 [PDT]
Last Update Date: 06/09/2003
Notification Time: 21:18 [ET]
Event Date: 05/21/2003
Event Time: 11:55 [PDT]
Last Update Date: 06/09/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
DAVID GRAVES (R4)
DAVID GRAVES (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
TEMPORARY LOSS OF RESIDUAL HEAT REMOVAL PUMP USED FOR SHUTDOWN COOLING
"This event notification is being made to report an event that could have prevented the fulfillment or the safety function to remove residual heat. On May 21, 2003, the plant was shutdown in Mode 5, with reactor pressure vessel (RPV) level being maintained greater than 22 feet above the RPV flange. Technicians were performing routine maintenance and removed an electrical lead from the wrong relay. As a result of removing the wrong lead, Residual Heat Removal (RHR) valve RHR-V-9 closed after receiving a close signal. RHR-V-9 is one of two primary containment isolation valves in the common suction piping to both RHR shutdown cooling loops. The valve closure caused pump RHR-P-2A to trip resulting in a loss of RHR shutdown cooling, and a loss of forced flow through the reactor core. Natural circulation was verified. RHR shutdown cooling could have been promptly restored if desired, but the plant remained in natural circulation to support other maintenance activities. The RHR-V-9 isolation logic was reset 31 minutes after the isolation occurred, at which time RHR-A was declared operable. This event was originally deemed to be not reportable by Columbia. This 8 hour report is being made 19 days after the event date."
The licensee notified the NRC Resident Inspector.
"This event notification is being made to report an event that could have prevented the fulfillment or the safety function to remove residual heat. On May 21, 2003, the plant was shutdown in Mode 5, with reactor pressure vessel (RPV) level being maintained greater than 22 feet above the RPV flange. Technicians were performing routine maintenance and removed an electrical lead from the wrong relay. As a result of removing the wrong lead, Residual Heat Removal (RHR) valve RHR-V-9 closed after receiving a close signal. RHR-V-9 is one of two primary containment isolation valves in the common suction piping to both RHR shutdown cooling loops. The valve closure caused pump RHR-P-2A to trip resulting in a loss of RHR shutdown cooling, and a loss of forced flow through the reactor core. Natural circulation was verified. RHR shutdown cooling could have been promptly restored if desired, but the plant remained in natural circulation to support other maintenance activities. The RHR-V-9 isolation logic was reset 31 minutes after the isolation occurred, at which time RHR-A was declared operable. This event was originally deemed to be not reportable by Columbia. This 8 hour report is being made 19 days after the event date."
The licensee notified the NRC Resident Inspector.