Event Notification Report for February 03, 2004
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/02/2004 - 02/03/2004
EVENT NUMBERS
4050340504405054050040555
Power Reactor
Event Number: 40503
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DAN AUTALA
HQ OPS Officer: MIKE RIPLEY
Region: 4 State: AZ
Unit: [1] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DAN AUTALA
HQ OPS Officer: MIKE RIPLEY
Notification Date: 02/03/2004
Notification Time: 18:52 [ET]
Event Date: 02/03/2004
Event Time: 15:35 [MST]
Last Update Date: 02/03/2004
Notification Time: 18:52 [ET]
Event Date: 02/03/2004
Event Time: 15:35 [MST]
Last Update Date: 02/03/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
ANTHONY GODY (R4)
GENE IMBRO (NRR)
RICHARD WESSMAN (IRO)
MICHAEL WEBER (NSIR)
ANTHONY GODY (R4)
GENE IMBRO (NRR)
RICHARD WESSMAN (IRO)
MICHAEL WEBER (NSIR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 99 | Power Operation | 45 | Power Operation |
TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO RCS PRESSURE BOUNDARY LEAKAGE
"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"On February 3, 2004 at approximately 14:18 MST, Palo Verde Nuclear Generating Station (PVNGS) Unit 1 identified reactor coolant system (RCS) pressure boundary leakage. PVNGS Unit 1 was in Mode 1 (Power Operation) at 99% power with normal RCS temperature and pressure at the time of discovery. A normal reactor shutdown was commenced at 15:35. Technical Specification Limiting Condition for Operation 3.4.14 (RCS Operational Leakage) allows no pressure boundary leakage and requires the plant to be in Mode 3 (Hot Shutdown) within 6 hours and Mode 5 (Cold Shutdown) within 36 hours and TLCO 3.14.103 (Structural Integrity).
"The leakage was discovered on a High Pressure Safety Injection Drain Valve (SIA-V056) with is connected to the RCS loop 1 hot leg and is non isolable. The location of the leak is at a weld on the valve socket weld and is estimated at 10 drops per second.
"No automatic or manual reactor protection system or engineered safety features actuations occurred and none were required. There were no other component failures, testing or work in progress that contributed to the leak. The leak is located within the containment building, therefore there is no release of radioactivity to the environment and no impact to the health and safety of the public. There is no elevated RCS activity and heat removal is via normal steaming to the main turbine condenser, The electric grid is stable."
The licensee has notified the NRC resident Inspector.
"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"On February 3, 2004 at approximately 14:18 MST, Palo Verde Nuclear Generating Station (PVNGS) Unit 1 identified reactor coolant system (RCS) pressure boundary leakage. PVNGS Unit 1 was in Mode 1 (Power Operation) at 99% power with normal RCS temperature and pressure at the time of discovery. A normal reactor shutdown was commenced at 15:35. Technical Specification Limiting Condition for Operation 3.4.14 (RCS Operational Leakage) allows no pressure boundary leakage and requires the plant to be in Mode 3 (Hot Shutdown) within 6 hours and Mode 5 (Cold Shutdown) within 36 hours and TLCO 3.14.103 (Structural Integrity).
"The leakage was discovered on a High Pressure Safety Injection Drain Valve (SIA-V056) with is connected to the RCS loop 1 hot leg and is non isolable. The location of the leak is at a weld on the valve socket weld and is estimated at 10 drops per second.
"No automatic or manual reactor protection system or engineered safety features actuations occurred and none were required. There were no other component failures, testing or work in progress that contributed to the leak. The leak is located within the containment building, therefore there is no release of radioactivity to the environment and no impact to the health and safety of the public. There is no elevated RCS activity and heat removal is via normal steaming to the main turbine condenser, The electric grid is stable."
The licensee has notified the NRC resident Inspector.
Power Reactor
Event Number: 40504
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: CLAY WILLIAMS
HQ OPS Officer: CHAUNCEY GOULD
Region: 4 State: CA
Unit: [] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: CLAY WILLIAMS
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 02/03/2004
Notification Time: 19:05 [ET]
Event Date: 02/03/2004
Event Time: 11:30 [PST]
Last Update Date: 02/03/2004
Notification Time: 19:05 [ET]
Event Date: 02/03/2004
Event Time: 11:30 [PST]
Last Update Date: 02/03/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
ANTHONY GODY (R4)
ANTHONY GODY (R4)
| 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 |
LICENSEE REPORTED A FISH KILL INVOLVING APPROXIMATELY 13,590 POUNDS OF SARDINES
Section 4.1 of Appendix B of the Operating License for Units 2 and 3 requires Southern California Edison (SCE) to report to the NRC within 24 hours any unusual or important environmental events, which includes unusual fish kills.
Between February 2 and February 3, 2004, SCE removed an unusually large number of sardines from the Units 2 and 3 intake structure. At approximately 1100 on February 3, 2004, SCE determined the quantity to be approximately 13,590 pounds (approximately 6940 pounds from Unit 2 and 6650 pounds from Unit 3). While the NRC has not specified a reporting limit for an unusual fish kill, SCE has internally defined this quantity as 4500 pounds. SCE believes the unusual
influx of sardines may be related to current winter storm conditions.
The NRC Resident Inspectors have been notified
The licensee will also give a courtesy call to the San Diego Regional Water Quality Control Board
Section 4.1 of Appendix B of the Operating License for Units 2 and 3 requires Southern California Edison (SCE) to report to the NRC within 24 hours any unusual or important environmental events, which includes unusual fish kills.
Between February 2 and February 3, 2004, SCE removed an unusually large number of sardines from the Units 2 and 3 intake structure. At approximately 1100 on February 3, 2004, SCE determined the quantity to be approximately 13,590 pounds (approximately 6940 pounds from Unit 2 and 6650 pounds from Unit 3). While the NRC has not specified a reporting limit for an unusual fish kill, SCE has internally defined this quantity as 4500 pounds. SCE believes the unusual
influx of sardines may be related to current winter storm conditions.
The NRC Resident Inspectors have been notified
The licensee will also give a courtesy call to the San Diego Regional Water Quality Control Board
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 40505
Facility: SEABROOK
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: DAMON RITTER
HQ OPS Officer: MIKE RIPLEY
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: DAMON RITTER
HQ OPS Officer: MIKE RIPLEY
Notification Date: 02/03/2004
Notification Time: 19:24 [ET]
Event Date: 02/03/2004
Event Time: 18:25 [EST]
Last Update Date: 02/04/2004
Notification Time: 19:24 [ET]
Event Date: 02/03/2004
Event Time: 18:25 [EST]
Last Update Date: 02/04/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
JOHN KINNEMAN (R1)
MATTHEW HAHN (TAS)
JOHN KINNEMAN (R1)
MATTHEW HAHN (TAS)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
SAFEGUARDS REPORT
"Discovered vulnerability in a safeguard system that could allow unauthorized or undetected access to safeguards material for which compensatory measures have not been employed. The licensee will be notifying the NRC Resident Inspector. Contact the Headquarters Operations Officer for additional details."
* * * * RETRACTION FROM D. RITTER TO M. RIPLEY 1748 ET 02/04/04 * * * *
"Seabrook Station is retracting the one-hour notification made at 1924, 3 Feb 04 under EN # 40505. Upon further review of reporting criteria, the incident will be documented in the station's Security Event Log."
The licensee will notify the NRC Resident Inspector and NRC Region 1 office. Notified R1 DO (J. Kinneman) and NSIR TAS (A. Danis).
"Discovered vulnerability in a safeguard system that could allow unauthorized or undetected access to safeguards material for which compensatory measures have not been employed. The licensee will be notifying the NRC Resident Inspector. Contact the Headquarters Operations Officer for additional details."
* * * * RETRACTION FROM D. RITTER TO M. RIPLEY 1748 ET 02/04/04 * * * *
"Seabrook Station is retracting the one-hour notification made at 1924, 3 Feb 04 under EN # 40505. Upon further review of reporting criteria, the incident will be documented in the station's Security Event Log."
The licensee will notify the NRC Resident Inspector and NRC Region 1 office. Notified R1 DO (J. Kinneman) and NSIR TAS (A. Danis).
Power Reactor
Event Number: 40500
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JAMES MILLIGAN
HQ OPS Officer: JOHN MacKINNON
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JAMES MILLIGAN
HQ OPS Officer: JOHN MacKINNON
Notification Date: 02/03/2004
Notification Time: 09:24 [ET]
Event Date: 02/03/2004
Event Time: 04:39 [CST]
Last Update Date: 02/03/2004
Notification Time: 09:24 [ET]
Event Date: 02/03/2004
Event Time: 04:39 [CST]
Last Update Date: 02/03/2004
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):
ANTHONY GODY (R4)
ANTHONY GODY (R4)
| 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 |
AUTOMATIC REACTOR TRIP DUE TO MAIN GENERATOR OUTPUT BREAKERS OPENING.
"AT 0439, 02/03/04, Callaway Plant experienced a reactor trip while operating transmission breakers located in the plant switchyard. Auxiliary feedwater actuated as expected to stabilize steam generator water levels. All other plant systems responded as expected. At present, the cause of the reactor trip is undetermined. Initial indications are that there were no voltage or frequency perturbations on the electrical grid. Plant staff is investigating potential areas in an effort to identify the cause of the trip."
The main generator output breakers opened when one of the transmission breakers in the switchyard was opened per the scheduled maintenance test. When the incoming Transmission line breaker was opened it should not have caused the main generator output breakers to open. All rods fully inserted into the core. Both Motor Driven Auxiliary Feedwater pumps automatically started on a loss of both main feedwater pumps and the Turbine Driven Auxiliary Feedwater pump started on low low steam generator water level. The "C" Steam Generator atmospheric steam dump valve opened for about 17 seconds before it closed (no leaking steam generator tubes in the "C" Steam Generator). All Emergency Core Cooling systems are fully operable except for the "A" Safety Injection System. It was declared inoperable when it failed a valve test last night at 0205 CST. All Emergency Diesel Generators are fully operable.
Turbine Driven Auxiliary Feedwater Pump discharge valves were closed after it had operator for about two hours. Approximately one hour after the valves were closed the Turbine Driven Auxiliary Feedwater pump tripped. This incident is being investigated.
The NRC Resident Inspector was notified of this event by the licensee.
"AT 0439, 02/03/04, Callaway Plant experienced a reactor trip while operating transmission breakers located in the plant switchyard. Auxiliary feedwater actuated as expected to stabilize steam generator water levels. All other plant systems responded as expected. At present, the cause of the reactor trip is undetermined. Initial indications are that there were no voltage or frequency perturbations on the electrical grid. Plant staff is investigating potential areas in an effort to identify the cause of the trip."
The main generator output breakers opened when one of the transmission breakers in the switchyard was opened per the scheduled maintenance test. When the incoming Transmission line breaker was opened it should not have caused the main generator output breakers to open. All rods fully inserted into the core. Both Motor Driven Auxiliary Feedwater pumps automatically started on a loss of both main feedwater pumps and the Turbine Driven Auxiliary Feedwater pump started on low low steam generator water level. The "C" Steam Generator atmospheric steam dump valve opened for about 17 seconds before it closed (no leaking steam generator tubes in the "C" Steam Generator). All Emergency Core Cooling systems are fully operable except for the "A" Safety Injection System. It was declared inoperable when it failed a valve test last night at 0205 CST. All Emergency Diesel Generators are fully operable.
Turbine Driven Auxiliary Feedwater Pump discharge valves were closed after it had operator for about two hours. Approximately one hour after the valves were closed the Turbine Driven Auxiliary Feedwater pump tripped. This incident is being investigated.
The NRC Resident Inspector was notified of this event by the licensee.
Power Reactor
Event Number: 40555
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: KEN LEFFEL
HQ OPS Officer: BILL GOTT
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: KEN LEFFEL
HQ OPS Officer: BILL GOTT
Notification Date: 02/28/2004
Notification Time: 15:47 [ET]
Event Date: 02/03/2004
Event Time: 00:00 [CST]
Last Update Date: 03/04/2004
Notification Time: 15:47 [ET]
Event Date: 02/03/2004
Event Time: 00:00 [CST]
Last Update Date: 03/04/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
MONTE PHILLIPS (R3)
MONTE PHILLIPS (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 25 | Power Operation | 25 | Power Operation |
DEAD FISH FOUND AT CLINTON POWER STATION
The licensee provided the following in accordance with their operating license Appendix B, Environmental Protection Plan.
"At approximately 2100 hrs. on 2/27/04, the Illinois Department of Natural Resources (IDNR) contacted Exelon corporate environmental personnel and informed them there was a fish loss on Clinton Lake. Corporate personnel notified Clinton Power Station personnel at 2130 hrs.
"An inspection on the lake shoreline on 2/28/04 occurred from 0800 to 1200 hrs by station personnel.
"The inspection revealed a total of several hundred deceased fish over several locations. The species predominantly observed were gizzard shad. As followup, the final tally of fish affected will be determined after further communication by CPS environmental personnel working with IDNR.
"The fish appeared have been deceased 3-5 weeks, based on observed decomposition. This 3-5 week time period closely coincides with Clinton Power Station's shutdown on 2/3/04 for refueling outage C1R09."
The Licensee notified the NRC Resident Inspector.
**** Update on 03/04/04 at 1648 EST from Leffel taken by MacKinnon *****
A press release of the dead fish found was issued today, 03/04/04, by the licensee.
R3DO (Jim Creed) notified.
NRC Resident Inspector was notified of this update by the licensee.
The licensee provided the following in accordance with their operating license Appendix B, Environmental Protection Plan.
"At approximately 2100 hrs. on 2/27/04, the Illinois Department of Natural Resources (IDNR) contacted Exelon corporate environmental personnel and informed them there was a fish loss on Clinton Lake. Corporate personnel notified Clinton Power Station personnel at 2130 hrs.
"An inspection on the lake shoreline on 2/28/04 occurred from 0800 to 1200 hrs by station personnel.
"The inspection revealed a total of several hundred deceased fish over several locations. The species predominantly observed were gizzard shad. As followup, the final tally of fish affected will be determined after further communication by CPS environmental personnel working with IDNR.
"The fish appeared have been deceased 3-5 weeks, based on observed decomposition. This 3-5 week time period closely coincides with Clinton Power Station's shutdown on 2/3/04 for refueling outage C1R09."
The Licensee notified the NRC Resident Inspector.
**** Update on 03/04/04 at 1648 EST from Leffel taken by MacKinnon *****
A press release of the dead fish found was issued today, 03/04/04, by the licensee.
R3DO (Jim Creed) notified.
NRC Resident Inspector was notified of this update by the licensee.