Event Notification Report for July 29, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/28/2003 - 07/29/2003
EVENT NUMBERS
40030400324003340034
Power Reactor
Event Number: 40030
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: NOEL KEMM
HQ OPS Officer: STEVE SANDIN
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: NOEL KEMM
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/29/2003
Notification Time: 14:48 [ET]
Event Date: 07/29/2003
Event Time: 14:01 [EDT]
Last Update Date: 07/29/2003
Notification Time: 14:48 [ET]
Event Date: 07/29/2003
Event Time: 14:01 [EDT]
Last Update Date: 07/29/2003
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
JAMES NOGGLE (R1)
BOB DENNIG (NRR)
NADER MAMISH (IRO)
MIKE EACHES (FEMA)
ANDREA HEINTZELMAN (DHS)
JAMES NOGGLE (R1)
BOB DENNIG (NRR)
NADER MAMISH (IRO)
MIKE EACHES (FEMA)
ANDREA HEINTZELMAN (DHS)
| 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 |
UNIT 1 DECLARED AN UNUSUAL EVENT DUE TO THE LOSS OF 500KV OFFSITE POWER
"Experienced breaker failure of 500 KV 1-5 breaker. The protective function of this took out 500 KV bus section 1. All 4 KV vital buses deenergized and were repowered by the emergency diesel generators. Also 2 of 4 group buses deenergized. Auxiliary feedwater pumps started on steam generator low levels. This all resulted in a reactor trip. The source of the failure has yet to be determined. Reactor coolant temperature is being controlled by turbine bypass valves."
The licensee informed state/local agencies and the NRC resident inspector.
* * * UPDATE ON 7/29/03 AT 1803 EDT FROM NOEL KEMM TO BILL GOTT * * *
"500 KV bus section one energized. 4KV vital bus 1B energized from offsite power by 13 station power transformer. Restoration of 1A and 1C 4KV vital buses from offsite power in progress. Initial problem appears to be a ground problem with 1-5 500 KV breaker and subsequent breaker failure relay scheme."
The licensee has notified the NRC Resident Inspector and Region 1 IRC.
* * * UPDATE ON 7/29/03 AT 2103 EDT FROM MARK FIOCCO TO GERRY WAIG * * *
"Current Plant Status: 500 KV Bus section one energized . 4KV vital buses 1B and 1C energized from offsite power by 13 station power transformer. Restoration of 1A 4KV vital bus from offsite power in progress."
The licensee has not notified the NRC Resident Inspector. The HQ Operatiions Officer notified NRC Region 1 IRC.
* * * UPDATE ON 7/29/03 AT 2201 EDT FROM MARK FIOCCO TO GERRY WAIG * * *
"Status Update: All 4KV vital buses energized from 13 station power transformer. Restoration of second source of offsite AC power is in progress. Making preparation to terminate Unusual Event." The licensee has notified the NRC Resident Inspector.
* * * UPDATE ON 7/29/03 AT 2211 EDT FROM MARK FIOCCO TO GERRY WAIG * * *
The Licensee terminated Notice of Unusual Event (NOUE) on 07/29/03 at 2211 hours EDT. The licensee has notified the NRC Resident Inspector.
The HQ Operatiions Officer notified FEMA (Butch Stiendurf) and DHS (Ed Welch) of the NOUE termination.
"Experienced breaker failure of 500 KV 1-5 breaker. The protective function of this took out 500 KV bus section 1. All 4 KV vital buses deenergized and were repowered by the emergency diesel generators. Also 2 of 4 group buses deenergized. Auxiliary feedwater pumps started on steam generator low levels. This all resulted in a reactor trip. The source of the failure has yet to be determined. Reactor coolant temperature is being controlled by turbine bypass valves."
The licensee informed state/local agencies and the NRC resident inspector.
* * * UPDATE ON 7/29/03 AT 1803 EDT FROM NOEL KEMM TO BILL GOTT * * *
"500 KV bus section one energized. 4KV vital bus 1B energized from offsite power by 13 station power transformer. Restoration of 1A and 1C 4KV vital buses from offsite power in progress. Initial problem appears to be a ground problem with 1-5 500 KV breaker and subsequent breaker failure relay scheme."
The licensee has notified the NRC Resident Inspector and Region 1 IRC.
* * * UPDATE ON 7/29/03 AT 2103 EDT FROM MARK FIOCCO TO GERRY WAIG * * *
"Current Plant Status: 500 KV Bus section one energized . 4KV vital buses 1B and 1C energized from offsite power by 13 station power transformer. Restoration of 1A 4KV vital bus from offsite power in progress."
The licensee has not notified the NRC Resident Inspector. The HQ Operatiions Officer notified NRC Region 1 IRC.
* * * UPDATE ON 7/29/03 AT 2201 EDT FROM MARK FIOCCO TO GERRY WAIG * * *
"Status Update: All 4KV vital buses energized from 13 station power transformer. Restoration of second source of offsite AC power is in progress. Making preparation to terminate Unusual Event." The licensee has notified the NRC Resident Inspector.
* * * UPDATE ON 7/29/03 AT 2211 EDT FROM MARK FIOCCO TO GERRY WAIG * * *
The Licensee terminated Notice of Unusual Event (NOUE) on 07/29/03 at 2211 hours EDT. The licensee has notified the NRC Resident Inspector.
The HQ Operatiions Officer notified FEMA (Butch Stiendurf) and DHS (Ed Welch) of the NOUE termination.
Power Reactor
Event Number: 40032
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: ROBERT WORRELL
HQ OPS Officer: BILL GOTT
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: ROBERT WORRELL
HQ OPS Officer: BILL GOTT
Notification Date: 07/29/2003
Notification Time: 20:59 [ET]
Event Date: 07/29/2003
Event Time: 20:00 [EDT]
Last Update Date: 07/31/2003
Notification Time: 20:59 [ET]
Event Date: 07/29/2003
Event Time: 20:00 [EDT]
Last Update Date: 07/31/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(1) - SURFACE CONTAM LEVELS > LIMITS
10 CFR Section:
20.1906(d)(1) - SURFACE CONTAM LEVELS > LIMITS
Person (Organization):
JAMES MOORMAN (R2)
PHILIP BROCHMAN (NSIR)
DANIEL GILLEN (NMSS)
JAMES MOORMAN (R2)
PHILIP BROCHMAN (NSIR)
DANIEL GILLEN (NMSS)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
SURFACE CONTAMINATION LEVELS ABOVE LIMITS
"This report is generated due to finding smearable contamination on the spent fuel shipping cask. Smearable contamination in excess of 10CFR71.87 requires a one hour report. Due to 10CFR21, we cannot disclose further information over non-secure communications."
The licensee informed the NRC Resident Inspector.
Additional information can be obtained from the NRC Operations Center.
* * * Update on 07/31/03 at 1011 EDT by G. Gazda to MacKinnon * * *
Highest corrected contamination level for beta gamma was 43,980 dpm per 100 square centimeter (limit is 22,000 dpm per 100 square centimeter). All other smears taken were within limits. R2DO (JIM MOORMAN) & NMSS (DANIEL GILLEN) notified.
NRC Resident Inspector was notified of this update by the licensee.
"This report is generated due to finding smearable contamination on the spent fuel shipping cask. Smearable contamination in excess of 10CFR71.87 requires a one hour report. Due to 10CFR21, we cannot disclose further information over non-secure communications."
The licensee informed the NRC Resident Inspector.
Additional information can be obtained from the NRC Operations Center.
* * * Update on 07/31/03 at 1011 EDT by G. Gazda to MacKinnon * * *
Highest corrected contamination level for beta gamma was 43,980 dpm per 100 square centimeter (limit is 22,000 dpm per 100 square centimeter). All other smears taken were within limits. R2DO (JIM MOORMAN) & NMSS (DANIEL GILLEN) notified.
NRC Resident Inspector was notified of this update by the licensee.
Power Reactor
Event Number: 40033
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [] [2] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DUANE KANITZ
HQ OPS Officer: STEVE SANDIN
Region: 4 State: AZ
Unit: [] [2] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DUANE KANITZ
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/29/2003
Notification Time: 21:13 [ET]
Event Date: 07/29/2003
Event Time: 15:16 [MST]
Last Update Date: 08/06/2003
Notification Time: 21:13 [ET]
Event Date: 07/29/2003
Event Time: 15:16 [MST]
Last Update Date: 08/06/2003
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 50.72(b)(2)(iv)(A) - ECCS INJECTION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(2)(iv)(A) - ECCS INJECTION
Person (Organization):
CHUCK CAIN (R4)
PAT GWYNN (RA)
WILLIAM BECKNER (NRR)
CHUCK CAIN (R4)
PAT GWYNN (RA)
WILLIAM BECKNER (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 98 | Power Operation | 0 | Hot Standby |
UNIT 2 WAS MANUALLY TRIPPED AFTER A STUCK OPEN SPRAY VALVE FAILED TO CLOSE
"On July 29, 2003, at approximately 1518 Mountain Standard Time (MST) Palo Verde Unit 2 plant operators manually tripped the reactor from approximately 98% rated thermal power due to reduced reactor coolant system pressure when a pressurizer spray valve opened and failed to close on operator demand. Unit 2 was at normal temperature and pressure prior to the trip. All CEAs inserted fully into the reactor core. This was an uncomplicated reactor trip. No emergency classification was required per the Emergency Plan. Containment Isolation and Safety Injection Actuation Signals were received following the manual reactor trip per design. Safety related buses remained energized during and following the reactor trip. No significant LCOs have been entered as a result of this event. The pressurizer spray valve that initiated the event was being placed in service following maintenance.
"Unit 2 is stabilized in Mode 3 at approximately 564 degrees F and 2200 psia. The reactor coolant system remains in natural circulation with heat removal via Steam Bypass Control to the main condenser. The event did not result in any challenges to fission product barriers and there were no adverse safety consequences as a result of this event. The event did not adversely affect the safe operation of the plant or the health and safety of the public.
"The Resident Inspector was informed of the Unit 2 reactor trip and this notification. The Resident Inspector is onsite to observe response to the reactor trip.
"The reactor coolant pumps were secured after the trip to stop continued spray flow and depressurization per the alarm response procedure. The offsite electrical power grid is stable."
* * * UPDATE ON 8/6/03 AT 2325 EDT FROM D. GRAFF TO E. THOMAS * * *
"At the time of the initial notification it was not believed that an ECCS discharge to the RCS occurred. Subsequent review of post-trip data determined that injection did occur. The total accumulated actuation cycles to date for Palo Verde Unit 2 is 8. The thermal fatigue limit is 160 cycles, thus the unit is well within the 0.70 (70%) usage threshold of 112 cycles.
"Unit 2 is in Mode 1 at approximately 98% power, normal operating temperature and pressure.
"The NRC Resident Inspector has been notified of this followup notification."
The ECCS actuation occurred on a low pressurizer pressure signal.
Notified R4DO (J. Whitten)
"On July 29, 2003, at approximately 1518 Mountain Standard Time (MST) Palo Verde Unit 2 plant operators manually tripped the reactor from approximately 98% rated thermal power due to reduced reactor coolant system pressure when a pressurizer spray valve opened and failed to close on operator demand. Unit 2 was at normal temperature and pressure prior to the trip. All CEAs inserted fully into the reactor core. This was an uncomplicated reactor trip. No emergency classification was required per the Emergency Plan. Containment Isolation and Safety Injection Actuation Signals were received following the manual reactor trip per design. Safety related buses remained energized during and following the reactor trip. No significant LCOs have been entered as a result of this event. The pressurizer spray valve that initiated the event was being placed in service following maintenance.
"Unit 2 is stabilized in Mode 3 at approximately 564 degrees F and 2200 psia. The reactor coolant system remains in natural circulation with heat removal via Steam Bypass Control to the main condenser. The event did not result in any challenges to fission product barriers and there were no adverse safety consequences as a result of this event. The event did not adversely affect the safe operation of the plant or the health and safety of the public.
"The Resident Inspector was informed of the Unit 2 reactor trip and this notification. The Resident Inspector is onsite to observe response to the reactor trip.
"The reactor coolant pumps were secured after the trip to stop continued spray flow and depressurization per the alarm response procedure. The offsite electrical power grid is stable."
* * * UPDATE ON 8/6/03 AT 2325 EDT FROM D. GRAFF TO E. THOMAS * * *
"At the time of the initial notification it was not believed that an ECCS discharge to the RCS occurred. Subsequent review of post-trip data determined that injection did occur. The total accumulated actuation cycles to date for Palo Verde Unit 2 is 8. The thermal fatigue limit is 160 cycles, thus the unit is well within the 0.70 (70%) usage threshold of 112 cycles.
"Unit 2 is in Mode 1 at approximately 98% power, normal operating temperature and pressure.
"The NRC Resident Inspector has been notified of this followup notification."
The ECCS actuation occurred on a low pressurizer pressure signal.
Notified R4DO (J. Whitten)
Power Reactor
Event Number: 40034
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DANN DAILEY
HQ OPS Officer: JOHN MacKINNON
Region: 4 State: AZ
Unit: [1] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DANN DAILEY
HQ OPS Officer: JOHN MacKINNON
Notification Date: 07/30/2003
Notification Time: 07:45 [ET]
Event Date: 07/29/2003
Event Time: 23:44 [MST]
Last Update Date: 07/30/2003
Notification Time: 07:45 [ET]
Event Date: 07/29/2003
Event Time: 23:44 [MST]
Last Update Date: 07/30/2003
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):
CHUCK CAIN (R4)
CHUCK CAIN (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 |
LOSS OF 9 OF THE 42 EMERGENCY EVACUATIONS SIRENS DUE TO STORM
"On July 29, 2003 at approximately 23:44 Mountain Standard Time, the Palo Verde Unit 1 control room was notified of a power failure, probably due to a storm that recently passed through the area of Buckeye, AZ, causing the loss of 9 of the 42 emergency evacuation sirens. The 9 affected sirens are estimated to impact approximately 26% of the population in the emergency planning zone (EPZ). This call is being placed due to the relatively large segment of the population affected, and the uncertainty of the length of time that will be needed to restore electrical power to the affected areas. The Palo Verde Emergency Plan (section 6.6.2.1) has a contingency for dispatching Maricopa County Sheriff's Office (MCSO) vehicles with loud speakers to alert persons within the affected area (s) when sirens are inoperable.
"There are no events in progress that require siren operation.
"The NRC Resident Inspector has been notified of the siren failure and this ENS call."
* * * UPDATE ON 7/30/03 AT 1200 EDT FROM DAN MARKS TO S. SANDIN * * *
"On July 30, 2003, at approximately 08:15 AM (MST), the Palo Verde Unit 1 control room was notified that power had been restored to the 9 emergency evacuation sirens. The NRC Resident Inspector has been notified."
Notified R4DO (Cain)
"On July 29, 2003 at approximately 23:44 Mountain Standard Time, the Palo Verde Unit 1 control room was notified of a power failure, probably due to a storm that recently passed through the area of Buckeye, AZ, causing the loss of 9 of the 42 emergency evacuation sirens. The 9 affected sirens are estimated to impact approximately 26% of the population in the emergency planning zone (EPZ). This call is being placed due to the relatively large segment of the population affected, and the uncertainty of the length of time that will be needed to restore electrical power to the affected areas. The Palo Verde Emergency Plan (section 6.6.2.1) has a contingency for dispatching Maricopa County Sheriff's Office (MCSO) vehicles with loud speakers to alert persons within the affected area (s) when sirens are inoperable.
"There are no events in progress that require siren operation.
"The NRC Resident Inspector has been notified of the siren failure and this ENS call."
* * * UPDATE ON 7/30/03 AT 1200 EDT FROM DAN MARKS TO S. SANDIN * * *
"On July 30, 2003, at approximately 08:15 AM (MST), the Palo Verde Unit 1 control room was notified that power had been restored to the 9 emergency evacuation sirens. The NRC Resident Inspector has been notified."
Notified R4DO (Cain)