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Event Notification Report for July 5, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/03/2013 - 07/05/2013

** EVENT NUMBERS **


49169 49170 49171 49172 49173

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Power Reactor Event Number: 49169
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: JAMES BLAZEK
HQ OPS Officer: PETE SNYDER
Notification Date: 07/03/2013
Notification Time: 00:24 [ET]
Event Date: 07/03/2013
Event Time: [MST]
Last Update Date: 07/03/2013
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
ART HOWELL (R4)
ERIC LEEDS (NRR)
WILLIAM GOTT (IRD)
VINCENT GADDY (R4DO)
HO NIEH (NRR)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 61 Power Operation

Event Text

NOTICE OF UNUSUAL EVENT DUE TO EXPLOSION IN A NON-SAFETY RELATED LOAD CENTER

"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 7/2/2013, at approximately 2027 MST, Palo Verde Unit 1 experienced a reactor power cutback from 100% rated thermal power due to explosion [in a non-safety related load center (1ENGNL02)]. The unit was at normal temperature and pressure prior to the cutback.

"At 2035 [MST] PVNGS Unit 1 declared an Unusual Event due to the explosion EAL HU 2.2.

"Unit 1 is stable at 61% rated thermal power. No ESF actuations occurred and none were required. The event did not result in any challenges to the fission product barrier or result in any releases of radioactive materials. There were no adverse safety consequences or implications as a result of this event. The event did not adversely affect the safe operation of the plant or health and safety of the public."

The licensee will notify the NRC Resident Inspector.

Notified DHS SWO, FEMA, DHS NICC, and Nuclear SSA via email.

* * * UPDATE ON 7/3/13 AT 0229 EDT FROM JEONG LIM TO PETE SNYDER * * *

"Palo Verde Unit 1 is stable at 58% rated thermal power and is implementing abnormal operating procedures for reactor power cutback due to loss of one Main Feedwater Pump and degraded electrical power due to loss of non-class 13.8kV load center 1ENGNL02. Load center 1ENGNL02 was damaged from an apparent electrical malfunction that originated within the load center. The 13.8kV supply breaker to load center 1ENGNL02 tripped to deenergize the load center. Palo Verde Fire Department personnel responded but determined that the load center was deenergized and no fire existed and no extinguishing agents were applied. No damage to other equipment in proximity to load center 1ENGNL02 was identified during a preliminary inspection of the area around the damaged load center. The NRC Resident Inspector has been notified.

"At 2315 [MST] on 07/02/2013, the Unusual Event was terminated."

Notified R4DO (Gaddy), NRR EO (Nieh), IRD MOC (Gott), DHS SWO, FEMA, DHS NICC, and Nuclear SSA via email.

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Power Reactor Event Number: 49170
Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BUD HINCKLEY
HQ OPS Officer: DONALD NORWOOD
Notification Date: 07/03/2013
Notification Time: 01:15 [ET]
Event Date: 07/03/2013
Event Time: 01:15 [EDT]
Last Update Date: 07/03/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MICHAEL KUNOWSKI (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

UNAVAILABILITY OF TECHNICAL SUPPORT CENTER VENTILATION SYSTEM DUE TO SCHEDULED MAINTENANCE

"At 0115 EDT on Wednesday, July 3, 2013, the Cook Nuclear Plant (CNP) Technical Support Center (TSC) air conditioning and charcoal filtration systems will be removed from service for scheduled maintenance.

"Under certain accident conditions the TSC may become unavailable due to the inability of the air conditioning and charcoal filtration systems to maintain a habitable atmosphere. Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary.

"TSC ventilation system maintenance and post maintenance testing is scheduled to be completed by 2100 EDT on July 3, 2013.

"The licensee has notified the NRC Resident Inspector.

"This notification is being made in accordance with 10CFR50.72(b)(3)(xiii) due to the loss of an emergency response facility."

* * * UPDATE FROM CHRIS PEAK TO JOHN SHOEMAKER ON 7/3/13 AT 1540 EDT * * *

"The TSC ventilation system maintenance and testing was completed satisfactorily and the system was restored to service at 1430 EDT on 7/3/13.

"The licensee has notified the NRC Resident Inspector."

Notified R3DO (Kunowski)

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Power Reactor Event Number: 49171
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: MICHAEL MCCARTHY
HQ OPS Officer: PETE SNYDER
Notification Date: 07/03/2013
Notification Time: 10:46 [ET]
Event Date: 07/03/2013
Event Time: 07:41 [EDT]
Last Update Date: 07/03/2013
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
Person (Organization):
JAMES NOGGLE (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 100 Power Operation 0 Hot Standby

Event Text

REACTOR TRIP FOLLOWING LOSS OF INSTRUMENT AIR TO MAIN FEEDWATER REGULATING VALVES

"On July 3, 2013, at 0741 EST, the Indian Point Unit 2 CCR received a trip of both Main Boiler Feed Pumps (MBFP) and entered 2-AOPFW-1, Loss of Feedwater. The unit was manually tripped at 0741 per 2-AOP-FW1 due to the trip of both MBFPs. Operators entered E-O, Reactor Trip or Safety Injection.

"All control rods fully inserted. All safety systems responded as expected. The Auxiliary Feedwater (AFW) System actuated as expected. Offsite power and plant electrical lineups are normal. No primary or secondary code safety valves lifted. The 23 and 24 Main Steam Isolation Valves (MSIV) failed closed as a result of the loss of Instrument Air (IA). The 21 and 22 MSIVs remain open with the Main Condensers being used for heat sink. The reactor is in Mode 3 and stable. Unit 3 was unaffected and remains at 100% power.

"Preliminary investigations determined a two inch copper IA line in the switchyard which is normally buried had a failed coupling causing loss of IA to the main feedwater regulating valves. The IA line traversed an excavated area of the switchyard going to the Auxiliary Boiler Feed Pump (ABFP)
Building. AFW operated using the Nitrogen backup supply to ABFP control valves until Instrument Air was restored to the ABFP building. An investigation is in progress."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 49172
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MIKE WEISE
HQ OPS Officer: PETE SNYDER
Notification Date: 07/03/2013
Notification Time: 11:37 [ET]
Event Date: 07/03/2013
Event Time: 09:59 [EDT]
Last Update Date: 07/03/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAMES NOGGLE (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation

Event Text

STACK RADIATION MONITOR PRE-PLANNED MAINTENANCE

Millstone Unit 2 has removed the High Range Stack Radiation Monitor, RM-8168 from service for pre-planned maintenance. The radiation monitor will be restored to service after maintenance is complete.

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 49173
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAN STERMER
HQ OPS Officer: VINCE KLCO
Notification Date: 07/03/2013
Notification Time: 12:51 [ET]
Event Date: 07/03/2013
Event Time: [PDT]
Last Update Date: 07/03/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
VINCENT GADDY (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 48 Power Operation 73 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

LOSS OF EMERGENCY RESPONSE COMMUNICATIONS DUE TO A LOSS OF ANCILLARY POWER

"At 0156 PDT on July 3, 2013, Diablo Canyon Power Plant experienced a loss of power to ancillary facilities on site. This affected power supplies to data systems used by the Emergency Response Facilities [EOF]. All plant status and performance data in the TSC [Technical Support Center] and EOF is available via telephone bridge line and control room phone talker.

"Additionally, the Emergency Response Data System (ERDS) has been determined to be unavailable.

"The data system loss occurred following depletion of backup batteries in the affected data center."

The licensee notified the NRC Resident Inspector and will notify state and local agencies.

* * * UPDATE FROM DAN STERMER TO JOHN SHOEMAKER AT 1948 EDT ON 7/3/13 * * *

"At 2120 PDT on 6/23/13, Diablo Canyon Power Plant (DCPP) experienced a loss of the offsite 230 kV startup power source due to an offsite transmission system relay actuation (see EN# 49143). At 1000 PDT on 7/3/13, PG&E identified that the conditions present on 7/3/13 that resulted in loss of plant status and performance data in the Technical Support Center (TSC) and Emergency Operations Facility (EOF) (see EN# 49173) also existed on 6/23/13. This update reports the 6/23/13 loss of plant status and performance data in the TSC and EOF due to loss of power in the data center that supports those facilities. All plant status and performance data required for emergency assessment and communication remained available via a telephone bridge line and control room phone talker. The data became unavailable in the TSC and EOF following depletion of backup batteries in the affected data center.

"On 7/3/13 PG&E reconfigured the TSC workstations to ensure they would function and provide data for emergency assessment capability independent of the status of the data center power supplies.

"The Emergency Response Data System was also unavailable following the loss of 230 kV startup power on 6/23/13 due to loss of power to the data center. This unavailability was as designed and as expected.

"This delayed event notification has been entered into the DCPP corrective action program."

The licensee has notified the NRC Resident Inspector. Notified the R4DO (Gaddy) and ERDS Group via email.

Page Last Reviewed/Updated Friday, July 05, 2013
Friday, July 05, 2013