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Event Notification Report for March 12, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/11/2014 - 03/12/2014

** EVENT NUMBERS **


49890 49891 49893 49894 49895 49898

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Power Reactor Event Number: 49890
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JOHN PANAGOTOPULOS
HQ OPS Officer: JEFF ROTTON
Notification Date: 03/11/2014
Notification Time: 03:38 [ET]
Event Date: 03/11/2014
Event Time: 03:00 [EDT]
Last Update Date: 03/11/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MARC FERDAS (R1DO)

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

Event Text

TECHNICAL SUPPORT CENTER VENTILATION REMOVED FROM SERVICE FOR PLANNED MAINTENANCE

"On March 11, 2014 at 0300 [EDT], the Hope Creek Technical Support Center (TSC) ventilation system was removed from service to perform planned maintenance. The removal of the ventilation potentially affects the TSC habitability during a declared emergency requiring activation. Appropriate compensatory measures are in place while the ventilation is out of service. The Emergency Response organization duty team has been notified of the maintenance and the possible need to activate the TSC in an alternate location. The ventilation system is scheduled to be out of service for approximately 78 hours."

The licensee will be notifying the NRC Resident Inspector and the Lower Alloways Creek Township.

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Power Reactor Event Number: 49891
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: WAYNE HARRELSON
HQ OPS Officer: JEFF ROTTON
Notification Date: 03/11/2014
Notification Time: 08:32 [ET]
Event Date: 03/11/2014
Event Time: 07:00 [EDT]
Last Update Date: 03/11/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MARC FERDAS (R1DO)

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

Event Text

NORMAL VENTILATION PROCESS RADIATION MONITOR OUT OF SERVICE FOR PLANNED MAINTENANCE

Normal ventilation - normal and high range process radiation monitor, 3HVR*RE10A/B, has been removed from service for planned maintenance. The maintenance window is scheduled for 7 hours.

The licensee notified the NRC Resident Inspector, the State of Connecticut Department of Environmental Protection, and Local police dispatch.

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Power Reactor Event Number: 49893
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: GERALD BAKER
HQ OPS Officer: CHARLES TEAL
Notification Date: 03/11/2014
Notification Time: 11:49 [ET]
Event Date: 03/11/2014
Event Time: 09:31 [EDT]
Last Update Date: 03/11/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MARC FERDAS (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

MILLSTONE STATION STACK RADMONITOR OUT-OF-SERVICE FOR PRE-PLANNED MAINTENANCE

At 0931 EDT on 3/11/14, the Millstone Station Stack Radmonitor RM-8168 was removed from service for pre-planned maintenance. This resulted in a loss of assessment capability and is being reported under 10 CFR 50.72 (b)(3)(xiii).

The licensee informed State/local agencies and the NRC Resident Inspector.

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Power Reactor Event Number: 49894
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: JEFFERY SEITER
HQ OPS Officer: CHARLES TEAL
Notification Date: 03/11/2014
Notification Time: 11:57 [ET]
Event Date: 03/11/2014
Event Time: 06:00 [CDT]
Last Update Date: 03/11/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
THOMAS FARNHOLTZ (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

NOTIFICATION TO STATE OF MISSISSIPPI IN RESPONSE TO CONTAMINATED SPILLS/LEAKS PROCEDURE

"This is a 4-hour notification to report a Notification to the State of Mississippi is being made in accordance with the Response to Contaminated Spills/Leaks procedure.

"A surface contamination event has occurred at the Grand Gulf Nuclear Station that meets the State reporting criteria of 'An unmonitored and inadvertent contaminated leak or spill greater than 15 cubic feet-solid to the environment occurs.'

"The source of the contamination is not known at this time, investigation to determine the source and extent of the event is in progress. The known contamination has been contained. Actions include sampling of storm drains to verify no unmonitored release outside the protected area, additional radiation protection monitoring of the area, removal of the contaminated liquid and soil, and covering of the affected ground. Installation of tenting over the area is in progress. There was no effect on plant operation. No one was injured during the event."

The licensee has notified the NRC Resident Inspector, State, and local governments.

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Part 21 Event Number: 49895
Rep Org: ASCO VALVE INCORPORATED
Licensee: ASCO VALVE INCORPORATED
Region: 1
City: AIKEN State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BOB ARNONE
HQ OPS Officer: CHARLES TEAL
Notification Date: 03/11/2014
Notification Time: 13:00 [ET]
Event Date: 03/11/2014
Event Time: [EDT]
Last Update Date: 03/11/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
PART 21 GROUP (EMAI)

Event Text

PART 21 - SCRAM SOLENOID PILOT VALVE NOT EXHAUSTING PROPERLY

The following was excerpted from a fax received from ASCO Valve, Inc.:

"Problem Description

"GE Hitachi Nuclear Energy (GEH) customer Energy Northwest reported that an ASCO scram solenoid pilot valve (SSPV) Catalog number HVL266000010J 115/60, GE-H part number 107E6022P014, serial number A272718-054, CRD-SPV-118/1043 did not exhaust properly. The valve had been installed in Energy Northwest's Columbia facility for approximately 7 months and had been cycled 60-70 times. Energy Northwest's internal investigation revealed the pilot head assembly spring was not in the groove of the associated core.

"Conclusion

"Various tests were performed to rule out possible manufacturing non-conformances in the spring or core. The successful completion of these tests has established that when the spring is properly installed on the core, the spring will not come off in service. We have not yet identified any other conditions that could cause the spring to come off the core, except for improper assembly.

"This configuration of spring and core design was used on the original 090405 scram valve. There has not been any design change to this core assembly since its inception in 1959. This spring/core assembly makes up the bulk of ASCO core solenoid offering. It is used across all of ASCO valve ranges in the Commercial, Nuclear, Military, and Petrochemical markets. ASCO has supplied over 10 million valves to these markets over the entire product offering. This Includes over 50,000 Nuclear Qualified Valves. With the exception of the 1994 and 2012 events, a review of ASCO return records found no other cases of this condition where a spring disengaged from the core.

"Since ASCO does not have adequate knowledge of the actual installations and operating conditions of these valves, it was not able to be determined if this could create a 'Substantial safety hazard' as defined in 10 CFR Part 21. This information is intended to provide interim investigation results.

"If you have any questions, you can contact Bob Arnone at 803-641-9395."

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Power Reactor Event Number: 49898
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: WILLIAM HART
HQ OPS Officer: CHARLES TEAL
Notification Date: 03/11/2014
Notification Time: 18:27 [ET]
Event Date: 03/11/2014
Event Time: 10:01 [PDT]
Last Update Date: 03/11/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
THOMAS FARNHOLTZ (R4DO)

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

POSTULATED HOT SHORT FIRE EVENT THAT COULD ADVERSELY IMPACT SAFE SHUTDOWN EQUIPMENT

"An extent of condition review of all unfused ammeters circuits in Direct Current (DC) distribution systems at Columbia Generating Station (Columbia) identified areas in the plant which may be susceptible to secondary fires due to hot shorts from these unfused ammeters. It is postulated that a fire in one fire area can damage these circuits and cause short circuits without protection that would overheat the cables and possibly result in secondary fires in other fire areas where the cables are routed. The secondary fires could adversely affect safe shutdown equipment and potentially cause the loss of the ability to conduct a safe shutdown as required by 10 CFR 50 Appendix R.

"This condition is reportable as an 8-hour ENS report in accordance with 10 CFR 50.72(b)(3)(ii)(B) as an unanalyzed condition.

"Compensatory measures (fire watches) have been implemented for affected areas of the plant.

"The licensee has notified the NRC Resident Inspector."

Page Last Reviewed/Updated Wednesday, May 14, 2014
Wednesday, May 14, 2014