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Event Notification Report for November 06, 2013

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
11/05/2013 - 11/06/2013

EVENT NUMBERS
4950749508495094951050021

!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 49507
Facility: PRAIRIE ISLAND
Region: 3     State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: STEVE INGALLS
HQ OPS Officer: PETE SNYDER
Notification Date: 11/06/2013
Notification Time: 03:26 [ET]
Event Date: 11/06/2013
Event Time: 00:58 [CST]
Last Update Date: 12/02/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CHRISTINE LIPA (R3DO)
Power Reactor Unit Info
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 N 0 Defueled 0 Defueled
Event Text
R-21 CIRCULATING WATER DISCHARGE RADIATION MONITOR PLANNED OUTAGE

"When transferring power supplies to a non-safety related cooling tower bus for planned outage maintenance, R-21, the Circulating Water Discharge Radiation Monitor was removed from service at 0058 [CST] and returned to service at 0111 [CST]. There is no installed backup for R-21 which has an emergency response function to provide indication of gaseous liquid effluent release to the environment. This monitor has no compensatory measure that will allow timely classification of two NUE (Notification of Unusual Event) and Alert classifications when out of service. This resulted in a loss of emergency assessment capability while R-21 was out of service.

"There are no radioactive leaks that impact the Circulating Water System.

"The licensee notified the NRC Resident Inspector."

* * * RETRACTION AT 1155 EST ON 12/2/13 FROM WAYNE EPPEN TO DANIEL MILLS * * *

"Based on further reviews of plant drawings and discussion with the Radiation Monitor System Engineer, R-21 was not inoperable when power supplies were transferred to the non-safety related Cooling Tower Bus. While R-21 was logged out of service during the transfer on November 6, 2013, it did not lose power and was not out of service. R-21 did not lose the ability to provide continuous monitoring of discharge canal effluent or monitoring in the event of an unplanned radiological release. Our defense in depth strategies are relied upon to take actions to protect the health and safety of the public.

"The licensee has notified the NRC Resident Inspector."

Notified the R3DO (Duncan).


Agreement State
Event Number: 49508
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: S&ME - GREENSBORO OFFICE
Region: 1
City: GREENSBORO   State: NC
County:
License #: 0922-3
Agreement: Y
Docket:
NRC Notified By: CHRIS FIDALGO
HQ OPS Officer: PETE SNYDER
Notification Date: 11/06/2013
Notification Time: 11:08 [ET]
Event Date: 11/06/2013
Event Time: 08:30 [EST]
Last Update Date: 11/06/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
JAMES NOGGLE (R1DO)
FSME EVENTS RESOURCE (EMAI)
Event Text
AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE

The following Agreement State Report was received via facsimile:

"The licensee contacted [the NC Radiation Protection] agency at approximately 0930 EST with the following info: A dump truck at a construction site ran over an lnstroTek Model 3500 Xplorer moisture density gauge. The area of the accident was cordoned off and the licensee RSO [was sent to] report back to agency with survey readings and leak test results. The gauge sources contain 11 mCi of Cs-137 and 44 mCi of Am-241/Be.

"A survey by the licensee [RSO] showed a maximum reading of 0.5 mrem/hr. The instrument make/model was of the survey meter was not specified. Sources appear to be intact. The gauge and debris were returned to the gauge case (doubles as shipping container- DOT 7A Yellow II). The gauge will be shipped to lnstroTek corporation for repair or disposition."

NC State Report Number: ICD 13-20


Power Reactor
Event Number: 49509
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: JOHN SHOEMAKER
Notification Date: 11/06/2013
Notification Time: 16:48 [ET]
Event Date: 11/06/2013
Event Time: 10:28 [EST]
Last Update Date: 11/06/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAMES NOGGLE (R1DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 98 Power Operation 98 Power Operation
Event Text
STACK RADIATION MONITORS REMOVED FROM SERVICE FOR PREPLANNED MAINTENANCE

"The Millstone Station stack radiation monitor, RM-8169, was removed from service for preplanned maintenance at 1028 [EST] and returned to service at 1513 [EST].

"The Unit 2 high range stack radiation monitor, RM-8168, was removed from service for preplanned maintenance at 1543 [EST] and will be removed from service for approximately 3 days."

The licensee has notified the NRC Resident Inspector and applicable state and local authorities.


Power Reactor
Event Number: 49510
Facility: OYSTER CREEK
Region: 1     State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: JEREMY SHARKEY
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 11/06/2013
Notification Time: 22:12 [ET]
Event Date: 11/06/2013
Event Time: 08:00 [EST]
Last Update Date: 11/06/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
JAMES NOGGLE (R1DO)
Power Reactor Unit Info
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
PROHIBITED ITEM FOUND IN THE PROTECTED AREA

"On November 6, 2013, at approximately 0800 hours [EST], a 40 oz. beer bottle containing what was believed to be 20 oz. of alcohol (beer) was discovered in the vicinity of the dilution plant trash raking system inside the protected area. The bottle was discovered during a routine tour and the finding was immediately reported to supervision. Based on the location of the bottle, the weathered condition of the bottle, and interviews with maintenance personnel who observed the bottle falling from the trash rake, it is known that the source of the bottle was the intake canal. The bottle was retrieved during automated raking evolutions and fell from the trash rake while the rake was in-transit to the dumpster. This report is submitted pursuant to 10 CFR 26.719 (b)(1) based on the presence of alcohol in the protected area."

The licensee has notified the NRC Resident Inspector.


Power Reactor
Event Number: 50021
Facility: PALO VERDE
Region: 4     State: AZ
Unit: [1] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DAVID HECKMAN
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/10/2014
Notification Time: 13:52 [ET]
Event Date: 11/06/2013
Event Time: 13:07 [MST]
Last Update Date: 04/10/2014
Emergency Class: UNUSUAL EVENT
10 CFR Section:
Person (Organization):
JAMES DRAKE (R4DO)
SAMSON LEE (NRR)
JEFFERY GRANT (IRD)
Power Reactor Unit Info
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
DISCOVERY OF AFTER-THE-FACT EMERGENCY CONDITION - UNUSUAL EVENT DUE TO EXPLOSION

"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 10 CFR 50.73.

"This notification describes a previously undeclared event that is now reported pursuant to the requirements of 10 CFR 50.72(a)(3). No emergency situation exists at this time.

"On November 6, 2013, while operating at 100% reactor power under steady state conditions, a U-1 control room alarm was received indicating low fluid pressure in the Train 'A' hydraulic accumulator of Main Steam system isolation valve MSIV-170. A plant operator was dispatched according to the alarm response procedure to perform a pre-charge check of the accumulator. A pre-charge check returns hydraulic fluid from the accumulator to a vented tank that serves as a fluid reservoir. During this operation the fluid reservoir tank and supporting piping were damaged by the rapid expansion of nitrogen gas that had entered the hydraulic system by way of a leak across an accumulator piston O-ring. As a result of the damage and loss of hydraulic fluid, MSIV-170 and its associated hydraulic accumulators were declared inoperable at 1307 Mountain Standard Time. It was determined at that time that the failure of the fluid reservoir due to rapid expansion did not constitute an explosion and a declaration of an Unusual Event was not made according to Emergency Action Level (EAL) HU2, 'Fire within the Protected Area not extinguished within 15 minutes of detection or explosion within the Protected Area.'

"Subsequent review has determined that the reservoir failure should have been characterized as an explosion within the Protected Area and that a declaration of an Unusual Event should have been made per EAL HU2.

"The NRC Resident Inspector has been notified."

The licensee has notified the State of Arizona and Maricopa County.