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Event Notification Report for October 31, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/30/2013 - 10/31/2013

** EVENT NUMBERS **


49466 49470 49480 49486 49487 49489

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Agreement State Event Number: 49466
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: ACUREN INSPECTION INC.
Region: 4
City: LA PORTE State: TX
County:
License #: 01774
Agreement: Y
Docket:
NRC Notified By: CHRIS MOORE
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/23/2013
Notification Time: 12:20 [ET]
Event Date: 10/23/2013
Event Time: [CDT]
Last Update Date: 10/23/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
WAYNE WALKER (R4DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - FAILURE OF RADIOGRAPHY CAMERA SOURCE TO FULLY RETRACT

The following report was received from the Texas Department of State Health Services, Radiation Branch, via e-mail:

"On October 23, 2013, the licensee notified the Agency [Texas Department of Health] that one of its radiography crews had been unable to retract an iridium-192 source back into a QSA 880D exposure device at a temporary work site in Baytown, Texas. Following an exposure, the source pigtail would not retract fully into the device. An authorized person, the Radiation Safety Officer (RSO), performed the source retrieval. He received an estimated 600 millirem dose. No member of the public received any exposure as a result of this event. The RSO reported that he had to disconnect the crank handle from the drive cables to pull the source back into the camera. The cause was an equipment failure of the drive cable which was binding. A new set of drive cables was attached to the camera and the source moved in and out freely about 10 times. The drive cables were only 3 weeks old. They will be returned to the manufacturer for inspection. An investigation into this event is ongoing. Information will be provided as it is obtained in accordance with SA-300.

"Camera and source information: QSA 880D camera, serial number D4621, source model number 424-9, source serial number 98960B."

Texas Incident Number: I-9130

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Agreement State Event Number: 49470
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: LARRY M. JACOBS AND ASSOCIATES, INC.
Region: 1
City: PENSACOLA State: FL
County:
License #: 1508-1
Agreement: Y
Docket:
NRC Notified By: JOHN WILLIAMSON
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/23/2013
Notification Time: 21:18 [ET]
Event Date: 10/23/2013
Event Time: [EDT]
Last Update Date: 10/23/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DANIEL HOLODY (R1DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - DAMAGED SOIL MOISTURE DENSITY GAUGE

The following report was received from the Florida Department of Health, Bureau of Radiation Control, via e-mail:

"A soil moisture density gauge was damaged by heavy construction equipment. The source was reported to be retracted and not exposed. The electronics panel and housing was reported to be damaged. A Bureau of Radiation Control Inspector is en route.

"The incident occurred at a temporary work site in Walnut Hill, Florida. The gauge contained a 10 mCi Cesium 137 source and a 50 mCi Americium241/Beryllium source."

The State of Florida Bureau of Radiation Control will update the report as more information is known.

Verbal information from the State indicated that the licensee could not verify the integrity of the source because the company does not have access to a radiation detector.

Florida Incident Number: FL13-074

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Power Reactor Event Number: 49480
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: CHRIS WEICHLER
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/29/2013
Notification Time: 05:01 [ET]
Event Date: 10/29/2013
Event Time: 05:00 [EDT]
Last Update Date: 10/30/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
PAUL KROHN (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
3 N Y 100 Power Operation 100 Power Operation

Event Text

MAIN STACK RADIATION MONITORS REMOVED FROM SERVICE

"At 0500 [EDT] Tuesday, October 29, the Peach Bottom Atomic Power Station (PBAPS) main stack radiation monitors will be removed from service for planned preventative maintenance activities on the flow elements. This maintenance is scheduled to be worked continuously until completion to minimize out of service time. The planned main stack radiation monitor outage is scheduled to be completed within 13 hours. Periodic gas sampling will be performed in accordance with the offsite dose calculation manual while the monitors are out of service.

"The NRC Resident Inspector has been notified.

"There are no follow-up written reports required for this event."

* * * UPDATE ON 10/30/13 AT 0216 EDT FROM BOB RAUCCI TO DONG PARK * * *

"This is an update to notification #49480. The out of service duration has been extended from the original estimated 13 hours due to work scope taking longer than expected with fatigue rule compliance requirements. The radiation monitor maintenance has been completed and the components have been restored to service, however, the post maintenance testing will be delayed until this morning (10/30/13) when the necessary component expert resource is next available. Periodic gas sampling remains in effect in accordance with the Off Site Dose Calculation Manual."

The licensee will notify the NRC Resident Inspector.

Notified R1DO (Krohn).

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Power Reactor Event Number: 49486
Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: BRIAN HASSELBRING
HQ OPS Officer: HOWIE CROUCH
Notification Date: 10/30/2013
Notification Time: 16:43 [ET]
Event Date: 10/30/2013
Event Time: 11:17 [CDT]
Last Update Date: 10/30/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
JAMES DRAKE (R4DO)

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

POSTULATED FIRE EVENT THAT COULD ADVERSELY IMPACT SAFE SHUTDOWN EQUIPMENT

"A review of industry operating experience regarding the impact of unfused Direct Current (DC) ammeter circuits in the control room has determined the described condition to be applicable to the Cooper Nuclear Station resulting in a potentially unanalyzed condition with respect to 10 CFR 50 Appendix R analysis requirements. The original plant wiring design and associated analysis for the Class 1E batteries control room ampere indications do not include overcurrent protection features to limit the fault current.

"In the postulated event, a fire could cause one of the ammeter wires to short to ground. Simultaneously, it is postulated that the fire causes another DC wire from the opposite polarity on the same battery to also short to ground. This could cause a ground loop through the unprotected ammeter wiring. This event could result in excessive current flow (i.e., heating) in the ammeter wiring to the point of causing a secondary fire in the raceway system. The secondary fire 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 being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B). Interim compensatory measures (i.e.., fire watches) have been implemented for affected areas of the plant.

"The licensee has notified the NRC Resident Inspector."

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Power Reactor Event Number: 49487
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: TODD PERKINS
HQ OPS Officer: PETE SNYDER
Notification Date: 10/30/2013
Notification Time: 16:44 [ET]
Event Date: 10/30/2013
Event Time: 15:25 [EDT]
Last Update Date: 10/30/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
PAUL KROHN (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

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

"A review of industry operating experience regarding the impact of unfused Direct Current (DC) ammeter circuits in the control room has determined the described condition to be applicable to Millstone Power Station Unit 2 resulting in an unanalyzed condition with respect to 10 CFR 50 Appendix R analysis requirements. The original plant wiring design and associated analysis for the Class 1E batteries control room ampere indications do not include overcurrent protection features to limit the fault current.

"In the postulated event, a fire in the control room could cause one of the ammeter wires to short to the ground plane. Simultaneously, it is postulated that the fire causes another DC wire from the opposite polarity on the same battery to also short to the ground plane. This could cause a ground loop through the unprotected ammeter wiring. This event could result in excessive current flow (i.e., heating) in the ammeter wiring to the point of causing a secondary fire in the raceway system. The secondary fire 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.

"Interim compensatory measures (i.e., fire watches) have been implemented for affected areas of the plant.

"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(B)."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 49489
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARTIN LICHTNER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/31/2013
Notification Time: 05:00 [ET]
Event Date: 10/31/2013
Event Time: 02:51 [EDT]
Last Update Date: 10/31/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
PAUL KROHN (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

SECONDARY CONTAINMENT DIFFERENTIAL PRESSURE NOT WITHIN LIMITS FOLLOWING TRIP OF EXHAUST FAN

"On October 31, 2013 at 0251, Secondary Containment Zone I (Unit 1 Reactor Building) differential pressure was lost following a routine transfer of Reactor Protection System Power supplies. Upon restoration from the power supply transfer, one of the Reactor Building Equipment Compartment Exhaust Fans tripped. There were no obvious malfunctions associated with the equipment and fan was able to be restarted. Zone II (Unit 2 Reactor Building) and III (Common Refuel Floor Area) ventilation remained in service and stable.

"Zone I differential pressure recovered within a few minutes and was verified to be stable. LCO 3.6.4.1 was entered for both units at 0251 and exited at 0255. Tech Spec Secondary Containment Operability requires a negative pressure of at least 0.25 inches water gauge.

"There have been no further perturbations in differential pressure and secondary containment remains operable.

"This event is being reported under 10 CFR 50.72(b)(3)(v) and per the guidance of NUREG 1022 Rev 3 section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment System."

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Thursday, October 31, 2013
Thursday, October 31, 2013