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Event Notification Report for December 7, 2015

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/04/2015 - 12/07/2015

** EVENT NUMBERS **


51569 51584 51585 51586 51587 51588

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Agreement State Event Number: 51569
Rep Org: UTAH DIVISION OF RADIATION CONTROL
Licensee: QUALITY TESTING AND INSPECTION
Region: 4
City: LINDON State: UT
County:
License #: UT 2500269
Agreement: Y
Docket:
NRC Notified By: MIKE GIVENS
HQ OPS Officer: JEFF ROTTON
Notification Date: 11/27/2015
Notification Time: 19:33 [ET]
Event Date: 11/26/2015
Event Time: 21:00 [MST]
Last Update Date: 11/27/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MARK HAIRE (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHY CAMERA SOURCE UNABLE TO BE FULLY RETRACTED

The following information was provided by the State of Utah via email:

"At approximately 2100 MST on November 26, 2015, two radiographers, working for QTI [Quality Testing and Inspection], were completing radiography operations [at a job site in Provo, UT for Dragon Manufacturing]. When the exposure was completed, the source was withdrawn to the camera but was not fully retracted into the shielded position when the locking mechanism was engaged. The radiographers could not move the source or cable. The source was secured, personnel exited the affected area and the radiographers notified the Radiation Safety Officer (RSO). Temporary lead shielding was placed over the affected camera. Licensee personnel waited in low dose areas until the RSO arrived at the site. Licensee personnel maintained visual control of the affected area.

"After performing radiation surveys of the camera, the RSO withdrew and inserted the source into the source changer. The RSO locked the source inside the source changer and transported the radiography equipment to the Licensee's facility.

"The source changer, camera and associated cables were removed from service and transported to the licensee shop. Radiation exposures (from self-reading dosimetry) to the licensee personnel were approximately 10 mRem. The RSO's dosimeters indicated an exposure of approximately 40 mRem. More information will be provided in coming days."

The licensee notified the State of Utah at 1200 MST on 11/27/2015.

The camera was a model IR 100, serial number -4122, which contained a 93 curie Ir-192 source, serial number - Z825.

UT Event Report ID No.: UT 150006

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Power Reactor Event Number: 51584
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: SAMANTHA BALDWIN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/04/2015
Notification Time: 01:33 [ET]
Event Date: 12/03/2015
Event Time: 21:07 [EST]
Last Update Date: 12/04/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
WILLIAM COOK (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

EXCESSIVE CONTROL ROOM IN-LEAKAGE IDENTIFIED

"On December 3, 2015 at 2107 [EST], the Control Room Emergency Ventilation System (CREVS) was declared inoperable due to a higher than allowed identified in-leakage rate for the Control Room Envelope (CRE) when in the Normal Operating Mode. Both Unit 1 & Unit 2 remain at 100 percent power and they share a common CRE.

"At the time of discovery, there is a reasonable expectation this condition could prevent the fulfillment of the safety function of a system that is required to mitigate the consequences of an accident, thus satisfying the reporting criteria for 10CFR50.72(b)(3)(v)(D).

"Actions to implement mitigating actions were immediately initiated in accordance with Technical Specification 3.7.10. CREVS has been placed in Recirculation Ventilation Mode, isolating the control room from outside air.

"The NRC Senior Resident Inspector has been notified of the condition."

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Power Reactor Event Number: 51585
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: TRACEY STEWART
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 12/04/2015
Notification Time: 18:06 [ET]
Event Date: 12/04/2015
Event Time: 14:00 [EST]
Last Update Date: 12/04/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
OMAR LOPEZ (R2DO)

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

Event Text

OFFSITE NOTIFICATION DUE TO SANITARY LIFT STATION OVERFLOW

"Off-site Notification to South Carolina Department of Health and Environmental Control (SCDHEC).

"At approximately 1400 [EST] on 12/4/15, site personnel discovered a sanitary lift station overflowing in the owner controlled area. The overflow entered a nearby storm drain that discharges into Outfall 13. The estimated release volume is between 10-15 gallons. The release has been stopped. At 1448, an initial notification was made to SCDHEC. The overflow appears to be the result of securing electrical power to the general area, including the lift station, to support construction activities. Power has been restored and clean-up is in progress.

"The NRC Senior Resident has been notified."

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Power Reactor Event Number: 51586
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: CHEE YUN
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 12/05/2015
Notification Time: 18:48 [ET]
Event Date: 12/05/2015
Event Time: 17:31 [EST]
Last Update Date: 12/05/2015
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):
WILLIAM COOK (R1DO)
SCOTT MORRIS (NRR)
BERNARD STAPLETON (IRD)

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

MANUAL REACTOR TRIP INITIATED DUE TO MULTIPLE DROPPED CONTROL RODS

"At 1731 [EST] on December 5, 2015, Indian Point Unit 2 Control Room operators initiated a Manual Reactor Trip due to indications of multiple dropped Control Rods. The initiating event was a smoldering Motor Control Center (MCC) cubicle in the Turbine Building that supplies power to the Rod Control System. The unit is stable in Mode 3 with heat sink provided by Auxiliary Feedwater and decay heat removal is via the steam dumps to the condenser. Offsite Power remains in service.

"The smoldering MCC cubicle had power removed from it when 24 MCC breaker tripped on overcurrent. The affected cubicle has ceased smoldering and is being monitored by on-site Fire Brigade trained personnel. The trip of 24 MCC removed power to 22 Battery Charger, 22 DC Bus remained powered from the 22 Battery without interruption, and 22 Battery Charger was subsequently repowered."

The cause of the smoldering MCC is being investigated and a post reactor trip evaluation is being conducted by the licensee. There was no impact on Unit 3, which continues to operate at 100% power.

The licensee has notified the NRC Resident Inspector and appropriate State and Local authorities.

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Power Reactor Event Number: 51587
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JASON WILLIS
HQ OPS Officer: DANIEL MILLS
Notification Date: 12/06/2015
Notification Time: 05:28 [ET]
Event Date: 12/06/2015
Event Time: 03:50 [EST]
Last Update Date: 12/06/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
WILLIAM COOK (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

LOSS OF SECONDARY CONTAINMENT DIFFERENTIAL PRESSURE DUE TO ICING OF INTAKE SUPPLY PLENUM SCREENS

"On December 06, 2015 at 0350 [EST], Reactor Building Zone 1 Secondary Containment differential pressure lowered to less than 0.25 inch Water Column (WC) [degrading vacuum] when the intake supply plenum screens were found to be iced over. This required a TS 3.6.4.1 entry for failure to meet SR 3.6.4.1.1 on Unit 1 and Unit 2.

"Snow melt heaters were manually started to melt the ice allowing restoration of Reactor Building Zone 1 Secondary Containment differential pressure to greater than 0.25 inch WC at 0434 on December 06, 2015.

"This event is being reported under 10 CFR 50.72 (b)(3)(c) 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.

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Power Reactor Event Number: 51588
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DARVIN DUTTRY
HQ OPS Officer: STEVEN VITTO
Notification Date: 12/06/2015
Notification Time: 09:58 [ET]
Event Date: 12/06/2015
Event Time: 05:46 [EST]
Last Update Date: 12/06/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
WILLIAM COOK (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

LOSS OF SECONDARY CONTAINMENT DIFFERENTIAL PRESSURE DUE TO EXHAUST FAN TRIP

"On December 06, 2015 at 0546 [EST], Reactor Building Zone 1 Secondary Containment differential pressure lowered to less than 0.25 inch Water Column (WC) [degrading vacuum] when the running Reactor Building Zone 1 exhaust fan tripped. This required a TS 3.6.4.1 entry for failure to meet SR 3.6.4.1.1 on Unit 1 and Unit 2.

"The standby fan automatically started, restoring of Reactor Building Zone 1 Secondary Containment differential pressure to greater than -0.25 inch WC. Field operators confirmed proper system response at 0553 [EST] December 06, 2015.

"This event is being reported under 10 CFR 50.72(b)(3)(v)(c) and per the guidance of NUREG 1022 Rev 3 section 3.2.7 as a loss of a Safety Function. "

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Monday, December 07, 2015
Monday, December 07, 2015