United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for December 20, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/19/2013 - 12/20/2013

** EVENT NUMBERS **


49623 49652 49661 49662 49663 49664 49665

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Agreement State Event Number: 49623
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: WILCO NDT
Region: 4
City: FARMINGTON State: NM
County:
License #: IR470-05
Agreement: Y
Docket:
NRC Notified By: IRENE CASARES
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 12/11/2013
Notification Time: 15:32 [ET]
Event Date: 12/10/2013
Event Time: [MST]
Last Update Date: 12/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GREG WERNER (R4DO)
BRIAN HOLIAN (FSME)
FSME EVENTS RESOURCE (EMAI)
ELIOT BRENNER (HQPA)

Event Text

AGREEMENT STATE REPORT - POTENTIAL OVEREXPOSURE TO RADIOGRAPHER AND MEMBER OF THE PUBLIC

The following information was obtained from the State of Texas via email:

"The owner of J-CAP manufacturing [located in Seminole, TX] reported at 14:10 CST [on 12/11/13] that an incident [involving industrial radiography of a pressure vessel occurred at his facility on December 10, 2013]. Individual reported that his site foreman was working with the industrial radiographer who was performing radiography of a pressure vessel. The radiographer approached the source collimator to change the film and the radiographer realized the source was still in the open - exposed position. The amount of exposure is still in question and the site foreman was escorted by his employer to the hospital for evaluation. The employee reported he was in the area for 5- 8 minutes and approximately 12-24 inches from the source. The employee was not working for the industrial radiography company, thus this is an exposure to the public. The radiographer also received a dose. The Radiation Safety Officer for Wilco NDT [licensed in Farmington, NM] was contacted by the Agency [Texas Department of State Health Services] to verify the incident. RSO for Wilco NDT reported that he contacted the State of New Mexico to report the incident and is currently working on sending [the radiographer's] monitoring badge to be read. RSO is still trying to contact his radiographer and review details of the incident. A calculated dose for the time period of 8 minutes with a distance of 1 foot from the Ir-192 source with 67 curies of activity was 40 rem/8 minutes. Investigation is ongoing and further details will be supplied as in accordance with SA300."

Texas Incident #: I-9142

* * * UPDATE FROM IRENE CASARES (VIA EMAIL) TO HOWIE CROUCH AT 1758 EST ON 12/13/13 * * *

"On December 13, 2013, at 1632 hours [CST], the licensee notified the Agency [that] their dosimetry processor had completed reading the radiographers' badges. One badge read 34 millirem DDE, and the other 30 millirem, DDE.

"Two Agency inspectors are scheduled to interview all parties involved in the event [on] Tuesday, December 17, 2013.

"Additional information will be provided as it is received in accordance with SA-300."

Notified R4DO (Werner) and FSME EO (Holian).

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Power Reactor Event Number: 49652
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: KEITH MAESTAS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 12/18/2013
Notification Time: 13:01 [ET]
Event Date: 12/18/2013
Event Time: 13:00 [EST]
Last Update Date: 12/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
SCOTT FREEMAN (R2DO)

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

Event Text

TECHNICAL SUPPORT CENTER INOPERABLE FOR PLANNED MAINTENANCE

"NRC Operations Center notification for planned routine preventative maintenance on the Technical Support Center HVAC. Expected start of the preventative maintenance is 12/18/13 at 1300 EST. Planned completion is 12/19/13 at 0100 EST. This maintenance renders the TSC non-functional. The planned TSC alternate location will be the Control Room."

The licensee notified the NRC Resident Inspector.

* * * UPDATE ON 12/19/13 AT 1621 EST FROM NICHOLAS DESANTIS TO DONG PARK * * *

At 1405 EDT, maintenance was completed, and the TSC was declared functional. The licensee will notify the NRC Resident Inspector.

Notified R2DO (Freeman).

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Power Reactor Event Number: 49661
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: GREG KNUDSON
HQ OPS Officer: DONALD NORWOOD
Notification Date: 12/19/2013
Notification Time: 12:58 [ET]
Event Date: 12/19/2013
Event Time: 08:38 [PST]
Last Update Date: 12/20/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RYAN LANTZ (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

BOTH DIVISIONS OF PRIMARY CONTAINMENT OXYGEN AND HYDROGEN ATMOSPHERIC MONITORS INOPERABLE FOR MAINTENANCE

"This notification is being made due to a loss of emergency assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii). At 0838 PST on 12/19/2013, the Division 1 sample rack for monitoring primary containment oxygen and hydrogen atmospheric concentrations was removed from service for planned maintenance activities. The Division 1 sample rack is expected to be out of service for 14 hours. The redundant Division 2 sample rack was previously removed from service for maintenance and remains out of service for repairs. Compensatory measures to monitor primary containment for hydrogen and oxygen are available via grab samples using chemistry procedures.

"The NRC Resident Inspector has been notified."

* * * UPDATE FROM QUOC VO TO VINCE KLCO AT 0130 EST ON 12/20/13 * * *

"Following completion of surveillance activities, the Division 1 sample rack for monitoring primary containment oxygen and hydrogen atmospheric concentrations was returned to operable status at 2114 PST on 12/19/2013, restoring its required emergency assessment capability.

"The NRC Resident Inspector has been notified."

Notified the R4DO (Lantz).

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Power Reactor Event Number: 49662
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: TIM MILLER
HQ OPS Officer: DONALD NORWOOD
Notification Date: 12/19/2013
Notification Time: 16:04 [ET]
Event Date: 12/19/2013
Event Time: 13:20 [EST]
Last Update Date: 12/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
SCOTT FREEMAN (R2DO)

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

UNANALYZED CONDITION AFFECTING UNIT 2 EMERGENCY DIESEL GENERATORS

"At 1320 ET on December 19, 2013, Florida Power and Light identified that atmospheric conditions that had sustained high winds exceeding approximately 50 miles per hour from the ENE direction could result in inadequate heat removal to support continuous operation of the Unit 2 emergency diesel generators. Upon identification of this condition, an adverse condition monitoring plan was issued requiring implementation of compensatory measures to assure adequate emergency diesel generator cooling to support continuous operation of the U2 emergency diesel generators, should weather forecasts identify conditions that would likely result in this condition.

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

"The NRC Resident Inspector has been notified of this condition."

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Power Reactor Event Number: 49663
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RUSSELL CRUZEN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 12/19/2013
Notification Time: 16:21 [ET]
Event Date: 12/19/2013
Event Time: 07:52 [PST]
Last Update Date: 12/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RYAN LANTZ (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

TWO OF THREE EMERGENCEY DIESEL GENERATORS INOPERABLE AT THE SAME TIME

"On 12/19/13 Unit 1 Emergency Diesel Generator (EDG) 1-2 was inoperable for scheduled maintenance.

"During an operational walk-down of the Unit 1 EDG 1-3, the associated fuel oil priming pump discharge fitting and pump housing were inadvertently damaged.

"Pacific Gas and Electric Company declared EDG 1-3 inoperable on 12/19/13 at 0752 PST.

"Since both Unit 1 EDGs were inoperable at the same time, this condition is reportable in accordance with 10 CFR 50.72(b)(3)(ii)(B) and 10 CFR 50.72(b)(3)(v)(D).

"The NRC Senior Resident Inspector has been notified."

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Part 21 Event Number: 49664
Rep Org: FISHER CONTROLS INTERNATIONAL, LLC
Licensee: FISHER CONTROLS INTERNATIONAL, LLC
Region: 3
City: MARSHALLTOWN State: IA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DENNIS SWANSON
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/19/2013
Notification Time: 16:42 [ET]
Event Date: 12/17/2013
Event Time: [CST]
Last Update Date: 12/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
SCOTT FREEMAN (R2DO)
RYAN LANTZ (R4DO)
PART 21 GROUP (EMAI)
KENNETH RIEMER (R3DO)

Event Text

PART 21 - FISHER TYPE 377 TRIP VALVES NOT PROCESSED AS REQUIRED

"Fisher Information Notice: FIN 2013-05

"Purpose: The purpose of this Fisher Information Notice (FIN) is to alert Dominion Virginia Power, Omaha Public Power District and Florida Power and Light that as of 17 December 2013, Fisher Controls International LLC ('Fisher') became aware of the possibility of a situation which may affect the performance of the applicable equipment. Fisher is informing you of this circumstance in accordance with Section 21.21 (b) of 10CFR Part 21.

"Applicability: This notice applies only to the subject equipment supplied by Fisher, identified in the above referenced orders.

"Discussion: The Type 377 Trip Valve assembly was subjected to the processing requirements of Fisher Controls FMP2K27 (Control of Commercial Grade Items to be Dedicated for Use in Nuclear Safety-Related Applications) and was supplied as a safety related component. However, for the above referenced orders, Fisher supplied various other parts, in addition to the Type 377 Trip Valve, that were not processed as required by the requirements of 2K27; thus, such parts were supplied as commercial items.

"Action Required: Each recipient needs to: (i) evaluate the situation for each application of the Type 377 Trip Valve; (ii) determine what portions of the Trip Valve system are 'essential to function'; and (iii) determine what commercial parts may be installed in the Type 377 Trip systems in their respective plants.

"10CFR21 Implications: Fisher requests that the recipient of this notice review it and take appropriate action in accordance with 10CFR Part 21.

"If there are any technical questions or concerns, please contact:

"George Baitinger
Manager, Quality
Fisher Controls International LLC
205 South Center Street
Marshalltown, La 50158
Fax: (641) 754-2854
Phone: (641) 754-2026
George.Baitinger@Emerson.com"

North Anna, Surry, Fort Calhoun, and St. Lucie plants are affected by this Fisher Information Notice.

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Power Reactor Event Number: 49665
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: MICHAEL MOORE
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/19/2013
Notification Time: 19:18 [ET]
Event Date: 12/19/2013
Event Time: 15:11 [EST]
Last Update Date: 12/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
ANTHONY DIMITRIADIS (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

LOSS OF REACTOR BUILDING VENTILATION

"At 1511 [EST] on December 19, 2013, bus 10A404 (D channel 4 kv 1E vital bus) deenergized while transferring infeed breakers after degraded voltage testing. Reactor building ventilation fans tripped resulting in a loss of secondary containment negative pressure. Filtration Recirculation and Ventilation System (FRVS) was manually started and secondary containment negative pressure was restored at 1525 [EST].

"Secondary containment pressure is stable with differential pressure negative.

"The technical specification requirement is to maintain secondary containment at a negative pressure for secondary containment integrity. Declaring secondary containment inoperable is reportable under 10CFR50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material.

"The standby reactor building ventilation fans did not automatically start and [the reason for that] is being investigated."

The licensee notified the NRC Resident Inspector and will notify the Lower Alloways Creek township.

Page Last Reviewed/Updated Friday, December 20, 2013
Friday, December 20, 2013