United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for June 13, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/12/2013 - 06/13/2013

** EVENT NUMBERS **


48585 48940 49089 49090 49106 49108 49109

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Part 21 Event Number: 48585
Rep Org: GE HITACHI NUCLEAR ENERGY
Licensee: GE HITACHI NUCLEAR ENERGY
Region: 1
City: WILMINGTON State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DALE E. PORTER
HQ OPS Officer: STEVE SANDIN
Notification Date: 12/13/2012
Notification Time: 08:41 [ET]
Event Date: 12/13/2012
Event Time: [EST]
Last Update Date: 06/12/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
DANIEL HOLODY (R1DO)
ALAN BLAMEY (R2DO)
JAMNES CAMERON (R3DO)
MARK HAIRE (R4DO)
NRR PART 21 (EMAI)

Event Text

60-DAY INTERIM REPORT INVOLVING AN EVALUATION OF A DESIGN CHANGE TO MAGNE-BLAST CIRCUIT BREAKERS

The following information was received via fax:

"Summary

"GE Hitachi Nuclear Energy (GEH) is investigating the adequacy of a Design Change in AM 4.16-350-2C and AM 4.16-350-2H Magne-Blast Circuit Breakers as a result of a breaker failure at a BWR Licensee.

"GEH has not completed the evaluation of this condition to determine reportability under 10 CFR Part 21 and is therefore issuing this 60-day Interim Notification. GEH will close or issue an update on this matter on or before June 14, 2013. Given the early status of the evaluation, GEH has no recommended actions at this time. This 60-day Interim Notification is issued in accordance with 10 CFR Part 21.21(a)(2), and will be sent to all GE BWR/2-6 plants and all PWRs.

"Recommendation

"GEH advises licensees to take no action at this time. However, if licensees wish to determine if the extent of this issue is present at their respective plants, they may identify breaker models AM 4.16-350-2H/2C with a date of manufacture prior to October 6, 1971. Other AM breaker styles do not use the booster cylinder as designed in breaker model AM 4.16-350-2H/2C and are not included in this concern. Therefore the extent is limited to the AM 4.16-350-2H/2C models manufactured prior to October 6, 1971.

"US Plants Potentially Affected

"Nine Mile Point 1-2, Fermi 2, Columbia, Grand Gulf, River Bend, FitzPatrick, Pilgrim, Vermont Yankee, Clinton, Dresden 2-3, LaSalle 1-2, Limerick 1-2, Oyster Creek, Peach Bottom 2-3, Quad Cities 1-2, Perry 1, Duane Arnold, Cooper, Susquehanna 1-2, Brunswick 1-2, Hope Creek, Hatch 1 - 2, Browns Ferry 1-3, Monticello, Callaway, Palo Verde 1-3 , Calvert Cliffs 1-2, Ginna, Arkansas Nuclear One 1-2, Indian Point 2-3, Millstone 2, Millstone 3, North Anna 1-2, Palisades, Surry 1-2, Waterford 3, Catawba 1-2, Oconee 1-3, McGuire 1-2, Braidwood 1-2, Exelon Byron 1-2 , Three Mi le Island 1, Beaver Valley 1-2, Davis-Besse, Seabrook, St. Lucie 1-2, Turkey Point 3-4, Point Beach 1-2, DC Cook 1-2, Prairie Island 1-2, Fort Calhoun, Diablo Canyon 1-2, Crystal River 3, Robinson, Shearon Harris, Salem 1, Salem 2, Summer, South Texas Project 1-2, San Onofre 2-3, Farley 1-2, Vogtle 1-2, Sequoyah 1-2, Watts Bar 1, Comanche Peak 1-2, and Wolf Creek.

"If you have an questions, please call me at (910) 819-4491.

Dale E. Porter
Safety Evaluation Program Manager
GE-Hitachi Nuclear Energy Americas LLC"

Hitachi Reference Number: MFN-128 R0

* * * RETRACTION FROM DALE PORTER TO NESTOR MAKRIS ON 6/12/13 AT 0959 EDT * * *

The following information was received via fax:

"[GE Hitachi Nuclear Energy] GEH has completed all testing and evaluations and has determined that the condition previously described in MFN 12-128 R0 is not a reportable condition under 10 CFR Part 21. This information will be sent to all GE BWR/2-6 plants and all PWRs that were previously notified under the 10CFR21.21(a)(2) communication."

Notified R1DO (Dentel), R2DO (Ehrhardt), R3DO (Lara), R4DO (Gepford), and Part 21 Group via email.

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 48940
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: LEE KELLY
HQ OPS Officer: VINCE KLCO
Notification Date: 04/17/2013
Notification Time: 23:19 [ET]
Event Date: 04/17/2013
Event Time: 16:00 [EDT]
Last Update Date: 06/12/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
STEVEN VIAS (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Defueled 0 Defueled

Event Text

DEGRADED CONDITION DUE TO SUSPECTED VALVE BODY LEAKAGE

"On April 17, 2013 at 1600 [EDT], while performing a valve inspection/repair of the Unit 2 'A' Reactor Coolant Loop Fill Valve (2- RC-HCV-2556A), the as-found inspection results identified evidence of a suspected flaw causing leakage from the valve body to the threads of a stud housing of the valve. This valve is a 2 [inch] 316 SS [Stainless Steel] cast ASME XI (Class 1) 1500 psi valve body of a globe style design. Due to this design and the installed orientation, the RCS pressure medium fills the upper portion of the valve bonnet where the leak is located during normal plant operations. Therefore, this leakage would be considered pressure boundary leakage. 2-RC-HCV-2556A is currently isolated from the Reactor Vessel and is at atmospheric pressure.

"This inspection was performed in response to dry discolored boric acid identified during the normal operating pressure boric acid accumulation inspection procedure during the Spring 2013 Unit 2 refueling outage shutdown. An engineering evaluation of the suspected defect will be performed and corrective actions implemented.

"This event is reportable in accordance to 10CFR50.72(b)(3)(ii)(A) for, 'Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded'."

The licensee notified the NRC Resident Inspector and local County Commissioners.

* * * RETRACTION FROM BOB PAGE TO CHARLES TEAL ON 6/12/13 AT 1109 EDT * * *

"Event Number 48940 was made on April 17, 2013 in accordance with 10CFR50.72(b)(3)(ii)(A) to document a suspected flaw resulting in RCS pressure boundary leakage on Unit 2 'A' Reactor Coolant Loop Fill Valve (2-RC-HCV-2556A). North Anna Power Station is retracting this notification following completion of a cause analysis and metallurgical examination. The analysis determined that the valve leakage was due to the body-to-bonnet gasket joint. The original valve body was especially susceptible to gasket creep, which lead to a loss of sufficient sealing stress. This resulted in body-to-bonnet leakage, not a through-wall leak. Based on this analysis, the reporting requirements of 10CFR50.72(b)(3)(ii)(A) are not met and this event report is being retracted.

"The licensee has notified the NRC Resident Inspector."

Notified R2DO (Ehrhardt).

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Agreement State Event Number: 49089
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: THE METHODIST HOSPITAL
Region: 4
City:  State: TX
County: HOUSTON
License #: 00457
Agreement: Y
Docket:
NRC Notified By: CHRIS MOORE
HQ OPS Officer: CHARLES TEAL
Notification Date: 06/04/2013
Notification Time: 13:33 [ET]
Event Date: 06/03/2013
Event Time: [CDT]
Last Update Date: 06/04/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
BLAIR SPITZBERG (R4DO)
FSME EVENT RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - SOURCE RETRACTION FAILURE

The following was received from the State of Texas via email:

"On June 3, 2013, the Agency [State of Texas] was notified by the licensee that on June 3, 2013, a medical event had occurred. The licensee reported a source retraction failure with a Novoste Beta-Cath intravascular brachytherapy system containing a 45.1 mCi strontium - 90 source. When the treatment was completed, upon source retraction, the source got stuck in another area of the blood vessel roughly 5 cm away from the treatment site for 1 minute.

"The unintended absorbed dose to that area of the vessel is in the range of 5-6 Gy. The source open in air time was roughly 3 seconds from being retracted from the patient before being secured in a bail out box. Personnel exposure issues or concerns are not expected, however, dosimeters will be assessed. A technical representative was notified and during the next several days will inspect the system and assist in packaging the system for return shipment back to the manufacturer. Additional information will be provided as it is received in accordance with SA-300."

Texas Incident #: I-9088

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

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Agreement State Event Number: 49090
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: IRISNDT MATRIX CORP.
Region: 4
City: DEER PARK State: TX
County:
License #: 06435
Agreement: Y
Docket:
NRC Notified By: CHRIS MOORE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/05/2013
Notification Time: 11:19 [ET]
Event Date: 06/04/2013
Event Time: [CDT]
Last Update Date: 06/05/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
BLAIR SPITZBERG (R4DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - UNABLE TO RETRACT RADIOGRAPHY SOURCE

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

"On June 5, 2013, the licensee's Radiation Safety Officer (RSO) reported to the Agency [Texas Department of Health] that on June 4, 2013, one of its radiography crews had been unable to retract the Iridium-192 source back into the SPEC 150 camera they were using in a fixed bay. The disconnect occurred after the first shot. The RSO was notified and he and two other employees performed the source retrieval. Readings from the pocket dosimeters were: RSO - 21.3 mrem; other employees performing source retrieval received 53.9 and 26.9 mrem. No member of the public received any exposure from this event. Cause of the event unknown at this time. Further information will be provided as it is obtained, per SA-300.

"Radiography Camera: Spec 150, SN: 407
"Source: Iridium-192, SN: UE2912"

Texas Event Number: I-9089

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Power Reactor Event Number: 49106
Facility: FARLEY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: WILLIAM ARENS
HQ OPS Officer: CHARLES TEAL
Notification Date: 06/12/2013
Notification Time: 01:33 [ET]
Event Date: 06/11/2013
Event Time: 21:05 [CDT]
Last Update Date: 06/12/2013
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
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
FRANK EHRHARDT (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Standby

Event Text

UNIT 1 AUTOMATIC REACTOR TRIP DUE TO THE LOSS OF A START-UP TRANSFORMER

"This is a report of an automatic RPS actuation and automatic ESF actuation per 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A). Additionally, this is to report intentions for a press release per 10CFR50.72(b)(2)(xi).

"At 2105 CDT on 6/11/13, Farley Unit 1 experienced an automatic reactor trip from 100% power. The initiating event was the loss of the 1B Start up Transformer which resulted in de-energization of the B-Train ESF 4KV buses and the 1B and 1C Reactor Coolant Pump Buses. The 1B Emergency Diesel Generator auto started and tied to the B-Train 4KV Emergency buses.

"Both MDAFW (Motor Driven Auxiliary Feedwater) Pumps and the TDAFW (Turbine Driven Auxiliary Feedwater) Pump auto-started and are supplying AFW flow to the steam generators. Decay heat removal is via the steam dumps to the main condenser.

"The cause of the loss of the 1B Start-up Transformer is unknown and is currently under investigation. All other systems functioned as expected in response to the loss of the 1B Start-up Transformer and reactor trip.

"The NRC Senior Resident Inspector has been notified.

"A press release is planned."

All control rods fully inserted. There is no impact on Unit 2. Currently the licensee does not plan to restart the 1B and 1C Reactor Coolant Pumps. Pressurizer spray has been isolated from the 1B loop per procedure. Main Condenser vacuum is adequate for decay heat removal.

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Power Reactor Event Number: 49108
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JAMES PRIEST
HQ OPS Officer: PETE SNYDER
Notification Date: 06/12/2013
Notification Time: 16:59 [ET]
Event Date: 06/12/2013
Event Time: 13:33 [EDT]
Last Update Date: 06/12/2013
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):
GLENN DENTEL (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 100 Power Operation 0 Hot Shutdown

Event Text

CIRCULATING WATER PUMP TRIP LEADS TO REACTOR SCRAM

"This is a report of a manual RPS actuation and manual RCIC actuation per 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A).

"At 1332 [EDT], on 6/12/13, the 'B' Circulating Water Pump tripped with a stuck open discharge valve resulting in a vacuum transient. Operators lowered reactor power from 100% in an effort to stabilize condenser vacuum. When vacuum reached 6.5 inches, the operators inserted a manual reactor scram at 1333 [EDT]. All control rods inserted as required. No automatic ECCS or RCIC initiations occurred. No primary or secondary containment isolations occurred. The plant is stable in OP CON 3 HOT SHUTDOWN with the condensate pumps in service. The Reactor Recirculation Pumps are in service.

"At the time of the event, a RCIC surveillance was in progress, but did not contribute to the event. The RCIC pump was secured and subsequently placed in service for inventory control. The only safety-related equipment out of service at the time of the scram was the C Service Water Pump, which was tagged for scheduled maintenance.

"No personnel injuries occurred. No radiation releases occurred. The NRC Resident Inspector has been informed."

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Power Reactor Event Number: 49109
Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: MICHAEL PLETCHER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/12/2013
Notification Time: 21:36 [ET]
Event Date: 06/12/2013
Event Time: 16:38 [EDT]
Last Update Date: 06/12/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GLENN DENTEL (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

TONE ALERT SYSTEM FAILURE

"Vermont Yankee Control Room was notified by E-Plan personnel at 1638 [EDT] that the tone test initiated by the National Weather Service from Albany, NY, failed to activate tone alert radios via the Ames Hill NOAA transmitter and would be out for greater than one hour. At 1712 [EDT] the tone alert radios were functionally tested from the backup transmitter link (WTSA Radio Studio) satisfactorily verifying the ability to activate tone alert radios is available."

The licensee suspects a phone service change was not sufficiently tested.

The licensee notified the NRC Resident Inspector.

Page Last Reviewed/Updated Thursday, June 13, 2013
Thursday, June 13, 2013