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Event Notification Report for March 18, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/15/2013 - 03/18/2013

** EVENT NUMBERS **


48795 48813 48823 48824

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 48795
Facility: HATCH
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JAMES ANDERSON
HQ OPS Officer: PETE SNYDER
Notification Date: 02/28/2013
Notification Time: 17:13 [ET]
Event Date: 02/28/2013
Event Time: 11:55 [EST]
Last Update Date: 03/15/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
RANDY MUSSER (R2DO)

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

Event Text

CLOSED COOLING WATER ISOLATION VALVE FAILS LOCAL LEAK RATE TEST

"On February 28, 2013, at 1155 EST, with the unit in Refueling Mode, a determination was made that reactor building closed cooling water (RBCCW) isolation valve (2P42-F051) exceeded its acceptance criteria for designed leakage when performing local leak rate testing. Diagnostic testing confirmed that all the leakage from its test boundary is going through this valve with an 'as found' leakage of >200,000 sccm at 32.87 psig. This valve is the outboard isolation barrier for that affected primary containment penetration with the inboard barrier being the RBCCW system itself as a 'closed' system.

"Previous practice is to conservatively include any leakage through this valve when performing as found leak rate tests as part of the primary containment leakage summary or as part of 0.6La. This is considered conservative since the RBCCW system inside containment is assumed to remain intact following a design basis accident (DBA) loss of coolant accident (LOCA). If the closed system remains intact there is no path for leakage to exit primary containment through this system.

"Since the past practice is to include the 'as found' leakage through this valve as part of 0.6La and since the 'as found' leakage would result in exceeding La, this condition is being considered a condition that results in the principal safety barriers being seriously degraded. This leakage would represent a loss of the containment function since the leak rate exceeded the Technical Specification limiting condition for operation (LCO) for primary containment. Further investigation is underway to determine if leakage through this single containment barrier is required to be included in the Appendix J primary containment leakage summary, since it is associated with a closed system."

The licensee notified the NRC Resident Inspector.

* * * RETRACTION ON 3/15/13 AT 1607 EDT FROM KENNY HUNTER TO DONG PARK * * *

"Further investigation revealed an Appendix J exemption that was granted for the Hatch Unit 2 local leak rate test (LLRT) program in the 1978 time frame that specifically addressed the primary containment penetration that has primary containment isolation valve (PCIV) 2P42-F051 as its outboard barrier and the 'closed' system as its inboard barrier. The exemption recognizes that this system is designed to be intact and water filled post-LOCA, allows testing of the of the PCIV with water and states that the leakage through this PCIV is not included in the 0.6 La total.

"Since the Hatch RBCCW system supplying components inside primary containment is a 'closed' system and remains intact and water filled post-LOCA, there is no leakage path from primary containment through this RBCCW penetration. Since no leakage from primary containment can occur through this penetration in its 'as found' state, this condition does not represent a condition that seriously degrades a principal safety barrier. As such this condition has been determined to no longer meet reporting requirement 10CFR50.72(b)(3) and is therefore not reportable. Based on this information the previous notification is being retracted."

The licensee notified the NRC Resident Inspector. Notified R2DO (O'Donohue).

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Agreement State Event Number: 48813
Rep Org: NJ DEQ RADIOACTIVE MATERIALS PRGM
Licensee: UNIVERSITY OF MEDICINE AND DENTISTRY
Region: 1
City: NEWARK State: NJ
County:
License #: NJ PI ID #450
Agreement: Y
Docket:
NRC Notified By: RICHARD PEROS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/08/2013
Notification Time: 12:54 [ET]
Event Date: 03/07/2013
Event Time: [EST]
Last Update Date: 03/08/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
BLAKE WELLING (R1DO)
FSME RESOURCES ()

Event Text

AGREEMENT STATE REPORT - MEDICAL UNDERDOSE DUE TO EQUIPMENT FAILURE

"A patient was treated with a Varian GammaMed plus iX HDR unit on March 7, 2013. The prescription dose was 700 cGy per fraction for 2 fractions, with a prescription dose of 800 cGy for a third fraction. The first two fractions were delivered to the patient as planned, the first fraction on February 26, 2013 and the second on February 28, 2013. The third fraction was to be delivered via tandem and ovoid. The planned tandem dose of 613 cGy was successfully delivered, and the source returned to its shielded position. However, prior to delivery of the ovoid dose of 187 cGy, the HDR unit displayed an error message of 'Electronics Defective error.'

"The staff could not correct the error. The manufacturer was notified and a service technician arrived later in the day to correct the problem. The remaining portion of the fraction was cancelled for the day and re-scheduled. The fractionated dose delivered differed from the prescribed fraction by 23.37%.

"The Varian service technician arrived later in the day and replaced the unit's indexer board, cleaned the indexer belt, tested a spring for tightness and re-set the wheel on the belt. The unit then functioned properly."


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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Power Reactor Event Number: 48823
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TIM TAYLOR
HQ OPS Officer: VINCE KLCO
Notification Date: 03/15/2013
Notification Time: 01:48 [ET]
Event Date: 03/14/2013
Event Time: 18:00 [CDT]
Last Update Date: 03/15/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
KATHLEEN O'DONOHUE (R2DO)

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 23 Power Operation 23 Power Operation
3 N Y 100 Power Operation 100 Power Operation

Event Text

PARTIAL LOSS OF OFFSITE COMMUNICATIONS

"On 03/14/2013 at 1800 CDT, Browns Ferry Nuclear Plant experienced a partial loss of offsite communication to include the Emergency Notification System to the NRC and normal phone communication to offsite. This loss of communications appears to be the result of an unplanned degraded voltage condition on the 48VDC Telephone Battery supplying power to the communications network. Main Control Room indications and assessment capability were not affected. The Nextel cellular phone system, the satellite phones in the Control Rooms, and the Health Physics Radio Network were available onsite to communicate offsite. The plant radio system was also unaffected. Required corrective maintenance is being evaluated. Communication capability is being periodically restored during maintenance troubleshooting, but has not yet been permanently corrected. Operation of Unit 1, Unit 2, and Unit 3 was not affected by the event.

"At 2145 CDT, the NRC Operations Center was notified of alternate contact numbers for [Browns Ferry] until the Telephone Battery is fully restored.

"The NRC Senior Resident Inspector has been notified.

"This event is reportable under 10CFR50.72(b)(3)(xiii)."

* * * UPDATE FROM CHRISTMAN TO KLCO ON 3/15/13 AT 0330EDT * * *

A spare battery charger was aligned to the 48 VDC Telephone Battery and offsite communications was restored.

The licensee notified the NRC Resident Inspector. Notified the R2DO (O'Donohue).

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Power Reactor Event Number: 48824
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK ARNOSKY
HQ OPS Officer: DONG HWA PARK
Notification Date: 03/15/2013
Notification Time: 17:23 [ET]
Event Date: 02/21/2013
Event Time: 10:12 [EDT]
Last Update Date: 03/15/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
GLENN DENTEL (R1DO)
PART 21 RX GROUP (EMAI)

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

PART 21 REPORT - INITIAL NOTIFICATION FOR FLOWSERVE MODEL 28KXL PUMP IMPELLER DEFECT

"This Part 21 initial notification addresses a pump impeller defect that resulted in a post maintenance test (PMT) failure. The 0C RHR Service Water Pump was being replaced due to degraded performance which caused an In-Service Test (IST) failure. The replacement pump impeller received from the supplier had not been machined to the purchase order specifications. The IST of the new pump could not be completed since the required test conditions could not be established. The pump was later replaced and the IST was completed successfully. The pump was declared operable on March 2, 2013.

"This Part 21 Initial Notification is being submitted pursuant to the requirements of 10CFR21.21 (d)(3)(i)."

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Monday, March 18, 2013
Monday, March 18, 2013