Alert

Due to a lapse in appropriations, the NRC has ceased normal operations. However, excepted and exempted activities necessary to maintain critical health and safety functions—as well as essential progress on designated critical activities, including those specified in Executive Order 14300—will continue, consistent with the OMB-Approved NRC Lapse Plan.

Event Notification Report for May 14, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
05/11/2012 - 05/14/2012

** EVENT NUMBERS **

!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Part 21	Event Number: 47735
Rep Org: ENERSYS Licensee: ENERSYS Region: 1 City: READING State: PA County: License #: Agreement: Y Docket: NRC Notified By: WILLIAM ROSS HQ OPS Officer: PETE SNYDER	Notification Date: 03/12/2012 Notification Time: 15:33 [ET] Event Date: 03/12/2012 Event Time: [EDT] Last Update Date: 05/11/2012
Emergency Class: NON EMERGENCY 10 CFR Section: 21.21(a)(2) - INTERIM EVAL OF DEVIATION	Person (Organization): GEORGE HOPPER (R2DO) NRR PART 21 GROUP (EMAI)

Event Text

INTERIM REPORT CONCERNING BATTERY CELLS WITH POTENTIALLY REDUCED DISCHARGE CAPACITY

"This letter will serve as the interim report to the Commission as pursuant to 10CFR21.21 (a) (2). The notification is in regards to a 2GN-23 battery manufactured by EnerSys and installed as part of Station Battery 2-2 at the Dominion Virginia Power, North Anna Station. Battery verification testing performed at North Anna indicated that although the battery was able to meet North Anna's 2 hour discharge requirements, cell #59 appeared to show reduced capacity. As a result, Dominion returned cells #59 and #60 to EnerSys. The cells were received at the EnerSys Corporate Laboratory under Return for Analysis (RFA) ENS-11204.

"During our analysis, which consisted of float charging, discharge testing at the 3 hour rate and an internal inspection it was determined that the cell was unable to meet the defined technical requirements for discharge capacity. Following the determination a series of analytical tests were ordered to perform more in depth analyses of the internal components. Testing on the component samples is currently underway. At this time we have not yet been able to determine if a "defect" as defined in Part 21 exists and therefore this interim report has been prepared. It is expected that the current tests will be completed by May 11, 2012. However, it should be noted that further analysis including the return of additional cells may be required to determine the cause and the reportability under Part 21 reporting."

"Throughout the return and analysis processes EnerSys has been in contact with representatives of the North Anna Station. They have been made aware of the electrical test results and recently of the internal inspection results. They are also aware that there has been no cause determination at this time. Station personnel have also been notified that this interim report has been issued."

* * * RETRACTION FROM WILLIAM ROSS TO HOWIE CROUCH AT 0953 EDT ON 5/11/12 * * *

The following information was received from EnerSys via fax:

"Subsequent to the March 12th letter, analytical testing on the components of the returned cells was completed. The results indicated there were no material composition discrepancies or assembly process anomalies. The only issue seen in cell #59 was that a portion of the positive active material physically separated from the positive grid structure. Additionally, data recorded during the manufacturing process was reviewed with no issues or nonconformities noted.

"A visit to the North Anna site was undertaken by EnerSys Engineering to review information from both Station 1 and Station 2. Battery verification testing at both stations showed all station batteries to have acceptable performance. A comparison of the testing performed by North Anna and the testing performed by EnerSys indicated that there was no further capacity degradation in cell #59. It is expected that the cells in the two station batteries will perform similarly.

"Based upon our further investigation we have concluded that no deviation per 10CFR21.21 exists. The positive active material separation was determined to be to a unique inconsistency in that plate curing lot."

Notified R2DO (Freeman) and NRR Part 21 Group via email.

Agreement State	Event Number: 47899
Rep Org: TEXAS DEPARTMENT OF HEALTH Licensee: RONE ENGINEERING Region: 4 City: DALLAS State: TX County: License #: L02356 Agreement: Y Docket: NRC Notified By: ROBERT FREE HQ OPS Officer: PETE SNYDER	Notification Date: 05/04/2012 Notification Time: 12:44 [ET] Event Date: 05/04/2012 Event Time: [CDT] Last Update Date: 05/04/2012
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE	Person (Organization): GREG WERNER (R4DO) JAMES DANNA (FSME)

Event Text

AGREEMENT STATE REPORT - MOISTURE DENSITY GAUGE DAMAGED AT JOBSITE

The State of Texas supplied the following information via email:

"The RSO for Rone Engineering contacted the Texas Radiation Program by phone on 4 May 2012 at approximately 10:15 AM CDT. The RSO reported a gauge had been damaged when run over by a water truck on a highway construction site in San Antonio. The RSO requested a radiation program inspector to conduct a radiation survey of the device because there was no radiation detection equipment immediately available.

"An inspector was dispatched to the site and reported that the device was severely damaged, but the radioactive sources were still shielded. However, the source rod was broken and radiation levels at the point where it broke were measured to be 86 millirem per hour. The licensee contacted a company licensed to recover and ship radioactive sources. The recovery company packaged the gauge and will return it to the manufacturer.

"The gauge was a Troxler 3430 plus, Serial number 60001. The gauge contained two sources; one 0.696 GBq Cs-137 and one 1.48 GBq Am-241 The Cs-137 source serial number was 77-7272 and the Am-241 source serial number was 78-4445."

Texas Incident #: I - 8951

Power Reactor	Event Number: 47915
Facility: SAINT LUCIE Region: 2 State: FL Unit: [ ] [2] [ ] RX Type: [1] CE,[2] CE NRC Notified By: TIM KUDO HQ OPS Officer: HOWIE CROUCH	Notification Date: 05/11/2012 Notification Time: 07:07 [ET] Event Date: 05/11/2012 Event Time: 03:55 [EDT] Last Update Date: 05/11/2012
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): SCOTT FREEMAN (R2DO)

Unit	SCRAM Code	RX CRIT	Initial PWR	Initial RX Mode	Current PWR	Current RX Mode
2	M/R	Y	99	Power Operation	0	Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO FEEDWATER CONTROL VALVE FAILURE

"On May 11, 2012, a failure of the High Power Feed Regulating Valve FCV-9011 resulted in '2A' S/G water level lowering. Manual operator control of the Main Feed Regulating system was unsuccessful in stabilizing S/G water level. '2A' S/G level lowered to the procedurally required manual reactor trip criteria. The crew inserted a manual trip. All CEAs fully inserted into the core. Following the trip, Auxiliary Feedwater actuated as designed and decay heat removal was via Auxiliary Feedwater and Steam Bypass to the Main Condenser. All equipment operated as expected. Currently, Unit 2 is maintaining pressurizer pressure at 2250 psia, temperature at 532 degrees F on Main Feedwater (using Low Power Feed Regulating Valves LCV-9005/9006) and Steam Bypass Control.

'Unit 1 was unaffected and remains in Mode 1 at 29% power.

"This event is reportable pursuant to 10CFR50.72(b)(2)(iv)(B) for the Reactor Trip, as well as 10CFR50.72(b)(3)(iv)(A) for specified system actuation (Auxiliary Feedwater)."

The licensee has notified the NRC Resident Inspector.

Fuel Cycle Facility	Event Number: 47916
Facility: HONEYWELL INTERNATIONAL, INC. RX Type: URANIUM HEXAFLUORIDE PRODUCTION Comments: UF6 CONVERSION (DRY PROCESS) Region: 2 City: METROPOLIS State: IL County: MASSAC License #: SUB-526 Agreement: Y Docket: 04003392 NRC Notified By: BOB STOKES HQ OPS Officer: JOHN KNOKE	Notification Date: 05/11/2012 Notification Time: 09:21 [ET] Event Date: 05/10/2012 Event Time: 10:20 [CDT] Last Update Date: 05/11/2012
Emergency Class: NON EMERGENCY 10 CFR Section: 40.60(b)(3) - MED TREAT INVOLVING CONTAM	Person (Organization): SCOTT FREEMAN (R2DO) LARRY CAMPBELL (NMSS)

Event Text

UNPLANNED MEDICAL TREATMENT OF WORKER

"On 05/10/12, approximately at 1020 CDT, a person working in the Feed Materials Building injured his foot while drumming off green salt. The employee received first aid treatment in the on-site dispensary. The individual was found to have contamination on his plant coveralls and boots. The employee was decontaminated and transported to an off-site medical facility. The employee was appropriately exit monitored and there was no detectable contamination on the employee when he left the site. Contamination on the employees right boot was 26,664 dpm/100cm2."

The chemical was Uranium Ore Concentrate.

The licensee has notified NRC Region 2 (Richard Gibson).

Power Reactor	Event Number: 47917
Facility: SEABROOK Region: 1 State: NH Unit: [1] [ ] [ ] RX Type: [1] W-4-LP NRC Notified By: ROBERT DUARTE HQ OPS Officer: HOWIE CROUCH	Notification Date: 05/11/2012 Notification Time: 09:20 [ET] Event Date: 05/11/2012 Event Time: 05:15 [EDT] Last Update Date: 05/11/2012
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE	Person (Organization): PAMELA HENDERSON (R1DO)

Unit	SCRAM Code	RX CRIT	Initial PWR	Initial RX Mode	Current PWR	Current RX Mode
1	N	Y	85	Power Operation	85	Power Operation

Event Text

BRIEF LOSS OF THE EMERGENCY NOTIFICATION SYSTEM PHONE

"At approximately 0515 EDT today, Seabrook experienced a brief loss of the Emergency Notification System (ENS). The ENS was inoperable for approximately four minutes due to an unknown cause. During this time, commercial telephone lines were available as a means of communication with the NRC. A subsequent communications check using the ENS phone was satisfactory.

"This event is being reported as an eight-hour notification in accordance with 10CFR50.72(b)(3)(xiii) for a loss of offsite ENS communications capability. Investigation into the cause continues and will be documented via the corrective action process."

The licensee has notified the NRC Resident Inspector.

Power Reactor	Event Number: 47919
Facility: SUSQUEHANNA Region: 1 State: PA Unit: [ ] [2] [ ] RX Type: [1] GE-4,[2] GE-4 NRC Notified By: RON FRY HQ OPS Officer: DONG HWA PARK	Notification Date: 05/11/2012 Notification Time: 21:27 [ET] Event Date: 05/11/2012 Event Time: 16:03 [EDT] Last Update Date: 05/11/2012
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION	Person (Organization): PAMELA HENDERSON (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

LOSS OF CONTROL ROOM FLOOR COOLING

"At 16:03 hours on 5/11/12, Susquehanna Steam Electric Station Unit 2 entered LCO 3.0.3 due to two control room floor cooling systems being inoperable.

"A discharge damper for the 'A' train of control room floor cooling had failed earlier during the same day at 05:23 hours, rendering the associated 'A' fan inoperable. The redundant 'B' train fans and associated Control Structure Chiller automatically started as a result of a fan low flow interlock. The 'A' train logic was left in 'Start' and the 'B' train logic was left in 'Auto' as directed by an alarm response procedure.

"During application of a clearance order for repair of the failed 'A' fan damper, the 'A' control room cooling fan switch was placed in 'Stop' position. This resulted in an automatic start of the 'A' Control Structure Chiller and all the associated 'A' fans except for the control room cooling fan, and a trip of the 'B' train fans and chiller. This condition caused a loss of both control room cooling fans.

"The control room operators immediately recognized the loss of cooling and took manual action to restart the 'B' train.

"LCO 3.0.3 was exited at 16:18 hours without a reactor power reduction. This condition is reportable as loss of entire safety function under 10CFR50.72(b)(3)(v) & (vi)."

The licensee has notified the NRC Resident Inspector.

Power Reactor	Event Number: 47920
Facility: FARLEY Region: 2 State: AL Unit: [1] [2] [ ] RX Type: [1] W-3-LP,[2] W-3-LP NRC Notified By: BLAKE MITCHELL HQ OPS Officer: JOHN KNOKE	Notification Date: 05/13/2012 Notification Time: 01:00 [ET] Event Date: 05/12/2012 Event Time: 20:15 [CDT] Last Update Date: 05/13/2012
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
1	N	Y	100	Power Operation	100	Power Operation
2	N	Y	100	Power Operation	100	Power Operation

Event Text

HVAC FOR TECHNICAL SUPPORT CENTER OUT OF SERVICE

"The facility Technical Support Center (TSC) was rendered non-functional due to the TSC HVAC Air Handling Unit (AHU) ventilation system being out of service. Investigation into the cause of the failure of the TSC ventilation AHU found a tripped supply breaker. The supply breaker was subsequently reset and the TSC HVAC unit placed back in service.

"This report is being generated per TRM bases 13.13.1 condition B for the TSC emergency response facility being out of service for greater than 30 minutes. The total out of service time was 44 minutes."

The licensee has notified the NRC Resident Inspector.

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