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Event Notification Report for August 16, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/15/2013 - 08/16/2013

** EVENT NUMBERS **


49250 49251 49272 49285 49286 49287

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Agreement State Event Number: 49250
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: AEROJET ORDNANCE TENNESSEE
Region: 1
City: JONESBOROUGH State: TN
County:
License #: S-90009
Agreement: Y
Docket:
NRC Notified By: LAURA TURNER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 08/08/2013
Notification Time: 11:09 [ET]
Event Date: 08/05/2013
Event Time: 10:00 [EDT]
Last Update Date: 08/08/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES TRAPP (R1DO)
FSME EVENT RESOURCES (E-MA)

Event Text

AGREEMENT STATE REPORT - ELEVATED AIRBORNE URANIUM LEVELS DUE TO EQUIPMENT MALFUNCTION

The following report was received from the State of Tennessee Division of Radiological Health via e-mail:

"Tennessee's Division of Radiological Health was notified on Wednesday August 7, 2013 by the RSO from Aerojet Ordnance Tennessee, regarding the failure of a primary ventilation system. On August 5, 2013 at 10:00 AM, an employee at the Deflash Station observed smoke outside the operation booth while grinding burrs off radiography camera castings. A supervisor was notified and investigation showed the ventilation system was working, but the belt connecting the pump and fan was broken. Operations were suspended and personnel evacuated.

"The belt was replaced on the pumps and the ventilation system was up and operational by 10:30 AM. Event resulted in elevated airborne uranium concentrations. All personnel in the building submitted urinalysis. Workers at the Deflash station were wearing respiratory protection during time of event as part of standard procedures. Area air samplers along with environmental air samplers were pulled and analyzed; initial results identified no concerns of elevated concentrations.

"The State will follow-up and keep NRC informed of the status of our investigation."

Tennessee Report Number:TN-13-134

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Agreement State Event Number: 49251
Rep Org: NEW YORK STATE DEPT. OF HEALTH
Licensee: NCM USA BRONX, LLC
Region: 1
City: Bronx State: NY
County:
License #: NYS C5494 & C
Agreement: Y
Docket:
NRC Notified By: ROBERT DANSEREAU
HQ OPS Officer: HOWIE CROUCH
Notification Date: 08/08/2013
Notification Time: 16:06 [ET]
Event Date: 07/15/2013
Event Time: [EDT]
Last Update Date: 08/08/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES TRAPP (R1DO)
FSME EVENTS RESOURCE (EMAI)
PAMELA HENDERSON (FSME)

Event Text

AGREEMENT STATE REPORT - EXTREMITY DOSE EXCEEDS LIMIT

The following information was obtained from the State of New York via facsimile:

"On 08/07/2013, the licensee called to report an overexposure of an individual as measured with an extremity monitoring device (ring badge). The licensee had been notified by the processor on the morning of 08/07/13 in regard to the 242 rem shallow extremity dose. The monitoring period for the ring badge is one week, and the whole body monitors are exchanged on a monthly basis. The affected individual is a male production technologist whose duties include cyclotron operations. The RSO and consulting health physicist are investigating and NYS DOH [New York State Department of Health] will perform an onsite review. The licensee has reassigned the technologist to non-radiological duties, sent the individual's whole body badge via overnight service for an emergency read and has requested the badge vendor to perform any additional analysis of the ring badge that may provide additional information. This event summary will be updated after the results of the licensee's and DOH's investigations are available."

New York Event Number: NY-13-04

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Power Reactor Event Number: 49272
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: NAVEEN KOTEEL
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 08/13/2013
Notification Time: 07:41 [ET]
Event Date: 08/13/2013
Event Time: 02:25 [EDT]
Last Update Date: 08/15/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
SCOTT SHAEFFER (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

TECHNICAL SUPPORT CENTER VENTILATION FAILURE

"A condition is being reported per Technical Requirements Manual 13.13.1 emergency response facilities action B.2. The functionality of the Technical Support Center (TSC) has been lost due to a failure to start of the TSC HVAC unit. Alternate facilities are available to provide emergency response functions and actions are proceeding to return the TSC to functional status with high priority. The NRC Resident Inspector has been notified."

* * * UPDATE FROM NAVEEN KOTEEL TO HOWIE CROUCH AT 0744 EDT ON 8/15/13 * * *

The Technical Support Center HVAC system was returned to service at 1100 EDT on August 14, 2013. The licensee has notified the NRC Resident Inspector.

Notified R2DO (Musser).

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Power Reactor Event Number: 49285
Facility: HATCH
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KENNY HUNTER
HQ OPS Officer: DONG HWA PARK
Notification Date: 08/15/2013
Notification Time: 16:47 [ET]
Event Date: 08/15/2013
Event Time: 16:10 [EDT]
Last Update Date: 08/15/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
RANDY MUSSER (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

A HOT SHORT IN THE RHR SHUTDOWN COOLING CONTROL CABLE COULD RESULT IN AN INTER-SYSTEM LOCA

"A condition was identified that resulted from an inter-cable circuit analysis as part of the safe shutdown analysis that identified a vulnerability associated with two Unit 2 valves with controls in Fire Area 2203. Specifically, during the postulated fire scenario, an inter-cable hot short could occur on the control cables for the RHR shutdown cooling suction valve 2E11-F008 valve and cause the valve to open in the event of a postulated fire in Fire Area 2203F which is in the vicinity of the Unit 2 remote shutdown panel. In addition, a spurious opening of RHR shutdown cooling suction valve 2E11-F009 valve could occur due to a hot short on the control cables. The fire is postulated while in Mode 1 which could cause both valves to open during power operation. This postulated event would expose the low pressure RHR-shutdown cooling suction line to normal operating pressures which would result in an inter-system LOCA.

"Immediate actions were taken to de-energize the valves in the 'closed' position which removed the vulnerability. When this condition was first discovered, the consequences of this postulated condition were evaluated and there was reasonable assurance that the condition did not represent an unanalyzed condition that significantly degrades/degraded plant safety. A review of the FSAR, design documents and regulatory requirements was performed to document the foundational logic for the engineering judgment to support the original conclusion that there was reasonable assurance that the inter-system LOCA did not represent an unanalyzed condition that significantly degraded plant safety and that this would not result in a loss of a safety function. Based on information learned in this review there was not sufficient information to make a conclusive determination. Since a conclusive determination cannot be made at this time and since there is some doubt regarding whether or not the report is needed, this report is being made in accordance with 10CFR50.72(b)(3)(ii)."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 49286
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: KEN LEFFEL
HQ OPS Officer: DONG HWA PARK
Notification Date: 08/15/2013
Notification Time: 17:53 [ET]
Event Date: 08/15/2013
Event Time: 09:15 [CDT]
Last Update Date: 08/15/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JOHN GIESSNER (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 92 Power Operation 92 Power Operation

Event Text

DIESEL GENERATOR DECLARED INOPERABLE DUE TO DAMPER FAILING TO OPEN

"During a run of the Division 3 Diesel Generator room ventilation fan to perform thermograph, it was identified that the damper (1VD01YC) that provides the flow path from the outside area into the ventilation room would not open when the fan was started. This renders the Division 3 Diesel Generator inoperable. High Pressure Core Spray was declared inoperable at 1420 hours [CDT], but remains available. This report is being made pursuant to 10CFR50.72(b)(3)(v)(D) as an event or condition that could have prevented fulfillment of a safety function needed to mitigate the consequences of an accident.

"The cause of the damper failing to open has not yet been determined. Troubleshooting is in progress to determine the cause and actions required to restore operability. The Division 1 and Division 2 Diesel Generators are operable."

The licensee is in a 14-day shutdown TS LCO.

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 49287
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DARRELL JOHNSON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 08/16/2013
Notification Time: 02:36 [ET]
Event Date: 08/15/2013
Event Time: 18:24 [PDT]
Last Update Date: 08/16/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
RAY KELLAR (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

LOSS OF STARTUP POWER RESULTS IN VALID STARTS OF ALL THREE EMERGENCY DIESEL GENERATORS

"At 1824 PDT on August 15, 2013, Unit 1 experienced a loss of startup power due to a failure of Startup Transformer 1-1 load tap changer. This loss caused a valid auto-start signal to all three emergency diesel generators and they all started successfully. At 1921, all EDGs were shutdown and returned to standby per plant procedures."

As a result of the loss of startup power, power was also lost to site service buildings. ERDS was lost but compensatory measures are in place to transmit required data via the ENS line if required.

The plant is in a 72-hr. shutdown LCO action statement under T.S. 3.8.1 for the loss of one of three qualified circuits. The two other qualified circuits (vital power via auxiliary transformers and the EDGs) remain operable.

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Friday, August 16, 2013
Friday, August 16, 2013