United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for October 27, 2011

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/26/2011 - 10/27/2011

** EVENT NUMBERS **


47363 47374 47375 47376

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Agreement State Event Number: 47363
Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: PAYNE & DOLAN INC
Region: 3
City: MADISON State: WI
County:
License #: 133-1220-01
Agreement: Y
Docket:
NRC Notified By: MARK PAULSON
HQ OPS Officer: JOE O'HARA
Notification Date: 10/21/2011
Notification Time: 11:13 [ET]
Event Date: 10/21/2011
Event Time: 03:30 [CDT]
Last Update Date: 10/21/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAVID HILLS (R3DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - MOISTURE DENSITY GAUGE STRUCK BY VEHICLE AT CONSTRUCTION SITE

The following was received from the state via fax:

"The on-duty State Response Coordinator (SRC) for the Wisconsin Department of Health Services (DHS) received a phone call at approximately 3:30 am that a moisture density gauge had been struck by a motor vehicle. The incident occurred at a road construction site near 1221 Northport Drive, Madison, WI. The gauge was in use with the operator in contact with it, when a car veered out of traffic into the construction lane. The operator was forced to jump out of the path of the vehicle, leaving the gauge. The vehicle struck the gauge, shattering the housing. The source rod with the Cesium-137 source detached from the housing. The Americium/Beryllium source remained within the housing. The SRC and licensee's RSO responded to the scene to supervise source recovery.

"The Cesium source was leak tested in-situ and determined to be intact. Surveys were performed in the affected area, with no contamination detected. A portion of the housing designed to hold the retracted Cesium source rod was found partially intact. The Cesium source was placed within the cavity and securely taped. The housing assembly was placed in the transport container for transport back to a licensed service provider for assistance with disposal.

"The driver who struck the gauge has yet to be located by the police. The licensee will be submitting a 30 day written report concerning this event."


Event Report ID Number: WI110017

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Power Reactor Event Number: 47374
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: MARK MOEBES
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/25/2011
Notification Time: 23:49 [ET]
Event Date: 10/25/2011
Event Time: 15:34 [CDT]
Last Update Date: 10/26/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
BRIAN BONSER (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 50 Power Operation 50 Power Operation
2 N Y 100 Power Operation 100 Power Operation
3 N Y 100 Power Operation 100 Power Operation

Event Text

DEFICIENCY IDENTIFIED IN TRANSITION TO PERFORMANCE BASED STANDARD FOR FIRE PROTECTION

"At 1534 on 10/25/11 Site Engineering and Licensing reported the following to the Operations Department:

"The following deficiency was identified during reviews for NFPA 805 Transition: Cable 1B11 (#12 awg - Fire Area Route 16, 17) from the shunt in the 250 VDC Battery Board 1 (0-BDDD-280-0001) compartment #1, to the control room ammeter 1-EI-57-38 mounted on Control Room Panel 1-9-8, is not fused or otherwise protected against an electrical fault. The 250 VDC Battery 1 is an un-grounded DC system. However, in a scenario where the 250 VDC Battery Board system negative becomes grounded at the same time the ammeter cable 1B11 has a fault to ground, the cable may not be protected and the cable could auto-ignite anywhere along the cables length from the ground fault location back to the battery source. For example, in a Fire Area 16 (Control Bay) scenario, these ground faults could result in a fire being spread from Fire Area 16 to Fire Area 17 (Battery Board 1). Fuses should be added to protect these cable conductors.

"A similar condition exists for the remote ammeters on Unit Battery Board 2 (Cable 2B11 - Fire Area Route 16, 18), Unit Battery Board 3 (Cable 3B11 - Fire Area Route 16, 19), Unit Battery Board 4 (Cable 2B4018 - Fire Area Route 16, 26), Unit Battery Board 5 (Cable 1B383 - Fire Area Route 16, 26), and Unit Battery Board 6 (Cable 3B336 - Fire Area Route 16, 26).

"This condition is reportable as an 8 hour notification to the NRC IAW 10CFR 50.72(b)(3)(ii)(B), 'Any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.'

"This is also reportable as 60 day written report IAW 10CFR 50.73(a)(2)(ii)(B).

"Fire watch compensatory measures are in place for the Fire Areas of concern. Ref. FPIP#09-1920

"The NRC resident has been notified of this event.

"This event was entered into the licensee's Corrective Action Program as PER# 452185."

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Research Reactor Event Number: 47375
Facility: RHODE ISLAND ATOMIC ENERGY COMM
RX Type: 2000 KW POOL
Comments:
Region: 1
City: NARRANGANSETT State: RI
County: WASHINGTON
License #: R-95
Agreement: Y
Docket: 05000193
NRC Notified By: HANK BICEHOUSE
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/25/2011
Notification Time: 13:07 [ET]
Event Date: 10/25/2011
Event Time: 11:15 [EDT]
Last Update Date: 10/26/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
NON-POWER REACTOR EVENT
Person (Organization):
DUANE HARDESTY (NRR)
BETH REED (NRR)
QUICHOCHO (NRR)
SLOAN (NRR)

Event Text

24 HOUR TECHNICAL SPECIFICATION REQUIRED REPORT BASED ON A POTENTIAL OVER-EXPOSURE EVENT

At approximately 1115 EDT on 10/25/11 an intern entered the dry gamma room at the Rhode Island Nuclear Science Center Facility during an ion probe calibration procedure. The intern received an estimated unplanned dose of between 2-3 rem based on a stay time of 5 minutes in a 500 mr/min field. His dosimetry, an OSL (Optically Stimulated Luminescence) badge, has been sent to Landauer for expedited processing. The dry gamma room is properly posted as a high radiation area with administrative controls in effect to limit access. The assistant Director of the facility is performing an investigation including event reconstruction to determine the cause.

* * * UPDATE FROM JEFF DAVIS (LICENSEE) TO HUFFMAN ON 10/26/11 AT 10:03 EDT * * *

The licensee clarified that the call to the Operations Center made on 10/25/11 was a 24 hour notification required by the facility's Technical Specification 1.25.8 based on the potential for over-exposure.

NRR Backup Project Manager (Hardesty) notified.

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Fuel Cycle Facility Event Number: 47376
Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
                   6903 ROCKLEDGE DRIVE
                   BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: JOE BARLETTO
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/26/2011
Notification Time: 21:24 [ET]
Event Date: 10/26/2011
Event Time: 13:20 [CDT]
Last Update Date: 10/26/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
BRIAN BONSER (R2DO)
DENNIS DAMON (NMSS)

Event Text

24 HOUR REPORT DUE TO DETECTION OF LINEAR DEFECT IN SURGE VOLUME ACCUMULATOR

"At 1320 CDT, on 10-26-11 the Plant Shift Superintendent (PSS) was notified that the C-310 Side Accumulator had a linear defect in the vessel shell that caused a UF6 release on 10-21-2011. The UF6 liquid accumulators serve the product withdrawal system. The side accumulator is a monel tank used in the product withdrawal system to provide a surge volume. The safety function of the side accumulator is to provide UF6 primary system integrity for the withdrawal process that contains a gaseous and liquid UF6. TSR 2.3.5.6 is a design feature that requires the withdrawal area UF6 condensers and accumulator vessels to have a minimum required metal thickness in accordance with ASME requirements to prevent UF6 releases. There are no LCO actions associated with this TSR but there is a 5 year surveillance requirement to perform a visual inspection including thickness measurements. The side accumulator was in service when a small UF6 release occurred on 10-21-2011. The release was contained to the immediate area and the side accumulator was taken out of service for investigation and subsequent repairs.

"This event is reportable as a 24 hour event in accordance with 10CFR 76.120(c)(2)(i). This is an event in which equipment is disabled or fails to function as designed when: a.) the equipment is required by a TSR to prevent releases, prevent exposures to radiation and radioactive materials exceeding specified limits, mitigate the consequences of an accident, or restore this facility to a pre-established safe condition after an accident; b.) the equipment is required by a TSR to be available and operable and either should have been operating or should have operated on demand, and c.) no redundant equipment is available and operable to perform the required safety function.

"The NRC Senior Resident has been notified of this event.

"PGDP Assessment and Tracking Report No. ATR-11-2856; PDGP Event Report No. PAD-2011-19. "

Page Last Reviewed/Updated Thursday, March 29, 2012
Thursday, March 29, 2012