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Event Notification Report for September 29, 2016

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
09/28/2016 - 09/29/2016

EVENT NUMBERS
522775227052271522735270853140

Agreement State
Event Number: 52277
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: TOXCO
Region: 1
City: Oak Ridge   State: TN
County:
License #: R-01037
Agreement: Y
Docket:
NRC Notified By: ANDREW HOLCOMB
HQ OPS Officer: BETHANY CECERE
Notification Date: 10/04/2016
Notification Time: 10:58 [ET]
Event Date: 09/29/2016
Event Time: 14:45 [EDT]
Last Update Date: 10/04/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
JON LILLIENDAHL (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
ANGELA MCINTOSH (NMSS)
PATRICIA MILLIGAN (EMAI)
Event Text
AGREEMENT STATE REPORT - UNPLANNED CONTAMINATION EVENT

The following was received by fax from the Tennessee Division of Radiological Health:

"While emptying a 55 gallon drum of lead for reuse into a B-12 box, unknown and unsuspected contamination levels in bottom of drum resulted in a contamination of the area to max levels of 2,000,000 dpm/100 cm2 beta. Contamination levels in drum determined to be 2,000,000 dpm/100 cm2 max post event. Pre job surveys identified no elevated contamination levels in top of drum. Isotope and activity are unknown at this time. Isotope is a weak pure beta emitter. Analysis is underway for isotopic determination. [Three] 3 persons with skin contamination were deconned. Bioassays are underway for internal dose assessment. Area is being recovered, however, not within 24 hours resulting in reporting of event. Dose assessments are forthcoming."

State Event Report ID No.: TN-16-138


Power Reactor
Event Number: 52270
Facility: LIMERICK
Region: 1     State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: BRIAN DEVINE
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/30/2016
Notification Time: 02:11 [ET]
Event Date: 09/29/2016
Event Time: 17:00 [EDT]
Last Update Date: 09/30/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
WILLIAM COOK (R1DO)
Power Reactor Unit Info
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
TSC VENTILATION INDICATION ISSUE IDENTIFIED FOLLOWING SURVEILLANCE TESTING

"On 9/29/2016 at 1700 [EDT] the MCR [Main Control Room] was notified of a potential Technical Support Center [TSC] emergency ventilation indication issue following surveillance testing. At 2350 troubleshooting revealed a blown control power fuse which affected functionality of TSC HVAC emergency mode. The system was restored to operable as of 0043 on 9/30/16.

"If an emergency had been declared and TSC activation was required, the TSC would have been staffed and activated unless the TSC became uninhabitable due to ambient temperatures, radiological or other conditions. The Station Emergency Director would assess habitability in accordance with station procedures. If TSC relocation becomes necessary, then personnel would be directed as required until such time that the TSC emergency ventilation system was returned to service."

The licensee informed the NRC Resident Inspector.


Power Reactor
Event Number: 52271
Facility: ARKANSAS NUCLEAR
Region: 4     State: AR
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: MARK GOHMAN
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/30/2016
Notification Time: 04:01 [ET]
Event Date: 09/29/2016
Event Time: 21:00 [CDT]
Last Update Date: 09/30/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
WILLIAM COOK (R1DO)
CHRIS MILLER (NRR)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling
Event Text
UNISOLABLE LEAK ON DECAY HEAT REMOVAL PIPING DUE TO WELD FAILURE ON A 1" COMMON PIPE

"At 2100 CDT on 09/29/16, while in Mode 6, both trains of Decay Heat (Residual Heat Removal) were declared inoperable due to a cracked weld on a 1" common pipe. The leak developed in a USAS B31.7, Class1 pipe at a weld upstream of pressure indication isolation valve DH-1037. The leak is not isolable from the common 8-inch Decay Heat piping and encompasses approximately 1/3 [one third] of the pipe circumference.

"At the time of discovery, the unit was in Lowered Inventory with both Loops of Decay Heat in service. Subsequently, one train of Decay Heat has been secured to reduce the likelihood of crack propagation. One Train of Decay Heat remains in service providing the function of removing Decay Heat and the other train is readily available. The leakage impacts redundant equipment required to fulfill a safety function. In the current condition, both trains are required to be operable to meet Technical Specification LCO 3.9.5, Decay Heat Removal (DHR) and Coolant Circulation-Low water Level.

"This condition is reportable per 10 CFR 50.72(b)(3)(v)(B) for any event or condition that results in a loss of Safety Function associated with the Decay Heat System (Residual Heat Removal System).

"The licensee has notified the NRC Resident Inspector."

The leak is approximately 0.25 gallons per minute and pipe pressure is 140 psi. Compensatory measures are in place and include an individual posted to watch the pipe in case plugging is necessary. Repairs to the pipe will be completed once pipe is able to be drained.


Power Reactor
Event Number: 52273
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: TODD CHRISTENSEN
HQ OPS Officer: HOWIE CROUCH
Notification Date: 09/30/2016
Notification Time: 16:19 [ET]
Event Date: 09/29/2016
Event Time: 19:00 [CDT]
Last Update Date: 10/03/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
BINOY DESAI (R2DO)
FITNESS FOR DUTY GRO (EMAI)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 81 Power Operation 81 Power Operation
2 N Y 100 Power Operation 100 Power Operation
3 N Y 100 Power Operation 100 Power Operation
Event Text
FITNESS FOR DUTY REPORT - LICENSED OPERATOR CONFIRMED POSITIVE FOR ALCOHOL

A licensed operator had a confirmed positive for alcohol on a random fitness for duty test. The employee's access to the plant has been terminated.

The licensee has informed the NRC Resident Inspector.


Part 21
Event Number: 52708
Rep Org: CB&I AREVA MOX SERVICES
Licensee: SHAW SSS FABRICATORS
Region: 1
City: AIKEN   State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DAVID DEL VECCHIO
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/26/2017
Notification Time: 13:34 [ET]
Event Date: 09/29/2016
Event Time: 00:00 [EDT]
Last Update Date: 04/26/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
RAY MCKINLEY (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
PART 21 MATERIALS (EMAI)
MICHAEL HAY (R4DO)
ANTHONY MASTERS (R2DO)
Event Text
PART 21 REPORT - WELDS ON MODULAR FRAME ASSEMBLIES DETERMINED TO BE DEFECTIVE

The following is the summary of information received from CB&I AREVA MOX Services, Savannah River Site, via fax:

MOX Services has determined that some welds on modular frame assemblies supplied by Shaw SSS Fabricators in Addis, LA do not comply with procurement documents and require repair. It is unknown by MOX Services if Shaw SSS Fabricators supplied any assemblies to other facilities.

Individual informing the Commission was David Del Vecchio, President and Project Manager, CB&I AREVA MOX Services, Savannah River Site, P.O. Box 7097, Aiken, SC 29804-7097.


Fuel Cycle Facility
Event Number: 53140
Facility: GLOBAL NUCLEAR FUEL - AMERICAS
Region: 2     State: NC
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
LEU FABRICATION
LWR COMMERICAL FUEL
NRC Notified By: SCOTT MURRAY
HQ OPS Officer: STEVE SANDIN
Notification Date: 12/29/2017
Notification Time: 13:00 [ET]
Event Date: 09/29/2016
Event Time: 11:00 [EST]
Last Update Date: 12/29/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(1) - SURFACE CONTAM LEVELS > LIMITS
Person (Organization):
BRIAN BONSER (R2DO)
NMSS_EVENTS_NOTIFICA (EMAI)
FUELS GROUP (EMAI)
Event Text
PACKAGE RECEIVED WITH REMOVABLE SURFACE CONTAMINATION EXCEEDING APPLICABLE LIMITS

"Consistent with paragraphs 111.1 and V.1 of the NRC Confirmatory Order of December 14, 2017 in EA-17-090, GNF-A makes the following report.

"GNF-A [Global Nuclear Fuels - Americas] is making this report to the NRC Operations Center, pursuant to 10 CFR 20.1906(d)(1) to state that the NRC has concluded GNF-A received a package on September 29, 2016, which had removable radioactive surface contamination on its external surfaces that exceeded the applicable limits set forth in 10 CFR 71.87(i).

"This report is solely for the purposes of reaching resolution from an October 25, 2017 alternative dispute resolution because GNF-A maintains that the removable radioactive surface contamination on the external surfaces of the package (an open metal dumpster) and the removable surface contamination on scrap pipes contained in the dumpster did not exceed the applicable limits set forth in 10 CFR 71.87(i).

"Safety Significance of Event: At no time was an unsafe condition.

"Status of Corrective Action: Issue resolved during Alternative Dispute Resolution."

The licensee will inform the NRC Region II Project Manager, State of North Carolina and New Hanover County Emergency Management.