United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for January 10, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/09/2012 - 01/10/2012

** EVENT NUMBERS **


47539 47568 47570 47571 47574 47578 47580 47581 47582

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Part 21 Event Number: 47539
Rep Org: DRESSER CONSOLIDATED
Licensee: DRESSER CONSOLIDATED
Region: 4
City: ALEXANDRIA State: LA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BILL ALEXANDER
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/20/2011
Notification Time: 14:26 [ET]
Event Date: 12/20/2011
Event Time: [CST]
Last Update Date: 01/10/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
BOB HAGAR (R4DO)
PART21 GROUP ()

Event Text

PART 21 - CAPACITY FAILURE OF PRESSURE RELIEF VALVE

The following information was received via facsimile:

"A potential issue exists involving Dresser's pressure relief device model 1982. The Part 21 investigation was initiated because of a nameplate capacity failure during National Board certification testing. The Dresser model 1982 pressure relief device is used for system overpressure protection. Dresser's engineering and quality assurance departments are currently working to identify the root cause of this capacity failure and to determine if the equipment is being used in safety related applications subject to 10 CFR Part 21. Should it be determined that the equipment at issue is being used in safety related applications, a notification will be provided in accordance with the requirements of 10 CFR Part 21."

* * * UPDATE AT 1431 EST ON 1/9/12 FROM PHILIP WALTZ TO HUFFMAN VIA FACSIMILE * * *

The following is a summary of an interim report on this issue:

"During the investigation process of 10 CFR Part 21, File No. 2011-02, in accordance with 10 CFR
Part 21, GE Dresser has not been able to obtain the required flow capacity and does not have the required information regarding the system to determine the required flow capacity of the valve in question.

"We have completed a Transfer of Information in accordance with 10 CFR Part 21.21 (b) to Enertech and Exelon to assist in the determination of Part 21 reportability.

"The Transfer of Information letter [below] has been sent to Enertech and Exelon.

"GE Dresser supplied a pressure relief valve dedicated as ASME Section VIII Safety Related to Enertech, which was then sold to Exelon and installed at the Dresden Nuclear Power Station, Unit 2. As a result of an investigation of the effect of outlet piping on the flow capacity of similar pressure relief valves it was noted that the pressure relief valve installed at Dresden, Unit 2 may not relieve its ASME certified flow capacity when installed with outlet piping. In order to determine if a reportable condition exists, the flow capacity provided by a pressure relief valve to prevent the protected system from exceeding a pressure 10% greater than systems design pressure is required. GE Dresser has not been able to obtain the required flow capacity and does not have the required information regarding the system to determine the required flow capacity. As such GE Dresser cannot determine if the identified deviation from technical requirements would create a reportable condition within the requirements of 10CFR Part 21. GE Dresser provides this Transfer of Information, in accordance with 10 CFR Part 21.21(b) to Enertech and Exelon to assist in the determination of Part 21 reportability."

NRC R3DO (Orth) and R4DO (Lantz) have been notified. The NRC Part 21 Group has been sent a copy of this interim report.

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Agreement State Event Number: 47568
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: COILPLUS TEXAS, INC.
Region: 4
City: SAN ANTONIO State: TX
County:
License #: 02242
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: DONALD NORWOOD
Notification Date: 01/04/2012
Notification Time: 16:24 [ET]
Event Date: 01/04/2012
Event Time: [CST]
Last Update Date: 01/04/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL VASQUEZ (R4DO)
CHRISTEPHER MCKENNEY (FSME)

Event Text

AGREEMENT STATE REPORT - GAUGE SHUTTER FAILED IN CLOSED POSITION

The following information was received via facsimile:

"On January 4, 2012, the licensee reported to the Agency [Texas Department of State Health Services, Inspection Unit, Radiation Branch] that it had had a gauge shutter fail in the closed position during a routine shutter test on an Xact Ray, Model 5310, which houses a 1,000 millicurie Americium-241 source. The gauge is on a machine that is not in service and the shutter is kept closed. When the licensee attempted to open the shutter for the routine check, it would not open. More information will be provide as it is obtained."

Texas Incident #: I-8915

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Agreement State Event Number: 47570
Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: NOVA QA CONSULTING
Region: 1
City: ORANGE State: NJ
County:
License #: 110003-507392
Agreement: Y
Docket:
NRC Notified By: ED TRUSKOWSKI
HQ OPS Officer: CHARLES TEAL
Notification Date: 01/05/2012
Notification Time: 11:52 [ET]
Event Date: 01/05/2012
Event Time: 09:30 [EST]
Last Update Date: 01/05/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DANIEL HOLODY (R1DO)
DENNIS ALLSTON (ILTA)
ANGELA MCINTOSH (FSME)

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE

The following was received via email:

At 10:45 a.m. today, 1/05/12, the [NJ] Bureau of Environmental Radiation (BER) received a call from the RSO for Nova QA Consulting to report that one of his inspector's car was stolen in front of the client's facility in Orange, NJ this morning between 09:30 and 10:00 a.m. In the locked car was a Troxler Model 4640 serial #2375 with less than 9 mCi of Cs-137. His inspector called the Orange police and the RSO is also in communication with the Orange police. At 11:05 a.m. the RSO said that he will call Trenton Dispatch. Trenton Dispatch called the BER at 11:25 a.m.


THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

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Agreement State Event Number: 47571
Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: CANBERRA
Region: 1
City: DOVER State: NJ
County:
License #: 110002-440566
Agreement: Y
Docket:
NRC Notified By: JENNY GOODMAN
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/05/2012
Notification Time: 14:26 [ET]
Event Date: 12/21/2011
Event Time: [EST]
Last Update Date: 01/05/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DANIEL HOLODY (R1DO)
CHRISTEPHER MCKENNEY (FSME)
ILTAB via email ()

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT INVOLVING A MISSING AMERICIUM-241 CHECK SOURCE

The following report was received from the State of New Jersey via email:

"Canberra is terminating their license and in reconciling their inventory, and on 12/21/11 they discovered that a 8uCi Am-241 source [used as a check source] was missing. The source was last used by an employee in June or August. That employee had a stroke and did not return to work. Other employees cleaned out his cube area, mailed his personal belongings to his house, and threw everything else in the garbage. NJDEP instructed Canberra to go to the former employee's home. They will send a technician to do a search/survey."

This incident was reported by Canberra to the State of New Jersey on 1/4/12.

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

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Agreement State Event Number: 47574
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: DANA FARBER
Region: 1
City: BOSTON State: MA
County:
License #: 19-7612
Agreement: Y
Docket:
NRC Notified By: BRUCE PACKARD
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/05/2012
Notification Time: 16:45 [ET]
Event Date: 01/05/2012
Event Time: [EST]
Last Update Date: 01/05/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DANIEL HOLODY (R1DO)
CHRISTEPHER MCKENNEY (FSME)

Event Text

AGREEMENT STATE REPORT INVOLVING CONTAMINATION FROM A SUSPECTED BROKEN EXIT SIGN

The following information was provided by the Commonwealth of Massachusetts via email:

"Large area swipes reading up to 14,000 DPM H-3 were found in the loading dock area. No cause is known. Activity is distributed evenly on the floor and walls so airborne deposition is suspected. Current theorized cause is a broken exit sign.

"Licensee has evacuated unnecessary personnel from loading dock and is trying to find the extent of contamination.

"Since a broken exit sign could cause a release over 5 ALI, immediate notification was given to NRC over the phone."
.

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Fuel Cycle Facility Event Number: 47578
Facility: NUCLEAR FUEL SERVICES INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU CONVERSION & SCRAP RECOVERY
                   NAVAL REACTOR FUEL CYCLE
                   LEU SCRAP RECOVERY
Region: 2
City: ERWIN State: TN
County: UNICOI
License #: SNM-124
Agreement: Y
Docket: 07000143
NRC Notified By: RANDY SHACKELFORD
HQ OPS Officer: BILL HUFFMAN
Notification Date: 01/09/2012
Notification Time: 14:32 [ET]
Event Date: 01/09/2012
Event Time: 11:55 [EST]
Last Update Date: 01/09/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (c) - OFFSITE NOTIFICATION/NEWS REL
Person (Organization):
DAVID AYRES (R2DO)
MARISSA BAILEY (NMSS)
FUELS OUO GROUP (E-MA)

Event Text

REPORT TO OFFSITE GOVERNMENT AGENCIES AND PRESS RELEASE DUE TO A CHEMICAL SPILL ONSITE

The licensee reported that approximately 300 gallons of nitric acid spilled in the bulk chemical storage outdoor area from a storage tank. The nitric acid spilled into a dike that surrounds the tank. The leak was isolated and it is believed that no acid breached the dike and entered the environment. Due to fumes from the acid, the licensee shut down production activities and evacuated non-essential personnel from nearby buildings. The licensee is currently remediating the spill and evaluating when to permit personnel normal access to the onsite areas that were evacuated. This event did not involve any radiological material and did not meet emergency declaration criteria. There was no offsite impact from this event. Site security was maintained throughout. No injuries have been reported. The cause of the spill is still being investigated.

This event is being reported to the NRC Operations Center as a "Concurrent Report" because the licensee has notified state, county, and local authorities and will be making a press release. The licensee has also notified the NRC Resident Inspector and Region 2 (Pelchat).

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Independent Spent Fuel Storage Installation Event Number: 47580
Rep Org: DIABLO CANYON
Licensee: PACIFIC GAS & ELECTRIC CO.
Region: 4
City: AVILA BEACH State: CA
County: SAN LUIS OBISPO
License #: SNM-2511
Agreement: Y
Docket: 72-26
NRC Notified By: MICHAEL QUITTER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 01/09/2012
Notification Time: 23:44 [ET]
Event Date: 01/09/2012
Event Time: 14:05 [PST]
Last Update Date: 01/09/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
72.75(d)(1) - SFTY EQUIP. DISABLED OR FAILS TO FUNCTION
Person (Organization):
RYAN LANTZ (R4DO)
WILLIAM RULAND (NRR)
CHRISTEPHER MCKENNEY (FSME)

Event Text

NUT ON HOLD-DOWN STUD WAS FOUND LOOSE

"On January 9, 2012, at 1405 [PST], plant personnel notified the Diablo Canyon shift manager that a nut on a hold-down stud on an Independent Spent Fuel Storage Installation(ISFSI) HISTORM spent fuel storage cask was loose to the touch. Plant personnel hand tightened the nut and verified that none of the other 16 casks in the facility had nuts that were loose to the touch.

"The Diablo Canyon ISFSI design requires that each spent fuel storage cask be installed with the cask compressed against the embedment plate using 16, two-inch diameter, anchor studs. Each stud is pre-loaded to approximately 157,000 lbf. This design ensures the cask will remain stable during a seismic event. A manufacturer's analysis of the stability of the cask with all of the 16 hold down stud nuts installed with no pre-load concluded that the cask would maintain its stability during a seismic event.

"PG&E has contracted the vendor to re-tension the stud and expect[s] completion [by] 1/13/2012. PG&E will assess the need to verify tension of the remaining studs based on the extent of condition evaluation.

"Cause of the loose nut has not yet been determined.

"The NRC Senior Resident Inspector has been informed."

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Power Reactor Event Number: 47581
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: CJ CAMPBELL
HQ OPS Officer: JOHN KNOKE
Notification Date: 01/10/2012
Notification Time: 00:55 [ET]
Event Date: 01/09/2012
Event Time: 17:22 [EST]
Last Update Date: 01/10/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAMES TRAPP (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
3 N Y 100 Power Operation 100 Power Operation

Event Text

TECHNICAL SUPPORT CENTER DETERMINED TO BE NON-FUNCTIONAL

"On January 09, 2012 the Technical Support Center(TSC) ventilation was discovered to be non-functional during system testing. At 1722 hours [EST], it was identified that control power was lost to four motor operated dampers. Investigation revealed that a control power fuse was blown. In addition, the TSC ventilation Supply Fan (AHU-1) was identified to have one of two fan belts failed. The fuses were replaced at 19:45 [EST] and the system was restored to service. However, the system has been removed from service this evening to replace the fan belts. An update will be provided when the system is restored to full functionality."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 47582
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: RUSS LONG
HQ OPS Officer: JOHN KNOKE
Notification Date: 01/10/2012
Notification Time: 04:49 [ET]
Event Date: 01/10/2012
Event Time: 04:36 [EST]
Last Update Date: 01/10/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
JAMES TRAPP (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 25 Power Operation 0 Hot Standby

Event Text

EXCESSIVE LEAKAGE FROM RCP SEAL RETURN

"Plant shutdown from 100% due to increased leakage from 21 RCP [Reactor Coolant Pump] seal return was commenced at 0100 EST. A manual reactor trip was actuated in accordance with plant procedures at 25% power. Auxiliary feedwater pump was placed in service prior to the reactor trip, per plant procedures. Decay heat is being removed via the condenser steam dumps. All offsite power sources are available. All equipment operated as expected."

The licensee has notified the NRC Resident Inspector and other government agencies.

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