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Event Notification Report for September 19, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/18/2013 - 09/19/2013

** EVENT NUMBERS **


49338 49353 49355 49356

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Agreement State Event Number: 49338
Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: FROEHLING & ROBERTSON
Region: 1
City: SUTHERLAND State: VA
County: DINWIDDIE
License #: VA-760-096-02
Agreement: Y
Docket:
NRC Notified By: MICHAEL WELLING
HQ OPS Officer: DONALD NORWOOD
Notification Date: 09/11/2013
Notification Time: 17:24 [ET]
Event Date: 09/11/2013
Event Time: [EDT]
Last Update Date: 09/12/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
FSME EVENTS RESOURCE (E-MA)
ILTAB (E-MA)

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

Event Text

AGREEMENT STATE REPORT - STOLEN TROXLER GAUGE

The following information was received via facsimile:

"A Troxler model 3411 gauge was stolen from the licensee's truck while at a temporary jobsite. The authorized user placed the gauge in the back of the truck and stepped away to perform other work. When he returned, he found the gauge was gone. He contacted his RSO. The Dinwiddie Sheriff's office was notified and a report filed. The licensee searched the near area but did not find the gauge.

"A press release is being issued by VDH [Virginia Department of Health] utilizing the Richmond and Petersburg area media outlets."

Virginia Report Number: VA-13-08

* * * UPDATE FROM MIKE WELLING TO JOHN SHOEMAKER AT 1605 EDT ON 9/12/13 * * *

"On September 12, 2013, a member of the public returned the gauge to a local business who then contacted the local authorities. The [Virginia] RMP (Radiation Materials Program) was notified and a staff member was dispatched to ascertain the gauge condition. A survey was performed and all readings were found to be within expected dose rates. A wipe test of the gauge was performed and no contamination was found. The licensee was notified and arrived on scene. The gauge was returned to the licensee and an observation was made of the gauge being blocked and braced and secured with cables in the vehicle. An investigation is being performed by RMP."

Notified R1DO (Cahill), FSME Events Resource (via email), and ILTAB (via email).

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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Power Reactor Event Number: 49353
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHNATHAN ZARNDT
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 09/18/2013
Notification Time: 11:15 [ET]
Event Date: 09/18/2013
Event Time: 05:10 [CDT]
Last Update Date: 09/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
KENNETH RIEMER (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Defueled 0 Defueled

Event Text

BOROSCOPIC INSPECTION OF REACTOR VESSEL HEAD DETERMINED EVIDENCE OF BOUNDARY LEAKAGE

"Boroscopic inspection of the reactor head assembly during refuel outage A1R17 has determined that white powder residue observed at reactor head penetrations 41, 49, 61, 65, and 73 is evidence of past Reactor Coolant System pressure boundary leakage at one or more of these locations. This determination was made today at 0510 [CDT] after completion of boroscopic inspections and consultation with the reactor head vendor. These reactor head penetrations are control rod drive mechanism (CRDM) penetrations. The location of the identified leakage is suspected to be the omega seal welded threaded connection on one or more of these CRDM penetrations. Further inspections must be performed to confirm the exact leakage location. This condition will be repaired before U-1 returns to mode 4."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 49355
Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JAMES KRITZER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 09/18/2013
Notification Time: 18:48 [ET]
Event Date: 09/18/2013
Event Time: 12:59 [EDT]
Last Update Date: 09/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DON JACKSON (R1DO)

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

HIGH PRESSURE COOLANT INJECTION SYSTEM DECLARED INOPERABLE DUE TO STEAM LEAK

"On 9/18/13, during performance of the High Pressure Coolant Injection (HPCI) pump operability surveillance, a minor steam leak was discovered on the governor valve inspection cover flange. Due to the leak, HPCI was declared inoperable.

"Actions taken: A 14-day LCO per TS 3.5.E.2 has been entered and corrective actions are in progress."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 49356
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: LT. IHLENFELDT
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/19/2013
Notification Time: 03:10 [ET]
Event Date: 09/18/2013
Event Time: 22:29 [CDT]
Last Update Date: 09/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
KENNETH RIEMER (R3DO)

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

BOTH SECONDARY CONTAINMENT ACCESS DOORS BRIEFLY OPENED SIMULTANEOUSLY

"While performing the secondary containment airlock door interlock surveillance, the interlock to the main plenum room did not prevent the opening of both doors to the plenum room airlock (DOOR-85 and DOOR-86). The plenum room airlock doors were immediately closed. The time both doors were opened is estimated to be approximately one (1) second.

"When both doors open, Technical Specification surveillance requirement SR 3.6.4.1.3 was not met and secondary containment was declared inoperable. Secondary containment was declared operable after independently verifying at least one secondary containment access door was closed.

"There were no radiological releases associated with this event. The NRC resident inspector has been notified."

Page Last Reviewed/Updated Thursday, September 19, 2013
Thursday, September 19, 2013