United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for December 2, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/01/2010 - 12/02/2010

** EVENT NUMBERS **


46348 46439 46443 46444 46445

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General Information or Other Event Number: 46348
Rep Org: GE HITACHI NUCLEAR ENERGY
Licensee: GE HITACHI NUCLEAR ENERGY
Region: 1
City: WILMINGTON State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DALE PORTER
HQ OPS Officer: ERIC SIMPSON
Notification Date: 10/20/2010
Notification Time: 12:54 [ET]
Event Date: 10/20/2010
Event Time: [EDT]
Last Update Date: 12/01/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
MARIE MILLER (R1DO)
RANDY MUSSER (R2DO)
STEVE ORTH (R3DO)
VIVIAN CAMPBELL (R4DO)
PART 21 GP VIA EMAIL ()

Event Text

PART 21 - CRACK INDICATIONS IN MARATHON CONTROL ROD BLADES

The following was received via facsimile:

"A recent inspection of near 'End-of-Life' Marathon Control Rod Blades (CRB) at an international BWR/6 has revealed crack indications. The CRB assemblies in question were manufactured in 1997. GE Hitachi Nuclear Energy (GEH) continues to investigate the cause(s) of the crack indications. Once the cause of the crack indications is determined, GEH will evaluate the nuclear and mechanical lifetime limits of the Marathon Control Rod Blade design in light of the new inspection data, and make revised lifetime recommendations, if necessary.

"This 60-day interim notification, in accordance with 10CFR Part 21.21(a)(2), is sent for all plants that are D lattice, BWR/2-4 or S lattice, BWR/6 plants. Since there have been no reported cracking occurrences in C lattice assemblies to date, these CRBs are tentatively eliminated from the investigation. C lattice, BWR/4-5 plants have been included on Attachment 2 for identification. Should the results of the investigation implicate the C lattice plants, the final resolution to this 10CFR Part 21 evaluation will include the C lattice plants."

The D lattice and S lattice plants in the US that are affected by this notification include Nine Mile Point, Unit 1; Millstone, Unit 1; Fitzpatrick; Pilgrim; Vermont Yankee; Grand Gulf; River Bend; Clinton; Oyster Creek; Dresden, Unit 2; Dresden, Unit 3; Peach Bottom, Unit 2; Peach Bottom, Unit 3; Quad Cities, Unit 1; Quad Cities, Unit 2; Perry, Unit 1; Duane Arnold; Cooper; Monticello; Brunswick, Unit 1; Brunswick, Unit 2; Hatch, Unit 1; Hatch, Unit 2; Browns Ferry, Unit 1; Browns Ferry, Unit 2; and Browns Ferry, Unit 3.

* * * UPDATE FROM DALE PORTER TO ERIC SIMPSON VIA FAX AT 1556 ON 12/1/2010 * * *

"In August 2010, GE Hitachi (GEH) performed the planned inspection of four near 'End-of-Life' CRBs at 'Plant O.' The inspection revealed crack indications on all four Control Rod Blades (CRBs). The observed cracks are much more numerous, and have more material distortion than previously observed. Further, the cracks occur at a much lower reported local B-10 depletion than previously observed, with cracking predominantly starting at approximately 40% local depletion, whereas previous inspections observed cracking only above 60% local depletion.

"The cracks at 'Plant O' are also more severe, in that they resulted in missing capsule tube fragments from two of the inspected CRBs. A lost parts analysis performed for 'Plant O' determined that there is no negative affect on plant performance due to the missing tube fragments.

"At this point in the investigation, no causal or contributing factors unique to the 'Plant O' CRBs, nor their operation, has been identified.

"Including the inspections at 'Plant O,' GEH has now completed the visual inspection of 97 irradiated Marathon CRBs, with 10 showing crack indications. As 'Plant O' is an S lattice design, all crack indications are still confined to D and S lattice applications, with no crack indications on C lattice designs. When considering only D and S lattice applications that are near 'End-of-Life' depletion limits, 10 of 23 control rod inspections have revealed crack indications."

Notified R1DO (Schmidt), R2DO (Shaeffer), R3DO (Ring), R4DO (Powers) and Part 21 Group.

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
General Information or Other Event Number: 46439
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: PROTECHNICS
Region: 4
City: HOUSTON State: TX
County:
License #: L03835
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/26/2010
Notification Time: 12:33 [ET]
Event Date: 11/26/2010
Event Time: [CST]
Last Update Date: 12/01/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
TOM ANDREWS (R4DO)
GLENDA VILLAMAR (FSME)

Event Text

AGREEMENT STATE REPORT - VEHICLE TRANSPORTING WELL LOGGING SOURCES INVOLVED IN ACCIDENT WITH FATALITY

The Texas Department of Health, Radiation Branch, received notification from the licensee that their truck, transporting well logging sources, was involved in a rollover accident in which the driver was killed. During the accident, the overpack carrying the sources was torn loose from the vehicle but remained intact. The overpack did sustain some damage but the source boxes appear to be intact and accounted for. A U.S. Border Patrol officer was on scene and performed surveys of the overpack and surrounding area and did not detect any abnormal background readings. The sources are currently under the control of the Texas Department of Public Safety officers (Texas State Troopers) at the scene awaiting recovery and transport by the licensee.

Due to the nature of the accident, all paperwork pertaining to the sources is scattered around the accident scene. Paperwork recovered at the scene indicate that the truck was carrying Iridium-192, Scandium-46 and Antimony-124 with total activity of all packages at approximately 726 mCi.

The accident occurred 4 miles outside of Encinal, TX on State Highway 44.

* * * UPDATE AT 1708 EST ON 11/26/10 FROM KAREN BLANCHARD TO S. SANDIN * * *

The licensee has arrived on-scene, confirmed that there was no release of radioactive material and taken possession of the following packages containing 240 mCi Iridium-192, 160 mCi Scandium-46 and 320 mCi Antimony-124 for return to their Alice, TX office.

Notified R4DO (Andrews) and FSME (Piccone).

* * * RETRACTION AT 1722 EST ON 12/1/10 FROM KAREN BLANCHARD TO P. SNYDER * * *

The State of Texas provided the following information via e-mail:

"It was determined after all information was collected that the incident does not meet any reporting requirement.

"The Agency [Texas Department of Health] is requesting that this event be retracted."

Notified R4DO (Powers) and FSME (Danna).

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Power Reactor Event Number: 46443
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: ERIC SWAIN
HQ OPS Officer: ERIC SIMPSON
Notification Date: 12/01/2010
Notification Time: 15:14 [ET]
Event Date: 12/01/2010
Event Time: 14:55 [EST]
Last Update Date: 12/01/2010
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
WAYNE SCHMIDT (R1DO)
JOHN THORP (NRR)
WILLIAM GOTT (IRD)
BRUCE BOGER (NRR)
BILL DEAN (R1 R)
DORA HEYMAN (FEMA)
TERRY FIELD (DHS)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 25 Power Operation 25 Power Operation

Event Text

UNUSUAL EVENT DECLARED DUE TO EXCESSIVE RCS LEAKAGE FROM "B" RECIRC PUMP SEAL

"Oyster Creek has declared an Unusual Event (MU7) due to Reactor Coolant System leakage greater than 10 gpm. Leakage has been determined to be from the 'B' reactor recirculation pump seals. The 'B' Reactor Recirculation Loop was isolated and leakage stopped."

The plant remained in the normal electrical lineup and no safety systems actuated during this evolution.

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM ERIC SWAIN TO ERIC SIMPSON AT 1548 ON 12/1/10 * * *

At 1537 EST, "Oyster Creek has terminated from an Unusual Event. Event terminated due to isolating leakage from the 'B' Reactor Coolant Loop."

The licensee notified the NRC Resident Inspector.

Notified R1DO (Schmidt), IRD (Gott), NRR EO (Nelson), DHS and FEMA.

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Fuel Cycle Facility Event Number: 46444
Facility: HONEYWELL INTERNATIONAL, INC.
RX Type: URANIUM HEXAFLUORIDE PRODUCTION
Comments: UF6 CONVERSION (DRY PROCESS)
Region: 2
City: METROPOLIS State: IL
County: MASSAC
License #: SUB-526
Agreement: Y
Docket: 04003392
NRC Notified By: MARK WOLF
HQ OPS Officer: STEVE SANDIN
Notification Date: 12/01/2010
Notification Time: 15:20 [ET]
Event Date: 11/30/2010
Event Time: 05:00 [CST]
Last Update Date: 12/01/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
SCOTT SHAEFFER (R2DO)
KING STABLEIN (NMSS)

Event Text

LOSS OF POWER TO INSTRUMENTATION IN THE OPERATING UNITS OF THE FEED MATERIALS BUILDING

"Description of the Event: This report is performed pursuant to 10 CFR 40.60(b)(2) reporting requirements.

"On Tuesday, November 30, 2010, at approximately 0500, the failure of F-Substation caused a loss of instrumentation in operating units in the Feed Materials Building. At 0505, various weight, temperature and pressure indications were not available.

"Due to the loss of power to a load cell component, the UF6 Vaporizer weight exceeded the administrative limit. During the power loss the vessel's weight measurement was not available to the operator.

"At 0538, power was restored and instrumentation readings returned to normal. The loss of the Vaporizer weight control did not have any safety consequences.

"Isotope, Quantities and Chemical Form: No material release.

"Personnel Radiation Exposure Date (if applicable): No additional exposure to radiation or radioactive materials."

The licensee will inform the NRC Region II Office.

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Power Reactor Event Number: 46445
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: PETER SCHOETTLER
HQ OPS Officer: ERIC SIMPSON
Notification Date: 12/01/2010
Notification Time: 17:40 [ET]
Event Date: 12/01/2010
Event Time: 13:59 [EST]
Last Update Date: 12/01/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
WAYNE SCHMIDT (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

OFFSITE NOTIFICATION OF PETROLEUM SPILL INTO THE SUSQUEHANA RIVER

"On 12/01/10, at 1359 EST, Peach Bottom Atomic Power Station reported a petroleum product spill in the discharge canal. Total quantity of substance is less than 1 quart. Lewis Environmental agency has been contacted to aid in containment and cleanup of the spill.

"This report is being submitted pursuant to 10 CFR 50.72(b)(2)(xi) and 10 CFR 72.75(b)(2)."

The spill did not reach Comprehensive Environmental Response Compensation and Liability Act (CERCLA) reportable quantities. The licensee notified the Pennsylvania Department of Environmental Protection, United States Coast Guard, and EPA Region 3.

The NRC Resident Inspector has been notified.

Page Last Reviewed/Updated Saturday, February 05, 2011
Saturday, February 05, 2011