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Event Notification Report for August 6, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/05/2010 - 08/06/2010

** EVENT NUMBERS **


46152 46153 46154 46155 46156

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Power Reactor Event Number: 46152
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: RANDY SANDS
HQ OPS Officer: STEVE SANDIN
Notification Date: 08/05/2010
Notification Time: 13:43 [ET]
Event Date: 08/06/2010
Event Time: 07:00 [CDT]
Last Update Date: 08/05/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HIRONORI PETERSON (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

TECHNICAL SUPPORT CENTER (TSC) PLANNED MAINTENANCE ACTIVITY

"On 8/6/10 at 0700 CDT the Monticello Nuclear Generating Plant's [MNGP] Technical Support Center uninterruptible power supply will be isolated to perform a planned maintenance activity. The maintenance activity requires implementation of compensatory measures to maintain TSC functions during the activity. The compensatory measures include having the Emergency Director report to the Control Room and co-locating the remaining TSC staff at the EOF should an event be declared requiring ERO activation. The ERO has previously successfully demonstrated the ability to implement these compensatory measures. The maintenance activity is scheduled to be completed with the TSC returned to full functionality by the end of the dayshift on 8/6/10. The Site Emergency Response Organization has been notified of the maintenance activity and instructed on the planned compensatory measures to be implemented during the activity. MNGP will notify the NRC upon completion of the activity restoring full TSC operability. This event is considered reportable per 10CFR50.72(b)(3)(xiii). The licensee has notified the NRC Resident Inspector."

The licensee will inform both State and local agencies.

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Power Reactor Event Number: 46153
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: STEVE SANDIN
Notification Date: 08/05/2010
Notification Time: 14:53 [ET]
Event Date: 08/05/2010
Event Time: 13:55 [EDT]
Last Update Date: 08/05/2010
Emergency Class: UNUSUAL EVENT
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
BRIAN BONSER (R2DO)
JEFFERY GRANT (IRD)
JOHN THORP (NRR)

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

DISCOVERY OF AFTER-THE-FACT EMERGENCY CONDITION MEETING UNUSUAL EVENT CRITERIA

"At 1345 EDT, following maintenance on 1-CHLCV-1115A, VCT divert valve, testing was commenced. At 1355 EDT, the valve failed to the full divert position and could not be repositioned from the normal control system, resulting in 75 gpm letdown flow being diverted to the gas stripper.

"At 1401 EDT, the normal letdown flowpath was isolated in accordance with plant procedures and the leakage isolated.

"The identified flow rate exceeded the threshold for entry into a Notice of Unusual Event under EAL tab SU6.1 due to identified leakage greater than 25 gpm."


The licensee will inform State and local agencies and has notified the NRC Resident Inspector.

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Other Nuclear Material Event Number: 46154
Rep Org: ARCELORMITTAL BURNS HARBOR
Licensee: ARCELORMITTAL BURNS HARBOR
Region: 3
City: BURNS HARBOR State: IN
County:
License #: 13-32670-01
Agreement: N
Docket:
NRC Notified By: CHRIS SARVANIDIS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 08/05/2010
Notification Time: 15:13 [ET]
Event Date: 07/22/2010
Event Time: 02:30 [EDT]
Last Update Date: 08/05/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
HIRONORI PETERSON (R3DO)
ROBERT LEWIS (FSME)

Event Text

NUCLEAR GAUGE DISLODGED FROM STEEL CASTER AND LATER RETRIEVED

"After completion of casting operations at the #1 Slab Caster, a trained worker proceeded to the mold strand area to remove the Berthold Co-60 rod source from the mold and place it in proper storage. The source is 3.97 mCi [Co-60] and is used to measure mold level of liquid steel. After all machinery and equipment was moved away from the mold so it could be accessed, the trained worker removed the plug to access the source for proper removal. Upon removing the plug, the trained worker noticed dirt and debris in the opening so he used compressed air to clean the area. The force of the compressed air into the source opening caused the source rod to lift out of the seated position and drop approximately 10 feet into the mold. The trained worker and a co-worker were able to retrieve the rod and place it back into its appropriate source holder. Investigation and exposure calculations indicated that neither employee was exposed above regulatory limits."

The licensee performed exposure calculations and estimated the trained radiation worker received a dose to the hands of 10.2 mRem. The assistant (not a trained radiation worker and not carrying dosimetry) received a calculated dose to the hands of 0.12 mRem.

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Power Reactor Event Number: 46155
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: RANDY SAND
HQ OPS Officer: STEVE SANDIN
Notification Date: 08/05/2010
Notification Time: 15:30 [ET]
Event Date: 08/05/2010
Event Time: 11:45 [CDT]
Last Update Date: 08/05/2010
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):
HIRONORI PETERSON (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

MOMENTARY LOSS OF SECONDARY CONTAINMENT DUE TO PERSONNEL PASSING THROUGH OPEN AIRLOCKS

"On August 5, 2010 at 1145 CDT, both doors in Airlock 413 from Secondary Containment (SCT) to the 985 ft Radwaste Pump Room were simultaneously open for a period of approximately five (5) seconds and subsequently reclosed. This condition caused an unplanned entry into Technical Specification 3.6.4.1.A for SCT. The condition could have prevented the Standby Gas Treatment system from developing a negative pressure with SCT following a design basis accident. This negative pressure is required to prevent ground level release of radioactivity and to minimize onsite and offsite dose consequences following an accident. The Standby Gas Treatment system remained operable throughout the event."

The licensee will inform the State and has notified the NRC Resident Inspector.

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Power Reactor Event Number: 46156
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: SHANNON GAYDOS
HQ OPS Officer: STEVE SANDIN
Notification Date: 08/05/2010
Notification Time: 15:39 [ET]
Event Date: 08/05/2010
Event Time: 15:00 [CDT]
Last Update Date: 08/06/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BOB HAGAR (R4DO)

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

LOSS OF ALL POWER AND EMERGENCY RESPONSE FUNCTION AT THE TECHNICAL SUPPORT CENTER DUE TO SCHEDULED MAINTENANCE

"The Technical Support Center (TSC) will be without power during performance of planned maintenance activities starting at approximately 1500 CDT on August 5, 2010. The maintenance activities, including electrical isolation and restoration, are expected to last approximately 12 hours. Contingency plans for emergency [response] situations have been established and the Emergency Response Organization members have been notified of their contingency actions.

"This event is reportable per 10CFR50.72(b)(3)(xiii) since this constitutes a loss of an emergency response facility for the duration of the maintenance activities.

"Region IV was notified of this planned outage.

"The licensee notified [State and local agencies and] the NRC Resident Inspector."

* * * UPDATE ON 8/6/10 ATA 0407 FROM BONVILLIAN TO HUFFMAN * * *

The Technical Support Center was restored to functional status at 0407 EDT. All systems verified operational. The licensee will notify State and local agencies and the NRC Resident Inspector. R4DO (Hagar) notified.

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Thursday, March 29, 2012