United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for March 29, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/28/2012 - 03/29/2012

** EVENT NUMBERS **


47763 47768 47778 47780 47781 47782 47783 47784 47785 47786

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Agreement State Event Number: 47763
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: UNIVERSITY OF PENNSYLVANIA
Region: 1
City: PHILADELPHIA State: PA
County:
License #: PA-0131
Agreement: Y
Docket:
NRC Notified By: DAVID J. ALLARD
HQ OPS Officer: PETE SNYDER
Notification Date: 03/22/2012
Notification Time: 20:26 [ET]
Event Date: 03/20/2012
Event Time: [EDT]
Last Update Date: 03/26/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
WAYNE SCHMIDT (R1DO)
CHRISTIAN EINBERG (FSME)

Event Text

AGREEMENT STATE REPORT - UNDERDOSE DURING LIVER DISEASE TREATMENT

"Event type: A medical event (ME) involving the administration of Yittrium-90 SIR-Spheres which is reportable under 10 CFR 35.3045(a)(1)(i).

"Notifications: On March 21,2012, the Department's [Pennsylvania Department of Environmental Protection, Bureau of Radiation Protection] Southeast Regional Office received notification via a phone call about this ME.

"Event Description: The patient was being treated for disease of the liver and received 77% of the intended dose.

"CAUSE OF THE EVENT: Currently under investigation and unknown at this time.

"ACTIONS: No harm to the patient is expected. The treating physician notified the patient.

"The Department [Pennsylvania Department of Environmental Protection, Bureau of Radiation Protection] plans to do a reactive inspection."

PA Event Report ID: PA120009.

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

* * * RETRACTION FROM JOSEPH MELNIC TO VINCE KLCO ON 3/26/12 AT 0937 EDT VIA FAX * * *

"Notifications: On March 21, 2012, the Department's Southeast Regional Office received notification via a phone call about this ME. After the HOO notification was made the Department was informed that the measurement for actual dose delivered was repeated two times, both indicating the administration was within acceptable limits.

"Event Description: The patient was being treated for disease of the liver and was initially thought to have received 77% of the intended dose, however after additional measurements were made the dosage delivered was determined to be 81.2% and 82.2%.

"ACTIONS: Medical Event is being retracted."

Notified the R1DO (Newport) and FSME EO (McIntosh).

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Agreement State Event Number: 47768
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: NON-DESTRUCTIVE INSPECTION CORPORATION
Region: 4
City: LAKE JACKSON State: TX
County:
License #:
Agreement: Y
Docket: L02712
NRC Notified By: ROBERT FREE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/25/2012
Notification Time: 09:20 [ET]
Event Date: 03/24/2012
Event Time: 16:00 [CDT]
Last Update Date: 03/26/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - OVEREXPOSURE TO RADIOGRAPHER WHEN CAMERA SOURCE BECAME DISCONNECTED

The following information was received by facsimile:

"On March 24, 2012, the licensee notified the Agency that it one of its radiography teams had experienced a disconnect of a 65 curie iridium-192 on a QSA Delta 880 radiography camera at a temporary work site in Pasadena, Texas. The crank out drive cable had broken and the source had completely disconnected. After an authorized individual performed the source retrieval, the licensee's RSO learned that the radiographer trainer disconnected the source tube from the camera and had carried the source tube around his neck while he climbed down the ladder of the scaffold. The source was in the tube at this time, but it is uncertain at this time the source's location within the tube. When the radiographer trainer reached the platform he removed the source tube from his neck. The licensee's initial dose estimates for the radiographer trainer are a whole body dose of at least 56 rem and an extremity limit that may exceed 100 rem. The radiographer's film badge is being sent for immediate reading. The licensee is conducting an investigation.

"NOTE: During the licensee's initial phone call to the Agency, the Agency understood the whole body dose estimate to be 6 rem and considered the event to be a 24-hour report (the Agency did report to the NRC HOO within 24 hours). However, when the Agency received the written initial report this morning, March 26, 2012, it was discovered that the estimate is 56 rem, which requires immediate notification. This report is being submitted to update and upgrade the event. More information will be provided as it is obtained.

The State also corrected the source strength to 65 curie Ir-192 source. REAC/TS was notified on 03/26/12 and the licensee has made contact with them.

Texas Incident: I-8942

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Power Reactor Event Number: 47778
Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: FRED SCHIZAS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/28/2012
Notification Time: 10:02 [ET]
Event Date: 03/28/2012
Event Time: 11:30 [CDT]
Last Update Date: 03/28/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
THOMAS FARNHOLTZ (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

TONE ALERT RADIOS OUT OF SERVICE FOR PLANNED MAINTENANCE

"On March 27, 2012, Cooper Nuclear Station was informed by the National Weather Service that the Shubert NOAA Transmitter will be down for maintenance starting at 1130 on March 28, 2012 with maintenance lasting until approximately 1400 on March 28, 2012. This affects the tone alert radios Cooper Nuclear Station provides to members of the public to notify them of an emergency condition. This is considered to be a major loss of the Public Prompt Notification System capability, and is reportable under 10CFR50.72(b)(3)(xiii).

"State authorities and local county authorities within the 10 mile EPZ have been notified of the condition of the NOAA Transmitter and the effect on the tone alert radios and will utilize Local Route Notification (backup notification method). The licensee has notified the NRC Resident Inspector of the condition."

* * * UPDATE FROM ANDREW OHRABLO TO CHARLES TEAL AT 1636 EDT ON 3/28/12 * * *

At 1151 CDT the Shubert NOAA transmitter was removed from service. At time 1411 CDT the NOAA transmitter was restored to service. The State and local governments have been notified as well as the NRC Resident Inspector.

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Power Reactor Event Number: 47780
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DUNCAN HATFIELD
HQ OPS Officer: BILL HUFFMAN
Notification Date: 03/28/2012
Notification Time: 12:55 [ET]
Event Date: 03/28/2012
Event Time: 05:25 [EDT]
Last Update Date: 03/28/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MARK LESSER (R2DO)

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 N 0 Refueling 0 Refueling

Event Text

PLANNED MAINTENANCE ON TSC VENTILATION SYSTEM

"Planned maintenance activities are in progress on Catawba Nuclear Station's Technical Support Center (TSC) Emergency Ventilation System. These planned activities include replacement of a relay and relay base that render the ventilation system temporarily inoperable.

"The planned maintenance window is not expected to exceed 24 hours.

"This report is being made in accordance with 10CFR50.72, criterion (b)(3)(xiii), and in accordance with NUREG-1022, Revision 2, as a condition that may impair the functionality of an Emergency Response Facility."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 47781
Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [ ] [ ]
RX Type: [2] W-3-LP
NRC Notified By: MARTIN ARNOLD
HQ OPS Officer: BILL HUFFMAN
Notification Date: 03/28/2012
Notification Time: 17:14 [ET]
Event Date: 03/28/2012
Event Time: 15:03 [EDT]
Last Update Date: 03/28/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
MARK LESSER (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 55 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP DUE TO STEAM GENERATOR HIGH WATER LEVEL CONDITION

"At 1503 hours EDT on March 28, 2012, with the unit in Mode 1 at 55% power, an automatic reactor trip occurred. The reactor trip was the result of a turbine trip from a 'B' Steam Generator Hi Level. All Reactor Coolant Pumps (RCP) remained running.

"The Auxiliary Feeedwater (AFW) System automatically actuated due to both main feedwater pump breakers opening from a valid feedwater isolation signal. Steam Generator Levels were then controlled by Auxiliary Feedwater pumps. Steam Generator Blowdown was automatically isolated with the AFW actuation. The RCS Code Safety valves, Pressurizer Power Operated Relief Valves (PORVs), Steam Generator PORVs or the Main Steam Safety valves (MSSVs) did not open during the event. All control rods fully inserted following the reactor trip.

"The normal post-trip electrical lineup is providing power to the plant and the electrical system is stable. Decay heat is being removed via the condenser. The reactor is currently in Mode 3 and stable.

"There were no radiological consequences or releases as a result of this event.

"The cause of the Steam Generator Hi Level is under investigation.

"The Resident NRC Inspector has been informed."

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Power Reactor Event Number: 47782
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: TOM PROELL
HQ OPS Officer: BILL HUFFMAN
Notification Date: 03/28/2012
Notification Time: 18:19 [ET]
Event Date: 03/28/2012
Event Time: 16:48 [CDT]
Last Update Date: 03/28/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
BILLY DICKSON (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

OFFSITE NOTIFICATION OF POTENTIAL RELEASE OF AMERTAP BALLS TO MISSISSIPPI

"On 3/28/2012, Xcel Energy Personnel determined that approximately 50% of the Amertap balls recently used were not recovered. A survey of the Mississippi River bank downstream of the plant by site personnel recovered an additional 3 Amertap balls, indicating that the balls were not released to the river. Monticello Nuclear Generating Plant (MNGP) is required to report to the Minnesota Pollution Control Agency (MPCA) when greater than 20% (1 .5 barrels or approximately 7,500) of the Amertap balls are not recovered. This is based on an agreement with the MPCA dated September 12, 2008. The MPCA was notified at 1648 CDT on 3/28/12."

The NRC Resident Inspector has been notified.

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Power Reactor Event Number: 47783
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: TIM HOLLAND
HQ OPS Officer: BILL HUFFMAN
Notification Date: 03/28/2012
Notification Time: 18:26 [ET]
Event Date: 03/28/2012
Event Time: 15:00 [CDT]
Last Update Date: 03/28/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
THOMAS FARNHOLTZ (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

DEGRADED CONDITION IDENTIFIED IN THE B TRAIN CONTAINMENT COOLER UNITS

"At 1500 on March 28, 2012, Callaway Plant personnel discovered that the installation of a modification on the two 'B' train containment cooler units had inadvertently introduced a potential failure mechanism to the 'B' train containment coolers. Specifically, with the containment cooling fans initially in fast-speed operation, combined with certain initial plant conditions, thermal overload tripping of the coolers could occur.

"In such an event, during some postulated accidents, slow-speed restart of the containment coolers by the Load Shedding and Emergency Load Sequencing system could be prevented. As a result, the 'B' train containment coolers could be rendered unavailable for a portion of a postulated accident. Thus, the safety function of the 'B' train containment cooling fans cannot be assured when this degraded equipment condition is present and the containment cooling fans are run in fast-speed operation.

"This condition existed for the 'B' train containment cooling units since they were restored to service from maintenance at 0400 on March 15, 2012.

"Upon identification of this condition, the 'B' train containment cooling fans were switched from fast-speed to slow-speed operation and restored to operable status at 1515. This action precludes this degraded equipment condition from adversely affecting containment cooling fan function during an accident.

"Concurrent with this condition, the opposite train of containment coolers was removed from service for scheduled maintenance at 0505 on March 27, 2012. As a result, from 0505 on March 27, 2012 until 1515 on March 28, 2012, the safety function of the containment cooling system could not be assured for certain postulated accident conditions.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 47784
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: DAVID HALL
HQ OPS Officer: BILL HUFFMAN
Notification Date: 03/28/2012
Notification Time: 22:44 [ET]
Event Date: 03/28/2012
Event Time: 16:15 [CDT]
Last Update Date: 03/28/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
MARK LESSER (R2DO)

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
3 N Y 96 Power Operation 96 Power Operation

Event Text

UNANALYZED CONDITION DISCOVERED DURING NFPA 805 TRANSITION IMPACTING EMERGENCY DIESEL GENERATOR LOADING

"On March 14, 2012, it was determined that in the event of an Appendix R fire, fire damage to cables in Fire Area 2-4, 3-3, or 25-1 could cause a Residual Heat Removal Service Water System (RHRSW) pump to spuriously start. This unanalyzed condition was originally determined to be not reportable. However, during subsequent review on March 28, 2012, this condition was determined to be reportable since the additional load from the spurious start of the RHRSW pump on the associated Emergency Diesel Generator (EDG) could result in the design maximum loading of the EDG being exceeded. As a result of the EDG maximum loading being exceeded, the EDG credited in the Appendix R fire analysis to supply required Appendix R safe shutdown loads could fail. The issue has significant safety impact since the capability to supply power to the Appendix R safe shutdown equipment for the credited EDG is necessary to provide adequate core cooling and decay heat removal during performance of the Browns Ferry Nuclear Plant Safe Shutdown Instructions in an Appendix R fire event."

The NRC Resident Inspector has been notified.

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Power Reactor Event Number: 47785
Facility: OCONEE
Region: 2 State: SC
Unit: [1] [2] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: SANDRA LOSKOSKI
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/29/2012
Notification Time: 00:02 [ET]
Event Date: 03/24/2012
Event Time: 18:10 [EDT]
Last Update Date: 03/29/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MARK LESSER (R2DO)

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
3 N Y 100 Power Operation 100 Power Operation

Event Text

SEWAGE SPILL IN THE TURBINE BUILDING THAT DISCHARGES TO THE KEOWEE RIVER

"On 3/24/12 at 1810 hrs EDT, a four inch sewage line in the turbine building failed. This allowed sanitary wastewater to spill into the turbine building basement. An estimated 100 gallon entered into trench drains and then to the station sump which discharges into the conventional wastewater system. This conventional wastewater system is discharged to the Keowee River from NPDES [National Pollutant Discharge Elimination System] outfall 002. The discharge of outfall 002 is into the Keowee River below the Keowee River Hydro Station. The normal discharge path for sanitary wastewater is to the City of Seneca. South Carolina DHEC [Department of Health and Environmental Control] was notified of the spill on 3/24/12 at 2259 hrs EDT. After further review, this was determined to be reportable under 10CFR50.72(b)(2)(xi)."

This event was determined to be reportable at 2150 EDT on 3/28/2012. The event was entered into the corrective action program. There was no impact on plant operations and the cleanup has been completed. The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 47786
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: JEREMY HITE
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 03/29/2012
Notification Time: 04:04 [ET]
Event Date: 03/29/2012
Event Time: 04:00 [EDT]
Last Update Date: 03/29/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CHRISTOPHER NEWPORT (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 VENTILATION SYSTEM OUTAGE

"At 0400 (EDT) on Thursday March 29th, the Peach Bottom Atomic Power Station (PBAPS) Technical Support Center (TSC) supply and exhaust fans will be removed from service for planned preventative maintenance activities on the exhaust fan. This maintenance is scheduled to be worked continuously until completion to minimize out of service time. The planned TSC ventilation outage is scheduled to be completed within 14 hours. If TSC staffing is required, it will take a maximum of 4 hours to return the ventilation system back to an operable status."

The licensee has notified the NRC Resident Inspector.

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