| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/29/2012 - 07/02/2012 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 47897 | Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [ ] [ ]
RX Type: [3] CE
NRC Notified By: JESSE BOHNENKAMP
HQ OPS Officer: DONALD NORWOOD | Notification Date: 05/03/2012
Notification Time: 21:07 [ET]
Event Date: 05/03/2012
Event Time: 16:13 [CDT]
Last Update Date: 06/29/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
GREG WERNER (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text BOTH TRAINS OF THE CONTROLLED VENTILATION AREA SYSTEM INOPERABLE
"This is a non-emergency 8 hour notification being made in accordance with 10CFR50.72(b)(3)(ii) Degraded or Unanalyzed Condition and 10CFR50.72(b)(3)(v) Prevented Safety Function. Both trains of the Controlled Ventilation Area System (CVAS) were considered inoperable from 1613 to 1641 CDT on 5/3/2012.
"Waterford 3 was performing planned maintenance on CVAS Train A with the train declared inoperable. Operations supervision was informed by maintenance personnel that an electrical conduit near the work area and not related to the work in progress had been found with a conduit connection unthreaded and separated. The contained wires could be seen and appeared intact. Investigation by engineering personnel determined that the conduit was associated with CVAS Train B. Operations declared CVAS Train B inoperable and entered Technical Specification (TS) 3.0.3 at 1613 hours.
"Operations personnel were already restoring CVAS Train A following completion of maintenance. After performing the planned retest, Operations declared CVAS Train A operable and exited TS 3.0.3 at 1641 hours. No actions were taken to commence a power reduction or reactor shutdown.
"The CVAS is required following a design basis accident to draw all exhaust air from the CVAS areas of the Reactor Auxiliary Building through HEPA and charcoal filters before discharge to the atmosphere. The CVAS areas contain equipment such as the shutdown cooling heat exchangers, safety injection pumps and other areas with containment penetrations. The CVAS is credited in accident analysis for limiting the radiological release under a Loss of Coolant Accident condition.
"Following repair of the conduit connection, Operations declared CVAS Train B operable at 1956 hours.
"Waterford 3 remained stable at 100% power during the condition. Both trains of offsite and onsite electrical sources, ECCS, and Containment Cooling safety systems remained operable during the condition."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION FROM WILLIAM HARDIN TO VINCE KLCO ON 6/29/2012 AT 1515 EDT * * *
"This is a non-emergency notification from Waterford 3 retracting a previous notification.
"On 5/3/2012 at 2107 EDT, Waterford 3 communicated Notification Message EN 47897, pursuant to 10 CFR 50.72(b)(2)(ii), Degraded or Unanalyzed Condition and 10 CFR 50.72(b)(3)(v), Prevented Safety Function, stating that both trains of the Controlled Ventilation Area System (CVAS) were considered inoperable from 1613 to 1641 CDT on 5/3/2012.
"Subsequent engineering evaluation has determined that the as-found condition would not cause the inoperability of CVAS Train B. With one train operable, the plant remained within analyzed conditions and capable of fulfilling safety functions. As such, no condition existed which required reporting.
"Based on this information, Waterford 3 is retracting notification message EN 47897."
The licensee has notified the NRC Resident Inspector.
Notified the R4DO (Clark). |
| Power Reactor | Event Number: 48056 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CHARLES BROESCHE
HQ OPS Officer: JOE O'HARA | Notification Date: 06/29/2012
Notification Time: 13:04 [ET]
Event Date: 06/29/2012
Event Time: 10:28 [EDT]
Last Update Date: 06/29/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
JONATHAN BARTLEY (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 | Event Text UNANALYZED CONDITION DUE TO INCREASE IN PROBABLE MAXIMUM FLOOD LEVEL
"On June 29, 2012, TVA issued an updated calculation titled 'PMF Determination for Tennessee River Watershed' The calculation resulted in an increase in the Watts Bar Nuclear (WBN) probable maximum flood (PMF) level from Elevation 734.9 to Elevation 739.2. All flood sensitive safety related systems, structures, and components have been reviewed and been determined to remain unaffected by the revised PMF surge elevation, with the exception of the Thermal Barrier Booster Pump Motors and Essential Raw Cooling Water (ERCW) equipment required for flood mode operation located on Elevation 722 of the Intake Pumping Station (IPS). The updated PMF of Elevation 739.2 could impact the ability of the thermal barrier booster pumps and the Elevation 722 IPS ERCW equipment to perform their design accident protection function. Because of the unanalyzed condition. the potential existed for WBN to exceed its PMF design basis and adversely affect plant safety.
"This notification is being made pursuant to 10 CFR 50.72(b)(3)(ii)(B).
"Compensatory measures have been prepared to install a temporary flood protection barrier around the thermal barrier booster pumps and provide additional protection of Elevation 722 of the IPS in the event of a flood alert.
"The potential for the increased PMF level and the associated compensatory measures were previously discussed in a public meeting between TVA and the NRC on May 31, 2012 and in correspondence between TVA and the NRC dated June 13, 2012 and June 25, 2012.
"All safety related equipment is currently operable. There are no indications of conditions that might result in a flood in the near term.
"The licensee notified the NRC Resident Inspector of this condition." |
| Fuel Cycle Facility | Event Number: 48057 | Facility: GLOBAL NUCLEAR FUEL - AMERICAS
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
LEU FABRICATION
LWR COMMERICAL FUEL
Region: 2
City: WILMINGTON State: NC
County: NEW HANOVER
License #: SNM-1097
Agreement: Y
Docket: 07001113
NRC Notified By: SCOTT MURRAY
HQ OPS Officer: JOE O'HARA | Notification Date: 06/29/2012
Notification Time: 14:00 [ET]
Event Date: 02/13/2012
Event Time: 09:20 [EDT]
Last Update Date: 06/29/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(2) - LOSS OR DEGRADED SAFETY ITEMS
| Person (Organization):
JONATHAN BARTLEY (R2DO)
MERAJ RAHIMI (NMSS)
| Event Text MASS CONTROL LIMIT EXCEEDED
"It was discovered on 2/13/12 that the mass control limit in the gadolinia pellet press operation was exceeded. An improperly installed valve allowed a total of 43 kg of uranium powder into the favorable geometry press feed tube, exceeding the 36 kg limit. This resulted in a failed item relied on for safety (IROFS) < 1 hour condition where a criticality control was not maintained. The press feed mass control is a sole IROFS for a fire accident sequence. Control indications functioned as designed and provided notification of the malfunction to the operator and the operation was secured. The other controls on geometry and moderation were maintained at all times.
"At no time was an unsafe condition present. The gadolinia pellet press operation was shut down and the powder was removed by 1000 on 2/13/2012.
"Additional corrective actions, extent of condition, and extent of cause have been documented.
"SAFETY SIGNIFICANCE OF EVENTS: At no time was an unsafe condition present
"SAFETY EQUIPMENT STATUS: Equipment was shut down and powder removed
"STATUS OF CORRECTIVE ACTIONS: Additional corrective actions, extent of condition, and extent of cause have been documented.
"This event is being communicated in order to administratively meet the reporting requirements of 10CFR70, Appendix A."
The licensee has spoken with Region 2 (Thomas) regarding this issue, and discussed the issue in a Reply to Notice of Violation dated 6/29/2012 letter book number SPM12-030. |
| Power Reactor | Event Number: 48059 | Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JOHN MACDONALD
HQ OPS Officer: JOE O'HARA | Notification Date: 06/29/2012
Notification Time: 21:15 [ET]
Event Date: 06/29/2012
Event Time: 17:46 [EDT]
Last Update Date: 06/29/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
ANNE DeFRANCISCO (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 OFFSITE NOTIFICATION DUE TO AN EMPLOYEE MEDICAL EMERGENCY
"On June 29, 2012, at 1746 EDT hours and the reactor at 100% core thermal power, the following informational statement was issued by Entergy Nuclear regarding a medical emergency involving a member of the Pilgrim Station Security Department.
"This afternoon, a security employee at Pilgrim Station who appeared to be in medical distress was immediately transported to the hospital for observation and professional medical care.
"The individual was observing and monitoring union picket line activities and was not filling a position required by the Pilgrim Station Security Plan.
"The Resident Inspector staff has been informed of this press release and notification.
"This notification is being made in accordance with 10 CFR 50.72(b)(2)(xi).
"The licensee will notify the Massachusetts Emergency Management Agency." |
| Power Reactor | Event Number: 48060 | Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BUD HINCKLEY
HQ OPS Officer: BILL HUFFMAN | Notification Date: 07/02/2012
Notification Time: 01:49 [ET]
Event Date: 07/02/2012
Event Time: 02:00 [EDT]
Last Update Date: 07/02/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
NICK VALOS (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text UNAVAILABILITY OF TSC VENTILATION SYSTEM DUE TO SCHEDULED MAINTENANCE
"At 02:00 EDT on Monday, July 2, 2012, the Cook Nuclear Plant (CNP) Technical Support Center (TSC) air conditioning and charcoal filtration systems will be removed from service for scheduled maintenance.
"Under certain accident conditions the TSC may become unavailable due to the inability of the air conditioning and charcoal filtration systems to maintain a habitable atmosphere. Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary.
"TSC ventilation system maintenance and post maintenance testing is scheduled to be completed by 15:00 EDT on Monday, July 2, 2012.
"The licensee has notified the NRC Resident Inspector.
"This notification is being made in accordance with 10 CFR 50.72 (b)(3)(xiii) due to the loss of an emergency response facility." | |