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Event Notification Report for October 29, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/28/2010 - 10/29/2010

** EVENT NUMBERS **


46331 46361 46370 46372 46373 46374

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Power Reactor Event Number: 46331
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: JORGE RODRIGUEZ
HQ OPS Officer: HOWIE CROUCH
Notification Date: 10/14/2010
Notification Time: 13:18 [ET]
Event Date: 10/14/2010
Event Time: 09:15 [MST]
Last Update Date: 10/28/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MARK HAIRE (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
2 N Y 100 Power Operation 100 Power Operation
3 N N 0 Refueling 0 Refueling

Event Text

EMERGENCY SIRENS WILL BE TAKEN OUT OF SERVICE FOR PLANNED MAINTENANCE

"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.

"From October 14, 2010 to October 22, 2010, Palo Verde personnel will be performing maintenance on public prompt notification system sirens. Sirens will be removed from service one at a time, and then each will be restored prior to continuing to the next siren.

"Siren #36 provides notification to approximately 470 members of the public within five miles of Palo Verde.
"Siren #23 provides notification to approximately 614 members of the public within five miles of Palo Verde.
"Siren #25 provides notification to approximately 335 members of the public within five miles of Palo Verde.
"Siren #18 provides notification to approximately 586 members of the public within five miles of Palo Verde.
"Siren #15 provides notification to approximately 1133 members of the public within five to ten miles of Palo Verde.
"Siren #22 provides notification to approximately 1015 members of the public within five miles of Palo Verde.
"Siren #17 provides notification to approximately 1196 members of the public within five miles of Palo Verde.

"Each of these are considered by Palo Verde to be a 'large segment of the population.'

"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii). The Palo Verde Emergency Plan has a contingency for dispatching Maricopa County Sheriff's Office (MCSO) vehicles with loud speakers to alert persons within the affected area. The MCSO is prepared to implement this contingency should it become necessary.

"There are no events in progress that require siren operation. A follow-up call will be placed when the affected sirens are returned to service.

"The NRC Resident Inspector has been notified of the siren maintenance and this ENS call."

* * * UPDATE FROM JORGE RODRIGUEZ TO JOE O'HARA AT 1149 EDT ON 10/28/10 * * *

"Maintenance on the Palo Verde public prompt notification sirens listed on ENS #46331 has been completed. The sirens are operable and are back in service.

"The NRC Resident Inspector has been notified of the siren maintenance and this ENS call."

Notified R4DO (Proulx).

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General Information or Other Event Number: 46361
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: TICONA POLYMERS, INC.
Region: 4
City: BISHOP State: TX
County:
License #: L02441
Agreement: Y
Docket:
NRC Notified By: RAY JISHA
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/25/2010
Notification Time: 13:30 [ET]
Event Date: 10/24/2010
Event Time: [CDT]
Last Update Date: 10/25/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAVID PROULX (R4DO)
KEITH McCONNELL (FSME)

Event Text

SHUTTER FOUND PARTIALLY STUCK OPEN ON A FIXED NUCLEAR GAUGE

The following information was received from the State of Texas via email:

"On October 25, 2010, the licensee reported that while making preparations to perform plant maintenance, the shutter on a Ohmart Corporation model SH-F2-45 nuclear gauge containing 60 milliCuries (original activity) of Cesium (Cs)-137 was found to be stuck in a partially opened position. The licensee stated that they are going to shield the source to reduce the dose rate to below 2 millirem/hour, remove it form the vessel, and lock it in their Radioactive Material storage building. No significant exposure has occurred due to this event. The licensee has contacted the manufacture for repairs or replacement of the gauge. The cause for the event is under investigation. Additional information will be provided as it is received IAW SA 300."

Texas Incident #: I-8795

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Power Reactor Event Number: 46370
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: GLENDON BURNHAM
HQ OPS Officer: CHARLES TEAL
Notification Date: 10/28/2010
Notification Time: 07:59 [ET]
Event Date: 10/28/2010
Event Time: 07:59 [EDT]
Last Update Date: 10/28/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RICHARD SKOKOWSKI (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

EMERGENCY RESPONSE DATA SYSTEM (ERDS) OOS

"Beginning at approximately 0800 hours EDT on October 28, 2010, Perry Plant personnel will be taking the plant Integrated Computer System (ICS) out of service for planned maintenance. During the time ICS is out of service, the Safety Parameter Display System (SPDS), the Emergency Response Data System (ERDS), and the automatic mode calculation of the Computer Aided Dose Assessment Program (CADAP) will be unavailable. The computer outage is scheduled for six hours.

"In the event of an emergency, plant parameter data will be orally transmitted to the facilities through the Status Board Ring Down circuit with back-up [using] the Private Branch Exchange, Off-Premise Exchange, and various redundant intra-facility circuits throughout the emergency facilities. The dose assessment function will be maintained during the out of service time period by manual input of data into CADAP and, if required, by manual calculation. The ability to open and maintain an 'open line' using the Emergency Notification System will not be affected and will be the primary means of transferring plant data to the NRC as a contingency until the ERDS can be returned to service during the period of unavailability.

"This event is being reported in accordance with 10 CFR 50.72(b)(3)(xiii), as a condition that results in a major loss of offsite communications capability. A follow-up notification will be made when the maintenance activities are completed and the equipment is restored. The NRC Resident Inspector has been notified."

* * * UPDATE AT 1301 EDT ON 10/28/10 FROM GLENDON BURNHAM TO DONG PARK * * *

At 1100 EDT, the plant ICS has been returned to service and functioning normally.

The NRC Resident Inspector has been informed.

Notified R3DO (Skokowski).

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Power Reactor Event Number: 46372
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: MARK ZICKEFOOSE
HQ OPS Officer: JOHN KNOKE
Notification Date: 10/28/2010
Notification Time: 15:21 [ET]
Event Date: 10/28/2010
Event Time: 10:45 [CDT]
Last Update Date: 10/28/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
RICHARD SKOKOWSKI (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

STANDBY LIQUID CONTROL SYSTEM TEST TANK SEISMIC ANALYSIS FAULTY

"This report is being made pursuant to 10CFR50.72(b)(3)(v), Event or Condition that could have prevented fulfillment of a Safety Function. As part of a recent NRC Component Design Basis Inspection (CDBI), the seismic analysis of the Unit One and Unit Two Standby Liquid Control (SBLC) system test tanks was questioned. During the formal operability determination process initiated on 10/27/10, Engineering was verifying design data and calculations. During this review, on 10/28/10, Engineering determined that the historical calculation used the wrong formula in determining the test tank's natural frequency. The consequence is that if the test tank is filled with water, the possibility exists that the test tank could fall over or collapse during a seismic event and adversely affect adjacent safety-related items (i.e. SBLC). Calculations confirm that empty test tanks are seismically qualified.

"The SBLC test tanks on both units had been drained of water on 10/27/10 and thus both Unit One and Unit Two SBLC systems are fully operable at this time."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 46373
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: DONG HWA PARK
Notification Date: 10/27/2010
Notification Time: 16:25 [ET]
Event Date: 10/27/2010
Event Time: 11:07 [EDT]
Last Update Date: 10/28/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
72.75(c )(2) - SPENT FUEL, HLW OR RX-REL GTCC RED. EFECT
Person (Organization):
JOHN CARUSO (R1DO)
JOHN THORP (NRR)
RAYMOND LORSON (NMSS)
JEFFERY GRANT (IRD)

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

SPENT FUEL STORAGE RELATED DEFECT - CASK LEAKAGE RATE GREATER THAN TECHNICAL SPECIFICATION

"On 10/27/10, at 1107 [EDT], troubleshooting of Independent Spent Fuel Storage Installation (ISFSI) Cask TN-68-01 identified that a helium leak exists in the cask lid sealing area at a leak rate greater than allowed by ISFSI Cask Technical Specification Section 3.1.3, Cask Helium Leak Rate. TS 3.1.3 limits the Cask Helium Leak Rate to 1.0 E-O5 ref-cc/sec. The cask was in LOADING OPERATIONS and is currently located within the [Peach Bottom Atomic Power Station] PBAPS Unit 2 containment building. Preliminary review indicates that a leak exists in the Cask Main Lid Outer Closure Seal. The cask will be repaired and tested prior to returning the cask to the Independent Spent Fuel Storage Installation (ISFSI). No release of radiation occurred as a result of this issue.

"This report is being submitted pursuant to 10CFR 72.75(c)(2) as a result of a reduction in the effectiveness of the cask confinement system.

"The Certificate of Compliance for this cask is 1027 (Amendment 0)."

The NRC Resident Inspector has been informed.

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Power Reactor Event Number: 46374
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: TIM PRY
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/28/2010
Notification Time: 20:25 [ET]
Event Date: 10/28/2010
Event Time: 17:51 [EDT]
Last Update Date: 10/28/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
OTHER UNSPEC REQMNT
Person (Organization):
RICHARD SKOKOWSKI (R3DO)
ANTHONY PARSONS (DOE)
JACQUELINE ARSENAULT (EPA)
DAVID TIMMONS (USDA)
JOEL RICHARDSON (HHS)
DENNIS VIA (FEMA)

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 SODIUM HYPOCHLORITE LEAK FROM UNDERGROUND PIPING

"On October 28, 2010, at 1740 hours, the plant entered the Off-Normal Instruction for spills and unauthorized discharges. At 1751 hours, notification of a sodium hypochlorite spill was made to the U.S. Environmental Protection Agency (EPA), National Response Center. At the time of the event, the plant was in Mode 1 at 100% power. The sodium hypochlorite spill is believed to be the result of a leak in an underground piping supply line to the Emergency Service Water pump house. The leak is estimated to be approximately 130 gallons of a 12.5% Sodium Hypochlorite (Bleach) solution (80 gallons in a 24 hour period is the reportable quantity). The associated chlorination systems have been isolated, and current storage tank level is stable, indicating no more leakage in progress.

"Additionally, the Ohio EPA: State Emergency Response Commission, Perry Township Fire Department, Lake County Emergency Planning Committee, and the U.S. Coast Guard were notified in accordance with plant procedures. This event is also being reported in accordance with the Operating License, Appendix B, Environment Protection Plan, which states in part, 'Any occurrence of an unusual or important event that indicates or could result in significant environmental impact causally related to plant operation shall be recorded and reported to the NRC within 24 hours followed by a written report ..' Specifically, ' ..unanticipated or emergency discharge of waste water or chemical substances.' The NRC Resident Inspector has been notified."

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