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Event Notification Report for November 07, 2008

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
11/06/2008 - 11/07/2008

EVENT NUMBERS
44638446394464044643446444464544637

Power Reactor
Event Number: 44638
Facility: OCONEE
Region: 2     State: SC
Unit: [] [] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: GRAHAM DAVENPORT
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/07/2008
Notification Time: 12:05 [ET]
Event Date: 11/07/2008
Event Time: 08:34 [EST]
Last Update Date: 11/07/2008
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):
MALCOLM WIDMANN (R2)
ANTHONY McMURTRAY (IRD)
JOHN THORP (NRR)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
3 A/R Y 100 Power Operation 0 Hot Standby
Event Text
AUTOMATIC REACTOR TRIP

"At 0834 on 11-7-08, Oconee Nuclear Station (ONS) Unit 3 experienced an automatic reactor trip due to a reactor protective systems (RPS) actuation. ONS Unit 3 post trip parameters are normal. Main Feedwater remained in service following the event and Emergency Feedwater was not required and remained available. Electrical power automatically transferred to the Startup power source from the switchyard and emergency AC power sources were not required and remained available. The cause of the RPS actuation and automatic reactor trip are under investigation.

"ONS Unit 1 remained at 100% power with no issues following the ONS Unit 3 reactor trip. ONS Unit 2 remained in No-Mode. No other safety systems have actuated or exhibited abnormal behavior. Therefore, the safety significance of this condition is low."

All control rods fully inserted during this event. The unit is removing decay heat to the main condenser. No primary relief valves lifted and Main Steam relief valves cycled following the trip. There are no Steam Generator tube leaks.

The licensee notified the NRC Resident Inspector.


General Information or Other
Event Number: 44639
Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: GSG MATERIAL TESTING
Region: 3
City: CHICAGO   State: IL
County:
License #: IL-02340-01
Agreement: Y
Docket:
NRC Notified By: DAREN PERRERO
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/07/2008
Notification Time: 14:21 [ET]
Event Date: 11/07/2008
Event Time: 07:00 [CST]
Last Update Date: 11/07/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
JAMNES CAMERON (R3)
GREG SUBER (FSME)
ILTAB (E-MAIL)
Event Text
AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE

"On November 7, at 7:00 AM the Illinois Emergency Management Agency's Communications Center contacted our [Illinois Emergency Mgmt. Agency] Radiation Duty Officer to advise they had been told of a theft of radioactive material. The report was filed by the Radiation Safety Officer of GSG Material Testing Inc. A portable moisture density gauge had been stolen from their temporary worksite in Chicago during the night. The Troxler model 3430 (s/n 35592) had been forcibly removed from a construction trailer at 704 West 42nd Street, Chicago, IL. The gauge contains two sources; 9 milliCi Cs-137and 40 milliCi Am-241:Be. The call to the IEMA Comm Ctr came from the licensee's Radiation Safety Officer [DELETED]. The gauge was last seen in the trailer yesterday at the close of business. The Chicago Police Department was contacted and had arrived at the scene to complete a report. Evidence at the scene indicated thieves had entered by bending bars which were over a window and then breaking the glass. They had ransacked the trailer looking for items of worth. They broke the lock on the transport container which held the gauge and then removed the gauge from the trailer. The licensee indicated that, contrary to instructions, the field technician assigned the gauge had left the device in the trailer. The RSO also indicated that during today's police interview, they were advised that the trailer had a previous break-in a few months prior, of which they were unaware. The Agency [Illinois Emergency Mgmt. Agency] is awaiting additional information from the licensee before potentially taking enforcement action. A reactive inspection may be justified. We [Illinois Emergency Mgmt. Agency] are considering this matter open."

Illinois Report Number: IL0800065

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks.


Power Reactor
Event Number: 44640
Facility: SEQUOYAH
Region: 2     State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT BROWN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/07/2008
Notification Time: 15:24 [ET]
Event Date: 11/07/2008
Event Time: 13:37 [EST]
Last Update Date: 11/07/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
MALCOLM WIDMANN (R2)
Power Reactor Unit Info
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 Hot Shutdown 0 Hot Shutdown
Event Text
FITNESS FOR DUTY

A licensed employee supervisor had a confirmed positive for illegal drugs during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.


General Information or Other
Event Number: 44643
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: GEOTECHNICAL CONSULTANTS
Region: 1
City: HUBBARDSTON   State: MA
County:
License #: 48-0334
Agreement: Y
Docket:
NRC Notified By: JOHN SUMARES
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/07/2008
Notification Time: 15:36 [ET]
Event Date: 11/07/2008
Event Time: 09:00 [EST]
Last Update Date: 11/07/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
SAM HANSELL (R1)
GREG SUBER (FSME)
ILTAB (e-mail)
Event Text
AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE

The following report was transmitted by the state via facsimile:

"Licensee called the Agency [Massachusetts] to report a stolen Troxler gauge, model # 3440 and serial # 21550. Gauge user had the locked transport case and the locked gauge stored inside a personal vehicle for the purpose of driving to a work site scheduled for 11/7/08. The vehicle was parked in Hubbardston, MA overnight (11/6 - 11/7/08). In the morning of 11/7/08, it was discovered that the personal vehicle had been broken into and the transport case and gauge was missing and presumed stolen. Other personal vehicles in the local area also had been broken into on the same night."

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks.


Power Reactor
Event Number: 44644
Facility: PEACH BOTTOM
Region: 1     State: PA
Unit: [2] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: LARRY SLOAN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/07/2008
Notification Time: 18:01 [ET]
Event Date: 11/07/2008
Event Time: 18:00 [EST]
Last Update Date: 11/08/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
SAM HANSELL (R1)
Power Reactor Unit Info
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
PLANNED LOSS OF EMERGENCY PHONE SERVICE

"The Emergency Notification System (ENS), Emergency Response Data System (ERDS), Health Physics Network (HPN), Protective Measures Counterpart Link (PMCL), Reactor Safety Counterpart Link (RSCL), and site commercial telephone lines are being removed from service for a planned maintenance outage. The outage is scheduled for duration of 12 hours. The plant radio system, plant page system and 3-digit OMNI phone system are unaffected by the maintenance.

"Temporary telephone lines have been assigned to the Peach Bottom Emergency Telephone System (ETS) to support station communications to and from the NRC. The ENS and ERDS lines in the Peach Bottom MCR and TSC and the HPN, RSCL and PMCL in the TSC will all have off-site dial capability throughout the outage. The NRC HOO has been provided the temporary numbers to be used to contact the station during this phone outage.

"This is an 8-hour reportable event per 10 CFR 50.72(b)(3)(xiii) Major Loss of Assessment Capability. The operation of plant systems will not be affected due to this planned action.

"The licensee has informed the NRC Resident Inspector."

* * * UPDATE FROM C.J.CAMPBELL TO JOE O'HARA AT 0211 ON 11/8/08 * * *

"As of midnight, the maintenance is complete, and the phone service has been returned to service. "

The licensee will notify the NRC Resident Inspector.


!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 44645
Facility: PALISADES
Region: 3     State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: BRUCE BAUER
HQ OPS Officer: JOHN KNOKE
Notification Date: 11/07/2008
Notification Time: 22:00 [ET]
Event Date: 11/07/2008
Event Time: 14:41 [EST]
Last Update Date: 12/30/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
KENNETH RIEMER (R3)
Power Reactor Unit Info
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
LOAD CALULATIONS FOR EDG WERE INCORRECT

"During a review it was determined that the Diesel Generator load calculation (EA-ELEC-LDTAB-005) did not account for worst case load from the Containment Air Cooler Fan Motors (V-1A, V-2A, V-3A). Initial review indicates that with the worst case fan motor loading, Diesel Generator 1-2 could be loaded beyond its 2 hour rating following a Loss of Coolant Accident (LOCA) during the time period prior to Recirculation Actuation (RAS).

"The horsepower loading for the motors used in the Diesel Generator load calculation was based on the original specification for the motors. In 1993 calculation EA-DPAL93-110 was done to determine the impact of partial flooding of the air coolers coils on the cooling fan performance. The 1993 calculation calculated a fan motor load that was higher than what is used in the diesel generator load calculation. However, the diesel generator load calculation was not updated as a result of the 1993 calculation.

"The higher motor power requirement is 17 kW per fan. There are 3 Containment Air Cooler fans loaded on Diesel Generator 1-2. The extra loading, when combined with the possible additional load from operating the diesel generator at increased frequency, raises the calculated load to 2782 kW, which is above the 2 hour rating of 2750 kW. The overload only applies during a time segment of the diesel generator load profile prior to RAS. This could result in the loss of the diesel generator.

"There is only 1 Containment Air Cooler Fan Motor (V4A) loaded on Diesel Generator 1-1 and has 121 kW margin available. Therefore, there is no concern about overloading Diesel Generator 1-1.

"Placed hand switches (42-299CS & 42-277CS) for Turbine Generator Emergency Air Side Seal Oil Backup Pump (P-23) and Turbine Turning Gear Oil Pump (P-26) in Pull-To-Lock position, which prevents the pumps from automatically starting. This reduces the potential load on 1-2 D/G by 71 kW. This restores the load on the diesel to within the margin."

Licensee has notified the NRC Resident Inspector

* * * RETRACTION AT 1416 EST ON 12/30/08 FROM DAVIS TO HUFFMAN * * *

"Entergy Nuclear Operations Inc. (ENO) is retracting Event Notification EN #44645 which reported a loss of a safety function due to the 1-2 emergency diesel generator (EDG) load calculation not accounting for the worst-case load from the containment air cooler fan motors. The initial review indicated that, with the worst-case fan motor loading, the 1-2 EDG could have been loaded beyond the 2750 kW two-hour peak loading limits following a loss-of-coolant accident during the time period prior to a recirculation actuation signal. This condition may have caused 1-2 EDG to become inoperable, and could have prevented fulfillment of a safety function.

"In a subsequent evaluation of loading capability, completed on December 18, 2008, ENO determined the 1-2 EDG was operable. The EDGs are rated for 2750 kW two-hour peak operation. It was determined that the postulated peak load for the 1-2 EDG would have been 2819 kW for a period of approximately thirty-eight minutes. However, based on engineering information obtained from the vendor of the 1-2 EDG, Fairbanks-Morris Engine, and reviewed by ENO, the 1-2 EDG could have been operated up to 2830 kW for fifty minutes before any susceptibility to damage might occur. In addition, under the peak loading condition of 2819 kW, the speed of the 1-2 EDG would have remained above the Technical Specification limit of 59.5 Hz. The subsequent review confirmed that the safety function would have been fulfilled. Therefore, ENO is retracting this event notification."

The licensee has notified the NRC Resident Inspector. R3DO (Cameron) notified.


Power Reactor
Event Number: 44637
Facility: SALEM
Region: 1     State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GARY MEEKINS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 11/07/2008
Notification Time: 11:31 [ET]
Event Date: 11/07/2008
Event Time: 09:55 [EST]
Last Update Date: 11/07/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
SAM HANSELL (R1)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Hot Shutdown 0 Hot Shutdown
Event Text
DISCHARGE OF BIODEGRADABLE OIL INTO INTAKE BAY

"Observation of discharge of Terasolve 146 biodegradable fish oil into the Delaware river at the 11B Circulating Water Pump intake bay. The discharge was from a dewatering pump leak that was stopped. The fish oil has dissipated. The amount was 2 - 3 oz."

The licensee has notified the NRC Resident Inspector.

The licensee will notify Lower Alloways Creek Township.

R1DO (Hansell) notified.