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Event Notification Report for November 10, 2008

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/07/2008 - 11/10/2008

** EVENT NUMBERS **


44543 44559 44628 44631 44637 44638 44640 44644 44645 44646 44647 44648
44649

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General Information or Other Event Number: 44543
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: FLINT HILLS RESOURCES LP
Region: 4
City: ODESSA State: TX
County:
License #: L00547
Agreement: Y
Docket:
NRC Notified By: BOB FREE
HQ OPS Officer: VINCE KLCO
Notification Date: 10/06/2008
Notification Time: 12:52 [ET]
Event Date: 10/06/2008
Event Time: [CDT]
Last Update Date: 11/07/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DALE POWERS (R4)
ANNA BRADFORD (FSME)

Event Text

TEXAS AGREEMENT STATE REPORT- SOURCE RETRACTOR FAILED TO FUNCTION

The following information was received from the State of Texas via e-mail:

"While servicing the level gauge [Ohmart Model A2102, Cs-137], an Ohmart technician discovered that the source retractor failed to function. The source is extended into a polymer vessel and is functioning normally while source is extended. Ohmart will recover the source and remove it from service. The licensee will arrange for disposal and discontinue use of the source."

Texas Report I-8570.

* * * UPDATE ON 11/7/2008 AT 1138 FROM ART TUCKER TO MARK ABRAMOVITZ * * *

This report from the state of Texas was received via e-mail:

"The licensee provided the Agency with a report on the investigation they conducted into the cause for the failure of the source to retract into the source holder on November 4, 2008. That report provided the following information.

"The gauge has been in place on the vessel since 1998. It appears that the source has not been retracted back into the source holder in a number of years. The source well is three feet deep and the total clearance between the source and the well wall is 0.322 inches.

"The source well is in a section of the vessel that contains a very thick, almost hardened, polymer material. The vessel was initially used to contain a polymer slurry, but the vessel's use was changed shortly after start up. This change resulted in the hardened polymer to form in the vessel. These actions all took place prior to the current owner taking possession of the facility.

"The licensee had tried to retract the source back into the source holder, but it only moved a distance of between 12 and 18 inches before it became stuck. The manufacturer's technician was able to move the source back to the end of the source well. This is the normal position for the source. It is believed that the weight of the polymer over the years has caused the well to bow to a point where it now limits the movement of the source.

"The licensee intends to remove and dispose of the source during a scheduled outage in 2009. The gauge is located at a height of 12 feet above grade. Dose rates taken at a height of 8 feet indicate a dose rate of 0.01 to 0.1 millirem per hour.

"Additional information regarding accessibility and occupancy of this area has been requested by the state."

Notified the R4DO (Campbell) and FSME (Suber).

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General Information or Other Event Number: 44559
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: WAL-MART
Region: 3
City: CINCINNATI State: OH
County:
License #: GL
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: JASON KOZAL
Notification Date: 10/10/2008
Notification Time: 17:40 [ET]
Event Date: 10/09/2008
Event Time: 13:45 [EDT]
Last Update Date: 11/07/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JULIO LARA (R3)
MARK DELLIGATTI (FSME)
ILTAB VIA EMAIL ()

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGNS

The following was provided by the state via e-mail:

"Wal-Mart Corporate Office reported a total of 8 tritium exit signs missing from various stores in Ohio. These signs were removed from service and were being held pending return to the manufacturer for disposal. The signs were discovered missing on or about October 8, 2008 at each store. Store management and maintenance personnel have conducted a search at each store and have determined that the signs are not on the premises. Wal-Mart is declaring these signs to be missing.

"Wal-Mart Corporate office notified the Ohio department of health by phone at approximately 1:45 PM on October 9, 2008, and followed with a written description of the signs on October 10, 2008."

The device information is as follows:

1. Location: Store number 01495 Huber Heights, Manufacturer - Isolite, Serial number - 272778, Curie content - 11.5.

2. Location: Store number 01724 Millersburg, Manufacturer - Isolite, Serial number - 260634, Curie content - 20.

3. Location: Store number 02441 Hamilton, Manufacturer - Isolite, Serial number - Unknown, Curie content - 11.5.

4. Location: Store number 02441 Hamilton, Manufacturer - Isolite, Serial number - 338664, Curie content - 11.5.

5. Location: Store number 02441 Hamilton, Manufacturer - Isolite, Serial number - 365140, Curie content - 11.5.

6. Location: Store number 03656 Cincinnati, Manufacturer - Isolite, Serial number - Unknown, Curie content - 11.5.

7. Location: Store number 03656 Cincinnati, Manufacturer - Isolite, Serial number - 362582, Curie content - 11.5.

8. Location: Store number 6327 Warren, Manufacturer - Isolite, Serial number - Unknown, Curie content - 11.5.

Ohio report number - OH080007

* * * UPDATE ON 11/7/2008 AT 1205 FROM MICHAEL SNEE TO MARK ABRAMOVITZ * * *

Received from the state of Ohio via e-mail:

A tritium exit sign was reported missing from the Wal-Mart store in Centerville, OH. The Isolite sign (S/N 318793) contained 11.5 Curies of tritium and was reported to Ohio at 1000 on 11/7/2008.

Ohio Report Number: OH080009

Notified R3DO (Cameron) and FSME (Suber).

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.

This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source

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General Information or Other Event Number: 44628
Rep Org: COLORADO DEPT OF HEALTH
Licensee: ROCKY MOUNTAIN CANCER CENTERS
Region: 4
City: DENVER State: CO
County:
License #: 1012-01
Agreement: Y
Docket:
NRC Notified By: ED STROUD
HQ OPS Officer: JASON KOZAL
Notification Date: 11/04/2008
Notification Time: 10:42 [ET]
Event Date: 11/04/2008
Event Time: [MST]
Last Update Date: 11/04/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
VIVIAN CAMPBELL (R4)
MICHELE BURGESS (FSME)

Event Text

AGREEMENT STATE - UNREPORTED FETAL OVEREXPOSURES

"During a routine inspection at Rocky Mountain Cancer Centers, Colorado License, two fetal overexposures were identified that had not been reported to the Department.

"The first case occurred on 8/23/05, and involved a PET/CT scan where the patient was injected with 16.3 mCi of FDG (F-18). After the procedure, the patient discovered she was pregnant. The fetal exposure was estimated to be 1.5 rem. The licensee determined the risk of congenital abnormalities to be negligible.

"The second case occurred on 11/28/06 and also involved a PET/CT scan where the patient was injected with 11.9 mCi of FDG (F-18). After the procedure, the patient discovered she was pregnant. The fetal exposure was estimated to be 1.02 rem. The licensee determined the risk of congenital abnormalities to be negligible.

"No other details are available at this time.

"Additional information will be reported through NMED as it becomes available."

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General Information or Other Event Number: 44631
Rep Org: COLORADO DEPT OF HEALTH
Licensee: EARTH ENGINEERING CONSULTANTS, INC.
Region: 4
City: WINDSOR State: CO
County:
License #: 867-01
Agreement: Y
Docket:
NRC Notified By: JAMES JARVIS
HQ OPS Officer: JASON KOZAL
Notification Date: 11/05/2008
Notification Time: 13:23 [ET]
Event Date: 11/04/2008
Event Time: 17:24 [MST]
Last Update Date: 11/05/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
VIVIAN CAMPBELL (R4)
GREG SUBER (FSME)
ILTAB VIA E-MAIL ()

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE - LOST TROXLER GAUGE

The following information was provided by the state via facsimile:

"The following information was reported to the Radiation Management Unit (RMU) of the Colorado Department of Public Health and Environment (CDPHE) by the acting RSO of a Colorado Licensee - Earth Engineering Consultants, Inc (EEC) - pertaining to a lost/stolen moisture density gauge.

"[On November 04, 2008] After taking a series of density tests of aggregate base course material for a new roadway on Jacoby Farms 5th Filing development project in Windsor, Colorado, (site location is on the north side of State Highway 392 and east 17th Street in Windsor, CO), the field technician placed gauge on his bumper, transferred the results onto his field paperwork, visited with the project supervisor and discussed the results, then entered his truck to complete additional paperwork, and received a call on his cell phone for his next project assignment. Time elapsed and the technician failed to secure the gauge back into the lock box within the pick-up truck. After realizing his dilemma, the technician immediately stopped the truck and began a search for the missing gauge. Phone calls were made to the project foreman, and an extensive search took place re-tracking the steps and paths taken. [The licensee] called the Health Department Radiation [Management Unit] and left several messages informing the state [of the missing Troxler].

"At approximately 11:45 AM on 11/5/08, CDPHE RMU followed up with the licensee via phone regarding the incident, at that time the licensee reported that he believed that the gauge had been recovered/found and had been dropped off at an area fire department by a member of the public last evening (11/4/08). The licensee indicated they were sending someone to the fire department to verify this and retrieve the gauge. The licensee indicated that the gauge was scratched but appeared to be intact and confirmed they would inspect the gauge and survey it. The licensee indicated that they would be sending the gauge to a local gauge repair company for leak testing and repair (as applicable). The CDPHE RMU is awaiting final confirmation/information from the licensee."

* * * UPDATE PROVIDED BY JAMES JARVIS TO JASON KOZAL VIA FAX ON 11/5/08 AT 1804 * * *

The following information was provided by the state via facsimile:

" At approximately 13:15 hours [MST on 11/5/08] the Radiation Management Unit (RMU) of the Colorado Department of Public Health and Environment (CDPHE) received confirmation that the moisture density gauge lost during the evening of 11/4/08 has been recovered and is now in possession of the licensee. The gauge and its radioactive materials were out of the licensee control for less than 24 hours. During a portion of the time the gauge was missing it was in the possession of a local fire department. The CDPHE RMU does not expect any impact to any members of the public as a result of the temporarily lost gauge due to the short duration of possession.

"Upon recovery, the licensee performed a visual inspection and radiological survey and has confirmed that the radioactive materials are present and intact. The gauge has been transferred to a local licensed gauge service provider where a leak test and through examination will be performed."

Notified the R4DO (Campbell), FSME (Suber), and ILTAB via e-mail.

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.

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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)

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.

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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)

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.

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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)

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.

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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)

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.

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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: 11/07/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
KENNETH RIEMER (R3)

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 horse power 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

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Power Reactor Event Number: 44646
Facility: HATCH
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: EDWIN URQUHART
HQ OPS Officer: JOE O'HARA
Notification Date: 11/08/2008
Notification Time: 09:06 [ET]
Event Date: 11/08/2008
Event Time: 08:35 [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):
MALCOLM WIDMANN (R2)

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

OSC INOPERABLE DUE TO PLANNED MAINTENANCE ON MOTOR CONTROL CENTER

"Planned maintenance activities are being performed today (November 8, 2008) on the Hatch Nuclear Plant's 1C 4160V Bus (1R22-S003) Frame 5 under work order number 1041640301. The planned work will remove power from 1R24-SO34 and 1R24-SPO60 which will affect the Unit 1 Service Building and Unit 2 Service Building Annex. This will deenergize power to the Primary Operations Support Center (OSC) rendering the OSC non-functional. (TRM - Section T 3.10.1 EMERGENCY RESPONSE FACILITIES) during the performance of this work activity.

"The specific work is to replace the breaker in frame 5 of 1C 4160V Bus (1R22-S-003) and perform routine preventative maintenance on 1R24-S034 and 2R24-S050 (Work Order # 1041641101) while they are de-energized to minimize future out of service time. This work activity is planned to be performed expeditiously and will be completed within 10 hours. If an emergency were to occur, it is estimated that power can be restored in approximately 1 hour. If an emergency condition occurs that requires activation of the OSC, the Alternate OSC in the Simulator Building will be used in accordance with plant procedure 73EP-EIP-021-0, Alternate Operations Support center (OSC) Activation, until power is restored.

"This event is reportable per 10CFR50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 1 since this work activity affects the emergency response facility."

The licensee notified the NRC Resident Inspector.

* * * UPDATE ON 11/8/2008 AT 1614 FROM EDWIN URQUHART TO MARK ABRAQMOVITZ * * *

At 1602 EST, power was restored to the OSC Motor Control Center.

Notified the R2DO (Widmann).

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Power Reactor Event Number: 44647
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: CURTIS DUNMORE
HQ OPS Officer: VINCE KLCO
Notification Date: 11/09/2008
Notification Time: 12:08 [ET]
Event Date: 11/09/2008
Event Time: 11:08 [EST]
Last Update Date: 11/09/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
MALCOLM WIDMANN (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 100 Power Operation 0 Hot Shutdown

Event Text

MANUAL REACTOR SCRAM DUE TO SPURIOUS SRV OPENING

"One hour reportable event based on a safety relief valve (SRV) failure to close (NUREG 0626 and NUREG 0660).

"On 11/09/08 at approximately 11:08 with Unit 2 at 100% steady state power SRV 2-B21-F013H spuriously failed full open with no operator action or testing in progress. The valve's control switch was cycled as required by Abnormal Operating Procedure AOP-30 with no success. At 1113 the valve was successfully closed by pulling the associated fuses. At 1117, a manual reactor scram was inserted based on a Torus temperature of 109.8 degrees F (Technical Specifications require a scram to be inserted at 110 degrees F). All control rods [fully] inserted from the manual scram signal. Reactor water level lowered to Low Level 2 resulting in Primary Containment Isolation System (PCIS) isolations of Groups 2, 3, 6, and 8. In addition, this resulted in a Reactor Core Isolation Cooling (RCIC) system actuation and injection into the reactor. The High Pressure Coolant Injection (HPCI) system actuated but did not inject because reactor water level recovered. An Alternate Rod Insertion signal was received, the Standby Gas Treatment (SBGT) system initiated, and the Reactor Recirculation Pumps tripped as designed.

"Plant safety systems responded as designed to the transient.

"[Licensee] investigations are underway to determine the cause of the SRV failure."

Reactor decay heat is being removed through the main turbine bypass valves to the condenser. Reactor make-up is being maintained by the normal feedwater system. The plant is in its normal shutdown electrical lineup supplied by offsite power. The diesel generators are available for service to the plant

The Licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 44648
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MIKE HENRY
HQ OPS Officer: VINCE KLCO
Notification Date: 11/09/2008
Notification Time: 20:44 [ET]
Event Date: 11/09/2008
Event Time: 15:30 [EST]
Last Update Date: 11/09/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MALCOLM WIDMANN (R2)

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

TECHNICAL SUPPORT CENTER HVAC OUT OF SERVICE

"The TSC Normal HVAC (A-1563-A7-001) and Normal Chilled Water Pump (A-1564-P7-001) tripped for unknown reasons after approximately 10 minutes of operation following restoration to normal from surveillance 14400A-1.

"This report is being made per Technical Requirements Manual 13.13.1, action B.2. With the TSC Normal HVAC and Chilled Water Pump inoperable, the Functionality of the TSC has been lost due to inability to maintain proper climate control. The alternate TSC facility is available and actions are being taken to return the TSC to Functional status with a high priority. The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 44649
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JULIOUS WHITWORTH
HQ OPS Officer: VINCE KLCO
Notification Date: 11/09/2008
Notification Time: 23:29 [ET]
Event Date: 11/09/2008
Event Time: 18:21 [EST]
Last Update Date: 11/09/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
MALCOLM WIDMANN (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R N 0 Hot Standby 0 Hot Standby

Event Text

REACTOR TRIP BREAKERS OPENED MANUALLY DUE TO INDICATED DROPPED CONTROL ROD

"On 11/19/08 at 1821 with unit 2 in Mode 3, the unit 2 reactor trip breakers were opened from the Main Control Room (MCR) due to indications of a Shutdown Bank "A" Rod E-11 dropping into the Reactor Core. At the time the reactor trip breakers were opened, the MCR Operators were in the process of withdrawing Shutdown Banks in preparations for entry into Mode 2. All other Shutdown Banks and Control Banks were inserted at the time the reactor trip breakers were opened. In addition, a Feedwater Isolation Signal was generated as designed. All safety related equipment operated as designed.

"The Plant is being maintained in Mode 3 at NOT/NOP, approximately 547 F and 2235 psig, with AFW supplying the S/G's and Steam Dumps to Main Condenser removing decay heat.

"No primary system or steam generator safety valves opened due to this trip.

"An investigation has been initiated to determine the cause of the indications of Shutdown Bank 'A' Rod E-11 dropping into the Reactor Core."

The licensee notified the NRC Resident Inspector.

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