Event Notification Report for July 21, 2011

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/20/2011 - 07/21/2011

** EVENT NUMBERS **


46994 47055 47057 47058 47059 47062 47068 47076 47077 47078 47079 47080
47081

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Agreement State Event Number: 46994
Rep Org: NEW YORK STATE DEPT. OF HEALTH
Licensee: FAIRWAY TESTING
Region: 1
City: STONY POINT State: NY
County:
License #: NYS C2322
Agreement: Y
Docket:
NRC Notified By: ROBERT SNYDER
HQ OPS Officer: PETE SNYDER
Notification Date: 06/27/2011
Notification Time: 15:50 [ET]
Event Date: 06/26/2011
Event Time: [EDT]
Last Update Date: 07/20/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
BLAKE WELLING (R1DO)
JIM LUEHMAN (FSME)
CANADA (FAX)

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

Event Text

AGREEMENT STATE REPORT - STOLEN PORTABLE MOISTURE DENSITY GAUGE

The following was received via fax:

"Fairway Testing Co. license no. C2322, called 6/27/11 to report that a Troxler model 3411 s/n 4363 portable density gauge was stolen from a company vehicle on Sunday, June 26. The device contained 8 mCi Cesium 137 and 40 mCi of Americium 241/Beryllium.

"The employee worked late on Friday, June 24 and did not have access to the permanent storage location since the building is locked after 5:00 p.m. The driver took the vehicle to his residence on Brookside Drive in Stony Point, Rockland County and parked it in his driveway. The device was in its transport container, which was doubly chained to the bed of the pickup truck.

"On Sunday morning, the employee observed that the container was still in the bed of the pickup before he left his residence for the day in a family vehicle. When he came home that night he did not check the vehicle.

"On Monday morning, he realized that both chains were cut and the transport box along with the device was stolen. Other items were also stolen from the vehicle which leads to speculation that the perpetrators were not specifically after the density gauge.

"The local police were notified and a police report has been initiated. The licensee has thirty days to send a written response and to notify the NYS DOH (New York State Department of Health) of any substantial development in the case."

NY State Event #: NY-11-11

* * * * UPDATED AT 1431 EDT ON 7/20/11 BY S. SANDIN * * * *

The following update was received from NY DOH via fax:

"On 7/5/11, DOH was notified via fax that a load of scrap metal tripped the alarm at Gerdau Ameristeel in Sayreville, NJ. The load was returned to the originator (Teplitz in Nanuet, NY) and then to Orange County Metal recycling (OCMR) in Middletown, NY. OCMR staff identified, isolated and secured the source of the trip and contracted Co-Physics to characterize. In cooperation with DOH, Co-Physics contacted Troxler with model and serial numbers from the item and identified it as the cesium source from the stolen gauge. Fairway Testing and Stony Point Police have been notified.

"Fairway Testing is aware of its responsibility for proper disposition of the source.

"The Am-Be source is still unaccounted for. A search of Teplitz is underway.

"No Reward offered. No Press Release issued."

Notified R1DO (Dentel), FSME (White) and Canada via fax.


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. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

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Agreement State Event Number: 47055
Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: CHIPPENHAM / JOHNSTON WILLIS HOSPITALS, INC.
Region: 1
City: RICHMOND State: VA
County: CHESTERFIELD
License #: 041-058-1
Agreement: Y
Docket:
NRC Notified By: MICHAEL WELLING
HQ OPS Officer: DONALD NORWOOD
Notification Date: 07/15/2011
Notification Time: 12:06 [ET]
Event Date: 06/22/2011
Event Time: 16:34 [EDT]
Last Update Date: 07/15/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES DWYER (R1DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - CONTAMINATED PATIENT / PATIENT ROOM

The following information was received via facsimile:

"On Wednesday, June 22, 2011 at 1634 EDT, an admitted patient was given a 182 mCi I-131 capsule for a thyroid ablation study. At approximately 0330 EDT on Thursday, June 23, 2011, the patient vomited onto herself and the floor. The nursing staff cleaned up the patient and the floor and then notified the Nuclear Medicine Department (NMD). NMD staff began to perform surveys of the patient and the room and found contamination. Further cleaning of the patient and room was performed. The patient was released on Saturday, June 26, 2011. The room was sealed off to allow the I-131 contamination to decay below regulatory limits. The room remains restricted. NMD staff are performing contamination surveys."

Virginian Report Number: VA-11-04

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Agreement State Event Number: 47057
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: LEHIGH VALLEY HEALTH NETWORK
Region: 1
City:  State: PA
County:
License #: PA-0232
Agreement: Y
Docket:
NRC Notified By: DAVID ALLARD
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/15/2011
Notification Time: 11:33 [ET]
Event Date: 07/12/2011
Event Time: [EDT]
Last Update Date: 07/15/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES DWYER (R1DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - MEDICAL EVENT INVOLVING TREATMENT DOSE ADMINISTERED TO WRONG SITE

The following event report was received from the Pennsylvania Bureau of Radiation Protection:

"The licensee called the PA Department of Environment Protection (PaDEP) Southeast Regional Office at 1050 EDT on July 14, 2011 to provide a 24-hour verbal notice of a Medical Event (ME). A total treatment dose was administered to the wrong site, consequently requiring a 24-hour report per 10 CFR 35.3045(a)(3). This event also meets the criteria for Abnormal Occurrence (AO) reporting.

"On July 12, 2011 a Yttrium-90 (Y-90) SIR-Sphere treatment was performed. The written directive was for treatment of the liver's right lobe, but the total treatment was delivered to the left lobe. The prescribed dose was 31.5 millicurie (mCi) of Y-90.

"There are several open questions regarding root cause, potential health impact on the patient and communications to the patient and their physician. PaDEP/BRP will be performing a reactive inspection, which is scheduled for Monday July 18, 2011. Updates to this NRC report will be made once we investigate the ME at Lehigh Valley Health Network and obtain the follow-up written report from the licensee."

PA report Number: PA110016

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.

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Agreement State Event Number: 47058
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: SHERWIN ALUMINA COMPANY
Region: 4
City: CORPUS CHRISTI State: TX
County:
License #: 00200
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/15/2011
Notification Time: 14:28 [ET]
Event Date: 07/15/2011
Event Time: [CDT]
Last Update Date: 07/15/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHUCK CAIN (R4DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - LOOSE SHUTTER ON PROCESS GAUGE

The following information was received via email from the State of Texas Health Services Radiation Branch:

"On July 15, 2011, the agency [Texas Department of Health] received an e-mail from the licensee's Radiation Safety Officer stating that during a routine inspection, the shutter on a Kay-Ray model 7062P nuclear gauge containing 100 millicuries of cesium - 137 (serial # KR 22151V) was loose and did not completely shield the source. The RSO stated that open is the normal operating condition for the gauge and that it did not create any additional exposure risk to any individual. The RSO stated that he was going to contact a vendor for repairs or replacement of the gauges. Additional information will be provided as it is received in accordance with SA-300."

Texas Report ID: I-8869

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Agreement State Event Number: 47059
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: SHERWIN ALUMINA COMPANY
Region: 4
City: CORPUS CHRISTI State: TX
County:
License #: 00200
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/15/2011
Notification Time: 14:22 [ET]
Event Date: 07/15/2011
Event Time: 08:00 [CDT]
Last Update Date: 07/15/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHUCK CAIN (R4DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - PROCESS GAUGE SHUTTER STUCK OPEN

The following information was received from the State of Texas Health Services Radiation Branch:

On July 15, 2011, the agency [Texas Department of Health] received an e-mail from the licensee's Radiation Safety Officer stating that during a routine inspection, the shutter of a Texas Nuclear model 5176 nuclear gauge containing 500 millicuries cesium - 137 (serial # B2623) was stuck in the open position. The RSO stated that open is the normal operating condition for the gauge and that it did not create any additional radiation exposure risk to any individual. The RSO stated that he was going to contact a vendor for repairs or replacement of the gauges. Additional information will be provided as it is received in accordance with SA-300.

Texas Incident # I-8870

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Agreement State Event Number: 47062
Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: ARCOS ENVIRONMENTAL SERVICES
Region: 3
City: TINLEY PARK State: IL
County:
License #: 9223740
Agreement: Y
Docket:
NRC Notified By: DARREN PERRERO
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/15/2011
Notification Time: 15:22 [ET]
Event Date: 07/13/2011
Event Time: [CDT]
Last Update Date: 07/15/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
TAMARA BLOOMER (R3DO)
ROBERT LEWIS (FSME)
ILTAB VIA E-MAIL ()

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

Event Text

AGREEMENT STATE REPORT - THEFT OF AN X-RAY FLUORESCENCE ANALYZER

The following report was received from the Radioactive Materials Section of the Illinois Emergency Management Agency:

"[Arcos Environmental] a General Licensee, called the agency [Illinois Emergency Management Agency (IEMA)] to advise that a x-ray fluorescence analyzer [containing a 5 millicurie Cd-109 source] for measuring lead content of paint was stolen from a locked vehicle while at a temporary jobsite. The device along with several other items was removed from the car's trunk while it was parked at 6020 S. Langley Ave., Chicago, IL. At the time of the theft, the responsible user was in a building performing other duties. The theft was promptly reported to the Chicago Police Department. The general licensee is considering a news paper ad to encourage return of the device to its Tinley Park offices.

"Use of the device requires a 'pass code' to activate the device's features and allow exposure of the radioactive source by the opening of an internal shutter. The pass code is maintained separate from the device. In addition, 6 years after the source has been installed, the device will no longer operate and a display message directs that the device be returned to the manufacturer. This device was initially sourced in Sept of 2007.

"The maximum surface dose rate from the device is less than 100 microR/h when the shutter is closed. Based on the SSDR safety evaluation the maximum exposure rate, should the safety and security features be defeated and the shutter opened, would be 3 milliR/h. As a result, the potential radiation exposure to the thief or any member of the public is projected to be extremely low.

"The general licensee has been advised of the requirement to file a written report within 30 days of the theft. The agency [IEMA] does not intend to conduct an on-site investigation unless additional information or circumstances change which warrant a visit."

Illinois Report Number: IL11086


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. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

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Agreement State Event Number: 47068
Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: DAN RIVER INC.
Region:
City: DANVILLE State:
County: PITTSYLVANIA
License #: GENERAL
Agreement: N
Docket:
NRC Notified By: MICHAEL WELLING
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/18/2011
Notification Time: 16:30 [ET]
Event Date: 07/14/2011
Event Time: 12:00 [EST]
Last Update Date: 07/18/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GLENN DENTEL (R1DO)
ROBERT LEWIS (FSME)
ILTAB VIA E-MAIL ()

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

Event Text

AGREEMENT STATE - SOURCE DISCOVERED IN SCRAP SHIPMENT - TWO OTHERS STILL MISSING

"On Thursday July 14 a scrap dealer contacted the Virginia Radioactive Materials Program (VRMP) indicating a load of steel had set off their alarm. The scrap yard was able to identify the material that set off the alarm and isolate. On Friday July 15 VRMP staff went to the scrap yard to perform surveys and identify the material in question. The investigation determined that the material had come from the demolishing site of Dan River, Inc, a former textile business that closed in 2008. The gauge was determined to contain Kr-85 utilizing a radionuclide identifier and the GL database, which lists three Mahlo Controls Kr-85 gauges being possessed by Dan River, Inc. The VRMP continues to work with the scrap yard and demolishing company looking for the other two gauges. VRMP is also working with Mahlo Controls in researching the three gauges in question."

The sources in these generally licensed devices were originally 100 milliCuries each. It is estimated that they have decayed three half-lives and the current strength is estimated at approximately 13 milliCuries each.



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. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

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Power Reactor Event Number: 47076
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: MARK JENKINS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/20/2011
Notification Time: 16:06 [ET]
Event Date: 07/20/2011
Event Time: 13:15 [CDT]
Last Update Date: 07/20/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
VIVIAN CAMPBELL (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

FIRE PROTECTION PROGRAM CONCERN

"On July 20, 2011 at 1315 hours it was determined that a design deficiency at the Wolf Creek Nuclear Operating Corporation (WCNOC) constituted a fire protection program concern which could adversely affect the ability to achieve and maintain safe shutdown in the event of a control room fire. In the event of a postulated control room fire, a normally closed valve (EFHV0060) on the Essential Service Water (ESW) system return from the Component Cooling Water (CCW) heat exchanger could spuriously open. If this occurs, the flow balance in the ESW system would be affected and cooling flow to other essential components could be reduced to below the minimum required flow.

"Present system operability is not affected as there has been no occurrence of a fire in the Control Room and compensatory actions are in place to detect and mitigate the effects of a fire in the Control Room. An hourly fire watch is currently in place in the control room and will remain in place until this issue is resolved. In addition to the hourly fire watch, alternate shutdown procedure OFN RP-017 is being revised to include interim compensatory actions to deenergize, and verify closed, valve EFHV0060.

"This event is being reported in accordance with 10 CFR 50.72 (b)(3)(ii)(B) and 10 CFR 50.72 (b)(3)(v)(A) as an unanalyzed condition that significantly degrades plant safety. A follow-up licensee event report will be made in 60 days.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 47077
Facility: SURRY
Region: 2 State: VA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: SCOTT G. BRAY
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/20/2011
Notification Time: 16:50 [ET]
Event Date: 06/05/2011
Event Time: 05:01 [EDT]
Last Update Date: 07/20/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
MARVIN SYKES (R2DO)
ROBERT NELSON (NRR)
SCOTT MORRIS (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

Event Text

DISCOVERY OF AFTER-THE-FACT EMERGENCY CONDITION - UNUSUAL EVENT

"At 1650 [EDT] on 7/20/2011 it was determined that a Notification of Unusual Event (NOUE) was not declared for an event on 6/5/2011. The event occurred at 0501 [EDT] on 6/5/2011 when a low oxygen atmosphere condition was measured in the Unit 2 reactor containment building. The NOUE should have been declared in accordance with Surry Power Station Emergency Action Level HU3.1 (Report or detection of toxic, corrosive, asphyxiant, or flammable gases that have or could enter the Owner Controlled Area in amounts that can affect normal plant operations). This condition occurred during a refueling outage with maintenance being performed using a liquid nitrogen supplied freeze seal. The freeze seal activity released nitrogen, which slowly caused the low oxygen atmosphere (<19.5%).

"In accordance with guidance provided in NUREG-1022, a one hour ENS notification is being made due to discovery of an undeclared condition that exceeded an Emergency Action Level."

The licensee will inform Surry County, the State of Virginia and has informed the NRC Resident Inspector.

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Power Reactor Event Number: 47078
Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WARREN MOORE
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/20/2011
Notification Time: 17:30 [ET]
Event Date: 07/20/2011
Event Time: 15:55 [EDT]
Last Update Date: 07/20/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MARVIN SYKES (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

Event Text

OFFSITE NOTIFICATION TO THE NORTH CAROLINA WILDLIFE RESOURCES COMMISSION

"Duke Energy Scientific Services group representative notified the NC Wildlife Resources Commission at 1555 hours that MNS was operating their LLI Pumps to maintain discharge temperatures within the NPDES permit average monthly temperature limit.

"Based on the elevated lake temperatures, action to align circulating water to the LLI (cooler water) is necessary to prevent exceeding discharge temperature limits. Operation of the LLI pumps is sometimes needed during this time of year to comply with the water permit. Substantial effort is taken to avoid this alignment due to the potential to accelerate the natural phenomenon of oxygen depletion in the lower depths of Lake Norman that occurs as water temperature increases. The normal seasonal oxygen level changes can stress the fish population in that depth of the lake.

"During the operation of the LLI pumps, Duke Energy's Scientific Services group monitors water quality and fish in the lake via the following activities,

1) Hydro acoustic surveys of the Cowan's Ford Dam fore-bay both immediate to the dam and also an approximate 2 mile run up the Catawba River channel.
2) Monitoring of fish behavior in the immediate vicinity of the LLI. A DIDSON camera sits atop the LLI (25 meter deep).
3) Water quality monitoring including dissolved oxygen and temperature profiles at every meter to the bottom of the lake. These profiles occur in the fore-bay and at multiple locations up the channel.
4) Hourly MNS discharge temperature monitoring.

"These activities will continue to be exercised until the LLI pumps are turned off or the natural cycle of oxygen depletion has ended.

"The licensee notified the NRC Resident Inspector."

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Power Reactor Event Number: 47079
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAVE BAHNER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/20/2011
Notification Time: 20:10 [ET]
Event Date: 07/20/2011
Event Time: 13:18 [PDT]
Last Update Date: 07/20/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
VIVIAN CAMPBELL (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

OFFSITE NOTIFICATION - PRESS RELEASE AFTER FIRE ON SITE

"On July 20, 2011 at 1318 PDT, during performance of STP M-9A, 'Diesel Engine Generator Routine Surveillance Test,' personnel reported a fire on the Unit 1 Emergency Diesel Generator (EDG) 1-1. No abnormal indications were observed in the control room and no annunciator for 'Fire Detected' was received. Operators shutdown the EDG and the onsite fire department responded immediately.

"On July 20, 2011 at 1322 PDT, personnel reported that the fire, which was centered around the exhaust insulation material, had been extinguished.

"EDG 1-1 is in a scheduled Maintenance Outage Window (MOW) and is not being relied on for emergency onsite power. The two sources of offsite power (the 230 kV startup system and the 500 kV system) along with the remaining two EDGs, are available and operable.

"Unit 2 was not affected by the event.

"The NRC Resident Inspector has been notified."

A press release will be issued by the licensee.

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Power Reactor Event Number: 47080
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: COREY GRAY
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/20/2011
Notification Time: 20:45 [ET]
Event Date: 07/20/2011
Event Time: 11:47 [EDT]
Last Update Date: 07/20/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
MARVIN SYKES (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

FITNESS-FOR-DUTY REPORT INVOLVING A CONTRACTOR SUPERVISOR

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

The licensee informed the NRC Resident Inspector.

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Power Reactor Event Number: 47081
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MATT LOVITT
HQ OPS Officer: CHARLES TEAL
Notification Date: 07/21/2011
Notification Time: 00:53 [ET]
Event Date: 07/20/2011
Event Time: 21:29 [EDT]
Last Update Date: 07/21/2011
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):
MARVIN SYKES (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP DUE TO NEGATIVE RATE TRIP FOLLOWING RAPID TURBINE LOAD REDUCTION

"At 2129 EST on 7/20/2011, Unit 1 reactor/turbine automatically tripped.

"Following the reactor trip, all safety-related equipment operated as designed. Auxiliary Feedwater automatically actuated as expected from the Feedwater Isolation Signal. Primary PORVs and/or safety valves lifted and reseated as indicated by tailpipe temperatures and PRT pressure.

"Unit 1 is currently being maintained in Mode 3 at NOT/NOP, approximately 548 F and 2235 psig, with Auxiliary Feedwater supplying the steam generators.

"At the time of the trip, maintenance was in progress on Preferred Inverter #1. AOP-P.09 'Loss of 120VAC Preferred Power' was used to restore power to #1 Preferred board after the trip.

"Method of decay heat removal is via steam dumps to the condenser with MSIVs open.
"Current temperature and pressure: Temperature - 548 degrees Fahrenheit and stable, Pressure 2235 - psig and stable
"No indication of any primary/secondary leakage.
"All rods are inserted.
"Electrical alignment is normal, supplied from off-site power.
"No impact on Unit 2. Unit 2 is operating at 100% power/Mode 1"

The NRC Resident Inspector has been informed. The licensee notified the State of Tennessee.

Page Last Reviewed/Updated Thursday, March 25, 2021