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Event Notification Report for October 21, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/17/2013 - 10/21/2013

** EVENT NUMBERS **


49421 49425 49427 49431 49446 49448 49449 49451 49452 49453 49454 49455
49456

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Agreement State Event Number: 49421
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: PROFESSIONAL SERVICE INDUSTRIES INC
Region: 4
City: HARLINGEN State: TX
County:
License #: 04944
Agreement: Y
Docket:
NRC Notified By: GENTRY HEARN
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/09/2013
Notification Time: 17:30 [ET]
Event Date: 10/09/2013
Event Time: 09:30 [CDT]
Last Update Date: 10/09/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL HAY (R4DO)
FSME EVENTS RESOURCE (EMAI)
JIM WHITNEY (ILTA)
MEXICO (FAX)

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

Event Text

AGREEMENT STATE REPORT - MISSING MOISTURE DENSITY GAUGE

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

"On October 9, 2013 at approximately 1445 CDT, the Agency [Texas Department of State Health Services] received notice by phone that the licensee had lost a Troxler 3430 (sn 28350) moisture/density gauge near the Donna International Bridge near Donna, Texas. The sources contained within are an 8 mCi Cs-137 source (QSA Global X1218 sn 7502362) and a 40 mCi Am-241/Be source (QSA Global AX1 X.1 X.1/2 sn 47-25061). The gauge had been left on a tailgate out of its transport container when the truck left the temporary job site at approximately 0930 CDT. Upon reaching the first light in town approximately 5 miles away, the driver/technician noticed the down tailgate and missing gauge. A search is still underway."

Texas Report # I 9123

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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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 49425
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: MATT HUMMER
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/10/2013
Notification Time: 14:08 [ET]
Event Date: 10/10/2013
Event Time: 08:09 [PDT]
Last Update Date: 10/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MICHAEL HAY (R4DO)

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

LOW PRESSURE CORE SPRAY DECLARED INOPERABLE

"At 0809 PDT on 10/10/2013, after starting Standby Service Water (SW) pumps, Columbia Generating Station (Columbia) received a flow low alarm for the Low Pressure Containment Spray (LPCS) pump motor cooling water. The flow indicator SW-FIS-19 was reported too low to support pump function. The LPCS system was declared inoperable, and the appropriate Technical Specification action statement was entered. The cause of the low flow alarm has not been determined. This event is reportable under criterion 10 CFR 50.72(b)(3)(v)(D) 'Any Event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to (D) Mitigate the consequences of an accident.'

"Columbia is continuing to troubleshoot and repair as appropriate to restore the SW flow to the LPCS pump.

"The licensee has notified the NRC Resident Inspector."

* * * UPDATE ON 10/11/13 AT 1653 EDT FROM MATT HUMMER TO DONG PARK * * *

"Subsequent to receipt of the low flow alarm, flushing of the flow indicating switch sensing lines was conducted. It has been determined that the instrument sensing lines are partially blocked providing a flow indication that is slow to respond to actual flow conditions. The flow is currently reading normally. The LPCS pump was declared operable on 10/10/13 at 1447 PDT. The initial notification incorrectly stated 'Low Pressure Containment Spray (LPCS)', the correct description is 'Low Pressure Core Spray (LPCS)'."

The licensee has notified the NRC Resident Inspector.

Notified R4DO (Hay).

* * * RETRACTION FROM DAVID HOLICK TO JOHN SHOEMAKER AT 2030 EDT ON 10/18/13 * * *

"Subsequent evaluation of this event found there was no actual low flow condition to the LPCS bearing cooler. A flow scan on the SW outlet line from the LPCS pump bearing cooler was conducted on 10/12/13 which confirmed the actual flow conditions were reading normally. The problem resides in the installed flow indication switch. Since there was no actual low flow condition to the LPCS bearing cooler, the LPCS pump could perform its safety function to mitigate an accident. Therefore, this event notification is being retracted."

Notified R4DO (Azua). The licensee has notified the NRC Resident Inspector.

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Agreement State Event Number: 49427
Rep Org: KENTUCKY DEPT OF RADIATION CONTROL
Licensee: BAPTIST HEALTH MADISONVILLE
Region: 1
City: MADISONVILLE State: KY
County:
License #: 202-141-26
Agreement: Y
Docket:
NRC Notified By: ERIC PERRY
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/10/2013
Notification Time: 15:38 [ET]
Event Date: 10/10/2013
Event Time: 09:30 [CDT]
Last Update Date: 10/10/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JON LILLIENDAHL (R1DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - MEDICAL EVENT INVOLVING POSSIBLE EQUIPMENT MALFUNCTION

The following was received from the Commonwealth of Kentucky via email:

"Licensee notified the Radiation Health Branch on October 10, 2013 at 0930 EDT of the possible event. The RSO, reported the following: A vaginal applicator using Cs-137 was found to be dislodged from the patient this morning. The RSO reported that the patient is paralyzed and would not have recognized the specific time that the applicator became dislodged. At this time, (1035 EDT) the RSO has received an email which requested him to provide all required notification information included in 902 KAR 100:072 section 15, has been provided a web link to the regulation, and has been provided with an information form to complete regarding the possible medical event. The RSO indicated he would provide the requested information to the Investigator by return email. The licensee is currently conducting an investigation into this matter to determine dose estimates for the patient and if there was an equipment failure."

KY Event Report ID No: KY130004

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: 49431
Rep Org: COLORADO DEPT OF HEALTH
Licensee: ST. MARY'S HOSPITAL AND MEDICAL CENTER
Region: 4
City: MONTROSE State: CO
County:
License #: CO-014-03
Agreement: Y
Docket:
NRC Notified By: JAMES H. GRICE
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/11/2013
Notification Time: 17:38 [ET]
Event Date: 10/10/2013
Event Time: [MDT]
Last Update Date: 10/11/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL HAY (R4DO)
PAMELA HENDERSON (FSME)

Event Text

AGREEMENT STATE REPORT - POTENTIAL DOSE FROM DECEASED PATIENT WITH PREVIOUSLY ADMINISTERED IODINE-131

The following was received from the State of Colorado via email:

"CDPHE [Colorado Department of Public Health and Environment] received telephone notification on 10/11/13 at approximately 2:00 p.m. of a deceased patient who had been administered 150 mCi of I-131 approximately 10-14 hours prior to his death. A male patient, 35 years of age, was administered 150 mCi of I-131 at St. Mary's Hospital and Medical Center on Wednesday October 9, 2013. The RSO at St. Mary's was notified on Thursday that the patient had passed at some point in the night of the 9th. County EMTs as well as staff from the county coroner's office were called to the scene and examined the body prior to the confirmation of death and the transport of the body to the Montrose Memorial Hospital in Montrose, Colorado.

"Section 7.22 of the Colorado Regulations require that the licensee shall notify the Department [Colorado Department of Public Health and Environment] by telephone immediately upon discovery that a patient or human research subject containing radioactive material has died, and it is possible that any individual could receive exposures in excess of 4.14 as a result of the deceased's body.

"At this time, the licensee has consulted with and performed contamination surveys of all of the members of the public who have come into contact with the deceased and has situated the body in a secluded portion of the morgue with lead aprons to reduce any potential exposure. The preliminary estimates on dose indicate that the highest dose would have been to the driver of the vehicle which was used to move the body and that dose is estimated to be 30 mrem. The pathology staff at the hospital would like to perform an autopsy since the patient was 35 years of age and was not expected to pass based on medical history.

"The Department [Colorado Department of Public Health and Environment] will keep communications open as details of the autopsy schedule are finalized and provide guidance on best practices and ALARA techniques for handling of the body.

"The licensee will submit a written report with more detail within thirty days. No other details are available at this time."

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Power Reactor Event Number: 49446
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: THOMAS MORSE
HQ OPS Officer: PETE SNYDER
Notification Date: 10/17/2013
Notification Time: 16:25 [ET]
Event Date: 10/17/2013
Event Time: 13:00 [EDT]
Last Update Date: 10/17/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
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

Event Text

POSTULATED HOT SHORT FIRE EVENT THAT COULD ADVERSELY IMPACT SAFE SHUTDOWN EQUIPMENT

"A review of industry operating experience regarding the impact of unfused Direct Current (DC) ammeter circuits in the control room has determined the described condition to be applicable to the Perry Nuclear Power Plant resulting in a potentially unanalyzed condition with respect to 10 CFR 50 Appendix R analysis requirements. The original plant wiring design and associated analysis for the Class 1 E batteries control room ampere indications do not include overcurrent protection features to limit the fault current.

"In the postulated event, a fire in the control room could cause one of the ammeter wires to hot short to the ground plane. Simultaneously, it is postulated that the fire causes another DC wire from the opposite polarity on the same battery to also hot short to the ground plane. This could cause a ground loop through the unprotected ammeter wiring. This event could result in excessive current flow (i.e., heating) in the ammeter wiring to the point of causing a secondary fire in the raceway system. The secondary fire could adversely affect safe shutdown equipment and potentially cause the loss of the ability to conduct a safe shutdown as required by 10 CFR 50 Appendix R.

"This condition is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B). Interim compensatory measures (i.e., fire watches) have been implemented for affected areas of the plant.

"The licensee has notified the NRC Resident Inspector."

See the following related Event Numbers: 49411, 49419, 49422, and 49444.

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Power Reactor Event Number: 49448
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: JEFF ISCH
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 10/18/2013
Notification Time: 13:47 [ET]
Event Date: 10/18/2013
Event Time: 12:11 [CDT]
Last Update Date: 10/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
RAY AZUA (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 80 Power Operation

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO LOSS OF COOLING TO SWITCHGEAR ROOMS

"Wolf Creek has commenced a plant shutdown in accordance with Technical Specifications. The A train class 1E electrical equipment air conditioning unit was declared non-functional due to a possible failed oil pressure sensor. This failure could prevent the [AC] unit from performing its required function over its required mission time, as required by Technical Specifications 3.8.4, 3.8.7, and 3.8.9. The following safety related electrical equipment was declared inoperable: 4.16KV bus NB01; 480 volt AC buses NG01 and NG03; 120 volt instrument AC inverters and buses NN11, NN13, NN01 and NN03; 125 VDC chargers and buses NK11, NK13, NK01 and NK03.

"Technical Specification 3.0.3 was entered at 1141 CDT on 10/18/2013 from Technical Specification 3.8.7 due to two out of four 120 VAC inverters (NN11 and NN13) being inoperable. Plant shutdown to Mode 5 commenced at 1211 CDT.

"All electrical systems listed above remain available but are declared inoperable due to inadequate room cooling capability.

"No major equipment is out of service. No switchgear room temperature limits were challenged.

"The NRC Resident Inspector has been notified."

See event notifications; EN #49339, EN #49126, and EN #49008 for similar events.

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Power Reactor Event Number: 49449
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: DAN GENEVA
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/18/2013
Notification Time: 14:05 [ET]
Event Date: 10/18/2013
Event Time: 08:30 [EDT]
Last Update Date: 10/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
PAUL KROHN (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

POSTULATED HOT SHORT FIRE EVENT THAT COULD ADVERSELY IMPACT SAFE SHUTDOWN EQUIPMENT

"At 0830 EDT, Calvert Cliffs Nuclear Power Plant determined that the following was an unanalyzed condition:

"As a result of recent industry operating experience (OE 305419) regarding the impact of unfused direct current (DC) ammeter circuits in the Control Room, Calvert Cliffs performed a review of ammeter circuitry. The review determined the described condition to be applicable to Calvert Cliffs resulting in an unanalyzed condition with respect to 10 CFR 50 Appendix R analysis requirements. The wiring design for the ammeters contains a shunt in the current flow from each DC battery or charger. The ammeter wiring attached to the shunt does not contain fuses.

"It is postulated that a fire in the Unit 1 Cable Spreading Room could cause one of the ammeter wires to hot short to ground. Concurrently, the fire causes another DC wire from the opposite polarity on the same battery to also short to ground. This would cause a ground loop through the unfused ammeter cable. The potential exists that the cable could heat-up causing a secondary fire in the Unit 2 Cable Spreading Room. The secondary fire could adversely affect safe shutdown equipment and potentially cause the loss of the ability to safely shutdown per 10 CFR 50 Appendix R.

"This condition is reportable as an eight hour ENS report in accordance with 10 CFR 50.72(b)(3)(ii)(B) as an unanalyzed condition. Compensatory measures (fire watches) have been implemented for affected areas of the plant.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 49451
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: KELLEY BELENKY
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/18/2013
Notification Time: 15:52 [ET]
Event Date: 10/18/2013
Event Time: 15:05 [EDT]
Last Update Date: 10/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
NICK VALOS (R3DO)

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

OFFSITE NOTIFICATION DUE TO ONSITE OIL SPILL

"At 1505 EDT on October 18, 2013, Fermi 2 experienced an oil spill to navigable waters, requiring notification of the Nuclear Regulatory Commission, Pollution Emergency Alert System, Detroit Edison Corporate Environmental Management and Resources, and the Primary Public Safety Answering Point. The spill has not left site.

"Oil leaked from a fitting on a pump during the performance of fire truck testing. It is estimated that the volume of the overflow was less than four gallons. The overflow entered the on-site quarry. The source of the spill has been terminated.

"Media interest is anticipated.

"The NRC resident inspector has been notified."

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Power Reactor Event Number: 49452
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: AMY BURKHART
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 10/18/2013
Notification Time: 19:38 [ET]
Event Date: 10/18/2013
Event Time: 13:28 [CDT]
Last Update Date: 10/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
RAY AZUA (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

POTENTIAL FOR HIGH ENERGY LINE BREAK ON LETDOWN SYSTEM OUTSIDE CONTAINMENT

"A postulated High Energy Line Break (HELB) between the Letdown Heat Exchanger and its containment penetration has been identified in the Fort Calhoun Station calculation FC07885, Rev. 0, Stress Analysis of Small Bore Piping on Isometric CH-4106 High Energy Line Break Assessment.

"Based on this, there is a potential for a HELB on the inlet of the Letdown Heat Exchanger that may adversely impact the upstream piping and the outboard containment isolation valve. Assuming a single failure of the inboard isolation, this condition has the potential to degrade a principal safety barrier by bypassing the containment building."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 49453
Facility: VOGTLE
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAN MONAHON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 10/19/2013
Notification Time: 09:36 [ET]
Event Date: 10/19/2013
Event Time: 06:43 [EDT]
Last Update Date: 10/19/2013
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):
MIKE ERNSTES (R2DO)

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

Event Text

AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP

"VEGP [Vogtle Electric Generating Plant] unit two was at 100% power, normal activities, when the unit two turbine tripped causing an automatic reactor trip. All control rods fully inserted and nothing unusual was noted. Auxiliary feed water and feedwater isolation actuated as expected. The unit is currently stable in Mode 3 at normal operating temperature and pressure. A forced outage response team has been formed to determine the cause of the turbine trip and determine restart criteria and time of restart."

During the transient, no relief valves lifted. The electrical grid is stable and supplying plant safety loads. Decay heat is being removed via steam dumps to the condenser.

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 49454
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: KEN GOODALL
HQ OPS Officer: CHARLES TEAL
Notification Date: 10/19/2013
Notification Time: 09:57 [ET]
Event Date: 10/19/2013
Event Time: 03:31 [EDT]
Last Update Date: 10/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
PAUL KROHN (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 1 Startup 0 Hot Shutdown

Event Text

GROUP 1 ISOLATION DUE TO HIGH REACTOR WATER LEVEL

"On Saturday, October 19, 2013 at 0331 hours, with the reactor critical at approximately 1% core thermal power and the mode switch in start-up, a high reactor water level condition resulted in a main turbine trip and a valid Group 1 isolation signal. As a result, the Main Steam Isolation Valves (MSIVs) closed.

"The plant was in start-up from a forced outage. The initial plant conditions were reactor pressure at approximately 280 psig with a corresponding reactor coolant temperature for that pressure. Currently reactor pressure and water level are being maintained with the MSIVs closed in normal bands. The reactor is being cooled down in preparation for operation in shutdown cooling. Off-site power is supplying station power from the Start-up Transformer (normal power supply for shutdown operations). All plant systems responded as designed.

"The cause of the increase in reactor water level is currently under investigation.

"This event had no impact on the health and/or safety of the public.

"The USNRC Senior Resident Inspector has been notified."

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Power Reactor Event Number: 49455
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: MARK MOEBES
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/19/2013
Notification Time: 23:00 [ET]
Event Date: 10/19/2013
Event Time: 17:05 [CDT]
Last Update Date: 10/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
STEVEN RUDISAIL (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

PARTIAL LOSS OF OFFSITE COMMUNICATIONS DUE TO A BLOWN FUSE

"On 10/19/2013 at 1705 CDT, Browns Ferry Nuclear Plant (BFN) experienced a partial loss of offsite communications, which included the NRC Emergency Notification System, the Emergency Plan Paging System and normal phone communication to offsite. Main control room indications and assessment capability were not affected. The Nextel cellular phone system and the satellite phones in the control rooms were unaffected. The plant radio system was also unaffected. The Emergency Response Data System is currently out of service due to planned maintenance on the associated offsite power supply. Operation of BFN Unit 1, Unit 2, and Unit 3 was not affected by the event.

"The BFN facilities personnel found a blown fuse in one of the temporary Diesel Generators (DGs) supplying the node associated with the outside phone communications. The fuse was replaced and the DG has been in-service with no issues. Normal communications and access have been restored.

"The NRC Senior Resident Inspector has been notified.

"This event is reportable under 10CFR50.72(b)(3)(xiii), 'Any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability' (e.g., significant portion of control room indication, emergency notification system, or offsite notification system)."

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Power Reactor Event Number: 49456
Facility: SURRY
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JONATHAN FORD
HQ OPS Officer: HOWIE CROUCH
Notification Date: 10/20/2013
Notification Time: 11:07 [ET]
Event Date: 10/19/2013
Event Time: 23:20 [EDT]
Last Update Date: 10/20/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
STEVEN RUDISAIL (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 90 Power Operation 90 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

LICENSED OPERATOR TESTED POSITIVE FOR ALCOHOL ON A FOR-CAUSE FITNESS FOR DUTY TEST

A licensed operator had a confirmed positive for alcohol during a for-cause fitness for duty test. The employee's access to the plant has been placed on hold.

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Monday, October 21, 2013
Monday, October 21, 2013