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Event Notification Report for January 25, 2016

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/22/2016 - 01/25/2016

** EVENT NUMBERS **


51653 51656 51657 51658 51664 51674 51676 51677 51678 51679 51680 51681
51682 51683

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Agreement State Event Number: 51653
Rep Org: PA DEP BUREAU OF RAD PROTECTION
Licensee: CIVIL & ENVIRONMENTAL CONSULTANTS
Region: 1
City: PITTSBURGH State: PA
County:
License #: PA-1147
Agreement: Y
Docket:
NRC Notified By: JOE MELNIC
HQ OPS Officer: DANIEL MILLS
Notification Date: 01/14/2016
Notification Time: 10:31 [ET]
Event Date: 01/13/2016
Event Time: [EST]
Last Update Date: 01/14/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MEL GRAY (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE

The following report was received from the State of Pennsylvania via facsimile:

"On January 13, 2016, the Department [PA DEP Bureau of Radiation Protection] was notified that a Troxler gauge was damaged while on the job site in Pennsylvania. This event is reportable within 24-hours per 10 CFR 30.50(b)(2).

"A Troxler gauge was hit with a truck while on a job site. The source rod became detached from the gauge and rendered the gauge unusable. The area was secured and a local service provider was notified to recover the gauge. The gauge was not found to be leaking and was secured for shipment back to Troxler for repair. There was no exposure to workers or the public.

"Gauge Model: 3440
"Test Date: 7/6/2015
"Gauge S/N: 18936

"A local service provider assisted with retrieval of the gauge. A reactive inspection was performed by the Department. More information will be provided upon receipt."

PA Event Report ID No: PA160001

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Agreement State Event Number: 51656
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: SOUTHWEST RESEARCH INSTITUTE
Region: 4
City: SAN ANTONIO State: TX
County:
License #: 04958
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: JEFF HERRERA
Notification Date: 01/14/2016
Notification Time: 19:57 [ET]
Event Date: 01/14/2016
Event Time: [CST]
Last Update Date: 01/14/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY KELLAR (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE - RADIATION LEVELS ON PACKAGE GREATER THAN 1 REM/HR LIMIT

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

"On January 14, 2016, the licensee notified the Agency [Texas Department of State Health Services] that it had received an exclusive use shipment of sources in Type A containers that originated in Maryland. The dose rate on one of the containers, which held an 8.4 curie Cobalt-60 source (current activity/decay corrected), exceeded the 1,000 mR/hr limit. The highest dose rate reading on the exterior of the container was 1,900 mR/hr. The licensee surveyed the cab of the truck and measured a dose rate of less than 0.05 mR/hr for the driver. The exterior of the trailer was surveyed and the left side highest measurement was 120 mR/hr and the right side was 50 mR/hr. These dose rates for cab and trailer are below regulatory limits. The licensee reported that none of its workers received any overexposure. More information will be provided as it is obtained in accordance with SA-300."

Texas Incident #: I 9371

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Agreement State Event Number: 51657
Rep Org: PA DEP BUREAU OF RAD PROTECTION
Licensee: UNIVERSAL WELL SERVICES, INC
Region: 1
City: MEADVILLE State: PA
County:
License #: PA1446
Agreement: Y
Docket:
NRC Notified By: JOE MELNIC
HQ OPS Officer: DANIEL MILLS
Notification Date: 01/15/2016
Notification Time: 08:55 [ET]
Event Date: 01/14/2016
Event Time: [EST]
Last Update Date: 01/15/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MEL GRAY (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - SHUTTER MALFUNCTION

The following was received from Pennsylvania via fax:

"On January 14, 2016, the Department [PA DEP Bureau of Radiation Protection] was notified by Universal Well Services that a malfunction of a roll pin on a shutter handle occurred at the Hop Bottom, Pennsylvania temporary job site. It is reportable per 10 CFR 30.50(b)(2).

"A roll pin, which holds the shutter handle to the shutter shaft, on an in-line density gauge, became dislodged rendering the gauge unusable. The shutter is in the closed position and out of service awaiting repair from a service provider. No exposures occurred.

"Radionuclide: Cs-137
"Manufacturer: Berthold
"Model: LB 8010
"Serial Number: 10059
"Activity: 20 mCi

"The shutter is in the closed position and the gauge is out of service and secure. There was no other damage to the gauge. A reactive inspection is planned by the Department."

PA Event ID # PA160002

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Agreement State Event Number: 51658
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: LA PIGMENT COMPANY, L.P.
Region: 4
City: WESTLAKE State: LA
County:
License #: LA-6491-L01
Agreement: Y
Docket:
NRC Notified By: JOSEPH NOBLE
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/15/2016
Notification Time: 17:09 [ET]
Event Date: 01/14/2016
Event Time: 12:01 [CST]
Last Update Date: 01/15/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY KELLAR (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - FIXED GAUGE WITH SHUTTER STUCK IN OPEN POSITION

The following Agreement State Report was received from the State of Louisiana via email:

"The RSO [Radiation Safety Officer], called to report that a gauge installed on a process at the licensee's Westlake, LA facility, had a shutter malfunction. The gauge is installed on a routing process for material at the facility. The gauge shutter is stuck in the open position.

"The Gauge is a Berthold Technologies, Model: Berthold Systems, LB-330 utilizing a 12 mCi Cs-137 source, Model: Lab. Prof. Dr. Berthold Dwg. #2653.100-001. The source and gauge will remain on the process in operation until the Berthold Technician arrives over the weekend service the gauge. This will be either make the necessary repairs to the shutter or remove the gauge from service and perform the disposal. Due to the age of the gauge, if it cannot be repaired, disposal is the resolution. This will be determined by the Berthold personnel performing the repair. The service order request has the repairs scheduled to be made over this weekend.

"There are no exposure or health and safety issues involved with this event. The gauge and rod source will remain installed on the functioning process. The resolution of the situation will be directed by the ability to be repaired or if the gauge should be de-installed and sent for disposal.

"The corrective action: Will be determined by the ability of the Berthold Technician to repair the shutters on the gauge or if the gauge needs to be de-installed and sent for disposal. The repairs and or corrective actions will be determined by a site visit and assessment by Berthold Technologies."

The State of Louisiana considers this event to be closed.

State Event Report ID No: LA 160002

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Power Reactor Event Number: 51664
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: ROBERT MONTGOMERY
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/19/2016
Notification Time: 18:41 [ET]
Event Date: 01/20/2016
Event Time: 04:00 [CST]
Last Update Date: 01/22/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAMNES CAMERON (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
3 N Y 100 Power Operation 100 Power Operation

Event Text

TECHNICAL SUPPORT CENTER OUT OF SERVICE FOR PLANNED PREVENTATIVE MAINTENANCE

"At 0400 CST on Wednesday, January 20, 2016, the Dresden Nuclear Power Station (DNPS) Technical Support Center (TSC) emergency ventilation system will be removed from service for planned maintenance activities. During the maintenance, the TSC Ventilation will be shut down. The TSC air filtration fan and dampers will be non-functional, rendering the TSC HVAC accident mode non-functional. This maintenance is scheduled to minimize out of service time. The planned TSC ventilation outage is scheduled to be completed in approximately 43 hours.

"Contingency plans are in place so that if an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing Emergency Planning (EP) procedures and checklists. If radiological or environmental conditions require TSC facility evacuation during ventilation system restoration; the Station Emergency Director will relocate the TSC staff in accordance with station procedures.

"The NRC Resident Inspector has been notified."


* * * UPDATE AT 0049 EST ON 1/22/16 FROM STEVEN MELL TO JEFF HERRERA * * *

"At 2223 CDT on 1/21/16, Dresden TSC Ventilation was restored. The Dresden TSC Ventilation is functional at this time.

"The NRC Resident Inspector has been notified."

Notified R3DO (Cameron).

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Part 21 Event Number: 51674
Rep Org: CURTISS WRIGHT NUCLEAR DIVISION
Licensee: CURTISS WRIGHT NUCLEAR DIVISION
Region: 1
City: HUNTSVILLE State: AL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: SAMUEL BLEDSOE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/22/2016
Notification Time: 14:09 [ET]
Event Date: 01/21/2016
Event Time: [CST]
Last Update Date: 01/22/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
HAROLD GRAY (R1DO)
PART 21/50.55 REACT (EMAI)

Event Text

PART 21 NOTIFICATION - POTENTIAL DEFECT IN OKONITE TAPE SPLICES

The following information was obtained from Curtiss-Wright Nuclear Division via fax and email:

"This letter is issued to provide initial notification of a potential defect in Okonite Tape Splices. The potential defect is inadequate radiation testing performed by Steris/lsomedix.

"In response to NRC Information Notice 2015-12: 'Unaccounted for Error Terms Associated with the Irradiation Testing and Environmental Qualification of Important-to-Safety Components,' an investigation was performed to determine if products had radiation testing performed by Steris/lsomedix, and any impact. This investigation commenced on November 25, 2015.

"It was determined on January 21, 2016 that the qualification of Okonite Tape Splices is affected by the unaccounted for error terms discussed in Information Notice 2015-12. This product has only been provided to James A. FitzPatrick Nuclear Power Plant. This customer will be notified today.

"As a corrective action, Qualification Report PEI-TR-842900-1 will be revised to decrease the Total Integrated Dose (TID) reported by 9.6% based upon the guidance of Information Notice 2015-012. This revision will be provided to James A. FitzPatrick Nuclear Power Plant within 30 days of this notification. Notification will be provided when this corrective action is complete.

"If additional information is required, please contact me by the methods provided below or Quality Assurance Manager Tony Gill: 256-426-4558, tgill@curtisswright.com."

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Power Reactor Event Number: 51676
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: DEREK ETUE
HQ OPS Officer: JEFF HERRERA
Notification Date: 01/23/2016
Notification Time: 00:20 [ET]
Event Date: 01/22/2016
Event Time: 19:35 [EST]
Last Update Date: 01/23/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JAMNES CAMERON (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

LOW PRESSURE COOLANT INJECTION PUMP ISOLATION VALVE WOULD NOT REOPEN

"While performing a Technical Specification surveillance functional test of the Low Pressure Coolant Injection (LPCI) pump and valve surveillance, the Division 1 LPCI outboard Isolation Valve E1150F017A was closed for stroke time testing and would not reopen. Not being able to be open this valve renders the LPCI Loop Select function inoperable. Time of the event was 1935 [EST]. This inoperability of LPCI loop Select results in entry into Technical Specification 3.0.3.

"Power reduction activities were briefed at time 2020, however, no power reduction commenced due to resolving the issue with the LPCI outboard Isolation Valve E1150F017A. During the investigation there was a loose screw found preventing the close contactor from fully releasing and allowing the open contactor to engage. No other abnormalities were found during this investigation. This screw was removed and the close contactor functioned normally and the valve was opened. The valve was retested satisfactory and the station exited Technical Specification 3.0.3 at 2145.

''This report is made pursuant to 10 CFR 50.72(b)(3)(v)(D), an event or condition that could have prevented the fulfillment of the safety function of systems needed to mitigate the consequences of an accident.

"The NRC Resident Inspector was notified."

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Power Reactor Event Number: 51677
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: ANDREW KRUKOWSKI
HQ OPS Officer: DANIEL MILLS
Notification Date: 01/23/2016
Notification Time: 08:26 [ET]
Event Date: 01/23/2016
Event Time: 05:51 [EST]
Last Update Date: 01/23/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HAROLD GRAY (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

Event Text

LOSS OF POWER TO THE SITE EMERGENCY BUILDING

"Oyster Creek Generating Station has experienced a loss of power to the Site Emergency Building, which renders the TSC ventilation system non-functional until power is restored.

"If an emergency is declared requiring TSC activation during the time TSC ventilation is non-functional, the TSC will be staffed and activated using existing emergency planning procedure unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff to an alternate location in accordance with applicable site procedures.

"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xii) due to potential loss of the TSC. An update will be provided once the TSC ventilation has been restored to normal operation."

The NRC Resident Inspector has been notified.

* * * UPDATE FROM ANDREW KRUKOWSKI TO JEFF HERRERA AT 1121 EST ON 1/23/16 * * *

"Due to a loss of power to the Site Emergency Building the Plant Process Computer needed to be secured. Due to the loss of the Plant Process Computer the Emergency Response Data System (ERDS) functions are not available for communications to the NRC.

"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii) due to the loss of úEmergency Response Data System (ERDS) communication capability."

The licensee has notified the NRC Resident Inspector. Notified R1DO (Gray).

* * * UPDATE FROM ANDREW KRUKOWSKI TO HOWIE CROUCH AT 1446 EST ON 1/23/16 * * *

Power was restored to the Site Emergency Building. TSC Ventilation and the ERDS systems were returned to service at 1440 EST.

The licensee has notified the NRC Resident Inspector. Notified R1DO (Gray).

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Power Reactor Event Number: 51678
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: SHAUN MCHUGH
HQ OPS Officer: VINCE KLCO
Notification Date: 01/23/2016
Notification Time: 19:48 [ET]
Event Date: 01/23/2016
Event Time: 17:03 [EST]
Last Update Date: 01/23/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
GERALD MCCOY (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 99 Power Operation 97 Power Operation

Event Text

PARTIAL LOSS OF POWER RESULTS IN EMERGENCY DIESEL GENERATORS STARTING

"At 1703 [EST] on 1/23/16, with Unit 1 and Unit 2 operating at 100% power, the North Anna 34.5 kv Bus 3, off-site power feed to the 'C' Reserve Station Service Transformer, was lost which resulted in the loss of power to the Unit 1 'H' Emergency Bus and the Unit 2 'J' Emergency Bus. Loss of 34.5kV Bus 3 resulted from feeder breaker L102 opening. As a result of the power loss, the 1H Emergency Diesel Generator and the 2J Emergency Diesel Generator automatically started as designed and restored power to the associated emergency bus. During this event, the Unit 1 'B' Charging Pump, 1-CH-P-18 automatically started as designed due to the loss of power event.

"The valid actuation of these ESF components due to the loss of electrical power is reportable per 10 CFR 50.72 (b)(3)(iv)(A).

"The Unit 1 'H' Emergency Bus off-site power source was restored to service and the 1H Emergency Diesel Generator was secured and returned to Automatic. The Unit 2 'J' Emergency Bus power feed continues to be from the 2J Emergency Diesel Generator. Restoration of offsite power to operable status is currently being pursued. The Unit 1 'B' Charging Pump has been secured and returned to automatic.

"Both units are in a stable condition. An investigation is underway to determine the cause of the L102 feeder breaker opening resulting in the 34.5 kv Bus 3 loss of power."

The licensee notified the NRC Resident Inspector

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Power Reactor Event Number: 51679
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DAVID O'DONNELL
HQ OPS Officer: DANIEL MILLS
Notification Date: 01/24/2016
Notification Time: 00:56 [ET]
Event Date: 01/23/2016
Event Time: 21:22 [EST]
Last Update Date: 01/24/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
JAMNES CAMERON (R3DO)
SCOTT MORRIS (NRR)
WILLIAM GOTT (IRD)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 90 Power Operation 0 Hot Shutdown

Event Text

TS REQUIRED SHUTDOWN DUE TO UNIDENTIFIED LEAKAGE IN DRYWELL

"At 2100 hours [EST], on January 23, 2016, the Perry Nuclear Power Plant commenced a reactor shutdown due to unidentified leakage in the drywell. At 2122 hours, drywell unidentified leakage exceeded the Technical Specification 3.4.5.d limit of 'less than or equal to 2 gpm increase in unidentified LEAKAGE within the previous 24 hour period in Mode 1.' The unidentified leakage increased to approximately 3.8 gpm at 2122 hours. Current unidentified leakage is 3.02 gpm.

"Technical Specification 3.4.5 actions allow 4 hours to reduce the leakage within limits or be in Mode 3 within 12 hours and Mode 4 within 36 hours. The plant is required to be in Mode 3 by 1322 hours on January 24, 2016 and Mode 4 by 1322 hours on January 25, 2016.

"A drywell entry will be made in Mode 3 to identify the leak source.

"This notification is being made due to an expected inability to restore the leakage within limits prior to exceeding the LCO action time.

"Follow up question from NRC: Event times do not match (2100 versus 2122) - explained downpower was commenced at 2100 with leakage less than TS limit. When Reactor Core flow was reduced, un-identified leakage increased above the TS limit."

The Licensee has notified the NRC Resident Inspector.

* * * UPDATE FROM MIKE DOTY TO DANIEL MILLS AT 1123 EST ON 1/24/16 * * *

"At 1007 hours, on January 24, 2016 with the plant at 8% power during a feedwater shift to place the motor feed pump in service, reactor level rose to the level 8 scram set point and the Reactor Protection System (RPS) initiated, scramming the reactor. During the scram, all rods fully inserted into the core. Decay heat is being removed via turbine bypass valves to the main condenser. Reactor level control is currently being maintained via feedwater. The plant is stable with cool down and depressurization to Mode 4 to follow. The cause of the rise in feedwater level is under investigation. This notification is being made under 50.72(b)(2)(iv)(B) for a RPS initiation while critical."

All safety shutdown systems are available. The electric plant is in its normal shutdown alignment being supplied by offsite power.

The licensee has notified the NRC Resident Inspector. Notified R3DO (Cameron). NRR (Morris) and IRD (Gott) were notified via email.

* * * UPDATE FROM DAVID O'DONNELL TO HOWIE CROUCH AT 1915 EST ON 1/24/16 * * *

"Following a shutdown required by plant Technical Specifications a small leak was identified coming from the Reactor Recirculation Loop A Pump Discharge Valve vent line. The Recirculation Loop is part of the reactor coolant system making this reportable under 50.72(b)(3)(ii)(A) as a degraded condition. It was subsequently determined to require a plant cool down in accordance with Technical Specification 3.4.5, Action C which requires the plant to be in MODE 4 within 36 hours. Technical Specification 3.4.5 was previously entered for increased unidentified leakage in the drywell. The plant is required to be in Mode 4 by 1322 hours on January 25, 2016."

The licensee has notified the NRC Resident Inspector. Notified R3DO (Cameron). NRR (Morris) and IRD (Gott) were notified via email.

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Power Reactor Event Number: 51680
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: CRAIG LOHR
HQ OPS Officer: DANIEL MILLS
Notification Date: 01/24/2016
Notification Time: 01:10 [ET]
Event Date: 01/23/2016
Event Time: 22:41 [EST]
Last Update Date: 01/24/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
HAROLD GRAY (R1DO)
SCOTT MORRIS (NRR)
WILLIAM GOTT (IRD)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 89 Power Operation 0 Hot Shutdown

Event Text

MANUAL SCRAM DUE TO LOWERING INTAKE LEVEL

"At 2241 [EST] on 1/23/2016, James A FitzPatrick inserted a manual scram from 89 percent power due to lowering intake level. Following the successful scram, a residual transfer occurred, resulting in a loss of the non-vital busses, loss of all Circulating Water Pumps, and a manual closure of the Main Steam Isolation Valves (MSIVs). The cause of the residual transfer is unknown.

"RPV [Reactor Pressure Vessel] level shrink during the scram resulted in a successful Group 2 isolation. Reactor Vessel [level] and pressure are being maintained with the High Pressure Coolant Injection System which was manually started. A cooldown is in progress."

FitzPatrick will proceed to Mode 5 until the cause is identified and corrected. The Emergency Diesel generators auto started as a result of the loss of power to the non-vital busses. Offsite power remained available throughout the event. Operators are controlling pressure manually via the relief valves. FitzPatrick will notify the Public Service Commission of the event.

The NRC Resident Inspector was notified.

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Power Reactor Event Number: 51681
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: MIKE DOTY
HQ OPS Officer: DANIEL MILLS
Notification Date: 01/24/2016
Notification Time: 11:23 [ET]
Event Date: 01/24/2016
Event Time: 03:57 [EST]
Last Update Date: 01/24/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
JAMNES CAMERON (R3DO)
SCOTT MORRIS (NRR)
WILLIAM GOTT (IRD)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 52 Power Operation 52 Power Operation

Event Text

AVERAGE POWER RANGE MONITORING SYSTEM INOPERABLE

"At 0357 hours [EST] on January 24, 2016, during a shut down required by plant Technical Specifications (see EN#51679), the 3A Feedwater heater isolated while performing a Reactor Recirculation Pump downshift. A consequence of this Feedwater heater isolation was that all 8 of the Average Power Range Monitors (APRM) became inoperable due to a calibration set point being out of tolerance. The APRM's are relied upon for the reactors high neutron flux trips. The inoperable APRM's resulted in a loss of RPS Trip Capability and a loss of safety function. The manual reactor trip function and other RPS functions remained available. RPS Trip capability for the APRM's was restored at 0445 hours on January 24, 2016. This notification is being made under [10 CFR] 50.72(b)(3)(v)(A) for an event or condition that could have prevented the fulfillment of a safety function affecting the ability to shut down the reactor."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 51682
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MARK STROLLO
HQ OPS Officer: DANIEL MILLS
Notification Date: 01/25/2016
Notification Time: 03:21 [ET]
Event Date: 01/25/2016
Event Time: 01:47 [EST]
Last Update Date: 01/25/2016
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):
HAROLD GRAY (R1DO)

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 DUE TO REACTOR COOLANT PUMP TRIP

At 0147 EST on 1/25/16, the 'B' Reactor Coolant Pump (RCP) tripped offline. This caused a reactor trip on low coolant flow. As expected, the Aux Feedwater System (AFW) initiated on the reactor trip. The trip was uncomplicated and the plant is currently shutdown in Mode 3 with a normal electrical lineup and decay heat is being removed via steam dumps to the condenser. The cause of the 'B' RCP trip is under investigation. A containment entry is planned for dayshift on 1/25/16 to inspect and troubleshoot the 'B' RCP.

The Licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 51683
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: ERVIN LYSON
HQ OPS Officer: DANIEL MILLS
Notification Date: 01/25/2016
Notification Time: 05:45 [ET]
Event Date: 01/25/2016
Event Time: 03:15 [EST]
Last Update Date: 01/25/2016
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):
HAROLD GRAY (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 10 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO ELEVATED CONDENSER SODIUM LEVELS

At 0315 EST on 1/25/16, Calvert Cliffs Unit 1 was manually tripped from 10 percent power due to elevated condenser sodium levels. All systems responded per design. Main Feed was secured and auxiliary feed water was initiated. The elevated sodium levels are believed to be due to a condenser tube leak. The reactor is currently shutdown and stable in Mode 3 and will remain in Mode 3 until repairs are effected. Unit 2 was not affected and remains at full power.

The Licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Monday, January 25, 2016
Monday, January 25, 2016