United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for February 19, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/15/2013 - 02/19/2013

** EVENT NUMBERS **


48727 48728 48729 48734 48742 48747 48754 48755 48756 48758 48760 48761
48763 48764 48765 48766

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Agreement State Event Number: 48727
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: DBA EARTH SYSTEMS CONSULTANTS
Region: 4
City: VENTURA State: CA
County:
License #: 0368-19
Agreement: Y
Docket:
NRC Notified By: DONALD OESTERLE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/07/2013
Notification Time: 12:16 [ET]
Event Date: 02/06/2013
Event Time: 14:00 [PST]
Last Update Date: 02/07/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DON ALLEN (R4DO)
FSME EVENTS RESOURCE (E-MA)

Event Text

AGREEMENT STATE REPORT - MOISTURE DENSITY GAUGE DAMAGED

The following information was received from the California Radiologic Health Branch via e-mail:

"On February 6, 2013, the licensee notified the California Department of Public Health that one of their moisture density gauges (CPN MC-1DRP, 10 mCi Cs-137, 50 mCi Am:Be-241, S/N MD00605734) was struck by a small bobcat tractor at a construction site at approximately 2:00 P.M. The gauge user had placed the gauge on the ground by the back bumper as he went to retrieve something from the cab of this truck. He no sooner started walking from the back of the truck to the side of the truck when the bobcat ran over the gauge.

"The RSO reported that although the gauge's guide tube was broken off, the body of the gauge itself was not damaged and the Cs-137 and Am-241:Be sources remained fully shielded. The external shutter, however, was slightly open. The gauge was returned to the transport case and was transported back to the licensee's facility. The RSO then contacted the manufacturer, InstroTek who instructed the RSO on how to close the shutter safely. There was no additional exposure through the external shutter even though it was slightly open because the internal shutter had remained closed during the entire event as the source rod was in the 'safe' position.

"The gauge user was wearing a whole body dosimeter which was immediately sent in for immediate processing. On February 7, 2013, [representatives from] the California Department of Public Health met with the licensee. All survey measurements were as expected for this type of gauge and there was no removable contamination found. An additional piece of lead was taped to the external shutter as a precaution during transit. The dose to any individual from this incident is estimated to be less than 0.5 millirem. The gauge is being shipped to InstroTek later today for repair."

California Report 020613

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Agreement State Event Number: 48728
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: UNKNOWN
Region: 1
City: MAYNARD State: MA
County:
License #: GENERAL
Agreement: Y
Docket:
NRC Notified By: JOHN SUMARES
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/07/2013
Notification Time: 14:10 [ET]
Event Date: 01/28/2013
Event Time: [EST]
Last Update Date: 02/07/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY POWELL (R1DO)
FSME EVENTS RESOURCE (E-MA)

Event Text

AGREEMENT STATE REPORT - SMOKE DETECTORS FOUND AT SCRAP METAL RECYCLING FACILITY

The following report was received from the Commonwealth of Massachusetts Radiation Control Program via facsimile:

"On 1/28/13, the radiation monitors at `Schnitzer Steel', a scrap metal dealer, detected radiation coming from an incoming truck loaded with scrap metal for disposal. The measured radiation level was 5.3 uR/hr with a background of 3.1 uR/hr. The load was rejected. The MA Radiation Control Program issued a 'DOT-SP 10656 shipment approval form' in order for the truck to return to 'Testa Corporation' [originator of the scrap shipment] of Maynard, MA. At the Maynard site, a consultant unloaded the scrap onto the ground and discovered 21 old smoke detectors. The smoke detector label identified the manufacturer as `Kiddie Corporation, Ashland, MA' and stated the smoke detector contained 1 uCi of Ra-226. The consultant secured all of the smoke detectors from unauthorized removal and is arranging for disposal via a licensed radioactive materials (RAM) waste broker."

Massachusetts Report Number: 13-0592

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Agreement State Event Number: 48729
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: EQUISTAR CHEMICALS L.P.
Region: 4
City: PASADENA State: TX
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/07/2013
Notification Time: 15:13 [ET]
Event Date: 02/07/2013
Event Time: [CST]
Last Update Date: 02/07/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DON ALLEN (R4DO)
FSME EVENTS RESOURCE (E-MA)

Event Text

AGREEMENT STATE REPORT - PROCESS GAUGE SHUTTER STUCK OPEN

The following report was received from State of Texas Radiation Branch via e-mail:

"On February 7, 2013, the Agency [State of Texas Radiation Branch] was notified by the licensee that the shutter on an Ohmart model SH-F1A nuclear gauge was stuck in the open position. The gauge contains a 50 millicurie cesium - 137 source. Open is the normal operating position for this gauge. The licensee has notified their personnel that no entry into the vessel the gauge is mounted on is allowed until the gauge is repaired. The manufacturer has been contacted and arrangements to repair the gauge are being completed. The failure does not create an exposure risk to any individual. This gauge had previously failed in February of 2012 (EN47691). Additional information will be provided as it is received in accordance with SA - 300."

Texas Report: I-9039.

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Non-Agreement State Event Number: 48734
Rep Org: AVERILL ENVIRONMENTAL LABS
Licensee: AVERILL ENVIRONMENTAL LABS
Region: 1
City: PLAINVILLE State: CT
County:
License #: 06-23384-01
Agreement: N
Docket:
NRC Notified By: LAWTON AVERILL
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/08/2013
Notification Time: 14:10 [ET]
Event Date: 02/08/2013
Event Time: [EST]
Last Update Date: 02/08/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
RAY POWELL (R1DO)
FSME EVENTS RESOURCE (E-MA)

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

Event Text

MISSING NICKEL-63 SOURCE USED FOR ELECTRON CAPTURE DETECTOR

The licensee called to report a missing 15 millicurie Nickel-63 source (serial #5404) used in a gas chromatograph electron capture detector. The licensee is in the process of moving their business location and discovered that this specific source was missing. It was last inventoried 29 days ago. All other sources possessed by the licensee have been accounted for. The licensee is still searching for the source which may have been misplaced in the move. However, there is a possibility that the source may have been inadvertently disposed.

The licensee has notified NRC Region 1 (Jackson).

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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Non-Agreement State Event Number: 48742
Rep Org: DEPARTMENT OF VETERANS AFFAIRS
Licensee: CARL VINSON VA MEDICAL CENTER
Region: 1
City: DUBLIN State: GA
County:
License #: 03-23853-01VA
Agreement: Y
Docket:
NRC Notified By: THOMAS HUSTON
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/11/2013
Notification Time: 18:01 [ET]
Event Date: 02/11/2013
Event Time: 14:00 [EST]
Last Update Date: 02/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(1) - SURFACE CONTAM LEVELS > LIMITS
Person (Organization):
PATTY PELKE (R3DO)
FSME EVENTS RESOURCE (E-MA)

Event Text

PACKAGE RECEIVED AT VA MEDICAL CENTER WITH OUTSIDE CONTAMINATION EXCEEDING LIMITS

"[The Department of Veterans Affairs, Veterans Health Administration (VHA) National Health Physics Programs] has a master materials license from Nuclear Regulatory Commission. License number is 03-23853-01VA.

"Per 10 CFR 20.1906(d), [the VHA] is reporting receipt of a package of radioactive material with removable surface contamination on the outside of the package greater than NRC reporting limits.

"The package was received today (February 11, 2013) at around 2:00 PM ET by Carl Vinson VA Medical Center, Dublin, Georgia. This medical center holds permit number 10-09569-01 under the VHA master materials license.

"Wipe tests performed on the external surface of the package indicated a removable contamination level of 561 dpm/cm2 as compared to the regulatory limit of 220 dpm/cm2 for beta-gamma emitters.

"The package contained two radiopharmaceuticals dosages of Technetium-99m and two doses of Thallium-201 and was shipped from Cardinal Health in Augusta, Georgia. The inner packaging materials were not contaminated, and the four dosages were able to be used.

"The VA facility Nuclear Medicine Technologist immediately notified the vendor/shipper, who serves as the final delivery carrier, about the contaminated package at about 2:30 PM ET.

"As corrective actions: the packaging materials were set aside in a restricted area at the VA Medical Center for decay; staff with access to the area were notified about the contaminated packaging materials; and surveys were performed to ensure that contamination did not spread beyond the immediate area where the package was received and checked in.

"[The VHA has also] notified NRC Region III (P. Pelke) of this event."

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Power Reactor Event Number: 48747
Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BEN HUFFMAN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/12/2013
Notification Time: 18:01 [ET]
Event Date: 02/12/2013
Event Time: 15:30 [EST]
Last Update Date: 02/15/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
TAMARA BLOOMER (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

NOTIFICATION OF OFFSITE AGENCIES DUE TO DISCOVERY OF POTENTIAL HUMAN REMAINS

"At 1530 EST on February 12, 2013, bones were discovered in the debris removal baskets in the Screen House at the Cook Nuclear Plant. These bones have the potential to be human remains.

"Local law enforcement agencies have been notified and the remains were removed by law enforcement personnel.

"The NRC Senior Resident Inspector was notified. Plant operations was not impacted by the event.

"This notification is being made in accordance with 10 CFR 50.72(b)(2)(xi) due to notification of offsite agencies and potential for media involvement related to the discovery."

* * * UPDATE FROM GREG KANDA TO CHARLES TEAL ON 2/15/13 AT 1045 EST * * *

"After analysis by the Berrien County Sheriff's Department, it was determined that the bones discovered in the debris removal baskets in the screenhouse at the Cook Nuclear Plant on February 12, 2013 at 1530 EST were not of human origin, but most likely from a deer or other animal."

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

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Power Reactor Event Number: 48754
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: LT. DANA ANTON
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/14/2013
Notification Time: 18:31 [ET]
Event Date: 02/14/2013
Event Time: 17:10 [CST]
Last Update Date: 02/15/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
PATTY PELKE (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

OFFSITE NOTIFICATION DUE TO RELEASE OF AMERTAP BALLS INTO THE MISSISSIPPI RIVER

"On 2/14/2013, Xcel Energy personnel determined that approximately 44% of the Amertap balls recently used were not recovered. Monticello Nuclear Generating Plant is required to report to the Minnesota Pollution Control Agency (MPCA) when greater than 20% of the Amertap balls are not recovered. This is based on an agreement with the MPCA dated September 12, 2008. The MPCA was notified at 1710 CST on 2/14/2013."

The licensee has notified the NRC Resident Inspector.

* * * UPDATE FROM MICHAEL STIDMON TO HOWIE CROUCH AT 1352 EST ON 2/15/13 * * *

"Update for 50.72 non-emergency notification number 48754:

"The referenced report number was made at 1831 EST on 2/14/2013. This report stated the Minnesota Pollution Control Agency (MPCA) was notified that 44% of Amertap balls recently used were not recovered at 1710 CST on 2/14/2013. Due to a miscommunication between the Monticello Nuclear Generating Plant Chemistry Department and the Xcel Energy Corporate Environmental Services contractor, the actual MPCA notification was not made until 0930 CST on 2/15/2013. This update report is to ensure the correct time of the MPCA notification was documented."

The licensee notified the NRC Resident Inspector. Notified R3DO (Pelke).

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Power Reactor Event Number: 48755
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: RON SIMS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 02/14/2013
Notification Time: 23:58 [ET]
Event Date: 02/14/2013
Event Time: 21:30 [CST]
Last Update Date: 02/15/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
BOB HAGAR (R4DO)

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

Event Text

HYDRAULIC OIL LEAK TO ENVIRONMENT

"Approximately 15 gallons of hydraulic oil was spilled from excavation equipment onto the ground inside the protected area boundary. Notifications have been made to the National Response Center and the Kansas Department of Health and Environment. Cleanup by on-site personnel is in progress.

"NRC Resident Inspector has been notified."

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Power Reactor Event Number: 48756
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CHRIS DAHMS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/15/2013
Notification Time: 13:01 [ET]
Event Date: 02/15/2013
Event Time: 20:00 [EST]
Last Update Date: 02/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ANTHONY DIMITRIADIS (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

TECHNICAL SUPPORT CENTER TAKEN OUT OF SERVICE FOR PLANNED MAINTENANCE

"This report is being submitted in accordance with the requirements of 10 CFR 50.72(b)(3)(xiii), for planned maintenance which will result in temporary power outages for the Salem Technical Support Center.

"Planned maintenance will commence on the Salem 13 kV Substation 5, the normal power supply for the Salem Technical Support Center on February 15, 2013 at approximately 2000 hrs. [EST]. Normal and backup power supplies to the Salem Technical Support Center will be removed for approximately 3-4 hours during initial clearance tagging and system alignment, after which the Technical Support Center Emergency Diesel Generator will be available for manual starting to power the facility if needed while the normal power supply is unavailable.

"Substation 5 maintenance is scheduled to be completed by the afternoon of February 17, 2013 when the Salem Technical Support Center Emergency Diesel Generator backup power supply will again be isolated for a period of 3-4 hours during clearance tag removals and system realignment.

"While normal and backup power supplies are unavailable, Salem emergency plan procedures provide guidance for use of the Hope Creek Technical Support Center and the Emergency Operations Facility as backup facilities should activation of the Salem Technical Support Center be required.

"The NRC Resident Inspector has been notified."

The licensee will be notifying Lower Alloways Creek Township.

* * * UPDATE FROM POWELL TO SNYDER ON 2/18/13 AT 0015 EST * * *

The licensee completed work on the power supplies. Normal power was restored at 0010 EST on 12/18/13.

The licensee will notify the NRC Resident Inspector. Notified R1DO (Dimitriadis).

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Power Reactor Event Number: 48758
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: TERRY DAVIS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/15/2013
Notification Time: 15:05 [ET]
Event Date: 02/15/2013
Event Time: 13:00 [EST]
Last Update Date: 02/15/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
PATTY PELKE (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 55 Power Operation

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO COMPONENT COOLING WATER TRAIN OUT OF SERVICE

"At 2030 hours [EST] on February 14, 2013, technical specification (TS) 3.7.7 condition A was entered due to the right train of the component cooling water (CCW) system being declared inoperable. The cause of the inoperable train was the identification of an approximate 40 gallon per hour CCW system to service water system leak inside the 'A' CCW heat exchanger. TS 3.7.7 condition A requires restoration of the inoperable train within 72 hours. If the restoration is not completed within 72 hours, the plant must be in Mode 3 within 6 hours and in Mode 5 within the subsequent 36 hours.

"Due to the inability to repair the leak within the required 72 hour time frame during power operation, a plant shutdown was initiated at approximately 1300 hours on February 15, 2013. Entry into Mode 3 is expected at approximately 1700 hours on February 15, 2013. The plant will enter Mode 5 to execute leak repair. Mode 5 entry is expected at approximately 0800 hours on February 16, 2013.

"This event has no impact on the health and safety of the public. The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 48760
Facility: HATCH
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KENNY HUNTER
HQ OPS Officer: CHARLES TEAL
Notification Date: 02/16/2013
Notification Time: 08:38 [ET]
Event Date: 02/16/2013
Event Time: 03:10 [EST]
Last Update Date: 02/16/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
MICHAEL F. KING (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Refueling 0 Refueling

Event Text

REACTOR PROTECTION SYSTEM SCRAM SIGNAL DUE TO SCRAM DISCHARGE VOLUME HIGH LEVEL

"On 2/16/13, at 0310 EST, with the reactor shutdown for a refueling outage, a full RPS actuation was received on Hatch Unit 2 due to Scram Discharge Volume High level. The Operations crew placed the Unit 2 mode switch to the Start-up/Hot Standby position per approved procedure for the purpose of performing the U2 Refueling Interlock functional test. The cause of the Scram was due to a Scram Discharge Volume high level caused by a malfunctioning SDV drain valve. Hatch Condition Report 591279 has been generated to document the event."

The NRC Resident Inspector has been informed.

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Power Reactor Event Number: 48761
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOEL GORDON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/16/2013
Notification Time: 17:05 [ET]
Event Date: 02/16/2013
Event Time: 14:03 [EST]
Last Update Date: 02/16/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MICHAEL F. KING (R2DO)
MELANIE GALLOWAY (NRR)
SCOTT MORRIS (IRD)

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 97 Power Operation 97 Power Operation

Event Text

OFFSITE NOTIFICATION DUE TO ONSITE CONTRACTOR FATALITY

"At approximately 1318 hours (EST), the Main Control Room was notified of a contract employee slumped over on a fork lift inside the protected area. First Responders were dispatched to the scene. Off-site assistance was requested and arrived on-site at approximately 1330 hrs. CPR was administered by the First Responders and Paramedics. At 1403 hrs., the paramedics determined that the efforts to revive the patient were unsuccessful. The cause of death has not yet been determined.

"Unit 1 remains in Mode 1 at 100% power. Unit 2 remains in Mode 1 at 97% power. Power is limited due to end of cycle maximum core flow conditions.

"A press release is not planned at this time. The Occupational Safety and Health Administration (OSHA) will be notified of the fatality. This notification is being performed in accordance with 10CFR50.72(b)(2)(xi) for notification to an off-site government agency. The NRC Resident Inspector has been notified.

* * * UPDATE FROM STUART BYRD TO HOWIE CROUCH @ 1744 EST ON 2/16/13 * * *

"The Occupational Safety and Health Administration was notified of the fatality on 2/16/13 at 1730 EST."

The NRC Resident Inspector was notified of this update.

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Power Reactor Event Number: 48763
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JAMES GROOM
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/17/2013
Notification Time: 15:51 [ET]
Event Date: 02/17/2013
Event Time: 13:45 [EST]
Last Update Date: 02/17/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
ANTHONY DIMITRIADIS (R1DO)

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

Event Text

PRESSURE BOUNDARY LEAKAGE DISCOVERED DURING CONTAINMENT WALKDOWN

"CCNPP [Calvert Cliffs Nuclear Power Plant] U-2 discovered during the Mode 3 NOP/NOT containment walkdown that 2CV-100F Pressurizer Spray valve had a pin hole leak on the leak-off welded cap. This indicates that the bellows has a leak and in addition, the packing is leaking, pressurizing the leak-off line thus the leak-off line is the pressure boundary making this pressure boundary leakage. Technical Specification 3.4.13 [Action B] requires the unit be in mode 3 in 6 hrs. Unit was in mode 3 when discovered and unit will be placed in mode 5 within 36 hrs. Currently, the plant is at 400 degrees and 950 PSIA."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 48764
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: KEITH MAESTAS
HQ OPS Officer: PETE SNYDER
Notification Date: 02/18/2013
Notification Time: 03:19 [ET]
Event Date: 02/18/2013
Event Time: 01:31 [EST]
Last Update Date: 02/18/2013
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):
MICHAEL F. KING (R2DO)

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

Event Text

MANUAL REACTOR TRIP DUE TO HIGH SEAL LEAKOFF ON REACTOR COOLANT PUMP 3A

"This is an non-emergency event notification to the NRCOC in Accordance with 10 CFR 50.72(b)(2)(iv)(B) for a valid actuation of the Reactor Protection System (RPS) (four hour notification) and 10 CFR 50.72(b)(3)(iv)(A) for a valid Engineered Safeguards (ESF) actuation due to Auxiliary Feedwater (AFW) initiation (eight hour notification).

"On 2/18/2013 at 0055 Unit 3 commenced a unit shutdown due to high # 1 seal leak-off on the 3A Reactor Coolant Pump (RCP). At 0129 3A RCP #1 seal leak-off exceeded operating limits. Unit 3 reactor was manually tripped. Auxiliary feedwater actuated as designed based on steam generator levels as a result of the trip. Unit 3 is currently in Mode 3 and stable.

"No complications were noted as a result of the reactor trip. Steam generator levels are being returned to normal level following the reactor trip. All other plant systems functioned as designed during and after the reactor trip. 3A RCP high #1 seal leak-off is under investigation."

All control rods fully inserted on the trip. Decay heat was removed by AFW to the steam generators out the atmospheric reliefs. There was no primary to secondary leakage. Electrical buses are being supplied via offsite power.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 48765
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: MARK DODDS
HQ OPS Officer: CHARLES TEAL
Notification Date: 02/18/2013
Notification Time: 11:35 [ET]
Event Date: 02/18/2013
Event Time: 03:18 [CST]
Last Update Date: 02/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
PATTY PELKE (R3DO)

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

Event Text

HIGH PRESSURE CORE SPRAY DECLARED INOPERABLE

"On February 18, 2013, at 0318 hours (CST), the Main Control Room received an alarm associated with a transfer of the Division 4 Nuclear System Protection System (NSPS) inverter to the alternate source. Plant Technicians were performing a Technical Specification (TS) Surveillance, 'Average Power Range Monitor Flow Biased/Neutron Flux Response Time Test,' when a test cable connector contacted a fuse block staple jumper, causing the transfer of the Division 4 NSPS bus from normal inverter source to its alternate source.

"TS 3.8.7, 'Inverters - Operating' Surveillance Requirement 3.8.7.1 is not met with the inverter on the alternate source, and Condition C, requires High Pressure Core Spray (HPCS) system to be declared inoperable immediately since the Division 4 NSPS bus was not energized from the inverter. Since HPCS is an emergency core cooling system and is a single train safety system, this is a condition that could have prevented fulfillment of a safety function and is reportable under 10 CFR 50.72(b)(3)(v)(D), system needed to mitigate the consequences of an accident.

"At 0925 CST, the Division 4 NSPS bus has been restored to service on the normal source. At 0925 CST, HPCS has been declared Operable.

"The NRC Resident has been notified."

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Power Reactor Event Number: 48766
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: MIKE HETTWER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/18/2013
Notification Time: 16:30 [ET]
Event Date: 02/18/2013
Event Time: 05:15 [EST]
Last Update Date: 02/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
ANTHONY DIMITRIADIS (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

24 HOUR NOTIFICATION OF INOPERABLE SCRAM DISCHARGE VOLUME VALVE BASED ON NRC BULLETIN 80-14

"On February 18, 2013 at 0515 hours, with the reactor at 100% core thermal power, a scram discharge volume valve, CV-302-22B was declared inoperable as required by station procedural direction due to an observed degradation in opening stroke time during performance of quarterly surveillance testing of the Scram Discharge Instrument Volume Vent and Drain Valves. This action was taken consistent with NRC IE Bulletin 80-14.

"Currently, station engineering is evaluating the valve stroke time trend data of CV-302-22B and a plan to address this issue will be developed as part of the Corrective Action Program. Pilgrim Technical Specification 3.3.G applies due to the inoperability of CV-302-22B.

"This notification is being made in accordance with NRC IE Bulletin 80-14, 'Degradation of BWR Scram Discharge Volume Capability,' Part A.3, which states, 'By procedures, require that the SDV [scram discharge volume] vent and drain valves be normally operable, open and periodically tested. If these valves are not operable or are closed for more than 1 hour in any 24 hour period during operation, the reason shall be logged and the NRC notified within 24 hours (Prompt Notification).

"This event has no impact on the health and safety of the public.

"The NRC Senior Resident Inspector has been informed."

The licensee will inform the State.

Page Last Reviewed/Updated Tuesday, February 19, 2013
Tuesday, February 19, 2013