The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Event Notification Report for November 3, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/31/2014 - 11/03/2014

** EVENT NUMBERS **


50564 50586 50587 50588

To top of page
Agreement State Event Number: 50564
Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: CASTLE METALS
Region: 3
City: FRANKLIN PARK State: IL
County:
License #: 9223619
Agreement: Y
Docket:
NRC Notified By: DAREN PERRERO
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 10/24/2014
Notification Time: 12:28 [ET]
Event Date: 10/03/2014
Event Time: [CDT]
Last Update Date: 10/24/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
PATTY PELKE (R3DO)
FSME EVENTS RESOURCE (EMAI)
ILTAB (EMAI)

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

Event Text

AGREEMENT STATE REPORT - LOST PORTABLE FLUORESCENCE ANALYZER

"During a routine request for an annual inventory audit by the Agency [Illinois Emergency Management Agency], the generally licensed registrant was unable to locate their hand held thin metal alloy analyzer. The unit was a 'triple head' unit containing 3 sources. It was replaced by a newer x-ray producing unit a few years ago but was retained as a back up. Current and past employees were questioned during the investigation and the registrant will continue its search although they believe it unlikely to be fruitful. When it went unused, it was believed to be discarded with other equipment and junked. At this time, the radioactive iron and cadmium sources are decayed to less than milliCurie quantities and have a negligible radiation profile associated with them and they pose no threat to public health and safety were they some how removed from the device. The americium source however remains and if disposed as described, the device would show no elevated radiation levels from its surface. Based on similar equipment information in the sealed source device registry, if the internal shutter mechanism were somehow to be rotated open with the Am-241 source in the analyze position, the only measurable radiation would be found at the front of the device and would be less than 2 millirem/h at a foot. Pending additional developments, the Agency is considering this matter closed."

Device Name: FLUORESCENCE ANALYZER.
Model Number: XL 309-831S.
Manufacturer: NITON.
Serial Number: U3052 6125LY.

Containing the following sources;

Sealed Source: .014 Ci, AM-241.
Manufacturer: AMERSHAM.
Model Number: AMC.P4.
Serial Number: 1076CW

Sealed Source: .0007 Ci, CD-109.
Manufacturer: AMERSHAM
Model Number: IEC.A1.
Serial Number: 8819LG.

Sealed Source: .000007 Ci, CD-109.
Manufacturer: AMERSHAM.
Model Number: CUCP.1.
Serial Number: 6125LY.

Cause: Human Error.

Illinois Item Number: IL14020.

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

To top of page
Power Reactor Event Number: 50586
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WES FIANT
HQ OPS Officer: DANIEL MILLS
Notification Date: 11/01/2014
Notification Time: 02:07 [ET]
Event Date: 10/31/2014
Event Time: 17:40 [PDT]
Last Update Date: 11/01/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JACK WHITTEN (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
2 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

AUTOMATIC EMERGENCY DIESEL GENERATOR START DUE TO LOSS OF OFFSITE 230KV STARTUP POWER SUPPLY

"At 1740 PDT, Diablo Canyon Power Plant experienced a loss of the offsite 230 kV startup power source. This was due to a 230 kV switchyard bus differential relay actuation during a rainstorm, resulting in valid anticipatory starts of each unit's three emergency diesel generators. All diesels successfully started but were not loaded. All systems operated as designed with no problems observed.

"The 230 kV startup power source is the offsite power system designed to be immediately available following an accident. However, the safety related onsite emergency diesel system would have provided power to mitigate the consequences of an accident while the 230 kV [supply] was unavailable.

"Unit 1 remains on line at 100 percent power. Unit 2 is currently in Mode 5 in the process of completing a planned refueling outage. Unit 2 power was supplied from the 500kV offsite power source at the time of this event and was therefore unaffected.

"The offsite 230 kV startup power source has been restored to service."

The NRC Resident Inspector has been notified.

The normal offsite power supply remained available and unaffected.

To top of page
Power Reactor Event Number: 50587
Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: PERRY GRAHAM
HQ OPS Officer: DANIEL MILLS
Notification Date: 11/01/2014
Notification Time: 05:03 [ET]
Event Date: 11/01/2014
Event Time: 02:48 [EDT]
Last Update Date: 11/01/2014
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):
CHRISTINE LIPA (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 100 Power Operation 0 Hot Standby
2 M/R Y 50 Power Operation 0 Hot Standby

Event Text

DUAL UNIT MANUAL REACTOR TRIPS DUE TO LOWERING CONDENSER VACUUM AND DEGRADED FOREBAY

"On November 1, 2014, at 0249 [EDT], DC Cook Unit 1 reactor was manually tripped and at 0248 [EDT] DC Cook Unit 2 was manually tripped due lowering condenser vacuum caused by degraded forebay conditions (observed thick grass and sand). U-1 and U-2 entered Abnormal Operating Procedure for Degraded Forebay on November 1, 2014 at 0153 [EDT]. Conditions degraded in U-1 and U-2 until all but 2 screens in each unit were tripped on overload and main condenser vacuum was lowering. U-1 and U-2 met criteria in the Degraded Forebay procedure to remove the units from service and remove all circulating water pumps from service.

"This event is reportable under 10 CFR 50.72(b)(2)(iv)(B), Reactor Protection System (RPS) actuation, as a four (4) hour report, and under 10 CFR 50.72(b)(3)(iv)(A), specified system actuation of the Auxiliary Feedwater System, as an eight (8) hour report.

"The electrical grid is stable. Unit 1 and Unit 2 are being supplied by offsite power. All control rods fully inserted in both units. Decay heat is being removed by steam generator PORVs. Preliminary evaluation indicates all plant systems functioned normally following the reactor trip with the exception of U-1 turbine driven auxiliary feed pump. DC Cook Unit 1 and Unit 2 remain stable in Mode 3 while conducting the post trip review. No radioactive release is in progress as a result of this event.

"Additional information received determined the Unit 1 turbine driven auxiliary feedwater pump tripped for unknown reasons. Feedwater flow to all steam generators was maintained by the U-1 east and west motor driven auxiliary feedwater pumps.

"U-2 reactor power was lowered from 100 percent to 50 percent over the hour prior to the trip in accordance with the Degraded Forebay Procedure.

"The DC Cook NRC Resident Inspector has been notified."

* * * UPDATE PROVIDED BY RICHARD HARRIS TO JEFF ROTTON AT 0945 EDT ON 11/01/2014 * * *

At 0921 EDT, DC Cook issued a press release regarding the event described earlier.

The licensee notified the NRC Resident Inspector.

Notified R3DO (Lipa)

To top of page
Power Reactor Event Number: 50588
Facility: HATCH
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: SCOTT BRITT
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/02/2014
Notification Time: 12:26 [ET]
Event Date: 11/02/2014
Event Time: 07:20 [EDT]
Last Update Date: 11/02/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ALAN BLAMEY (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

Event Text

OPERATIONS SUPPORT CENTER VENTILATION SYSTEM OUT OF SERVICE

"On November 2, 2014 EST, the bus providing power to the Health Physics emergency HVAC system for climate control tripped unexpectedly and has been out of service for greater than 30 minutes. The Health Physics emergency HVAC system for climate control is required for functionality of the Operations Support Center (OSC), which is a required emergency response facility (ERF). Actions to determine the cause of loss of 1R24-S030 Load Center and to return ERF to functional status are in progress with high priority. In the interim, the backup OSC remains fully functional and capable of providing the required support as defined in the Hatch Emergency Plan and emergency implementing procedures.

"This notification is being made in accordance with the plant's Technical Requirements Manual Specifications to make the notification within 8 hours in accordance with 10 CFR 50.72 (b)(3)(xiii) due to the unplanned loss of an emergency response facility. An update will be provided once the OSC has been restored to normal operation."

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM JOHN MITCHELL TO HOWIE CROUCH AT 2126 EST ON 11/2/14 * * *

Power was restored to the 1R24-S030 Load Center at 1955 EST. At 2038 EST, power to the Health Physics emergency HVAC system was restored. The OSC was returned to service at 2120 EST.

The licensee has notified the NRC Resident Inspector. Notified R2DO (Blamey).

Page Last Reviewed/Updated Thursday, March 25, 2021