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Event Notification Report for June 24, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/21/2013 - 06/24/2013

** EVENT NUMBERS **


49111 49118 49140 49141 49142 49143 49144

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Agreement State Event Number: 49111
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: NRG TEXAS POWER LLC
Region: 4
City: THOMPSONS State: TX
County:
License #: 02063
Agreement: Y
Docket:
NRC Notified By: CHRIS MOORE
HQ OPS Officer: NESTOR MAKRIS
Notification Date: 06/13/2013
Notification Time: 16:26 [ET]
Event Date: 06/12/2013
Event Time: [CDT]
Last Update Date: 06/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
HEATHER GEPFORD (R4DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - FAILURE OF GAUGE SHUTTERS TO OPERATE

"On June 13, 2013, the licensee notified the Agency [State of Texas] that after completing maintenance on cables on Hoppers that one of the retest was to operate shutters on all nuclear gauges. The failures were identified on June 12, 2013. Eight gauge shutters failed to operate. The shutters are on Thermo Fisher Model #5197 gauges each containing 100 mCi of Cesium-137. The licensee stated that open is the normal operating position for the shutter and the gauge does not pose an exposure risk to any individual. The sources are not accessible to the general public or workers in the area. The licensee stated that a service provider will most likely remove and possible replace the gauges. The gauges have been in operation for approximately 30 years. Additional information will be provided as it is received in accordance with SA 300."

Texas Incident # I-9091

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Agreement State Event Number: 49118
Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: UNKNOWN
Region: 4
City: PHOENIX State: AZ
County:
License #:
Agreement: Y
Docket:
NRC Notified By: AUBREY GOODWIN
HQ OPS Officer: PETE SNYDER
Notification Date: 06/14/2013
Notification Time: 14:16 [ET]
Event Date: 11/19/2012
Event Time: [MST]
Last Update Date: 06/14/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
HEATHER GEPFORD (R4DO)
FSME EVENTS RESOURCE (EMAI)
ILTAB (EMAI)

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

Event Text

AGREEMENT STATE REPORT - ILLEGAL TRANSFER OF A DEVICE CONTAINING AMERICIUM-241

The following information was receive from the State of Arizona via e-mail:

"On May 16th, 2013, the Agency [Arizona Radiation Regulatory] received notification from the State of Texas that an illegal transfer of a device containing 30 millicuries of Americium-241 occurred on November 19, 2012. The device is a Thermo Niton XLP818 and the device serial number is 6380. The device was shipped from Longview Scrap & Metal, Inc. in Texas to an individual. The address that was given was to a mailbox company where the device was picked up. The company was not able to look up the reference number, due to it being 6+ months since the shipping date.

"The Agency continues to investigate the location of the device."

AZ First Notice: 13-010

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

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Power Reactor Event Number: 49140
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: THOMAS BUSSIERE
HQ OPS Officer: CHARLES TEAL
Notification Date: 06/21/2013
Notification Time: 10:50 [ET]
Event Date: 06/21/2013
Event Time: 10:30 [EDT]
Last Update Date: 06/21/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BINOY DESAI (R2DO)

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

Event Text

TECHNICAL SUPPORT CENTER TAKEN OUT OF SERVICE FOR PLANNED MAINTENANCE

"A condition is being reported per TRM 13.13.1 Emergency Response Facilities Action B.2. The Functionality of the Technical Support Center (TSC) has been lost due to planned maintenance activities performed on TSC Support Systems. Alternate facilities are available to provide emergency response functions and actions are proceeding to return the TSC to FUNCTIONAL status with high priority. A 10CFR50.54 (q) evaluation has been performed for this planned maintenance activity. The NRC Resident Inspector has been notified."

* * * UPDATE AT 1444 EDT ON 06/21/13 FROM THOMAS BUSSIERE TO S. SANDIN * * *

"Exit TRM 13.3.1: The functionality of the TSC has been restored and scheduled maintenance activities performed complete and satisfactory at 1410 EDT on 6/21/13. The NRC resident inspector has been notified."

Notified R2DO (Desai).

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Power Reactor Event Number: 49141
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: STEVE PETZEL
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 06/22/2013
Notification Time: 13:04 [ET]
Event Date: 04/24/2013
Event Time: 04:04 [CDT]
Last Update Date: 06/22/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
WAYNE WALKER (R4DO)

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

Event Text

60-DAY OPTIONAL TELEPHONE NOTIFICATION FOR AN INVALID SPECIFIED SYSTEM ACTUATION

"This 60-day telephone notification is being made per the reporting requirements specified in 10CFR50.73(a)(2)(iv)(A) and 10CFR50.73(a)(1) to report an event involving an invalid actuation signal affecting the Auxiliary Feedwater (AFW) and Essential Service Water (ESW) systems.

"Initial conditions on 04/24/2013: refueling outage was in progress, there was no fuel in the reactor vessel (No MODE), a B safety-related train outage was in progress, and the A ESW train was in operation to support cooling of the A train safety-related equipment. Some separation group 2 bistables were in a tripped condition because instrument power bus NN02 was de-energized.

"At approximately 0400 [CDT] on 04/24/2013, Separation Group 4 DC bus NK04 experienced a ground condition. Plant personnel were using a plant procedure to search for the ground. When breaker NK5409 was opened, some unexpected Engineered Safety Features Actuation System (ESFAS) signals occurred. Opening the breaker removed power to the B ESFAS cabinet. With power removed to the B ESFAS cabinet, the circuit cards that generate cross-train trips failed to a tripped condition (thus generating cross-train trip signals) which resulted in some A train ESFAS actuations, in particular, auxiliary feedwater actuations for the A motor-driven and the turbine-driven AFW pumps. Additionally, an AFW Low Suction Pressure (LSP) circuit card tripped, and when combined with the bi-stable that was in a tripped state because bus NN02 was de-energized, the 2-out-of-3 logic was made up, resulting in an auxiliary feedwater LSP actuation. The LSP actuation resulted in the A Train ESW pump receiving a start signal, and the A motor-driven and the turbine-driven AFW pump suction supply valves receiving an actuation signal to transfer the suction supply from the normal source to the ESW system.

"Neither the motor-driven nor the turbine-driven auxiliary feedwater pumps started because they had been properly removed from service earlier in the outage. The A ESW pump was already running. No water was transferred from the ESW system to the AFW system since system tagging had been previously placed to isolate the two systems.

"The actuations were considered invalid because they were caused by opening breaker NK5409 which resulted in loss of power to the B ESFAS cabinet.

"The Senior Resident Inspector was notified."

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Power Reactor Event Number: 49142
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: TIMOTHY KUDO
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 06/23/2013
Notification Time: 20:39 [ET]
Event Date: 06/24/2103
Event Time: 00:00 [EDT]
Last Update Date: 06/23/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BINOY DESAI (R2DO)

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

Event Text

TECHNICAL SUPPORT CENTER UNAVAILABLE DUE TO PRE-PLANNED FACILITY UPGRADES

"On June 24, 2013, at 0000 EDT, the Technical Support Center (TSC) will be unavailable due to a pre-planned facility upgrade project. The TSC is expected to be restored to operational status on July 1, 2013.

"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures, and the TSC staff will be located at a preplanned alternate location in accordance with applicable site procedures.

"This notification is being made in accordance with 10CFR 50.72 (b)(3)(xiii) due to the loss of an emergency response facility (ERF). An update will be provided once the TSC has been restored to operational status. The NRC Resident Inspector has been notified."

The upgrades will require structural changes to the TSC.

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Power Reactor Event Number: 49143
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ADAM PECK
HQ OPS Officer: VINCE KLCO
Notification Date: 06/24/2013
Notification Time: 04:35 [ET]
Event Date: 06/23/2013
Event Time: 21:20 [PDT]
Last Update Date: 06/24/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
WAYNE WALKER (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 Y 100 Power Operation 100 Power Operation

Event Text

LOSS OF 230 KV OFFSITE POWER RESULTS IN THE AUTOMATIC START OF EMERGENCY DIESEL GENERATORS

"At 2120 PDT, Diablo Canyon Power Plant experienced a loss of the offsite 230 kV startup power source due to an offsite transmission system relay actuation, resulting in valid anticipatory starts of Units 1 and 2 three emergency diesel generators on each unit. 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 only 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 was unavailable.

"Restoration of the 230 kV offsite power system is in progress."

The licensee will notify the NRC Resident Inspector.

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Power Reactor Event Number: 49144
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: NAVEEN KOTEEL
HQ OPS Officer: CHARLES TEAL
Notification Date: 06/24/2013
Notification Time: 04:49 [ET]
Event Date: 06/24/2013
Event Time: 04:30 [EDT]
Last Update Date: 06/24/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BINOY DESAI (R2DO)

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

Event Text

PLANNED MAINTENANCE ON THE TECHNICAL SUPPORT CENTER BACKUP GENERATOR

"A condition is being reported per TRM 13.13.1 Emergency Response Facilities Action B.2. The functionality of the Technical Support Center (TSC) has been lost due to planned maintenance activities performed on the backup diesel generator that supplies TSC Support Systems. Alternate facilities are available to provide emergency response functions and actions are proceeding to return the TSC to FUNCTIONAL status with high priority. A 10CFR50.54 (q) evaluation has been performed for this planned maintenance activity. The NRC resident inspector has been notified."

Page Last Reviewed/Updated Monday, June 24, 2013
Monday, June 24, 2013