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Event Notification Report for May 8, 2009

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
05/07/2009 - 05/08/2009

** EVENT NUMBERS **


44242 45016 45039 45040 45041 45045 45046

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General Information or Other Event Number: 44242
Rep Org: OK DEQ RAD MANAGEMENT
Licensee: WALMART
Region: 4
City: ENID State: OK
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MIKE BRODERICK
HQ OPS Officer: JOHN KNOKE
Notification Date: 05/27/2008
Notification Time: 17:10 [ET]
Event Date: 05/01/2003
Event Time: [CDT]
Last Update Date: 05/07/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
WILLIAM JONES (R4)
TERRANCE REIS (FSME)

Event Text

AGREEMENT STATE REPORT - TRITIUM RELEASE FROM EXIT SIGNS

"Wal-Mart stores reported to Oklahoma DEQ that they had found three damaged tritium exit signs during an audit of their signage. Two of the signs released tritium, the third did not release tritium. All three signs were at the Wal-Mart in Enid, Oklahoma. It appears that the signs were damaged by a 'walkie stacker' (similar to a fork lift) at an unknown date in 2003. The radioactive content of the signs was not recognized at the time of the damage. All three signs have been sent to Isolite for disposal or recycling. The signs were manufactured by SRB Technologies, Inc. Serial numbers of the leaking signs were 290130 and 290103.

"Wipe tests revealed removable contamination of about 800 dpm/100 sq. cm on the wall directly behind one sign, and a maximum removable contamination of 82,800 dpm/100 sq. cm on the cement floor below the other sign. Both leaking signs were in the shipping and receiving area of the store. Wal-Mart has hired Dade Moeller & Associates as consultants, and this company took the measurement and conducted remediation. Dade Moeller states that they will have a technician at the store to remediate the remaining contamination by the end of this week."

* * * UPDATE AT 1715 EDT BY HOWIE CROUCH ON 06/04/08 * * *

This report is a duplicate of EN# 44225. EN# 44225 will be removed from the database and the public website.

* * * UPDATE ON 5/07/2009 AT 1611 EDT BY VINCE KLCO * * *

An update was provided from Ralph Johnson to Joe O'Hara at 0914 on 3/19/09. Wal-Mart in Oklahoma performed an inventory of their generally licensed tritium exit signs and confirmed that a total of twelve were broken. This update corrects a previous update to a duplicate event notification.

Notified R4DO (Pick) and FSME (Schaffer).

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 45016
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: TOM FOWLER
HQ OPS Officer: KARL DIEDERICH
Notification Date: 04/23/2009
Notification Time: 16:23 [ET]
Event Date: 04/23/2009
Event Time: 09:10 [EDT]
Last Update Date: 05/07/2009
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 N 0 Refueling 0 Refueling

Event Text

ACTUATION OF AUTO LOAD SEQUENCER DURING FAST BUS TRANSFER TESTING

"At 0910 during planned testing of the 10A401 vital bus, an unplanned momentary loss of power was experienced when testing the fast transfer function. A delay of approximately 1 second was experienced when forcing a fast transfer (simulating a transformer lockout via the 86 device) from the alternate to the normal 4KV bus infeeds. This condition resulted in an initiation of the 'A' channel LOP sequencer (ELS) as a direct result of bus under voltage and is considered valid ESF actuation. All other equipment operated as expected that was available for service.

"The bus de-energized for <1 second and restored power automatically from the bus normal infeed. No major loads were lost. The channel is currently inoperable for planned maintenance and is not required per tech specs.

"Prior to the transient, the reactor was shut down, in operational condition 5, with all control rods fully inserted, and the reactor cavity flooded and communicating with the spent fuel pool. All other 'A' and 'C' channel equipment, including the 'A' and 'C' emergency diesel generators are inoperable for maintenance. Decay heat is being removed by the 'B' loop of residual heat removal operating in the shutdown cooling mode.

"No personnel were injured. The licensee is conducting an investigation to understand the response and cause."

The licensee has notified the NRC Resident Inspector and will notify the township.

* * * RETRACTION ON 5/7/2009 AT 1309 FROM TOM FOWLER TO MARK ABRAMOVITZ * * *

"During a subsequent review of the event, it has been determined that this was not a valid actuation of one of the systems listed in 10CFR50.72(b)(3)(iv)(B). The original report was made based on the event being an actuation of (8) Emergency AC electrical power systems, including: emergency diesel generators (EDGs); hydroelectric facilities used in lieu of EDGs at the Oconee Station; and BWR dedicated Division 3 EDGs'.

"The Hope Creek (HC) Updated Final Safety Analysis Report (UFSAR) 8.3.1.1.2 states that there are three potential power sources for the Class 1E AC power system: (a) normal power source, (b) alternate power source and (c) dedicated standby diesel generator (SDG). The HC UFSAR 8.3.1.1.3 lists the components of the 'Standby Power System' (Emergency AC Power System). The ELS is not one of the components listed. Additionally, the sequence of events did not complete the required logic to actuate a start of the EDG.

"Since no EDG actuation signal was generated, this was neither a valid nor invalid actuation of a system listed in 10CFR50.72(b)(3)(iv)(B) and is not reportable."

The licensee notified the NRC Resident Inspector.

Notified the R1DO (Caruso).

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 45039
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: ARNIE CRIB
HQ OPS Officer: DONALD NORWOOD
Notification Date: 05/03/2009
Notification Time: 18:29 [ET]
Event Date: 05/03/2009
Event Time: 03:10 [EDT]
Last Update Date: 05/07/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
RESPONSE-BULLETIN
Person (Organization):
MIKE ERNSTES (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

24-HOUR NRC BULLETIN 80-24 REPORT DUE TO POSSIBLE SERVICE WATER SYSTEM LEAKAGE INTO CONTAINMENT

"V.C. Summer Nuclear Station is notifying the NRC in accordance with NRC Bulletin 80-24, regarding Service Water System leakage into containment.

"At approximately 0310 on 05/03/09, Reactor Building sump sample analyses, in response to increasing sump level, indicated a probable leak from the Industrial Cooling Water System at 0.38 gpm.

"In accordance with Bulletin 80-24, a 14 day written report will be submitted."

The licensee is continuing to monitor at this time. A corrective action plan to definitively identify where the leak is coming from will be developed.

The licensee notified the NRC Resident Inspector. The licensee plans on notifying State of South Carolina and the counties of Fairfield, Richland, Lexington, and Newberry EP representatives.

* * * RETRACTION ON 5/7/2009 AT 1705 FROM JASON WEATHERSBY TO MARK ABRAMOVITZ * * *

"On 05/06/2009, a reactor building entry was made, and the previously reported leak was determined to be from the Industrial Cooling Water system. The location of the leak was from a mechanical seal of a non-safety rod position indication equipment cabinet cooling pump. No degradation of a containment boundary exists. EN # 45039 is being retracted, and a 14 day report will not be submitted."

The licensee notified the NRC Resident Inspector.

Notified the R2DO (Guthrie).

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General Information or Other Event Number: 45040
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: DOW CHEMICAL COMPANY
Region: 4
City: PORT LAVACA State: TX
County:
License #: 00051
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 05/04/2009
Notification Time: 13:40 [ET]
Event Date: 04/15/2009
Event Time: [CDT]
Last Update Date: 05/04/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
WAYNE WALKER (R4DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - PROCESS LEVEL GAUGE SHUTTER STUCK OPEN

The following report was received from the Texas Department of State Health Services via e-mail:

"The licensee reported that during the performance of a routine six month inspection, the shutter on an Ohmart/VEGA level gauge model SH-F2, containing a 200 mCi Cesium (Cs) - 137 source, serial # 7548GK, would not properly close. The gauge is used as a level monitor on a vent stack. The source was left in its normal operating position and does not pose an exposure risk to individuals. Radiation levels in the area were measured and found to be normal. As a corrective action, the licensee lubricated the operating mechanism on the gauge. They again tried to operate the mechanism, but could not. They continued to lubricate the mechanism periodically in an effort to free the mechanism. The licensee contacted a service provider and arrangements were made for assistance in closing the shutter if needed. On 4/29/09, the licensee was able to close the mechanism and operate the shutter normally. There was no apparent damage to the shutter operating mechanism."

Texas Report Number I-8633

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General Information or Other Event Number: 45041
Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: KELLOGG USA, INC
Region: 4
City: OMAHA State: NE
County:
License #: GL0552
Agreement: Y
Docket:
NRC Notified By: TRUDY HILL
HQ OPS Officer: BILL HUFFMAN
Notification Date: 05/04/2009
Notification Time: 13:53 [ET]
Event Date: 04/29/2009
Event Time: [CDT]
Last Update Date: 05/04/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
WAYNE WALKER (R4DO)
CHRISTEPHER MCKENNEY (FSME)
ILTAB VIA E-MAIL ()

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

Event Text

AGREEMENT STATE REPORT - MISSING TRITIUM EXIT SIGNS

The Nebraska Office of Radiological Health provided the following report via e-mail:

"The [Kellogg USA] facility was not able to locate four H-3 exit signs (SRB Model BXU20WS containing 17.51 Curies [each] of H-3, for serial #'s 217897, 217965, & SRB Model B100BX20 containing 17.51 Curies [each] of H-3 for serial #'s 220063 and 220071) while completing their annual inventory. They have made a number of searches and can not locate the four missing signs. The company is planning on the removal and proper disposal of all H-3 exit signs in the facility by 8/31/2009. The facility has 230 plus exit signs."

Nebraska Report NE090010


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.

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Power Reactor Event Number: 45045
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: PAT LEAHY
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/07/2009
Notification Time: 00:29 [ET]
Event Date: 05/06/2009
Event Time: 22:56 [EDT]
Last Update Date: 05/07/2009
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):
EUGENE GUTHRIE (R2DO)

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

Event Text

MANUAL REACTOR TRIP DUE TO FEED REGULATING VALVE FAILURE

"On 5/6/09 at 2256 Sequoyah Unit-1 was manually tripped from 100% reactor power. The manual trip was in response to the failure of Loop 1 Feed Water Regulating Valve (FRV). Manual control was attempted to control level in Loop 1 Steam Generator however Loop 1 FRV failed to respond. A manual reactor trip was initiated as a result of this failure. In addition, Auxiliary Feedwater (AFW) initiated as required due to a Feedwater Isolation signal. The Loop 1 FRV did not isolate from the Feedwater Isolation signal, however the Loop 1 Feedwater Isolation Valve closed as designed.

"The Plant is currently being maintained in Mode 3 at NOT/NOP, approximately 547 [degrees] F and 2235 psig, with Auxiliary Feedwater supplying the steam generators and Steam Dumps to Main Condenser removing decay heat.

"Maintenance activities have been initiated to repair the Loop 1 FRV."

All rods inserted on the trip. No safety or relief valves lifted as a result of the transient. The plant is in its normal shutdown electrical lineup. No grid instabilities exist and there was no effect on Unit 2.

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 45046
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: TOM FOWLER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 05/07/2009
Notification Time: 13:09 [ET]
Event Date: 04/13/2009
Event Time: 16:46 [EDT]
Last Update Date: 05/07/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
JOHN CARUSO (R1DO)

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

Event Text

HUMAN PERFORMANCE ERROR WHILE TROUBLESHOOTING A POWER SUPPLY

"This telephone notification, instead of a written LER is provided in accordance with 10CFR50.73(a)(1), to report an invalid actuation reportable under 10CFR50.73(a)(2)(iv)(A).

"On 4/13/2009, during troubleshooting activities for a control room annunciator power supply problem, a 'D' channel LOCA Level 1 Isolation Logic relay trip occurred when the relay power supply was de-energized and then re-energized. De-energization of the relays caused the 'D' Emergency Diesel Generator (EDG) to auto start, the 'B' Control Room Emergency Filtration System to auto start and the 'D' Safety Auxiliaries Cooling System pump to auto start. The other components of this logic system were properly removed from service and did not actuate.

"This is classified as an 'invalid' actuation reportable under 50.73(a)(2)(iv)(A). The logic system actuation was due to a human performance error and not the plant conditions. At the time, the plant was in Operational Condition 5 with the reactor cavity flooded and 'A' RHR system in shutdown cooling. In accordance with the existing plant conditions, all actions that should have occurred for this actuation did occur; no other initiations or actuations were noted.

"This event was entered into the HCGS [Hope Creek Generating Station] corrective action program.

"There was no radiological release associated with this event.

"The NRC Senior Resident Inspector has been notified of this report."

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