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Event Notification Report for June 28, 2007

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/27/2007 - 06/28/2007

** EVENT NUMBERS **


43168 43449 43450 43451 43452 43453 43454

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Other Nuclear Material Event Number: 43168
Rep Org: MCCALLUM TESTING LABORATORY
Licensee: MCCALLUM TESTING LABORATORY
Region: 1
City: CHESAPEAKE State: VA
County:
License #: 45-15325-01
Agreement: N
Docket:
NRC Notified By: PHIL BERMAN
HQ OPS Officer: PETE SNYDER
Notification Date: 02/15/2007
Notification Time: 14:17 [ET]
Event Date: 02/15/2007
Event Time: 13:50 [EST]
Last Update Date: 06/27/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
JOHN WHITE (R1)
MICHELE BURGESS (NMSS)
ILTAB (e-mail) ()

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

Event Text

LOST TROXLER MOISTURE DENSITY GAUGE

A Troxler Moisture Density Gauge (model 3411, serial number 6957) was lost at a traffic intersection in Chesapeake, VA. The location of the intersection is at Route 17 and George Washington Parkway. The licensee called local police. The radiation safety officer (RSO) is responding to the site to see if the gauge can be found or if any damage to instrument exists.

* * * UPDATE AT 1447 ON 2/15/07 FROM P. BERMAN TO P. SNYDER * * *

The licensee reports that the gauge has been found and taken to the local fire department. The RSO is going to the location to examine the gauge for damage.


* * * UPDATE AT 1147 EDT ON 6/27/07 FROM BERMAN TO HUFFMAN * * *

When the RSO arrived at the fire department on 2/15/07, the gauge was determined to be damaged upon examination. Inspection revealed that the source rod was missing. The pickup truck driven by the city worker that found the gauge was still at the fire department. The truck was examined and the source rod was located loose in the bed of the truck. The RSO picked up the source rod and placed it back into the gauge. The source rod apparently fell out of the gauge while it was being transported to the fire department and was not handled by the individual who found the gauge. The extremity and whole body exposure for the RSO that handled the source rod is estimated to be less than annual limits. Subsequent leak testing of the source rod showed no compromise of the source. R1DO (Powell) and FSME EO (Hackett) notified.


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: 43449
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RANDALL RAHRIG
HQ OPS Officer: JASON KOZAL
Notification Date: 06/27/2007
Notification Time: 11:34 [ET]
Event Date: 06/27/2007
Event Time: 09:21 [CDT]
Last Update Date: 06/27/2007
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):
JAMNES CAMERON (R3)

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

Event Text

REACTOR TRIP DUE TO OFF-SITE POWER FLUCTUATION

"Switchyard line 2001 tripped and re-energized during a thunderstorm. This caused main generator output breaker, ACB 3-4, to trip open. At this time '1D' reactor coolant pump (RCP) tripped and caused a reactor trip. Cause for the '1D' RCP trip is under investigation.

"The heat sink is being provided by Aux Feedwater and the use of Steam Dumps. Electrical power is being provided by offsite power."

All rods inserted. There were no complications during the trip and all systems functioned as required. Offsite power remained available throughout the transient. The electrical transient had no impact on Unit 2.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 43450
Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [ ] [ ]
RX Type: [2] W-3-LP
NRC Notified By: CURTIS CASTELL
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/27/2007
Notification Time: 12:56 [ET]
Event Date: 05/01/2007
Event Time: 23:39 [EDT]
Last Update Date: 06/27/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
DAVID AYRES (R2)

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

Event Text

INVALID SYSTEM ACTUATION

"This telephone notification to report an invalid actuation is provided in accordance with 10 CFR 50.73(a)(1), which states, 'In the case of an invalid actuation reported under Sec. 50.73(a)(2)(iv), other than actuation of the reactor protection system (RPS) when the reactor is critical, the licensee may, at its option, provide a telephone notification to the NRC Operations Center within 60 days after discovery of the event instead of submitting a written LER.' The specific reporting requirement in 10 CFR 50.73(a)(2)(iv)(A), states, 'Any event or condition that resulted in manual or automatic actuation of any of the systems listed in paragraph (a)(2)(iv)(B).' For this report, the affected system was the emergency AC electrical power systems as listed in 10 CFR 50.73(a)(2)(iv)(B)(8). Specifically, the Train A emergency diesel generator (EDG) automatically started due to an invalid system actuation.

"On May 1, 2007, at approximately 2339 hours (EDT), with H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, in MODE 5 with reactor coolant system temperature at approximately 84 degrees F, during activities associated with surveillance testing as part of Refueling Outage 24, the Train A EDG automatically started from the standby condition. The Train A EDG did not automatically connect to the associated emergency bus (E-1), because no E-1 bus undervoltage (UV) signal was present. The automatic start was caused by the inadvertent grounding of a test connection lead that was being used to monitor the Train A EDG during testing. The grounding of the test lead resulted in a drop in voltage on the starting circuitry that caused the actuation of the 4A diesel start relay. The Train A EDG successfully started and achieved the required speed and voltage. As previously stated, the EDG did not load because no UV signal was present on the associated E-1 bus. No failures or abnormalities were noted.

"The Train B EDG remained operable during this event and the Train A EDG was able to provide power to E-1 emergency bus, if necessary.

"The invalid EDG start event was entered into the corrective action program for HBRSEP, Unit No. 2. The investigation of this event has been completed. The results of the investigation determined that the EDG start was caused by improper isolation of a safety significant power source from the field installed equipment. The Plant Nuclear Safety Committee has reviewed the investigation associated with this reportable event and concurred with the investigation. Corrective actions for this event are in progress and are being tracked via the corrective action program."

The licensee informed the NRC Resident Inspector.

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Power Reactor Event Number: 43451
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: BRIAN FINCH
HQ OPS Officer: BILL HUFFMAN
Notification Date: 06/27/2007
Notification Time: 14:33 [ET]
Event Date: 06/27/2007
Event Time: 10:15 [EDT]
Last Update Date: 06/27/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RAY POWELL (R1)

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 COMMUNICATIONS CAPABILITY AT EOF

"At approximately 1015, Nine Mile Point Emergency Planning noted the loss of phone service in the Emergency Operations Facility (EOF) and Joint News Center (JNC) during a routine surveillance. Nine Mile Point emergency planning staff were subsequently notified at 1030. [During] discussions with the Oswego County 911 center (sole 10 mile EPZ county), it was determined that phone service in the Windstream phone company that services that area was lost at approximately 1015 hours. Most telephone and data capability at the EOF and Joint Information Center (JIC) is out of service at this time. Cellular and satellite phone backups are available. The primary and backup means to notify the local and state agencies from Nine Mile Point and JA Fitzpatrick is unaffected and has been tested as operable. The Emergency Response Organization (ERO) notification system is unaffected and has been confirmed as operable. Sirens and tone alerts are unaffected.

"Local phone service provider is investigating cause which is currently unknown."

The licensee notified the NRC Resident Inspector.

See related Event #43453.

* * * UPDATE FROM MINNICK TO HUFFMAN AT 2034 EDT ON 6/27/07 * * *

"Repairs to the emergency phone systems have been completed and all systems tested satisfactory as of 2012 on June 27, 2007."

The licensee notified the NRC Resident Inspector. R1DO (Powell) notified.

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Power Reactor Event Number: 43452
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: THOMAS STEC
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/27/2007
Notification Time: 15:17 [ET]
Event Date: 05/03/2007
Event Time: 00:58 [EST]
Last Update Date: 06/27/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
JAMNES CAMERON (R3)

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

Event Text

INVALID SYSTEM ACTUATION

"This event is being reported in accordance with 10 CFR 50.73(a)(1) and 10 CFR 50.73(a)(2)(iv)(A). This condition meets the criteria of 10 CFR 50.73(a)(2)(iv)(A) for any event or condition that results in manual or automatic actuation for any of the systems listed in paragraph 10 CFR 50.73(a)(2)(iv)(B). The specific requirements apply here to 'General containment isolation signals affecting containment isolation valves in more than one system.'

"During the performance of surveillance instruction 'Low Pressure Coolant Injection (LPCI) 'B' and 'C' Initiation and Loss of EH12 Response Time Test,' the following valves auto closed during the test activities:

- 1G61-F0075 (Containment Equipment Drain Inboard Isolation),
- 1G61-F0165 (Containment Floor Drain Inboard Isolation),
- 1P11-F0090 (Containment Pools Drain Inboard Isolation), and
- 1P50-F140 (Containment Vessel Chilled Water Inboard Return MOV Isolation)

"The signals are considered to be invalid as the signals were a result of test activities and not actual plant conditions. The valve logic to close the valves was momentarily satisfied due to the sequence of electrical power restoration during the test; however, the test did not address the valve movement and the valve actuations could not be considered to be preplanned. The system actuations were considered to be partial, and the valves functioned successfully as designed.

"The event was captured within the corrective action program under condition report (CR) 07-19866.

"The resident inspector was notified of this event notification."

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Power Reactor Event Number: 43453
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: TIM PAGE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 06/27/2007
Notification Time: 15:20 [ET]
Event Date: 06/27/2007
Event Time: 10:15 [EDT]
Last Update Date: 06/27/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RAY POWELL (R1)

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 COMMUNICATIONS CAPABILITY AT EOF

"At approximately 1015 On June 27, 2007, with the James A. Fitzpatrick (JAF) Nuclear Power Plant operating at 100% reactor power, a loss of phone service occurred in the Emergency Operations Facility (EOF) and Joint information Center (JIC).

"Discussions with the Oswego County 911 Center (only county within the 10 mile EPZ) determined that phone service in the service area was lost at approximately 1015 hours on June 27,2007. Most telephone and data capability at the EOF and JIC are out of service at this time. Cellular arid satellite phone backups are available at the EOF and JIC. The primary and backup means to notify federal, state and local agencies from JAF are unaffected and have been tested and are operational. The Emergency Response Organization (ERO) notification system is unaffected and has been confirmed to be operational. Sirens and tone alert systems are unaffected.

"This loss of phone service is considered to be a major loss of offsite communications capability and is therefore reportable as an eight (8) hour telephone notification under 10 CFR 50.72(b)(3)(xiii).

"Repairs are in progress.

"The NRC resident inspector has been briefed and the New York State PSC will be notified."

See related Event #43451.

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Power Reactor Event Number: 43454
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JEFF TODD
HQ OPS Officer: BILL HUFFMAN
Notification Date: 06/27/2007
Notification Time: 18:44 [ET]
Event Date: 06/27/2007
Event Time: 15:55 [EDT]
Last Update Date: 06/27/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
DAVID AYRES (R2)

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 HABITABILITY ISSUE

"At 15:55 ET on 6/27/07 - notified by the Vogtle Emergency Preparedness that the limit switch full closed indication on the Technical Support Center (TSC) HVAC Outside Air Damper not being functional [which] impacted habitability of the TSC. This is due to the full closed limit switch providing a signal to inflate the sealing boot on the associated damper. This is reportable under 10CFR 5072(b)(3)(xiii). (8 hour notification)

"At 6:53 ET on 6/27/07 - TSC HVAC was placed in service in the filtration mode with the damper limit switch manually adjusted to provide full closed indication. The TSC HVAC is fully functional and supporting TSC habitability at this time.

"TSC HVAC will remain in service in the filtration mode until the repair plan for the damper is implemented."

The licensee notified the Region 2 Duty Officer (Ayres).

Page Last Reviewed/Updated Thursday, March 29, 2012
Thursday, March 29, 2012