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Event Notification Report for October 1, 2007

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/28/2007 - 10/01/2007

** EVENT NUMBERS **


43665 43671 43672 43673 43675 43676 43677

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General Information or Other Event Number: 43665
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: GEO-ENVIRONMENTAL, INC.
Region: 4
City: IRVINE State: CA
County:
License #: 7116-30
Agreement: Y
Docket:
NRC Notified By: DONELLE KRAJEWSKI
HQ OPS Officer: JASON KOZAL
Notification Date: 09/26/2007
Notification Time: 15:01 [ET]
Event Date: 09/25/2007
Event Time: 18:15 [PDT]
Last Update Date: 09/26/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CLAUDE JOHNSON (R4)
MICHELE BURGESS (FSME)

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

Event Text

AGREEMENT STATE REPORT - LOST / RECOVERED MOISTURE DENSITY GAUGE

"On September 25, 2006 at approximately 6:15 P.M., a gauge user from Geo-Environmental, Inc., had returned to the office to return Troxler gauge 3440, S/N 34036 (9 mCi Cs-137, 44 mCi Am-241:Be) to it's storage location, when he noticed that the gauge was missing and immediately contacted the RSO to report the incident. After the RSO had spoken with the gauge user, the RSO received a call from the office manager that the gauge had been recovered by the Irvine Police Department on Jamboree Rd. in Irvine near the intersection of Jamboree Rd., and Richter Ave. The gauge was returned to the Geo-Environmental, Inc., office at approximately 6:45 P.M. The gauge most likely was out of the control of the licensee for approximately one hour. The gauge case was intact with a single scuff mark. The gauge was inspected by the licensee and found to be intact. The RSO then contacted RHB [DELETED] by phone to report the incident by voice mail. At approximately 9:00 A.M. on September 26, 2007, [RHB] spoke with the RSO about the incident and instructed him to have the gauge inspected and leak tested by a service provider and the RSO stated that he would take the gauge to Maurer Technical Services to be inspected and leak tested. [RHB] also instructed the RSO to provide, within 30 days, a written report, in accordance to 10 CFR 20.2201 (a)(1)(i). The RSO stated that the gauge user involved was allowed to transport the gauge in an open bed truck and with two chains and two locks and with two locks on the gauge case. He also stated that the gauge was transported with only a single lock to secure both chains."

CA report number: 092607

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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Fuel Cycle Facility Event Number: 43671
Facility: PORTSMOUTH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
                   6903 ROCKLEDGE DRIVE
                   BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PIKETON State: OH
County: PIKE
License #: GDP-2
Agreement: Y
Docket: 0707002
NRC Notified By: RON CRABTREE
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 09/28/2007
Notification Time: 14:35 [ET]
Event Date: 09/28/2007
Event Time: 11:16 [EDT]
Last Update Date: 09/28/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
MALCOLM WIDMANN (R2)
ROBERT PIERSON (FSME)

Event Text

SMOKE FROM STEAM PLANT STARTUP REQUIRING STATE NOTIFICATION

"At 0930 hours, 09/28/07, the PORTS Plant Shift Superintendent's (PSS) Office was notified of an opacity exceedance, which had occurred at the X-600 Steam Plant on 09/18/07. The PORTS PSS Office notified the Ohio Environmental Protection Agency (OEPA) of this incident, at 1116 hours, 09/28/07. This notification to another government agency is reportable to the NRC as a 4-Hour Event per the United States Enrichment Corporation (USEC) Nuclear Regulatory Event Reporting Procedure UE2-RA-RE1030, Appendix D, Section P (Miscellaneous) which states: 'USEC shall notify NRC of any event or situation, related to the health and safety of the public or on-site personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made. Such an event may include an on-site fatality or inadvertent release of radioactively contaminated materials.'"

The start-up of the steam boiler was completed however, problems were encountered which created smoke after the state mandated time limit for startup smoke had expired.

The licensee notified the NRC Resident Inspector and the Department of Energy.

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Power Reactor Event Number: 43672
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: AVRAKOTOS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 09/28/2007
Notification Time: 14:40 [ET]
Event Date: 09/28/2007
Event Time: 13:00 [EDT]
Last Update Date: 09/28/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MEL GRAY (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

EMERGENCY SIREN ACTIVATED INADVERTENTLY DURING A THUNDERSTORM

"A single siren in the Nine Mile/FitzPatrick EPZ was inadvertently activated coincident with a thunderstorm and lightning strikes in the area of the siren. Oswego Co (New York) Emergency management officials are issuing a press release regarding the storm related siren activation. Attempts to silence the siren were not effective using the systems remote activation system further indicating that lightning affected the siren.

"A work crew has been dispatched to the siren to investigate and has silenced the siren. Notification is being provided to the NRC in regards to the potential for media inquiry."

The licensee informed the NRC Resident Inspector.

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Power Reactor Event Number: 43673
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: MARK ABRAMOVITZ
Notification Date: 09/28/2007
Notification Time: 16:12 [ET]
Event Date: 09/28/2007
Event Time: 13:10 [EDT]
Last Update Date: 09/28/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MEL GRAY (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

EMERGENCY SIREN ACTIVATED INADVERTENTLY DURING A THUNDERSTORM

"A single siren in the Nine Mile/FitzPatrick EPZ was inadvertently activated coincident with a thunderstorm and lightning strikes in the area of the siren. Oswego Co (New York) Emergency management officials are issuing a press release regarding the storm related siren activation. Attempts to silence the siren were not effective using the systems remote activation system further indicating that lightning affected the siren.

"A work crew has been dispatched to the siren to investigate and has silenced the siren. Notification is being provided to the NRC in regards to the potential for media inquiry."

The licensee informed the NRC Resident Inspector.

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Power Reactor Event Number: 43675
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: BRIEN STRIZZI
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 09/28/2007
Notification Time: 18:45 [ET]
Event Date: 09/28/2007
Event Time: 17:00 [EDT]
Last Update Date: 09/28/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
MEL GRAY (R1)

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

Event Text

REACTOR VESSEL HEAD VENT MAY NOT BE ISOLABLE DURING A FIRE

Plant engineering determined that in a postulated fire in the Control Room or Cable Spreading Room which required Control Room evacuation, that "hot shorts" may prevent the reactor vessel head vents from performing their emergency functions in accordance with the plant Emergency Operating Procedures (EOPs). Several relays in the letdown system are not isolated at the Auxiliary Shutdown Panel and have the potential for shorting during a fire. This letdown path can be aligned from the reactor vessel head vents during certain EOP scenarios.

The affected reactor vessel head vent isolation transfer switches are: 3RCS*SV8095A & B and 3RCS*SV8096A & B.

The site has implemented an hourly fire watch in the affected areas.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 43676
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: M. HINMAN
HQ OPS Officer: JOHN MacKINNON
Notification Date: 09/29/2007
Notification Time: 02:19 [ET]
Event Date: 09/28/2007
Event Time: 22:32 [EDT]
Last Update Date: 09/29/2007
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):
MALCOLM WIDMANN (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 30 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP DUE TO LOSS OF A STARTUP TRANSFORMER

"On September 28, 2007, while reducing power for a planned refueling outage with the reactor at approximately 30 percent power in MODE 1, an unplanned actuation of the reactor protection system occurred. At 2232 a fault pressure trip signal was received on the A Startup Transformer (SUT), causing a loss of power to Aux Buses D, A & C electrical buses as well as the A-SA safety bus. The loss of A & C buses initiated the RCP underfrequency trip which tripped the Reactor and all three RCPs as designed. The A Diesel Generator automatically started and reenergized bus A-SA as designed. The auxiliary feedwater system actuated as expected due to undervoltage on the A-SA safety bus and loss of the main feedwater pumps. All control rods inserted on the reactor trip. The operations staff responded to the event in accordance with applicable plant procedures. The plant stabilized at normal operating no-load reactor coolant system temperature and pressure following the reactor trip. Steam generator water levels are being maintained using auxiliary feedwater. All emergency core cooling system equipment is available. The plant electrical system is being restored at this time. The A SUT remains out of service. The cause of the loss of power from A SUT is under investigation.

"This condition is being reported as an unplanned reactor protection system actuation and specified system actuation in accordance with 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A)."

The NRC Resident Inspector was notified of this event by the licensee.

The plant was in natural circulation for approximately 1 hour. The Main Steam Isolation Valves (MSIVs) were manually isolated per procedure due to loss of EHC indication. Presently the B RCP has been restored to service, MSIVs are still closed, and the motor driven auxiliary feedwater pumps are feeding the Main Steam Generators. There are not any leaking steam generator tubes. The A EDG will be secured after backfeeding of the deenergized buses have been established.

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Power Reactor Event Number: 43677
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAN NIMICK
HQ OPS Officer: JOHN MacKINNON
Notification Date: 10/01/2007
Notification Time: 00:57 [ET]
Event Date: 09/30/2007
Event Time: 19:58 [PDT]
Last Update Date: 10/01/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
CLAUDE JOHNSON (R4)

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

Event Text

UNEXPECTED AUTOMATIC START OF THE 2-1 EMERGENCY DIESEL GENERATOR (EDG)

"A problem with voltage sensing circuit for 4 KV Bus G Startup power supply caused Diesel Generator 2-1 to automatically start. Loss of Startup voltage to a vital bus is an automatic start signal for the associated diesel generator. Startup power has been declared inoperable to 4 KV Bus G. All indications for Startup power to the other 2 vital busses remain normal. All systems functioned correctly in response to the sensed undervoltage condition. Unit 2 is in a 72 hour shutdown action statement per T. S. 3.8.1. An automatic start of a Diesel Generator is reportable per 10CFR50.72(B)(1)(iv)(A). The Diesel Generator has been shutdown per the annunciator response procedure and remains operable."

One of the four undervoltage relay starting power fuses for EDG 2-1 was found blown.

The NRC Resident Inspector was notified of this event by the licensee.

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Thursday, March 29, 2012