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Event Notification Report for November 1, 2006

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/31/2006 - 11/01/2006

** EVENT NUMBERS **


41936 42935 42946 42950 42951 42952

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General Information or Other Event Number: 41936
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: CONVERSE CONSULTANTS
Region: 4
City: COSTA MESA State: CA
County:
License #: 4841-30
Agreement: Y
Docket:
NRC Notified By: ROBERT GREGER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 08/22/2005
Notification Time: 13:39 [ET]
Event Date: 08/21/2005
Event Time: 12:00 [PDT]
Last Update Date: 10/31/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
LINDA SMITH (R4)
GREG MORELL (NMSS)
PEREZ (email) (TAS)
MEXICO CNSNS (fax) ()

Event Text

AGREEMENT STATE REPORT FROM CALIFORNIA: STOLEN AND RECOVERED CPN MOISTURE DENSITY GAUGE

"RHB received notification this morning that an MC-3 CPN moisture-density gauge with 10 mCi [millicuries] (nominal) Cs-137 AND 50 mCi (nominal) Am-241 was stolen from the back of a truck in the City of Garden Grove, sometime yesterday. The RSO had very few details, and intends to forward a copy of the police report as soon as he receives it. The "Other Contact" listed above is the gentleman who was transporting the gauge when it was stolen. The truck was parked at the individual user's home over the weekend, when the gauge was stolen. I asked whether they would be offering a reward, and the RSO said he would discuss that with company management.

"CPN MC3 M37027389
"Cs-137 370 MBq (10mCi)
"Am-241/Beryllium 1.85 GBq (50 mCi)"

State of California Assignment Number for the event: 082205.

* * * UPDATE FROM STATE (D. KRAJEWSKI) TO M. RIPLEY AT 1927 EST ON 10/31/06 * * *

The State provided the following information via email:

"On October 31, 2006, I received an e-mail from [NAME DELETED] from Converse Consultants [EMAIL ADDRESS DELETED] that the gauge (CPN, MC-3, SN # M37027389) was recovered by the Santa Ana Police Department [NAME DELETED] in the parking lot of an apartment complex. The gauge was returned to Converse Consultant who transported the gauge to Maurer Technical to have it leak tested and to get an estimate for repair. The handle of the gauge was in the 'safe' (shielded) position with the source retracted, but horizontal portion of the handle was broken off. The gauge had been repainted. The case was recovered also, but the gauge was not found in the case."

Notified R4 DO (D. Powers), NMSS EO (R. Pierson), Mexico (fax), and ILTAB (email)


Less than the quantity of a Category 3 source.

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.

For some of these sources, such as moisture density gauges or thickness gauges that are IAEA 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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General Information or Other Event Number: 42935
Rep Org: SC DIV OF HEALTH & ENV CONTROL
Licensee: MCLEOD REGIONAL MEDICAL CENTER
Region: 1
City: FLORENCE State: SC
County:
License #: 139
Agreement: Y
Docket:
NRC Notified By: MELINDA BRADSHAW
HQ OPS Officer: BILL GOTT
Notification Date: 10/26/2006
Notification Time: 17:34 [ET]
Event Date: 05/25/2006
Event Time: [EDT]
Last Update Date: 10/26/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES NOGGLE (R1)
ROBERT PIERSON (NMSS)

Event Text

AGREEMENT STATE REPORT

The State provided the following information via facsimile:

"The SC Department of Health and Environmental Control was notified on Wednesday, October 18, 2006, by letter dated October 9, 2006, that a possible Medical Event involving a fetus took place in May 2006. According to a letter from the RSO at McLeod Regional Medical Center, a female patient was dosed with 14 microcuries of Iodine 131 on May 24, 2006, and 15 millicuries of Technetium 99m on May 25 as a prelude to a Nuclear Medicine Thyroid Therapy Ablation. The patient denied the possibility of pregnancy and signed an informed consent specifically addressing pregnancy and fetal exposure. This was following an explanation by the Radiologist of the exact procedure. A dose of Iodine 131 in the amount of 14.8 millicuries was then given the patient for the thyroid ablation.

"The patient's OB/GYN physician notified the radiology department as of October 9, 2006, that the patient is now approximately 32 to 34 weeks pregnant. A calculation is being done to determine the exposure dose to the fetus and fetal thyroid. This information is to be sent to the Department once completed. This is all the information available on this situation and determination has not been made that it is a medical event. The investigation is still ongoing. The incident will be updated once additional material is received."


A "Medical Event" may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

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Power Reactor Event Number: 42946
Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MARK FIOCCO
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 10/30/2006
Notification Time: 01:10 [ET]
Event Date: 10/29/2006
Event Time: 20:11 [EST]
Last Update Date: 10/31/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JAMES NOGGLE (R1)

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

Event Text

AUTOMATIC START OF AUXILIARY FEEDWATER DURING MSIV TESTING

"This is an 8 hour notification being made to report that a valid ESF auxiliary feed actuation occurred. Salem Unit 2 is in Mode 4 with RHR providing shutdown cooling. 21, 22, and 23 reactor coolant pumps are in service providing forced circulation.

"While performing a main steam isolation valve stroke test for maintenance concurrent with main turbine valve surveillance testing, 22 steam generator narrow range level indication shrunk to 7%, which is below the low level trip setpoint of 14%, causing an automatic start of 21 and 22 auxiliary feedwater pumps. There was no other testing or evolutions in progress at the time of the event that contributed to the automatic start of the auxiliary feedwater pumps.

"Steam generator parameters at the time of the event where 0 psig and 223 degrees (T-cold). Main condenser vacuum was established.

"23 auxiliary feedwater pump was tagged for maintenance and did not start.

"22 steam generator level was restored to normal level and the 21 and 22 auxiliary feedwater pumps secured.

"There were no personnel injured."

During this event, the main turbine governor valves were off their closed seats when the MSIVs were stroked.

The licensee notified the NRC Resident Inspector.

* * * UPDATE PROVIDED BY STRAUBMULLER TO KOZAL ON 10/31/2006 AT 0146 * * *

"Subsequent to the initial notification, it has been determined that in addition to reporting the auxiliary feedwater pumps starting on low steam generator level, it is required to report that the reactor protection system opened the reactor trip breakers as designed. The reactor trip breakers were closed for surveillance testing of the main turbine. Actuation of the reactor trip breakers is reportable under [10 CFR] 50.72 (b)(3)(iv)(A) for this event."

The licensee notified the NRC Resident Inspector.

Informed R2DO (GRAY)

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Power Reactor Event Number: 42950
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: DON GREGOIRE
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 10/31/2006
Notification Time: 10:04 [ET]
Event Date: 10/31/2006
Event Time: 04:45 [PST]
Last Update Date: 10/31/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
DALE POWERS (R4)

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

Event Text

REACTOR TRIP FROM TURBINE TRIP ON LOW AUTO STOP OIL PRESSURE

"Reactor trip at 0445 following a turbine trip. Initial indication of cause is turbine trip due to low auto stop oil pressure. There were no complications in plant response. Plant is stabilized in mode three, heat removal is being maintained by turbine bypass valves."

All control rods fully inserted on the trip, no safety or relief valves lifted during the transient, reactor water level 3 isolations did isolate, and the minimum level attained during the transient was -6 inches. Vessel water level is being maintained with normal feedwater flow and the electrical lineup is the normal shut-down electrical lineup. The cause of the low auto stop oil pressure is under investigation.

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM LICENSEE (M. HUMMER) TO M. RIPLEY AT 1439 EST ON 10/31/06 * * *

"In response to questions raised during this event notification, a verbal response was provided to the NRC that an 8 hour notification in accordance with 50.72(b)(3)(iv)(A) [Specified System Actuation] was required. Upon further review it has been determined by Energy Northwest that this notification was not required because all required reporting was satisfied by 50.72(b)(2)(iv)(B)."

The licensee will notify the NRC Resident Inspector. Notified R4 DO (D. POWERS)

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Power Reactor Event Number: 42951
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: KELLI VOELSING
HQ OPS Officer: MIKE RIPLEY
Notification Date: 10/31/2006
Notification Time: 13:14 [ET]
Event Date: 10/31/2006
Event Time: 06:10 [EST]
Last Update Date: 10/31/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CAROLYN EVANS (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

Event Text

OFFSITE EMERGENCY SIRENS INOPERABLE

"At 0810, Eastern Standard Time, the Harris Nuclear Plant (HNP) determined that the offsite emergency sirens were not capable of being activated. This event requires an 8-hour non-emergency notification per 10CFR 50.72(b)(3)(xiii) due to the loss of a significant portion of the offsite notification system. The NRC Senior Resident Inspector was informed. In the event that the sirens had been needed, the State of North Carolina and all four counties within the 10-mile emergency planning zone would have implemented mobile route alerting, as detailed In the Emergency Plan. Tone Alert Radios for notification of residents within the 5-mile emergency planning zone were also available and operable.

"The siren failures began to occur during the regularly scheduled 12-hour test at 0510. The most probable cause was a failed 'B' Repeater which rendered the controller at the microwave tower unable to activate the sirens. The 'B' Repeater was removed from the system and all sirens were operating as designed following a satisfactory system test at 0748. The State of North Carolina and all four counties within the 10-mile emergency planning zone were briefed on this occurrence and notified of system restoration by 1145. The plant continues to troubleshoot to determine the cause of the 'B' Repeater failure. In the interim, HNP is conducting frequent interrogation of the siren system to ensure that the system continues to function correctly. The system is now operating with the 'A' Repeater. The 'B' Repeater will be replaced as a part of the troubleshooting and repair plan.

"HNP is responding to local media inquiries."

See directly related event EN # 42948 of 10/30/06

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Power Reactor Event Number: 42952
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: S. GANZ
HQ OPS Officer: MIKE RIPLEY
Notification Date: 10/31/2006
Notification Time: 20:14 [ET]
Event Date: 10/31/2006
Event Time: [CST]
Last Update Date: 10/31/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
DALE POWERS (R4)
MELVYN LEACH (IRD)
STUART RICHARDS (NRR)

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

CONTRACTOR EMPLOYEE FATALITY

"This report is being made pursuant to 10CFR50.72(b)(2)(xi), 4-hour Non-Emergency Report due to potential media interest and offsite notification. At approximately 1130 CST on October 31, 2006, the Callaway Plant control room was notified of a non-work related medical emergency involving a Wackenhut contract employee. Onsite medical personnel responded to the scene and administered first aid for an apparent heart attack. An ambulance was dispatched and the individual was transported offsite to a local hospital. The individual was not contaminated.

"At approximately 1545 [CST], Callaway Plant was notified that the individual had passed away. Wackenhut notified OSHA of the fatality at 1745 [CST]. At this time no press release is planned."

The licensee stated that the employee was a security officer attending classroom training and was not on duty at the time of the incident.

The licensee notified the NRC Resident Inspector.

Page Last Reviewed/Updated Friday, March 30, 2012
Friday, March 30, 2012