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Event Notification Report for June 4, 2008

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/03/2008 - 06/04/2008

** EVENT NUMBERS **


44111 44249 44250 44260 44262

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Power Reactor Event Number: 44111
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: ROBERT KIDDER
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/31/2008
Notification Time: 19:18 [ET]
Event Date: 03/31/2008
Event Time: 15:50 [EDT]
Last Update Date: 06/03/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
RICHARD SKOKOWSKI (R3)

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 NOTIFICATION TO OHIO EPA CONCERNING NON-COMPLIANCE WITH HAZARDOUS WASTE REMOVAL REQUIREMENTS

"At 1550 hours, a self identification call was made to the State of Ohio Environmental Protection Agency (EPA), offices in Columbus, Ohio to inform them of the recent discovery of non-compliance issues relating to the accumulation, storage, and shipment (i.e., 90 days to ship) of hazardous waste (reference 40 CFR 261, 'Identification and Listing of Hazardous Waste'). Guidance was requested from the state EPA for remediation and reporting of the condition. The Perry Nuclear Power Plant personnel were advised by the Ohio EPA to properly identify, package and ship the waste as soon as possible. The waste consists of three drums of floor grinding waste generated during the resurfacing of the Auxiliary Building floor in 2005, and approximately 100 bags of miscellaneous trash generated during disassembly of plant equipment in 2007. This issue was discovered during activities to prepare the waste for shipment off site. The waste will be shipped per the direction of the Ohio EPA and an out-of-cycle hazardous waste annual report will be made to the Ohio EPA.

"This report is being made in accordance with 10 CFR 50.72(b)(2)(xi) as an event or situation related to the protection of the environment for which a notification to another government agency has been made. The resident inspector has been notified."

The hazardous material contains low level rad waste.

* * * UPDATE FROM RICHARD O'CONNOR TO HOWIE CROUCH @ 1334 HRS EDT ON 6/03/08 * * *

"On March 31, 2008, in accordance with 10 CFR 50.72(b)(2)(xi), notification was made for an event or situation related to the protection of the environment for which a notification to another government agency was made. This report was made when a self-identification call was made to the State of Ohio Environmental Protection Agency (EPA) offices in Columbus, Ohio, for the discovery of potential non-compliance issues with 40 CFR 261 requirements for the accumulation, storage, and shipment of hazardous waste. Based on further investigation using a Toxicity Characterization Leachate Procedure analysis of the waste, it was determined that the waste was, in fact, non-hazardous and could be shipped for off-site disposal. The requirements of 40 CFR 261 had been and continue to be met."

The licensee has notified the NRC Resident Inspector and the State of Ohio. Notified R3DO ( Pelke).

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General Information or Other Event Number: 44249
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: HEALTH - PHYSICS, INC
Region: 1
City: TAMPA State: FL
County:
License #: 2133-1
Agreement: Y
Docket:
NRC Notified By: CHARLES ADAMS
HQ OPS Officer: JOE O'HARA
Notification Date: 05/30/2008
Notification Time: 07:55 [ET]
Event Date: 05/30/2008
Event Time: 05:00 [EDT]
Last Update Date: 05/30/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JOHN ROGGE (R1)
CINDY FLANNERY (FSME)

Event Text

AGREEMENT STATE REPORT - TRAFFIC ACCIDENT INVOLVING RAM

The following was provided by the State via e-mail:

"Just after 0500 [EDT] two vans carrying medical RAM collided. There were no injuries. All southbound lanes [of Highway 200 in Marion County] were closed while the vehicles were removed. Hazmat determined that there was no damage or spill from the packages. One van had the packages jammed and they couldn't be removed at the scene. That van and driver were transported to Ocala where the packages can be removed. The other licensee is Cardinal Health 414, 3425 SW 42nd Way, Gainesville, FL 32608; license 3452-3, 3B. The licensees maintain possession of all RAM. No further action will be taken on this incident."

The isotope was Tc-99m and Thallium, by-product in a liquid form. The activity level is unknown.

"FL Incident Number: FL08-082."

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General Information or Other Event Number: 44250
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: MOORE REGIONAL HOSPITAL
Region: 1
City: PINEHURST State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: RANDY D. CROWE
HQ OPS Officer: STEVE SANDIN
Notification Date: 05/30/2008
Notification Time: 10:32 [ET]
Event Date: 05/15/2008
Event Time: [EDT]
Last Update Date: 05/30/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JOHN ROGGE (R1)
CINDY FLANNERY (FSME)

Event Text

AGREEMENT STATE REPORT INVOLVING RECEIPT OF CONTAMINATED PACKAGES

On May 15, 2008, a driver for Cardinal Health Nuclear Pharmacy Services made deliveries of Tc-99 ammo boxes to the Womack Regional Hospital, the Moore Regional Hospital, the Pinehurst Medical and Pinehurst Cardiology followed by a final stop at the Moore Regional Hospital.

The driver was notified at the Moore Regional Hospital that his delivery was contaminated. The most probable initial source of the contamination is attributed to his recovery of old boxes picked up at Womack Regional Hospital during his delivery (a later survey confirmed high levels of surface contamination).

The State of NC is continuing their investigation.

NC Incident No.: 08-23

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Power Reactor Event Number: 44260
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK ARNOSKY
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/03/2008
Notification Time: 12:50 [ET]
Event Date: 04/09/2008
Event Time: 04:16 [EDT]
Last Update Date: 06/03/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
PAMELA HENDERSON (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

60-DAY OPTIONAL NOTIFICATION FOR INVALID SPECIFIED SYSTEM ACTUATION

"On Wednesday April 9, 2008 at 0416 hours, an invalid actuation of the 1B Refueling Floor Ventilation Exhaust Radiation Monitor occurred. The actuation caused a Division 2 Group 6C isolation signal, which caused primary containment isolation valves (PCIVs) to automatically close on the Containment Leak Detector Radiation Monitor (10-S182) and the Drywell Hydrogen/Oxygen Analyzer (10-S205). The 1A, 1C, and 1D channels were unaffected and indicated normal ventilation exhaust radiation levels during the event.

"The cause of the event was a failure of the K2 relay in the 1B Refueling Floor Ventilation Exhaust Radiation Monitor. The failed relay has been replaced and the radiation monitor was declared operable on Wednesday April 9, 2008 at 2024 hours.

"The portion of the primary containment isolation system that received an actuation signal functioned successfully. All of the affected open isolation valves automatically closed. The only equipment malfunction during the event was the failed K2 relay. The Division 2 Group 6C isolation was a partial actuation.

"This event is reportable per 10CFR50.73(a)(2)(iv)(A) since isolation valves for the Containment Leak Detector Radiation Monitor and Drywell Hydrogen/Oxygen Analyzer automatically closed due to an invalid signal."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 44262
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAVE JESTER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/03/2008
Notification Time: 19:26 [ET]
Event Date: 06/03/2008
Event Time: 13:13 [EDT]
Last Update Date: 06/03/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
ROBERT HAAG (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

LOSS OF CONTROL ROOM EMERGENCY VENTILLATION SYSTEM FOR 12 MINUTES

"At 1259 hours on June 3, 2008, the Control Room authorized replacement of solenoid valve 1-VA-SV-928, affecting the Unit 1 Cable Spread Room Supply / Exhaust Fan Dampers. This work rendered two subsystems of the Control Room Emergency Ventilation (CREV) system inoperable. Because Brunswick has a shared control room, Unit 1 and Unit 2 entered Technical Specification (TS) 3.7.3, 'Control Room Emergency Ventilation (CREV) System,' Required Action 5.1 (i.e., be in Mode 3 within 12 hours).

"At 1313 hours the three Control Room Air Conditioning subsystems, required by TS 3.7.4, 'Control Room Air Conditioning (AC) System,' tripped during the performance of this planned preventive maintenance activity. Unit 1 and Unit 2 entered TS 3.7.4, Required Action E.1 (i.e., enter LC0 3.0.3 immediately). At 1325 hours, following replacement of solenoid valve 1-VA-SV-928, the Control Room AC subsystems were restored to operable status and LCO 3.0.3 was exited. CREV system operability was restored at 1333 hours.

"No power reduction took place as a result of the LCO 3.0.3 entry. This report applies to both Units 1 and 2 and is being made in accordance with 10 CFR 50.72(b)(3)(v)(D), as a condition that at the time of discovery could have prevented the fulfillment of the safety function of a system needed to mitigate the consequences of an accident.

"The safety significance of this event is considered minimal. The condition existed for 12 minutes. Prior to the maintenance activity, the potential for loss of the Control Room AC system and established compensatory actions to be taken in the event of the loss were briefed. Plant staff took immediate actions to return the Control Room AC subsystems to service. For the brief time the Control Room subsystems were inoperable, performance of plant personnel and equipment in the Control Room was not adversely affected. The maximum Control Room back panel temperature during this event was approximately 73 degrees F.

"Operability of the Control Room AC system was restored at 1325 hours, following replacement of solenoid valve 1-VA-SV-928. CREV system operability was restored at 1333 hours. Further solenoid valve replacements affecting Control Building Emergency Ventilation have been placed on hold pending the completion of the loss of Control Room AC subsystem investigation."

The licensee notified the NRC Resident Inspector.

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