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Event Notification Report for January 30, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/29/2004 - 01/30/2004

** EVENT NUMBERS **


40479 40483 40486 40487

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General Information or Other Event Number: 40479
Rep Org: KANSAS DEPT OF HEALTH & ENVIRONMENT
Licensee: TAYLOR FORGE ENGINEERED SYSTEMS
Region: 4
City: PAOLA State: KS
County:
License #: 21-B108-01
Agreement: Y
Docket:
NRC Notified By: JAMES JOHNSON
HQ OPS Officer: BILL GOTT
Notification Date: 01/26/2004
Notification Time: 13:21 [ET]
Event Date: 01/23/2004
Event Time: 17:30 [CST]
Last Update Date: 01/26/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
WILLIAM JOHNSON (R4)
DOUG BROADDUS (NMSS)

Event Text

AGREEMENT STATE REPORT OF OVEREXPOSURE FROM RADIOGRAPHY SOURCE

"On 1/26/04, about 8:00 am (CST), [Kansas Department of Health and Environment] KDHE staff retrieved a phone message from the Assistant Radiation Safety Officer (ARSO), of Taylor Forge Engineered Systems, Inc (TFES). The ARSO called on 1/23/04, Friday, about 10:20 pm, stating that one of their radiographers may have received an exposure greater than 5 Rem. This was the initial phone call stating that an unusual event may have occurred. Around 5:30 pm, on 1/23/04, a radiographer was performing radiographic operations in the middle bullpen cell, using a Co-60, 62.1 curie source. According to the radiographer, the gamma alarm malfunctioned, thereby the lights, bells and alarms weren't working. He entered the vault to try and determine the cause of the malfunction, but failed to retract the source, resulting in a possible overexposure to himself. The radiographer was in the area about 10 - 15 minutes. The radiographer contacted the ARSO later that evening and related the above events.

"On 1/26/04, about 8:00 am, KDHE staff retrieved a phone message from the Radiation Safety Officer (RSO). The RSO called on 1/24/04, Saturday, about 7:00 am, stating that one of their radiographers had received an overexposure greater than the 5 Rem limit. This was the official 24 hour emergency notification. The radiographer's chirping alarm rate meter and pocket ion chambers (PICs 200 mrems / 500 mrems) were found to be off-scale. The radiographers film badge was overnighted to Landauer dosimetry services for processing. The radiographer has been relieved of his duties as they relate to IR. Preliminary dose calculation estimates, from the RSO, are that radiographer received between 15 - 30 rems whole body and up to 87 rems to the hand. TFES is currently investigating the incident and is trying to recreate the above mentioned conditions (using a dummy source) to determine what happened. KDHE is currently investigating the incident. We will provide updates when they occur."


Source:
Cobalt 60, 62.1 Curies
Manufacturer: AEA Technologies
Model Number: TECHOPS A-424-14
Serial Number: S/N 2899

Device:
Manufacturer: AEA Technologies
Model Number 660-B
Serial Number: S/N B-234

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Power Reactor Event Number: 40483
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: EDDIE BYARS
HQ OPS Officer: BILL GOTT
Notification Date: 01/27/2004
Notification Time: 13:33 [ET]
Event Date: 01/27/2004
Event Time: 12:00 [EST]
Last Update Date: 01/29/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GEORGE KUZO (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

LOSS OF ENS TELEPHONE AND SIREN SYSTEM

The licensee reported intermittent problems with the ENS telephone and Early Warning Siren System (EWSS) capability. EWSS capability is less than 75% and is currently 58%. The ENS phone system is repaired. Ice storms are the cause of the communication problems.

The licensee notified the NRC Resident Inspector.

* * * UPDATE 1138 EST ON 1/29/04 FROM ROBERT SWEET TO S. SANDIN * * *

The licensee is updating this report to indicate that greater than 75% of the EWSS capability has been restored. The licensee informed the NRC Resident Inspector. Notified R2DO(Kuzo).

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Power Reactor Event Number: 40486
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDON ROBINSON
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/29/2004
Notification Time: 00:05 [ET]
Event Date: 01/28/2004
Event Time: 20:33 [EST]
Last Update Date: 01/29/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
GLENN MEYER (R1)

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

OFFSITE NOTIFICATION TO LOCAL LAW ENFORCEMENT DUE TO FIRE BRIGADE ACTIVATION

"At 2018 hrs, the Control Room was notified of smoke coming from the Unit 2 Vital UPS room. The Field Unit Supervisor (FUS) was dispatched to the room to investigate. At 2026 hrs, the Fire Brigade was activated. When the FUS arrived at the Vital UPS Panel he reported that there was smoke coming from the panel. He opened the panel and observed smoke coming from the transformer in the panel. He did not observe any flames at any time while dealing with the event. At 2029 hrs, Security was notified and subsequently notified the State Police at 2033 hrs. At 2033 hrs, the transformer was deenergized and the smoke began to dissipate. Entry into the Emergency Plan was evaluated and it was determined that no entry conditions exists at this time.

"Due to the notification of the Local Law Enforcement Agency, this event constitutes an Offsite Notification and therefore reportable under 10CFR50.72(b)(2)(xi) requiring a 4 hr ENS notification."

When the transformer was deenergized, all loads were automatically transferred to the alternate power supply. The loss of this transformer did not affect any safety related equipment and does not require entry into any TS LCO Action Statements.

The licensee notified state/local agencies and the NRC Resident Inspector. No press release is planned.

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Power Reactor Event Number: 40487
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: DAVE RICHARDSON
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 01/29/2004
Notification Time: 13:50 [ET]
Event Date: 01/28/2004
Event Time: 15:30 [EST]
Last Update Date: 01/29/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
GLENN MEYER (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 97 Power Operation 97 Power Operation

Event Text

24-HOUR CONDITION OF LICENSE REPORT DUE TO INOPERABLE DIVISION II CONTROL ROOM SPECIAL FILTER TRAIN

"While attempting to perform the Control Room Special Filter Train Functional Test for Division ll, the required train flow test conditions could not be established. Investigation revealed that the inlet backdraft damper 2HVC*DMPV93 was latched closed and would not open automatically on a Special Filter Train start.

"The damper was found latched closed due to an improperly set spring-loaded 'stop.' As a result, the Division II Control Room Special Filter Train was declared inoperable as of 1530 on 1/28/04. Technical Specification 3.7.2, Condition A was entered which allows 7 days to restore the Division II Control Room Special Filter Train to an operable status.

"A review of plant computer data and monthly surveillance tests for the Division II Special Filter Train determined that the backdraft damper has been latched closed since October 2003. As a result, the Division Il Control Room Special Filter exceeded Technical Specification 3.7.2 action to restore Control Room Special Filter Train Subsystem to operable within 7 days. This is reportable under 50.73(a)(2)(i)(B) 'Any operation or condition which was prohibited by the plant's Technical Specifications,' and Section 2.F of the Nine Mile Point Operating License. Per Nine Mile Point Operating license, initial notification that the facility is not operated in accordance with the Technical Specifications shall be made within 24 hours to the NRC Operations Center via the Emergency Notification System, with written follow up within 30 days in accordance with 10 CFR 50.73(b), (c), and (e).

"A repair plan is being prepared with work to commence today (1/29). Following repairs, surveillance testing will be performed to confirm proper operation of the damper.

"An inspection of the redundant Division I Control Room Special Filter Train damper and review of monthly surveillance tests demonstrated that the latching mechanism does not interfere with the ability of the damper to open as designed. Therefore, operability of the Division I Control Room Special Filter Train has been confirmed."

The licensee informed the NRC Resident Inspector.

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