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Event Notification Report for January 6, 2005

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/05/2005 - 01/06/2005

** EVENT NUMBERS **


41258 41269 41303 41305 41309 41310

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 41258
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: BOB URRELL
HQ OPS Officer: MIKE RIPLEY
Notification Date: 12/14/2004
Notification Time: 14:55 [ET]
Event Date: 12/13/2004
Event Time: 15:12 [CST]
Last Update Date: 01/05/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
70.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
ROGER LANKSBURY (R3)
JOHN HICKEY (NMSS)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 94 Power Operation 94 Power Operation

Event Text

CRITICALITY MONITORING DOSIMETERS NOT CONFIGURED CORRECTLY

"On December 13, 2004, in preparations for new fuel receipt inspection activities, it was determined that the Electronic Dosimeters (Eds) that were previously used to meet criticality monitoring requirements of 10 CFR 70.24, were not configured correctly. Specifically, the dose rate alarm function of the Eds had been disabled. It is unknown at this time if the Eds had previously been used in this in-correct configuration during two previous new fuel receipt inspection activities. Based on the potential that the requirements of part 70.24 were not met, this event is being reported pursuant of part 70.50(b)(2), 'An event in which equipment is disabled or fails to function as designed.'"

The Electronic Dosimeters were immediately re-configured correctly and new fuel receipt inspection activities will recommence. The licensee notified the NRC Resident Inspector.


* * * RETRACTION ON 01/05/05 AT 1039 EST BY ROBERT URRELL TAKEN BY MACKINNON * * *

"The licensee performed an analysis that concluded that a monitoring system capable of detecting a criticality per 10 CFR 70.24 (a)(2) was in place during new fuel receipt. Specifically, the analysis demonstrated that the electronic dosimeters worn by the radiological workers involved adequately monitored for a criticality event." Therefore the licensee retracts the above event notification. R3DO (Sonia Burgess) & NMSS (Linda Gersey) notified.

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

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 41269
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: STEVEN BENEDICT
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/17/2004
Notification Time: 16:40 [ET]
Event Date: 12/17/2004
Event Time: 11:09 [EST]
Last Update Date: 01/05/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
ROGER LANKSBURY (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 99 Power Operation 99 Power Operation

Event Text

WATERLEG PUMP DISCHARGE CHECK VALVE IN HPCS SYSTEM FAILED TO OPEN

"During the performance of the High Pressure Core Spray system (HPCS) quarterly pump and valve operability test, the waterleg pump discharge low pressure alarm was unable to be cleared. It was determined that the waterleg pump discharge check valve had failed to open to provide keepfill flow.

"The HPCS system had been declared [inoperable at 0818 for a planned surveillance activity. At 1109, the low pressure alarm came in as expected, but was not able to be cleared. Subsequent mechanical agitation of the waterleg pump discharge check valve caused the valve to open and the low pressure condition to clear.

"Tech Spec 3.5.1 is applicable. Entry time 0818 on 12/17/04.

"Action is to restore HPCS to Operable within 14 days."

NRC Resident Inspector was notified.

* * * UPDATE ON 01/05/05 @1211 BY KEN MEADE TO CHAUNCEY GOULD * * * RETRACTION

"An 8 hour notification was made on December 17, 2004, in accordance with 10CFR50.72(b)(3)(v)(C) and 10CFR50.72(b)(3)(v)(D). The report was made due to a potential loss of the High Pressure Core Spray (HPCS) system safety function as a result of the loss of keep-fill pressure."

"The water-leg pump discharge check valve was determined to be the most likely cause of the loss of keep-fill pressure and was replaced. A preliminary investigation has determined that the water-leg pump discharge check valve had sufficient corrosion products (on the rising stem) to cause the valve disk to stick. With the check valve not able to fully open, the system low pressure alarm was activated."

"The lowest system pressure, about 24 psig, was determined to be just below the alarm setpoint of 27 psig. The alarm setpoint includes a 10 psig margin between receipt of the alarm and the pressure at which the piping would start to void. The pressure, 24 psig, was equivalent to the static head provided by the Condensate Storage Tank (CST) to the HPCS system. This alignment is the method used to maintain the system filled when the water-leg pump is unavailable."

"The 24 psig system pressure was adequate to maintain the system full. Since the system pressure was adequate and the HPCS system was maintained full, the safety function of the system was not adversely affected. Since the safety function was not affected, there is no reportable condition and Event Notification 41269 is retracted."

The NRC Resident Inspector was notified.

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General Information or Other Event Number: 41303
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: N/A
Region: 4
City: WACO State: TX
County:
License #:
Agreement: Y
Docket:
NRC Notified By: D. RAY JISHA
HQ OPS Officer: MIKE RIPLEY
Notification Date: 12/31/2004
Notification Time: 10:52 [ET]
Event Date: 12/27/2004
Event Time: [CST]
Last Update Date: 12/31/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
TOM FARNHOLTZ (R4)
ELMO COLLINS (NMSS)

Event Text

MILITARY RADIO WITH RADIUM-226 FOUND IN SCRAP METAL BIN

On Monday, December 27, 2004 the Agency was contacted by the Emergency Management Coordinator, for Waco-McLennan County with concerns over a metallic box retrieved from a scrap metal recycling bin. This item was first noted as being radioactive by a scrap metal firm under the name of Lipschitz on Elm Street in Waco who purportedly has sensitive scintillation detectors to screen in-coming scrap. Once the item was returned to the City of Waco landfill, the Emergency Management Coordinator confirmed that one end of the two part metal device or container was indeed emitting radiation at a rate of 2mR/hr at an unspecified distance as measured with a yellow CVD meter obtained from the local haz-mat team.

State personnel responded on Tuesday, December 28, 2004 to the landfill and performed extensive surveys of the grounds, personnel, and equipment that may have come in contact with the device. All results were negative as measured with a pancake GM and the surface dose rate of 10mR/hr was recorded. After triple bagging, the device was brought to the State's Austin office.

Trace amounts of removable contamination was noted only on the inside of the cover for the controls of the rad/rec/trans which was labeled with the following data: Type CKB-43069-A, Radio-Transmitter-Receiver, Model Maw-1,Serial #784, NAVSHIPS 91529A. Radium-226 was confirmed as the radionuclide present by spectral analysis on Thursday, December 30, 2004. The State is seeking contact within the Navy who will assist in appropriate disposition.

Texas Incident # I-8194.

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General Information or Other Event Number: 41305
Rep Org: MARYLAND DEPT OF THE ENVIRONMENT
Licensee: ADVANCED RADIOLOGY
Region: 1
City: GLEN BURNIE State: MD
County:
License #: MD-03-040-01
Agreement: Y
Docket:
NRC Notified By: RAY MANLEY
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 01/03/2005
Notification Time: 13:07 [ET]
Event Date: 12/21/2004
Event Time: [EST]
Last Update Date: 01/03/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES TRAPP (R1)
SCOTT MOORE (NMSS)

Event Text

AGREEMENT STATE REPORT OF A LOST COBALT- 57 SOURCE

The State Licensee, Advanced Radiology, located at the PET Center at North Arundel Tate Center in Glen Burnie, MD reported that a Model BM06 Gamma Reference Standard calibration device containing 5.66 milliCuries of Co-57 source is missing. The source has not been located and is believed to have been inadvertently disposed of in the trash by housekeeping when they made unauthorized entry to the hot lab. As a corrective action the hot lab door lock was changed. The State of Maryland responded on 12/30/04.

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Power Reactor Event Number: 41309
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: AL PROKASH
HQ OPS Officer: BILL HUFFMAN
Notification Date: 01/05/2005
Notification Time: 17:06 [ET]
Event Date: 01/06/2005
Event Time: 07:00 [CST]
Last Update Date: 01/05/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
INFORMATION ONLY
Person (Organization):
SONIA BURGESS (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

MODIFICATION TO PROCESS COMPUTER THAT WILL IMPACT ERDS AND SPDS

"The Plant Process Computer System (PPCS) will be taken out of service for an approximate 2 week period to implement a planned modification. The current PPCS is being replaced and the computer outage is required to allow cutover to the new PCCS. During this time period ERDS and SPDS will not be available. Also, a small portion of the plant annunciator system (Trouble Light Alarms) will not be available. Regulatory Guide 1.97 Category 2D Containment Temperature and Category 3D Component Cooling Water Temperature indicators will not be available in the Control Room, although other instrumentation is available to monitor these parameters.

"This is an 8-hour reportable event per 10 CFR50.72(b)(3)(xiii) Major Loss of Assessment Capability. The operation of plant systems will not be affected due to this planned action. ERDS and SPDS parameters will be monitored by control board indications. Compensatory actions have been developed."

The PPCS outage is expected to commence around 0700 CST on 1/6/05. The licensee has informed the NRC Resident Inspector.

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Power Reactor Event Number: 41310
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: FREDERICK SMITH
HQ OPS Officer: MIKE RIPLEY
Notification Date: 01/06/2005
Notification Time: 04:01 [ET]
Event Date: 01/06/2005
Event Time: 01:12 [EST]
Last Update Date: 01/06/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
SONIA BURGESS (R3)
JOHN HANNON (NRR)

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

Event Text

MANUAL REACTOR SCRAM DUE TO REACTOR RECIRCULATION PUMP TRIP

"At approximately 0106 on 1-6-05, Reactor Recirculation Pumps A and B down-shifted from fast to slow speed which resulted in reactor power decreasing from 100% to approximately 46%. As operators started to reduce power using control rod insertion, Reactor Recirculation Pump A tripped to 'off.' At 0112 on 1-6-05, a manual reactor scram was inserted due to operating under undesirable power to flow conditions. At approximately 0119, the operators were unable to start the Motor Feedwater Pump, Reactor Core Isolation Cooling system was manually started. Level control was established using a Reactor Feed Pump Turbine and Reactor Core Isolation Cooling. The Main Steam Isolation Valves were closed to limit cooldown. Reactor level is being controlled with the Reactor Core Isolation Cooling System and safety relief valves are available for reactor pressure control.

"The cause of the Reactor Recirculation Pumps down-shifting and the subsequent trip of Reactor Recirculation Pump A is still under investigation. The cause of the Motor Feedwater Pump failure to start is likewise under investigation."

All control rods fully inserted. The lowest reactor level reached was 154 inches above TAF. The electrical grid is stable and ESF systems remain available. Reactor pressure and level are being maintained by the Reactor Core Isolation Cooling system. The licensee notified the NRC Resident Inspector.

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