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Event Notification Report for July 22, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/21/2004 - 07/22/2004

** EVENT NUMBERS **

Power Reactor	Event Number: 40886
Facility: MONTICELLO Region: 3 State: MN Unit: [1] [ ] [ ] RX Type: [1] GE-3 NRC Notified By: Desmarais HQ OPS Officer: JOHN MacKINNON	Notification Date: 07/21/2004 Notification Time: 11:11 [ET] Event Date: 07/21/2004 Event Time: 05:12 [CDT] Last Update Date: 07/21/2004
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION	Person (Organization): KENNETH O'BRIEN (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

BOTH CONTROL ROOM VENTIALTION (CRV) SYSTEMS INOPERABLE.

Both control room ventilation systems were inoperable due to a seal failure on the in service control room ventilation unit. A 24 hour Limiting Condition of Operation (LCO) was entered at 0512 CDT. (V-EAC-14A) "A" CRV tripped and "B" CRV was isolated for planned maintenance. "B" CRV (V-EAC-14B) was unisolated and restored to service at 0545 CDT (33 minutes later) and the 24 hour LCO exited at 0600 CDT. The plant remains in a 30 day LCO for one train of the CRV being inoperable. Control room temperatures increased slightly during CRV inoperability and are within normal operating band at this time (Temp increased 5 degrees F). State and Local were notified of this by the licensee.

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

Power Reactor	Event Number: 40887
Facility: VERMONT YANKEE Region: 1 State: VT Unit: [1] [ ] [ ] RX Type: [1] GE-4 NRC Notified By: DAVID HALLONQUIST HQ OPS Officer: CHAUNCEY GOULD	Notification Date: 07/21/2004 Notification Time: 12:46 [ET] Event Date: 07/21/2004 Event Time: 11:20 [EDT] Last Update Date: 07/21/2004
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE	Person (Organization): JOHN KINNEMAN (R1) TERRY REIS (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

LOSS OF PUBLIC NOTIFICATION SYSTEM DUE TO LOSS OF NORMAL AND EMERGENCY POWER SUPPLY

"Vermont Yankee was notified by it's radio & siren vendor that the Ames Hill NOAA transmitter was inoperable between 1930 hours on 7/20/04 and 1055 hours on 7/21/04 due to a loss of normal power and a failure of it's backup generator. This failure caused the Public Notification System (PNS) to be inoperable during the period which is considered a major loss of emergency response capability."

The licensee informed the NRC Resident Inspector.

Fuel Cycle Facility	Event Number: 40888
Facility: WESTINGHOUSE ELECTRIC CORPORATION RX Type: URANIUM FUEL FABRICATION Comments: LEU CONVERSION (UF6 to UO2) COMMERCIAL LWR FUEL Region: 2 City: COLUMBIA State: SC County: RICHLAND License #: SNM-1107 Agreement: Y Docket: 07001151 NRC Notified By: MICHAEL O. CONNELLY HQ OPS Officer: STEVE SANDIN	Notification Date: 07/21/2004 Notification Time: 13:20 [ET] Event Date: 07/21/2004 Event Time: 09:00 [EDT] Last Update Date: 07/21/2004
Emergency Class: NON EMERGENCY 10 CFR Section: RESPONSE-BULLETIN	Person (Organization): STEPHEN CAHILL (R2) JOHN HICKEY (NMSS)

Event Text

4-HOUR 91-01 NRC BULLETIN NOTIFICATION DUE TO ADU IN NON-FAVORABLE GEOMETRY NITROGEN ACCUMULATOR TANK

"Facility: Westinghouse Electric Company, Commercial Fuel Fabrication Facility, Columbia SC,
low enriched (less than or equal to 5.0 wt.% U-235) PWR fuel fabricator for commercial light water reactors.

"License: SNM-1107.

Time and Date of Event: July 21, 2004, 0900

"Reason for Notification: During a highly unusual upset condition on Conversion line 3, ADU powder backed up in the elevator and hot oil dryer. Subsequently, the ADU backed up into the dryer filter housing, crushing stainless steel filter frames and opening a path via dual flexible lines to a non favorable geometry nitrogen accumulator tank. The tank normally serves as a nitrogen gas accumulator/heater to provide heated nitrogen to pulse/clean the bag filters in the dryer filter housing. No similar event has ever occurred in the history of the facility.

"In accordance with Westinghouse Operating License (SNM-1107), paragraph 3.7.3 (b.3), this event satisfies the criteria for a 4-hour notification, specifically, any determination that a criticality safety analysis or evaluation was deficient, or that a particular system was not previously analyzed.

"As Found Condition: 10.5 kg of dry material (primarily ADU) was removed from the nitrogen accumulator tank.

"Summary of Activity:

- The affected line remains shutdown until all equipment is cleaned out.
- The nitrogen accumulator tanks on all other Conversion lines have been inspected. No evidence of ADU powder has been found.

"Conclusions:

- This particular tank was not previously analyzed for criticality safety.
- There was less than a critical mass of SNM involved.
- At no time was the health or safety to any employee or member of the public in jeopardy. No exposure to hazardous material was involved.
- The Incident Review Committee (IRC) has determined that this is a safety significant incident in accordance with governing procedures.
- A causal analysis will be performed."

The licensee will inform the NRC Headquarters Criticality Specialist and the NRC Region 2 Office.

Power Reactor	Event Number: 40889
Facility: CALLAWAY Region: 4 State: MO Unit: [1] [ ] [ ] RX Type: [1] W-4-LP NRC Notified By: JIM MILLIGAN HQ OPS Officer: STEVE SANDIN	Notification Date: 07/21/2004 Notification Time: 19:32 [ET] Event Date: 07/21/2004 Event Time: 11:55 [CDT] Last Update Date: 07/21/2004
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE	Person (Organization): TOM FARNHOLTZ (R4)

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

EOF DECLARED INOPERABLE DUE TO UNACCEPTABLE AIR FLOW RATES IN FILTRATION MODE

"At 1155, 7/21/04, Callaway Plant declared the Emergency Offsite Facility (EOF) Inoperable due to unacceptable air flow rates when the ventilation system was in the Filtration mode. Normally the ventilation system is designed to operate with a positive pressure in the EOF in order to prevent in-leakage of unfiltered air. During regularly scheduled maintenance, it was discovered that if a fume hood exhaust fan was operated with the EOF ventilation in the Filtration mode, it was possible to develop a negative pressure condition within the EOF. A station Work Request has been generated and ventilation equipment has been aligned so that a positive pressure can be maintained until the problem has been corrected."

The licensee noted that regularly scheduled maintenance is performed on a yearly frequency. The licensee informed the NRC Resident Inspector.

Power Reactor	Event Number: 40890
Facility: DIABLO CANYON Region: 4 State: CA Unit: [1] [ ] [ ] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: JEFF KNISLEY HQ OPS Officer: JOHN MacKINNON	Notification Date: 07/22/2004 Notification Time: 00:57 [ET] Event Date: 07/21/2004 Event Time: 20:20 [PDT] Last Update Date: 07/22/2004
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(i) - PLANT S/D REQD BY TS	Person (Organization): TOM FARNHOLTZ (R4)

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

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN: NON-VITAL COMPONENT COOLING WATER LEAK INSIDE CONTAINMENT

"On July 21, 2004, with Unit 1 operating in Mode 1 (Power Operation) at approximately 100 percent power, a non-vital component cooling water (CCW) leak was identified inside containment. It was conservatively concluded that the leak could potentially disable both vital CCW loops, and thus the LCO for Technical Specification (TS) 3.7.7 "Vital CCW System" would not be met. Given there is no associated action for both vital loops inoperable, operators entered TS 3.0.3 at 1900 PDT, a unit shutdown was commenced at 20:20 PDT.

"The leak was identified at a cracked weld to the RCP 1-3 lube oil cooler, and is estimated at approximately 0.1 gallons per minute. While the leak is in the non-vital CCW loop and is stable, not currently a challenge to the function of the CCW system, and is not damaging plant equipment, based on the potential for the condition to rapidly degrade under loading such as a seismic event, operators applied TS 3.7.7.

"It is planned to place Unit 1 in Mode 3 (Hot Standby), restore both vital CCW loops to OPERABLE status by isolating the CCW supply to the RCP 1-3 lube oil cooler, and exit TS 3.0.3. The unit will be returned to service following repair of the cracked weld."

Reactor Coolant Pump (RCP) 1-3 CCW pipe diameter is 3 inches. Leak was first noticed by increasing containment sump level. Personnel entered containment and discovered the cracked weld on the 3 inch CCW piping. The maximum leak if the CCW pipe completely shared off would be greater than 200 gallons per minute (CCW system can handle a maximum leak rate of approximately 200 gallons per minute). The other three Reactor Coolant Pump CCW lube oil cooling piping were checked and no leaks were discovered.

All emergency core cooling systems and the emergency diesel generators are fully operable if needed. The electrical grid is also stable. At 2357 PDT Unit 1 was at a power at a level of 50% and decreasing.

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