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Event Notification Report for December 31, 2003

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/30/2003 - 12/31/2003

** EVENT NUMBERS **

Power Reactor	Event Number: 40418
Facility: FT CALHOUN Region: 4 State: NE Unit: [1] [ ] [ ] RX Type: [1] CE NRC Notified By: ERICK MATZKE HQ OPS Officer: CHAUNCEY GOULD	Notification Date: 12/30/2003 Notification Time: 12:27 [ET] Event Date: 12/30/2003 Event Time: 08:30 [CST] Last Update Date: 12/30/2003
Emergency Class: NON EMERGENCY 10 CFR Section: 26.73 - FITNESS FOR DUTY	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

LICENSED EMPLOYEE FAILED A RANDOM FITNESS FOR DUTY ALCOHOL TEST

Contact the HOO for additional details.

The NRC Resident Inspector was notified

Power Reactor	Event Number: 40419
Facility: COOK Region: 3 State: MI Unit: [ ] [2] [ ] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: SCOTT RICHARDSON HQ OPS Officer: CHAUNCEY GOULD	Notification Date: 12/30/2003 Notification Time: 15:01 [ET] Event Date: 12/30/2003 Event Time: 13:30 [EST] Last Update Date: 12/30/2003
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION	Person (Organization): KENNETH RIEMER (R3)

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

Event Text

REACTOR TRIPPED FROM 100% POWER DUE TO LOW STEAM GENERATOR

Cook unit 2 automatically tripped from 100% power due to low steam generator level coincident with feed flow less than steam flow. The cause of this condition is under investigation, but it is suspected that unplanned closure of the steam generator 2 & 3 feedwater isolation valves led to the initiating signal. It is believed that the feedwater isolation valve closure originated from an abnormality in the Control Room Instrument Distribution(CRID) 120VAC power system. Technicians were landing leads on a Residual Heat Removal (RHR) System flow transmitter which was fed from the suspected CRID supply at the time of the event. An arc was observed during the lead landing procedure.

The main generator also required a manual trip signal by control room operators due to sticking of the main stop valve which is also being investigated. All other systems responded as expected. All rods fully inserted, no ECCS actuation occurred, and no relief valves lifted. The unit is stable in mode 3 with aux feedwater providing heat sink supply.

The NRC Resident Inspector has been informed.

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