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Event Notification Report for December 23, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/22/2004 - 12/23/2004

** EVENT NUMBERS **


41277 41278 41280 41281

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Power Reactor Event Number: 41277
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [ ] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: WILLIAM DALTON
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/22/2004
Notification Time: 09:30 [ET]
Event Date: 12/22/2004
Event Time: 04:55 [EST]
Last Update Date: 12/22/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
RICHARD CONTE (R1)
TERRY REIS (NRR)

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

Event Text

REACTOR SCRAM AND ECCS INJECTION FOLLOWING OPENING OF TURBINE BYPASS VALVES

"At approximately 04:55 on December 22, 2004, Unit 2 experienced a malfunction of Electro-Hydraulic Control (EHC) system resulting in opening of main turbine bypass valves and resultant loss of reactor pressure. The reactor automatically shutdown on RPS with the completion of a Group I isolation signal (Reactor pressure 850 prig and Reactor mode switch in RUN) resulting in a closure of the Main Steam Isolation Valves (MSIVs). Reactor level lowered to (ECCS) initiation set-point of -48 inches and High Pressure Coolant Injection (HPCI) system and Reactor Core Isolation Coolant (RCIC) system automatically initiated and restored level. When reactor level lowered below the 1 inch set-point, Group II and III Primary Containment Isolation System (PCIS) signals initiated. All Unit parameters are stable and RPS/PCIS/ECCS systems performed as designed. MSIVs remain closed. Reactor level and pressure are stable with HPCI and RCIC systems in control. Group I, II, and III isolations have been reset. The EHC malfunction is presently under investigation by Station Management."

All systems functioned as required. The reactor water level is now at 23 inches and stable and the licensee is conducting a slow depressurization to Mode 4 to investigate the EHC system malfunction. The level transients experience during the scram would be expected with the closure of the MSIVs.

The licensee has notified the NRC Resident Inspector.

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Other Nuclear Material Event Number: 41278
Rep Org: SCI ENGINEERING
Licensee: SCI ENGINEERING
Region: 3
City: WARRENTON State: MO
County: WARREN
License #: 24-20039-01
Agreement: N
Docket:
NRC Notified By: WILLIAM GUERDAN
HQ OPS Officer: JOHN MacKINNON
Notification Date: 12/22/2004
Notification Time: 13:20 [ET]
Event Date: 12/22/2004
Event Time: 10:30 [CST]
Last Update Date: 12/22/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
Person (Organization):
LAURA KOZAK (R3)
SANDRA WASTLER (NMSS)

Event Text

DAMAGED HUMBOLDT MOISTURE DENSITY GAUGE.


Representative of SCI Engineering located in St. Charles, MO reported the following incident:


At approximately 1030 CST at a commercial job site in Warrenton, MO., a caterpillar truck ran over a Humboldt Model # 5100C moisture density gauge. The Humboldt case was cracked. The area around the damaged gauge has been roped off (50 feet from the gauge). The licensee did not know if the source rod had been broken off. R. M. Wester & Assoc. should be arriving shortly to take surveys and then take appropriate action based on their survey results. The gauge contains 11 millicuries of Cesium-137 and 40 millicuries of Am-241/Be. As far as the licensee knows there is no release. Warrenton is located about 30 miles West of St. Louis off of Interstate Highway 70.

* * * Update at 1447 EST on 12/22/04 by William Guerdan to MacKinnon * * *

R. M. Wester completed surveys and the results of the surveys are: no leaks and no contamination of the gauge. Both sources are intact and the area around the gauge is clean. The vehicle that ran over the gauge is also clean. R. M. Wester & Assoc. have taken possession of the gauge and they will take back to their St. Peter, Mo. office and perform a leak test of the gauge. Leak test of the gauge should be completed by the close of business today, 12/22/04.

R3DO (L.Kozak) and NMSS (S. Wastler) notified.

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Power Reactor Event Number: 41280
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: F. EHRHARDT
HQ OPS Officer: MIKE RIPLEY
Notification Date: 12/22/2004
Notification Time: 15:03 [ET]
Event Date: 12/22/2004
Event Time: 13:07 [CST]
Last Update Date: 12/22/2004
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):
LAURA KOZAK (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

RPS ACTUATION DUE TO STEAM GENERATOR LOW LEVEL SIGNAL

"Unit 2 reactor trip due to 2C steam generator LO-2 reactor protection signal. Auxiliary Feed Water actuated as expected. No additional malfunctions or unexpected plant response. Cause of LO-2 steam generator reactor protection signal under investigation.

"This is a 4 hour notification of an RPS actuation per 10 CFR 50.72(b)(2)(iv)(B). The 8 hour notification of Auxiliary Feed Water system actuation per 10 CFR 50.72 (b)(3)(iv)(B) is being made under this same telephone call."

The licensee notified the NRC Resident Inspector. All control rods fully inserted. Decay heat is being removed to the main condenser via the turbine by-pass valves. The electrical grid is stable.


* * * UPDATE FROM F. EHRHARDT TO M. RIPLEY 15:55 ET 12/22/04 * * *

The licensee has determined that the RPS and Auxiliary Feed Water actuations were the result of an actual low level in the 2C steam generator. The cause of the low level is under investigation. The NRC Resident Inspector was informed. Notified R3 DO (L. Kozak).

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Power Reactor Event Number: 41281
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: TOM ILIADIS
HQ OPS Officer: JOHN MacKINNON
Notification Date: 12/22/2004
Notification Time: 15:45 [ET]
Event Date: 12/22/2004
Event Time: 15:00 [EST]
Last Update Date: 12/22/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
RICHARD CONTE (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

OFFSITE NOTIFICATION MADE TO PENNSYLVANIA EMERGENCY MANAGEMENT AGENCY (PEMA)


An ambulance was called to the site because a plant employee, not in the power plant but in an onsite office building, complained of chest pains. The individual was taken by the ambulance to Berwick Hospital. PEMA was notified of this by the licensee.

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

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