Event Notification Report for March 17, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/16/2001 - 03/17/2001
EVENT NUMBERS
37845
Power Reactor
Event Number: 37845
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: TURNER
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: TURNER
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 03/18/2001
Notification Time: 00:03 [ET]
Event Date: 03/17/2001
Event Time: 21:13 [EST]
Last Update Date: 03/18/2001
Notification Time: 00:03 [ET]
Event Date: 03/17/2001
Event Time: 21:13 [EST]
Last Update Date: 03/18/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
PETE ESELGROTH (R1)
PETE ESELGROTH (R1)
| 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 |
REACTOR TRIP FROM 100% POWER DUE TO DECREASING STEAM GENERATOR WATER LEVELS
During 100% power operation of Unit 2, the Reactor Protection System (RPS) properly initiated an automatic Reactor Scram signal in response to decreasing Steam Generator (S/G) water levels. Steam Generator
water levels were decreasing due to an 'A' Main Feedwater Pump trip, which in turn had been caused by an 'A'
Condensate Pump trip. All rods fully inserted into the core, and all Safety Systems operated as designed. The
cause of the Condensate Pump trip is not currently known, and investigation is continuing. No Radiological Releases, RCS leaks, or S/G leaks occurred during this event.
The NRC Resident Inspector was notified.
During 100% power operation of Unit 2, the Reactor Protection System (RPS) properly initiated an automatic Reactor Scram signal in response to decreasing Steam Generator (S/G) water levels. Steam Generator
water levels were decreasing due to an 'A' Main Feedwater Pump trip, which in turn had been caused by an 'A'
Condensate Pump trip. All rods fully inserted into the core, and all Safety Systems operated as designed. The
cause of the Condensate Pump trip is not currently known, and investigation is continuing. No Radiological Releases, RCS leaks, or S/G leaks occurred during this event.
The NRC Resident Inspector was notified.