Event Notification Report for July 01, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/30/2001 - 07/01/2001
Power Reactor
Event Number: 38109
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: ALAN DAY
HQ OPS Officer: BOB STRANSKY
Region: 1 State: PA
Unit: [2] [] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: ALAN DAY
HQ OPS Officer: BOB STRANSKY
Notification Date: 07/01/2001
Notification Time: 04:35 [ET]
Event Date: 07/01/2001
Event Time: 02:10 [EDT]
Last Update Date: 07/01/2001
Notification Time: 04:35 [ET]
Event Date: 07/01/2001
Event Time: 02:10 [EDT]
Last Update Date: 07/01/2001
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
RICHARD BARKLEY (R1)
RICHARD BARKLEY (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 Shutdown |
AUTOMATIC TURBINE TRIP/REACTOR SCRAM DURING TROUBLESHOOTING
"During troubleshooting of Peach Bottom Unit 2 electrohydraulic control (EHC) system, the main turbine control valves fast closed, resulting in an automatic turbine trip, reactor protection system (RPS) trip and reactor scram.
"Additionally, as a normal result of the reactor scram, reactor water level lowered below 1 inch, causing a valid automatic group II/III primary containment isolation signal (PCIS) in multiple trains.
"The plant responded normally, RPS and PCIS signals were reset and unit 2 is continuing to a cooled-down depressurized condition. No radiological release"
The NRC resident inspector has been informed of this event by the licensee.
"During troubleshooting of Peach Bottom Unit 2 electrohydraulic control (EHC) system, the main turbine control valves fast closed, resulting in an automatic turbine trip, reactor protection system (RPS) trip and reactor scram.
"Additionally, as a normal result of the reactor scram, reactor water level lowered below 1 inch, causing a valid automatic group II/III primary containment isolation signal (PCIS) in multiple trains.
"The plant responded normally, RPS and PCIS signals were reset and unit 2 is continuing to a cooled-down depressurized condition. No radiological release"
The NRC resident inspector has been informed of this event by the licensee.
Power Reactor
Event Number: 38110
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: SCOT OEHRLE
HQ OPS Officer: FANGIE JONES
Region: 2 State: FL
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: SCOT OEHRLE
HQ OPS Officer: FANGIE JONES
Notification Date: 07/01/2001
Notification Time: 15:07 [ET]
Event Date: 07/01/2001
Event Time: 14:10 [EDT]
Last Update Date: 07/01/2001
Notification Time: 15:07 [ET]
Event Date: 07/01/2001
Event Time: 14:10 [EDT]
Last Update Date: 07/01/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
THOMAS DECKER (R2)
THOMAS DECKER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 90 | Power Operation | 90 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION DUE TO INJURED LOGGERHEAD SEA TURTLE
The licensee notified the State of Florida Fish and Wildlife Commission about the discovery of an injured loggerhead sea turtle from the intake bay. The turtle is being transported to rehabilitation.
The licensee notified the NRC Resident Inspector.
The licensee notified the State of Florida Fish and Wildlife Commission about the discovery of an injured loggerhead sea turtle from the intake bay. The turtle is being transported to rehabilitation.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 38111
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: DANIEL MALONE
HQ OPS Officer: FANGIE JONES
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: DANIEL MALONE
HQ OPS Officer: FANGIE JONES
Notification Date: 07/01/2001
Notification Time: 17:20 [ET]
Event Date: 07/01/2001
Event Time: 13:30 [EDT]
Last Update Date: 07/01/2001
Notification Time: 17:20 [ET]
Event Date: 07/01/2001
Event Time: 13:30 [EDT]
Last Update Date: 07/01/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
GEOFFREY WRIGHT (R3)
GENE IMBRO (NRR)
GEOFFREY WRIGHT (R3)
GENE IMBRO (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
NON-DESTRUCTIVE EXAMINATION OF CRDM PRESSURE HOUSING FOUND CRACK INDICATION
"During non-destructive examination (NDE) of welds on control rod drive mechanism (CRDM) pressure housings, an indication was discovered on CRDM-40. The method being utilized was ultrasonic testing (UT). The indication is axial, approximately 0.7 inches long, located-on the inner surface of the pressure housing. The depth of the indication is approximately 50% through-wall. The indication is located in the top side heat affected zone of an 8 inch butt weld which joins the pressure housing's tubular section to an eccentric reducer. The material of the pressure housing is type 347 stainless steel.
"The weld examinations were being conducted as part of an extent of condition evaluation resulting from an earlier discovery, on June 21, 2001, of a through-wall axial indication on CRDM-21. The CRDM-40 indication location corresponds to the location of the earlier discovered indication in CRDM-21(EN #38083) and CRDM-25 (EN #38103). Cause evaluation is ongoing."
The licensee notified the NRC Resident Inspector.
"During non-destructive examination (NDE) of welds on control rod drive mechanism (CRDM) pressure housings, an indication was discovered on CRDM-40. The method being utilized was ultrasonic testing (UT). The indication is axial, approximately 0.7 inches long, located-on the inner surface of the pressure housing. The depth of the indication is approximately 50% through-wall. The indication is located in the top side heat affected zone of an 8 inch butt weld which joins the pressure housing's tubular section to an eccentric reducer. The material of the pressure housing is type 347 stainless steel.
"The weld examinations were being conducted as part of an extent of condition evaluation resulting from an earlier discovery, on June 21, 2001, of a through-wall axial indication on CRDM-21. The CRDM-40 indication location corresponds to the location of the earlier discovered indication in CRDM-21(EN #38083) and CRDM-25 (EN #38103). Cause evaluation is ongoing."
The licensee notified the NRC Resident Inspector.