Event Notification Report for October 19, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/18/2000 - 10/19/2000
Power Reactor
Event Number: 37440
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: MCLENNAN
HQ OPS Officer: JOHN MacKINNON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: MCLENNAN
HQ OPS Officer: JOHN MacKINNON
Notification Date: 10/19/2000
Notification Time: 07:00 [ET]
Event Date: 10/19/2000
Event Time: 05:30 [CDT]
Last Update Date: 10/19/2000
Notification Time: 07:00 [ET]
Event Date: 10/19/2000
Event Time: 05:30 [CDT]
Last Update Date: 10/19/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - DEG/UNANALYZED COND
10 CFR Section:
50.72(b)(2)(i) - DEG/UNANALYZED COND
Person (Organization):
ROGER LANKSBURY (R3)
ROGER LANKSBURY (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
MAIN STEAM LINE ISOLATION VALVES FAIL LOCAL LEAK RATE TEST
At 0530 CT on 10/19/00, the total maximum pathway leakage for all main steam line isolation valves was determined by Local Leak Rate Testing to be in excess of Technical Specification 4.7.D.6 limit of < 46 scfh when tested at a test pressure of 25 psig.
The NRC Resident Inspector was notified of this event by the licensee.
At 0530 CT on 10/19/00, the total maximum pathway leakage for all main steam line isolation valves was determined by Local Leak Rate Testing to be in excess of Technical Specification 4.7.D.6 limit of < 46 scfh when tested at a test pressure of 25 psig.
The NRC Resident Inspector was notified of this event by the licensee.
Power Reactor
Event Number: 37442
Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: BRUCE PROCTOR
HQ OPS Officer: BOB STRANSKY
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: BRUCE PROCTOR
HQ OPS Officer: BOB STRANSKY
Notification Date: 10/19/2000
Notification Time: 15:53 [ET]
Event Date: 10/19/2000
Event Time: 13:40 [CDT]
Last Update Date: 10/19/2000
Notification Time: 15:53 [ET]
Event Date: 10/19/2000
Event Time: 13:40 [CDT]
Last Update Date: 10/19/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - DEG/UNANALYZED COND
10 CFR Section:
50.72(b)(2)(i) - DEG/UNANALYZED COND
Person (Organization):
JOHN PELLET (R4)
JOHN PELLET (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
BORIC ACID RESIDUE DISCOVERED ON REACTOR COOLANT SYSTEM INSTRUMENT NOZZLES
"During a bare metal inspection of reactor coolant system hot leg instrument nozzles, boric acid residue was found on two of the three mechanical nozzle seal assembly (MNSA) clamps installed during the previous refueling outage (3/99). The MNSA clamps were installed on previously identified leaking nozzles. The leakage from the clamps constitutes a reinitiation of RCS pressure boundary leakage, which is a degradation of the RCS pressure boundary."
The NRC resident inspector has been informed of this notification by the licensee.
"During a bare metal inspection of reactor coolant system hot leg instrument nozzles, boric acid residue was found on two of the three mechanical nozzle seal assembly (MNSA) clamps installed during the previous refueling outage (3/99). The MNSA clamps were installed on previously identified leaking nozzles. The leakage from the clamps constitutes a reinitiation of RCS pressure boundary leakage, which is a degradation of the RCS pressure boundary."
The NRC resident inspector has been informed of this notification by the licensee.