Event Notification Report for February 24, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/23/2001 - 02/24/2001
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 37779
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: RAY MARTIN
HQ OPS Officer: DOUG WEAVER
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: RAY MARTIN
HQ OPS Officer: DOUG WEAVER
Notification Date: 02/24/2001
Notification Time: 03:24 [ET]
Event Date: 02/24/2001
Event Time: 03:06 [EST]
Last Update Date: 03/25/2001
Notification Time: 03:24 [ET]
Event Date: 02/24/2001
Event Time: 03:06 [EST]
Last Update Date: 03/25/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
GLENN MEYER (R1)
GLENN MEYER (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Refueling | 0 | Refueling |
SAFEGUARDS DEGRADATION RELATED TO AREA BOUNDARY
IMMEDIATE COMPENSATORY ACTIONS TAKEN UPON DISCOVERY
THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. ADDITIONAL DETAILS MAY BE OBTAINED FROM THE OPERATIONS CENTER.
* * * RETRACTED AT 2121 EST ON 3/25/01 BY RAY MARTIN TO FANGIE JONES * * *
The licensee is retracting this event based on reportability evaluation. Additional details may be obtained from the operations center.
The licensee intends to notify the NRC Resident Inspector. The R1DO (Kenneth Jenison) was informed.
IMMEDIATE COMPENSATORY ACTIONS TAKEN UPON DISCOVERY
THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. ADDITIONAL DETAILS MAY BE OBTAINED FROM THE OPERATIONS CENTER.
* * * RETRACTED AT 2121 EST ON 3/25/01 BY RAY MARTIN TO FANGIE JONES * * *
The licensee is retracting this event based on reportability evaluation. Additional details may be obtained from the operations center.
The licensee intends to notify the NRC Resident Inspector. The R1DO (Kenneth Jenison) was informed.
Power Reactor
Event Number: 37780
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: J. TEMPLE
HQ OPS Officer: JOHN MacKINNON
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: J. TEMPLE
HQ OPS Officer: JOHN MacKINNON
Notification Date: 02/24/2001
Notification Time: 18:04 [ET]
Event Date: 02/24/2001
Event Time: 15:10 [CST]
Last Update Date: 02/24/2001
Notification Time: 18:04 [ET]
Event Date: 02/24/2001
Event Time: 15:10 [CST]
Last Update Date: 02/24/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MARK RING (R3)
ELINOR ADENSAM (NRR)
FRANK CONGEL (IRO)
MARK RING (R3)
ELINOR ADENSAM (NRR)
FRANK CONGEL (IRO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 94 | Power Operation |
HIGH PRESSURE COOLANT INJECTION (HPCI) AND BOTH INJECTION PATHS OF LOW PRESSURE COOLANT INJECTION (LPCI) DECLARED INOPERABLE.
HPCI and both injection paths of LPCI have been declared inoperable as a result of not meeting inservice testing of injection check valves as required by Technical Specification 4.15.B. Technical Specification shutdown required by Technical Specification 3.5.A (4), be in a Hot Shutdown condition within 24 hours (start time 1510 CT) . Plant shutdown commenced at 1608 CT.
Licensee was reviewing ASME Code Section XI requirements as a result of a snubber problem encountered last week. While reviewing ASME Code Section XI requirements it was determined that HPCI and LPCI injection test valves may not meet ASME Code Section XI inservice testing requirements as specified per their Technical Specification. The reactor has to be shutdown in order to test the LPCI injection test valves since personnel have to enter the drywell. A soft shutdown of the reactor will be performed (the reactor will not be scrammed from power). All other Emergency Core Cooling Systems and the Emergency Diesel Generators are fully operable if needed. Electrical grid is stable.
The NRC Resident Inspector will be notified by the licensee of this event.
HPCI and both injection paths of LPCI have been declared inoperable as a result of not meeting inservice testing of injection check valves as required by Technical Specification 4.15.B. Technical Specification shutdown required by Technical Specification 3.5.A (4), be in a Hot Shutdown condition within 24 hours (start time 1510 CT) . Plant shutdown commenced at 1608 CT.
Licensee was reviewing ASME Code Section XI requirements as a result of a snubber problem encountered last week. While reviewing ASME Code Section XI requirements it was determined that HPCI and LPCI injection test valves may not meet ASME Code Section XI inservice testing requirements as specified per their Technical Specification. The reactor has to be shutdown in order to test the LPCI injection test valves since personnel have to enter the drywell. A soft shutdown of the reactor will be performed (the reactor will not be scrammed from power). All other Emergency Core Cooling Systems and the Emergency Diesel Generators are fully operable if needed. Electrical grid is stable.
The NRC Resident Inspector will be notified by the licensee of this event.