Event Notification Report for October 24, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/23/2003 - 10/24/2003
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 40276
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: GERRY PAGE
HQ OPS Officer: JEFF ROTTON
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: GERRY PAGE
HQ OPS Officer: JEFF ROTTON
Notification Date: 10/24/2003
Notification Time: 19:34 [ET]
Event Date: 10/24/2003
Event Time: 17:55 [EDT]
Last Update Date: 10/28/2003
Notification Time: 19:34 [ET]
Event Date: 10/24/2003
Event Time: 17:55 [EDT]
Last Update Date: 10/28/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
LAWRENCE DOERFLEIN (R1)
LANCE ENGLISH (TAS)
LAWRENCE DOERFLEIN (R1)
LANCE ENGLISH (TAS)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
DEGRADED SAFEGUARDS ACCESS
Discovered vulnerability in a safeguard system that could allow access to a controlled access area for which compensatory measures were secured prematurely. The licensee notified the NRC Resident Inspector, the CT State Police and local law enforcement. Contact the Headquarters Operations Officer for additional details.
The NRC Resident Inspector was notified of this event by the licensee.
*****RETRACTED ON 10/28/03 AT 1315 FROM OCONNOR TO LAURA*****
"Subsequent investigation has determined that the event was properly compensated within 10 minutes of discovery, and therefore it is not a reportable event but does require a security log entry per the guidance in GL 91-03."
Notified TAS (L. English) and R1DO (D. Silk).
Discovered vulnerability in a safeguard system that could allow access to a controlled access area for which compensatory measures were secured prematurely. The licensee notified the NRC Resident Inspector, the CT State Police and local law enforcement. Contact the Headquarters Operations Officer for additional details.
The NRC Resident Inspector was notified of this event by the licensee.
*****RETRACTED ON 10/28/03 AT 1315 FROM OCONNOR TO LAURA*****
"Subsequent investigation has determined that the event was properly compensated within 10 minutes of discovery, and therefore it is not a reportable event but does require a security log entry per the guidance in GL 91-03."
Notified TAS (L. English) and R1DO (D. Silk).
Power Reactor
Event Number: 40277
Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: Oscar Pipkins
HQ OPS Officer: JOHN MacKINNON
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: Oscar Pipkins
HQ OPS Officer: JOHN MacKINNON
Notification Date: 10/25/2003
Notification Time: 07:53 [ET]
Event Date: 10/24/2003
Event Time: 23:00 [CDT]
Last Update Date: 10/25/2003
Notification Time: 07:53 [ET]
Event Date: 10/24/2003
Event Time: 23:00 [CDT]
Last Update Date: 10/25/2003
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):
DAVID LOVELESS (R4)
DAVID LOVELESS (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 |
DEGRADATION OF THE REACTOR COOLANT SYSTEM (RCS) PRESSURE BOUNDARY
"During inspection of the hot leg nozzles on RCP loop #2 in accordance with the Alloy 600 Program Plan during Refuel 12, evidence of leakage was identified on nozzle RC-IPT-0106B. This constitutes degradation of the RCS pressure boundary. Corrective action is being evaluated."
RC-IPT-0106B is a pressure transmitter that taps off of reactor coolant system hot leg (loop) # 2 . The location of the Pressure transmitter is found in Waterford Unit 3, FSAR Chapter 5.1, Flow Diagram Reactor Coolant System, Figure 5.1-3. The license said that the picture indicates a small amount of boric acid crystals in the area of the leakage. Licensee did not know if the leakage is from a weld, pin hole leak, etc.
The NRC Resident Inspector was notified of this event by the licensee.
"During inspection of the hot leg nozzles on RCP loop #2 in accordance with the Alloy 600 Program Plan during Refuel 12, evidence of leakage was identified on nozzle RC-IPT-0106B. This constitutes degradation of the RCS pressure boundary. Corrective action is being evaluated."
RC-IPT-0106B is a pressure transmitter that taps off of reactor coolant system hot leg (loop) # 2 . The location of the Pressure transmitter is found in Waterford Unit 3, FSAR Chapter 5.1, Flow Diagram Reactor Coolant System, Figure 5.1-3. The license said that the picture indicates a small amount of boric acid crystals in the area of the leakage. Licensee did not know if the leakage is from a weld, pin hole leak, etc.
The NRC Resident Inspector was notified of this event by the licensee.