Event Notification Report for October 07, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/06/2003 - 10/07/2003
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 40228
Facility: SEABROOK
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: O'Keefe
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: O'Keefe
HQ OPS Officer: JOHN MacKINNON
Notification Date: 10/07/2003
Notification Time: 18:13 [ET]
Event Date: 10/07/2003
Event Time: 11:00 [EDT]
Last Update Date: 10/14/2003
Notification Time: 18:13 [ET]
Event Date: 10/07/2003
Event Time: 11:00 [EDT]
Last Update Date: 10/14/2003
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):
FRANK COSTELLO (R1)
MICHAEL CASE (NRR)
FRANK COSTELLO (R1)
MICHAEL CASE (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 |
REACTOR COOLANT SYSTEM PRESSURE BOUNDARY LEAKAGE
At 1100 EDT on October 7, 2003, Seabrook Station concluded that the source of small boron deposits on the Reactor Vessel Head was a leaking conoseal weld on a CRDM housing.
The defect in primary coolant is not acceptable per ASME XI. This condition is reportable pursuant to 10 CFR 50.72 (b)(3)(ii).
The caller stated that through testing it is indicated that the leak had occurred in the last 2 months. A small amount of boric acid crystals was found.
The NRC Resident Inspector was notified of this event by the licensee.
* * * UPDATE ON 10/14/03 @ 1709 BY BEMIS TO GOULD * * *
This report supplements and retracts the 8 hour notification (Event Number 40228) made on October 7, 2003 pursuant to 10CFR50.72(b)(3)(ii)(A) documenting reactor coolant system pressure boundary leakage. FPL Energy Seabrook has determined that the initial report, although conservative, inappropriately interpreted canopy seal degradation to be pressure boundary leakage. The canopy seal weld is neither a structural weld nor a pressure retaining weld comprising the reactor coolant system pressure boundary. Therefore, the initial report is being retracted. A permanent plant design is being developed to repair the canopy seal using a standard canopy seal clamp and will be installed prior to startup from the current refueling outage.
The NRC Resident Inspector was notified.
Notified Reg 1 RDO (MCDERMOTT)
At 1100 EDT on October 7, 2003, Seabrook Station concluded that the source of small boron deposits on the Reactor Vessel Head was a leaking conoseal weld on a CRDM housing.
The defect in primary coolant is not acceptable per ASME XI. This condition is reportable pursuant to 10 CFR 50.72 (b)(3)(ii).
The caller stated that through testing it is indicated that the leak had occurred in the last 2 months. A small amount of boric acid crystals was found.
The NRC Resident Inspector was notified of this event by the licensee.
* * * UPDATE ON 10/14/03 @ 1709 BY BEMIS TO GOULD * * *
This report supplements and retracts the 8 hour notification (Event Number 40228) made on October 7, 2003 pursuant to 10CFR50.72(b)(3)(ii)(A) documenting reactor coolant system pressure boundary leakage. FPL Energy Seabrook has determined that the initial report, although conservative, inappropriately interpreted canopy seal degradation to be pressure boundary leakage. The canopy seal weld is neither a structural weld nor a pressure retaining weld comprising the reactor coolant system pressure boundary. Therefore, the initial report is being retracted. A permanent plant design is being developed to repair the canopy seal using a standard canopy seal clamp and will be installed prior to startup from the current refueling outage.
The NRC Resident Inspector was notified.
Notified Reg 1 RDO (MCDERMOTT)
Power Reactor
Event Number: 40229
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: STEPHEN MAGILL
HQ OPS Officer: JOHN MacKINNON
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: STEPHEN MAGILL
HQ OPS Officer: JOHN MacKINNON
Notification Date: 10/07/2003
Notification Time: 19:54 [ET]
Event Date: 10/07/2003
Event Time: 12:31 [PDT]
Last Update Date: 10/07/2003
Notification Time: 19:54 [ET]
Event Date: 10/07/2003
Event Time: 12:31 [PDT]
Last Update Date: 10/07/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
WILLIAM JOHNSON (R4)
WILLIAM JOHNSON (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
HIGH PRESSURE CORE SPRAY DECLARED INOPERABLE (HPCS)
At 1231 hours on October 7, 2003, the High Pressure Core Spray (HPCS) system at Columbia Generating Station was declared inoperable due to a failure to maintain system pressure while the system was being operated with the keep-fill piping isolated for maintenance on the system waterleg pump. This action rendered the HPCS system unable to perform its safety function to mitigate the consequences of an accident. Upon discovery of the inoperable condition, the Reactor Core Isolation Cooling system was verified to be operable and HPCS was restored to operable status at 1538 in accordance with the Required Action of plant Technical Specifications Limiting Condition for Operability 3.5.1, Conditions B.1 and B.2. All other Emergency Core Cooling System (ECCS) were operable during the time the HPCS system was inoperable. This event is being reported pursuant to the guidance for reporting under 50.72(b)(3)(v)(D) contained in NUREG 1022, which states for single train systems that perform a safety function, loss of a single train would prevent the fulfillment of the safety function and therefore is reportable.
The NRC Resident Inspector will be notified of this event by the licensee.
At 1231 hours on October 7, 2003, the High Pressure Core Spray (HPCS) system at Columbia Generating Station was declared inoperable due to a failure to maintain system pressure while the system was being operated with the keep-fill piping isolated for maintenance on the system waterleg pump. This action rendered the HPCS system unable to perform its safety function to mitigate the consequences of an accident. Upon discovery of the inoperable condition, the Reactor Core Isolation Cooling system was verified to be operable and HPCS was restored to operable status at 1538 in accordance with the Required Action of plant Technical Specifications Limiting Condition for Operability 3.5.1, Conditions B.1 and B.2. All other Emergency Core Cooling System (ECCS) were operable during the time the HPCS system was inoperable. This event is being reported pursuant to the guidance for reporting under 50.72(b)(3)(v)(D) contained in NUREG 1022, which states for single train systems that perform a safety function, loss of a single train would prevent the fulfillment of the safety function and therefore is reportable.
The NRC Resident Inspector will be notified of this event by the licensee.