Event Notification Report for October 04, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/03/2003 - 10/04/2003
Power Reactor
Event Number: 40222
Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] B&W-L-LP
NRC Notified By: BILL BANDHAUER
HQ OPS Officer: JEFF ROTTON
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] B&W-L-LP
NRC Notified By: BILL BANDHAUER
HQ OPS Officer: JEFF ROTTON
Notification Date: 10/04/2003
Notification Time: 16:11 [ET]
Event Date: 10/04/2003
Event Time: 10:32 [EDT]
Last Update Date: 10/04/2003
Notification Time: 16:11 [ET]
Event Date: 10/04/2003
Event Time: 10:32 [EDT]
Last Update Date: 10/04/2003
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):
MARK LESSER (R2)
MARK LESSER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
DEGRADED CONDITION DUE TO RCS PRESSURE BOUNDARY LEAKAGE
"At 1032 [EDT] on October 4, 2003 while in mode 4 conducting a planned refueling outage reactor coolant system inspection, Crystal River Unit 3 identified two potential RCS Pressure Boundary Leaks located in Pressurizer penetrations associated with upper level sensing lines. Upon closer inspection of the first one inch penetration, indications confirmed a Pressure Boundary Leak. A closer inspection of the second penetration is planned after obtaining access to the location. The last unidentified leak rate that was completed prior to the plant shutdown was 0.15 gpm. This defect in the primary coolant system is not acceptable per ASME XI. This condition is REPORTABLE per 10CFR 50.72 (b)(3)(ii)(A)."
Licensee reported that a small amount of boric acid residue and residual rust was identified during inspection in the vicinity of the upper level Pressurizer tap near the Pressurizer shell and the nozzle. A closer inspection is planned of the other two upper Pressurizer level taps.
The NRC resident has been notified by the Licensee.
"At 1032 [EDT] on October 4, 2003 while in mode 4 conducting a planned refueling outage reactor coolant system inspection, Crystal River Unit 3 identified two potential RCS Pressure Boundary Leaks located in Pressurizer penetrations associated with upper level sensing lines. Upon closer inspection of the first one inch penetration, indications confirmed a Pressure Boundary Leak. A closer inspection of the second penetration is planned after obtaining access to the location. The last unidentified leak rate that was completed prior to the plant shutdown was 0.15 gpm. This defect in the primary coolant system is not acceptable per ASME XI. This condition is REPORTABLE per 10CFR 50.72 (b)(3)(ii)(A)."
Licensee reported that a small amount of boric acid residue and residual rust was identified during inspection in the vicinity of the upper level Pressurizer tap near the Pressurizer shell and the nozzle. A closer inspection is planned of the other two upper Pressurizer level taps.
The NRC resident has been notified by the Licensee.
General Information or Other
Event Number: 40223
Rep Org: GE NUCLEAR ENERGY
Licensee: GE NUCLEAR ENERGY
Region: 4
City: San Jose State: CA
County:
License #: Various
Agreement: Y
Docket:
NRC Notified By: JASON POST
HQ OPS Officer: JEFF ROTTON
Licensee: GE NUCLEAR ENERGY
Region: 4
City: San Jose State: CA
County:
License #: Various
Agreement: Y
Docket:
NRC Notified By: JASON POST
HQ OPS Officer: JEFF ROTTON
Notification Date: 10/04/2003
Notification Time: 18:27 [ET]
Event Date: 10/04/2003
Event Time: 00:00 [PDT]
Last Update Date: 10/04/2003
Notification Time: 18:27 [ET]
Event Date: 10/04/2003
Event Time: 00:00 [PDT]
Last Update Date: 10/04/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
EUGENE COBEY (R1)
MARK LESSER (R2)
JULIO LARA (R3)
CHUCK CAIN (R4)
MICHAEL TSCHILTZ (NRR)
EUGENE COBEY (R1)
MARK LESSER (R2)
JULIO LARA (R3)
CHUCK CAIN (R4)
MICHAEL TSCHILTZ (NRR)
DEFECTS AND NONCOMPLIANCE REPORT
GE Nuclear Energy provided information concerning a reportable condition on the stability Option III Period Based Detection Algorithm (PBDA) for the Oscillation Power Range Monitor (OPRM) installed at the affected Licensee plants listed below. The basic component with the defect is specification of the allowable values for the adjustable period confirmation variables in the PBDA used in Stability Option III. The defect is that certain values of period tolerance and conditioning filter cutoff frequency within the previously specified acceptable range could produce sufficient successive confirmation count resets such that Safety Limit Minimum Critical Power Ratio (SLMCPR) protection might not be provided for all anticipated reactor instabilities.
This condition does not produce a substantial safety hazard and there is no threat of fuel failure. However, because the condition could contribute to exceeding the SLMCPR, it is a reportable condition.
List of Affected Plants:
Clinton
Brunswick 1 & 2
Nine Mile Point 2
Fermi 2
Columbia
Dresden 2 & 3
LaSalle 1 & 2
Limerick 1 & 2
Peach Bottom 2 & 3
Quad Cities 1 & 2
Perry 1
Susquehanna 1 & 2
Hope Creek
Hatch 1 & 2
Browns Ferry 2 & 3
GE Nuclear Energy provided information concerning a reportable condition on the stability Option III Period Based Detection Algorithm (PBDA) for the Oscillation Power Range Monitor (OPRM) installed at the affected Licensee plants listed below. The basic component with the defect is specification of the allowable values for the adjustable period confirmation variables in the PBDA used in Stability Option III. The defect is that certain values of period tolerance and conditioning filter cutoff frequency within the previously specified acceptable range could produce sufficient successive confirmation count resets such that Safety Limit Minimum Critical Power Ratio (SLMCPR) protection might not be provided for all anticipated reactor instabilities.
This condition does not produce a substantial safety hazard and there is no threat of fuel failure. However, because the condition could contribute to exceeding the SLMCPR, it is a reportable condition.
List of Affected Plants:
Clinton
Brunswick 1 & 2
Nine Mile Point 2
Fermi 2
Columbia
Dresden 2 & 3
LaSalle 1 & 2
Limerick 1 & 2
Peach Bottom 2 & 3
Quad Cities 1 & 2
Perry 1
Susquehanna 1 & 2
Hope Creek
Hatch 1 & 2
Browns Ferry 2 & 3
Power Reactor
Event Number: 40224
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: STEVE NEVELOS
HQ OPS Officer: JEFF ROTTON
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: STEVE NEVELOS
HQ OPS Officer: JEFF ROTTON
Notification Date: 10/04/2003
Notification Time: 20:04 [ET]
Event Date: 10/04/2003
Event Time: 17:13 [EDT]
Last Update Date: 10/05/2003
Notification Time: 20:04 [ET]
Event Date: 10/04/2003
Event Time: 17:13 [EDT]
Last Update Date: 10/05/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
EUGENE COBEY (R1)
EUGENE COBEY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
RPS ACTUATION WHILE CRITICAL
"Hope Creek Generating Unit was manually scrammed at 1713 hours [EDT] on 10/04/03 due to an Electro Hydraulic Control (EHC) System oil leak. Prior to the event the unit was at 100% power. The plant responded as designed for the scram, with lowest reactor level reaching -8 inches. Reactor level is currently being maintained between +12.5 inches and +54 inches with secondary condensate pumps. The unit is currently in Mode 3 - Hot Shutdown with reactor pressure being maintained between 500-600 psig with the main turbine bypass valves utilizing the main condenser as a heat sink. The EHC leak was validated to be associated with the #4 Combined Intermediate Control Valve (CIV) and has since been isolated. This report is being generated Law Event Classification Guide section 11.3.2 - Actuation of Reactor Protection System (RPS) when critical except preplanned. Current safety system status is normal with the exception that the `B' Emergency Diesel Generator (EDG) is inoperable as the result of a relay failure and the 'B' Control Room chiller is inoperable as the result of a failed economizer float. The 'B' EDG has been retested and validation of test results are currently underway to determine operability. Common mode failure testing is in progress for the remaining three EDG's."
All control rods inserted fully during the reactor scram. No relief valves lifted during the transient and there were no ECCS actuations or Primary Containment Isolation System actuations. The electrical grid remained stable during the event.
NRC Resident was notified by Licensee.
* * *UPDATE PROVIDED BY CLYDE BAUER TAKEN BY JEFF ROTTON AT 1728 EDT ON 10/05/03 * * *
During reactor level recovery following the scram, a second level 3 (+12.5 inches) RPS scram signal was received. The RPS system was still actuated upon receipt of this second level 3 signal. R1DO (Cobey ) notified of update.
NRC Resident will be notified by licensee.
"Hope Creek Generating Unit was manually scrammed at 1713 hours [EDT] on 10/04/03 due to an Electro Hydraulic Control (EHC) System oil leak. Prior to the event the unit was at 100% power. The plant responded as designed for the scram, with lowest reactor level reaching -8 inches. Reactor level is currently being maintained between +12.5 inches and +54 inches with secondary condensate pumps. The unit is currently in Mode 3 - Hot Shutdown with reactor pressure being maintained between 500-600 psig with the main turbine bypass valves utilizing the main condenser as a heat sink. The EHC leak was validated to be associated with the #4 Combined Intermediate Control Valve (CIV) and has since been isolated. This report is being generated Law Event Classification Guide section 11.3.2 - Actuation of Reactor Protection System (RPS) when critical except preplanned. Current safety system status is normal with the exception that the `B' Emergency Diesel Generator (EDG) is inoperable as the result of a relay failure and the 'B' Control Room chiller is inoperable as the result of a failed economizer float. The 'B' EDG has been retested and validation of test results are currently underway to determine operability. Common mode failure testing is in progress for the remaining three EDG's."
All control rods inserted fully during the reactor scram. No relief valves lifted during the transient and there were no ECCS actuations or Primary Containment Isolation System actuations. The electrical grid remained stable during the event.
NRC Resident was notified by Licensee.
* * *UPDATE PROVIDED BY CLYDE BAUER TAKEN BY JEFF ROTTON AT 1728 EDT ON 10/05/03 * * *
During reactor level recovery following the scram, a second level 3 (+12.5 inches) RPS scram signal was received. The RPS system was still actuated upon receipt of this second level 3 signal. R1DO (Cobey ) notified of update.
NRC Resident will be notified by licensee.