Event Notification Report for December 05, 2004
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/04/2004 - 12/05/2004
Power Reactor
Event Number: 41245
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ERIC POWELL
HQ OPS Officer: BILL HUFFMAN
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ERIC POWELL
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/05/2004
Notification Time: 15:54 [ET]
Event Date: 12/05/2004
Event Time: 10:15 [EST]
Last Update Date: 12/05/2004
Notification Time: 15:54 [ET]
Event Date: 12/05/2004
Event Time: 10:15 [EST]
Last Update Date: 12/05/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
JAMES TRAPP (R1)
JAMES TRAPP (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
REACTOR COOLANT LEAKAGE OUTSIDE OF CONTAINMEMT
"This is an 8-hour notification being made to report exceeding the design basis for the reactor coolant leakage outside of containment. The event is being reported under paragraph (b)(3)(v) of 10CFR50.72.
"On 12/05/04 at 1015 the control room was notified of leakage from a gasketed flange area on the 11 Residual Heat Removal Heat Exchanger. The leak rate has been conservatively quantified at 0.68 gpm, which is greater than the UFSAR limit of 2100 cc/hr (0.009 gpm) for ECCS leakage outside containment.
"With leakage greater than the UFSAR allowed limits, GDC-19 limits for control room habitability cannot be assured. Actions are in progress to torque the flange bolts to reduce the leakage.
"The licensee has notified the NRC Resident inspector of this event.
"Salem Unit One is in Mode 4 with the Residual Heat Removal system in service removing reactor decay heat. No ECCS system actuations occurred. No one was injured as a result of the leak."
"This is an 8-hour notification being made to report exceeding the design basis for the reactor coolant leakage outside of containment. The event is being reported under paragraph (b)(3)(v) of 10CFR50.72.
"On 12/05/04 at 1015 the control room was notified of leakage from a gasketed flange area on the 11 Residual Heat Removal Heat Exchanger. The leak rate has been conservatively quantified at 0.68 gpm, which is greater than the UFSAR limit of 2100 cc/hr (0.009 gpm) for ECCS leakage outside containment.
"With leakage greater than the UFSAR allowed limits, GDC-19 limits for control room habitability cannot be assured. Actions are in progress to torque the flange bolts to reduce the leakage.
"The licensee has notified the NRC Resident inspector of this event.
"Salem Unit One is in Mode 4 with the Residual Heat Removal system in service removing reactor decay heat. No ECCS system actuations occurred. No one was injured as a result of the leak."
Power Reactor
Event Number: 41246
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JEFF NIEBERDING
HQ OPS Officer: JOHN MacKINNON
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JEFF NIEBERDING
HQ OPS Officer: JOHN MacKINNON
Notification Date: 12/06/2004
Notification Time: 00:17 [ET]
Event Date: 12/05/2004
Event Time: 21:35 [EST]
Last Update Date: 12/06/2004
Notification Time: 00:17 [ET]
Event Date: 12/05/2004
Event Time: 21:35 [EST]
Last Update Date: 12/06/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
PAUL FREDRICKSON (R2)
PAUL FREDRICKSON (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC TURBINE TRIP/REACTOR TRIP DUE TO MOISTURE SEPARATOR REHEATER (MSR) HIGH LEVEL TRIP SIGNAL.
"Reactor Trip caused by Turbine trip. Turbine trip caused by a Moisture Separator Reheater 1B high level. Maintenance personnel were working in vicinity of level switches at time of trip. Root cause investigation in progress. All systems operated as designed on Reactor trip."
Maintenance personnel working in the vicinity of Moisture Separator Reheater 1B were setting up radiography equipment when the MSR 1B high level trip was generated. All rods fully inserted. Both Motor Driven Auxiliary Feedwater pumps actuated as expected. All Emergency Core Cooling Systems and the Emergency Diesel Generators are fully operable if needed. Catawba Unit 2 is operating at 100% power and the electrical grid is stable.
The NRC Resident Inspector was notified of this event by the licensee.
"Reactor Trip caused by Turbine trip. Turbine trip caused by a Moisture Separator Reheater 1B high level. Maintenance personnel were working in vicinity of level switches at time of trip. Root cause investigation in progress. All systems operated as designed on Reactor trip."
Maintenance personnel working in the vicinity of Moisture Separator Reheater 1B were setting up radiography equipment when the MSR 1B high level trip was generated. All rods fully inserted. Both Motor Driven Auxiliary Feedwater pumps actuated as expected. All Emergency Core Cooling Systems and the Emergency Diesel Generators are fully operable if needed. Catawba Unit 2 is operating at 100% power and the electrical grid is stable.
The NRC Resident Inspector was notified of this event by the licensee.