Event Notification Report for October 14, 1999
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/13/1999 - 10/14/1999
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 36290
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: MARK ABRAMSKI
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: MARK ABRAMSKI
HQ OPS Officer: JOHN MacKINNON
Notification Date: 10/14/1999
Notification Time: 12:29 [ET]
Event Date: 10/14/1999
Event Time: 11:30 [EDT]
Last Update Date: 11/09/1999
Notification Time: 12:29 [ET]
Event Date: 10/14/1999
Event Time: 11:30 [EDT]
Last Update Date: 11/09/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(ii)(B) - OUTSIDE DESIGN BASIS
10 CFR Section:
50.72(b)(1)(ii)(B) - OUTSIDE DESIGN BASIS
Person (Organization):
JAMES NOGGLE (R1)
JAMES NOGGLE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
The Charcoal Absorption Efficiency of Train 'B" Standby Gas Treatment System was discovered to be less than 99.8%.
An engineering review of the absorption capability of the Standby Gas Treatment charcoal filters has concluded that the "B" Division of Standby Gas Treatment has been inoperable since 03/30/99. On 04/10/99, samples of the charcoal of the Standby Gas Treatment system were sent offsite to check the absorption efficiency of the charcoal, and other properties of the charcoal. The results of the analysis were received by the licensee on 05/16/99. Today, it was discovered that the absorption efficiency of the charcoal is 99.3%. The licensee has a commitment that the absorption efficiency of the charcoal will be at least 99.8%. The "B" Division of Standby Gas Treatment System is inoperable at this time for another reason.
The NRC Resident Inspector was notified of this event by the licensee.
* * * RETRACTION 0801 11/9/1999 FROM COSTEDIO TAKEN BY STRANSKY * * *
The LOCA dose evaluations assume a standby gas treatment (SBGT) system charcoal efficiency of 99%. Based on the SBGT train 'B' charcoal efficiency test results of 99.37%, the licensee believes that reasonable assurance exists to conclude that the SBGT system would have performed its intended safety function. Based upon this conclusion, the plant did not operate outside of its design basis. The NRC resident inspector has been informed of this event by the licensee. Notified R1DO (Holody).
An engineering review of the absorption capability of the Standby Gas Treatment charcoal filters has concluded that the "B" Division of Standby Gas Treatment has been inoperable since 03/30/99. On 04/10/99, samples of the charcoal of the Standby Gas Treatment system were sent offsite to check the absorption efficiency of the charcoal, and other properties of the charcoal. The results of the analysis were received by the licensee on 05/16/99. Today, it was discovered that the absorption efficiency of the charcoal is 99.3%. The licensee has a commitment that the absorption efficiency of the charcoal will be at least 99.8%. The "B" Division of Standby Gas Treatment System is inoperable at this time for another reason.
The NRC Resident Inspector was notified of this event by the licensee.
* * * RETRACTION 0801 11/9/1999 FROM COSTEDIO TAKEN BY STRANSKY * * *
The LOCA dose evaluations assume a standby gas treatment (SBGT) system charcoal efficiency of 99%. Based on the SBGT train 'B' charcoal efficiency test results of 99.37%, the licensee believes that reasonable assurance exists to conclude that the SBGT system would have performed its intended safety function. Based upon this conclusion, the plant did not operate outside of its design basis. The NRC resident inspector has been informed of this event by the licensee. Notified R1DO (Holody).
Power Reactor
Event Number: 36292
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: NICK LAVATO
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: MD
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: NICK LAVATO
HQ OPS Officer: JOHN MacKINNON
Notification Date: 10/14/1999
Notification Time: 17:09 [ET]
Event Date: 10/14/1999
Event Time: 16:15 [EDT]
Last Update Date: 10/14/1999
Notification Time: 17:09 [ET]
Event Date: 10/14/1999
Event Time: 16:15 [EDT]
Last Update Date: 10/14/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(v) - OTHER ASMT/COMM INOP
10 CFR Section:
50.72(b)(1)(v) - OTHER ASMT/COMM INOP
Person (Organization):
JAMES NOGGLE (R1)
JAMES NOGGLE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
DEDICATED TELEPHONE LINES TO THE MARYLAND EMERGENCY MANAGEMENT AGENCY AND MARYLAND DEPARTMENT OF ENVIRONMENT INOPERABLE FOR ABOUT 10 MINUTES.
THE LICENSEE LOST THEIR DEDICATED LINES TO THE MARYLAND EMERGENCY MANAGEMENT AGENCY AND MARYLAND DEPARTMENT OF ENVIRONMENT FOR APPROXIMATELY 10 MINUTES DUE TO A LOCAL TELEPHONE OUTAGE PROBLEM IN CALVERT COUNTY. THE ONLY MEANS THE LICENSEE HAD TO NOTIFY THE MARYLAND EMERGENCY MANAGEMENT AGENCY AND THE MARYLAND DEPARTMENT OF ENVIRONMENT WAS THEIR RADIO COMMUNICATION SYSTEM.
THE NRC RESIDENT INSPECTOR WILL NOTIFIED OF THE EVENT BY THE LICENSEE.
THE LICENSEE LOST THEIR DEDICATED LINES TO THE MARYLAND EMERGENCY MANAGEMENT AGENCY AND MARYLAND DEPARTMENT OF ENVIRONMENT FOR APPROXIMATELY 10 MINUTES DUE TO A LOCAL TELEPHONE OUTAGE PROBLEM IN CALVERT COUNTY. THE ONLY MEANS THE LICENSEE HAD TO NOTIFY THE MARYLAND EMERGENCY MANAGEMENT AGENCY AND THE MARYLAND DEPARTMENT OF ENVIRONMENT WAS THEIR RADIO COMMUNICATION SYSTEM.
THE NRC RESIDENT INSPECTOR WILL NOTIFIED OF THE EVENT BY THE LICENSEE.
Power Reactor
Event Number: 36293
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ART ZAREMBA
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ART ZAREMBA
HQ OPS Officer: JOHN MacKINNON
Notification Date: 10/14/1999
Notification Time: 19:05 [ET]
Event Date: 10/14/1999
Event Time: 17:44 [EDT]
Last Update Date: 10/14/1999
Notification Time: 19:05 [ET]
Event Date: 10/14/1999
Event Time: 17:44 [EDT]
Last Update Date: 10/14/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
Person (Organization):
JAMES NOGGLE (R1)
JAMES NOGGLE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
TURBINE TRIP/REACTOR SCRAM. THE CAUSE OF THE TURBINE TRIP IS UNKNOWN AT THIS TIME.
THE LICENSEE RECEIVED A TURBINE TRIP/REACTOR SCRAM FOR UNKNOWN REASONS. ALL RODS FULLY INSERTED INTO THE CORE. HIGH PRESSURE COOLANT INJECTION (HPCI) AND REACTOR CORE ISOLATION COOLING (RCIC) AUTOMATICALLY START ON LOW REACTOR VESSEL WATER LEVEL (126.5 INCHES). HPCI AND RCIC DID NOT INJECT INTO THE CORE BECAUSE BOTH HPCI AND RCIC ISOLATED ON HIGH REACTOR VESSEL WATER LEVEL (222.5 INCHES) BEFORE THEY COULD INJECT TO THE REACTOR VESSEL. REACTOR FEEDWATER PUMPS REMAINED OPERATING AND CAUSED REACTOR VESSEL WATER LEVEL TO INCREASE TO THE HIGH LEVEL TRIP POINT OF 222.5 INCHES (REACTOR VESSEL WATER LEVEL DID NOT GET MUCH HIGHER THAN THIS LEVEL). NO SAFETY RELIEF VALVES OPENED. TURBINE BYPASS VALVES ARE BEING USED TO DUMP STEAM TO THE MAIN CONDENSER TO REDUCE REACTOR VESSEL WATER TEMPERATURE TO A COLD SHUTDOWN CONDITION. ALL EMERGENCY CORE COOLING SYSTEMS AND THE EMERGENCY DIESEL GENERATORS ARE FULLY OPERABLE IF NEEDED. THE ELECTRICAL GRID IS ALSO STABLE.
THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE OF THIS EVENT.
THE LICENSEE RECEIVED A TURBINE TRIP/REACTOR SCRAM FOR UNKNOWN REASONS. ALL RODS FULLY INSERTED INTO THE CORE. HIGH PRESSURE COOLANT INJECTION (HPCI) AND REACTOR CORE ISOLATION COOLING (RCIC) AUTOMATICALLY START ON LOW REACTOR VESSEL WATER LEVEL (126.5 INCHES). HPCI AND RCIC DID NOT INJECT INTO THE CORE BECAUSE BOTH HPCI AND RCIC ISOLATED ON HIGH REACTOR VESSEL WATER LEVEL (222.5 INCHES) BEFORE THEY COULD INJECT TO THE REACTOR VESSEL. REACTOR FEEDWATER PUMPS REMAINED OPERATING AND CAUSED REACTOR VESSEL WATER LEVEL TO INCREASE TO THE HIGH LEVEL TRIP POINT OF 222.5 INCHES (REACTOR VESSEL WATER LEVEL DID NOT GET MUCH HIGHER THAN THIS LEVEL). NO SAFETY RELIEF VALVES OPENED. TURBINE BYPASS VALVES ARE BEING USED TO DUMP STEAM TO THE MAIN CONDENSER TO REDUCE REACTOR VESSEL WATER TEMPERATURE TO A COLD SHUTDOWN CONDITION. ALL EMERGENCY CORE COOLING SYSTEMS AND THE EMERGENCY DIESEL GENERATORS ARE FULLY OPERABLE IF NEEDED. THE ELECTRICAL GRID IS ALSO STABLE.
THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE OF THIS EVENT.