Event Notification Report for May 20, 1999
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/19/1999 - 05/20/1999
Power Reactor
Event Number: 35748
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MIKE GWIRTZ
HQ OPS Officer: DICK JOLLIFFE
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MIKE GWIRTZ
HQ OPS Officer: DICK JOLLIFFE
Notification Date: 05/20/1999
Notification Time: 22:57 [ET]
Event Date: 05/20/1999
Event Time: 21:37 [EDT]
Last Update Date: 05/20/1999
Notification Time: 22:57 [ET]
Event Date: 05/20/1999
Event Time: 21:37 [EDT]
Last Update Date: 05/20/1999
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):
PETER ESELGROTH (R1)
PETER ESELGROTH (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 Standby |
- UNIT 1 TRIP FROM 100% DUE TO NEGATIVE RATE TRIP SIGNAL DUE TO A DROPPED CONTROL ROD -
AT 2137 ON 05/20/99, UNIT 1 REACTOR AUTOMATICALLY TRIPPED FORM 100% POWER DUE TO A NUCLEAR INSTRUMENTATION NEGATIVE RATE TRIP SIGNAL. PRELIMINARY INDICATIONS ARE THAT THE NEGATIVE RATE TRIP SIGNAL WAS DUE TO THE LOSS OF THE STATIONARY GRIPPER VOLTAGE TO CONTROL ROD #1A3 DUE TO A BLOWN FUSE FOR UNKNOWN REASONS CAUSING CONTROL ROD #1A3 TO DROP INTO THE CORE CAUSING THE NEGATIVE RATE TRIP SIGNAL ON NUCLEAR INSTRUMENT CHANNELS 2 AND 4. NO TESTING WAS BEING CONDUCTED AT THE TIME. ALL OTHER CONTROL RODS INSERTED COMPLETELY. THE AUXILIARY FEEDWATER SYSTEM ACTUATED, AS EXPECTED, DUE TO THE LOW-LOW STEAM GENERATOR LEVELS REACHED DURING THE TRIP, ALSO AS EXPECTED. NO SAFETY OR RELIEF VALVES LIFTED FOLLOWING THE TRIP. DECAY HEAT STEAM IS BEING DUMPED TO THE MAIN CONDENSER. UNIT 1 IS STABLE IN MODE 3 (HOT STANDBY) WITH REACTOR COOLANT SYSTEM TEMPERATURE AT 547°F AND PRESSURE AT 2235 PSIG.
NUMBER 11 CONTAINMENT FAN COIL UNIT WAS INOPERABLE PRIOR TO THE REACTOR TRIP AND WILL BE REPAIRED PRIOR TO THE RESTART OF UNIT 1.
THE LICENSEE PLANS TO INVESTIGATE THE CAUSE OF THE REACTOR TRIP, REPAIR THE ROD CONTROL SYSTEM, MAINTAIN HOT STANDBY MODE, AND PREPARE TO RESTART UNIT 1.
THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR AND LOCAL OFFICIALS, AND ON 05/21/99, ISSUE A PRESS RELEASE.
AT 2137 ON 05/20/99, UNIT 1 REACTOR AUTOMATICALLY TRIPPED FORM 100% POWER DUE TO A NUCLEAR INSTRUMENTATION NEGATIVE RATE TRIP SIGNAL. PRELIMINARY INDICATIONS ARE THAT THE NEGATIVE RATE TRIP SIGNAL WAS DUE TO THE LOSS OF THE STATIONARY GRIPPER VOLTAGE TO CONTROL ROD #1A3 DUE TO A BLOWN FUSE FOR UNKNOWN REASONS CAUSING CONTROL ROD #1A3 TO DROP INTO THE CORE CAUSING THE NEGATIVE RATE TRIP SIGNAL ON NUCLEAR INSTRUMENT CHANNELS 2 AND 4. NO TESTING WAS BEING CONDUCTED AT THE TIME. ALL OTHER CONTROL RODS INSERTED COMPLETELY. THE AUXILIARY FEEDWATER SYSTEM ACTUATED, AS EXPECTED, DUE TO THE LOW-LOW STEAM GENERATOR LEVELS REACHED DURING THE TRIP, ALSO AS EXPECTED. NO SAFETY OR RELIEF VALVES LIFTED FOLLOWING THE TRIP. DECAY HEAT STEAM IS BEING DUMPED TO THE MAIN CONDENSER. UNIT 1 IS STABLE IN MODE 3 (HOT STANDBY) WITH REACTOR COOLANT SYSTEM TEMPERATURE AT 547°F AND PRESSURE AT 2235 PSIG.
NUMBER 11 CONTAINMENT FAN COIL UNIT WAS INOPERABLE PRIOR TO THE REACTOR TRIP AND WILL BE REPAIRED PRIOR TO THE RESTART OF UNIT 1.
THE LICENSEE PLANS TO INVESTIGATE THE CAUSE OF THE REACTOR TRIP, REPAIR THE ROD CONTROL SYSTEM, MAINTAIN HOT STANDBY MODE, AND PREPARE TO RESTART UNIT 1.
THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR AND LOCAL OFFICIALS, AND ON 05/21/99, ISSUE A PRESS RELEASE.
Power Reactor
Event Number: 35744
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: BRADSKY
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: BRADSKY
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 05/20/1999
Notification Time: 10:23 [ET]
Event Date: 05/20/1999
Event Time: 10:14 [EDT]
Last Update Date: 05/21/1999
Notification Time: 10:23 [ET]
Event Date: 05/20/1999
Event Time: 10:14 [EDT]
Last Update Date: 05/21/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - DEG/UNANALYZED COND
10 CFR Section:
50.72(b)(2)(i) - DEG/UNANALYZED COND
Person (Organization):
PETER ESELGROTH (R1)
PETER ESELGROTH (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Refueling | 0 | Refueling |
- FAILURE OF BOTH SAFETY RELATED CONTAINMENT CUBICAL SUMP AIR DRIVEN PUMPS -
ON 5/16/99 DURING THE 18 MONTH SURVEILLANCE FOR THE SAFETY RELATED CONTAINMENT RECIRCULATION CUBICAL SUMP AIR DRIVEN PUMPS, BOTH PUMPS FAILED TO DISCHARGE WATER FROM THE SUMPS TO OUTSIDE THE ENGINEERING SAFETY FEATURES BUILDING. A REVISION TO THE SURVEILLANCE TO INCREASE THE AIR PRESSURE TO THE PUMPS WAS APPROVED ON 5/19/99. ON 5/19/99, BOTH AIR DRIVEN PUMPS WERE DECLARED INOPERABLE WHEN PUMP DAS*P15A FAILED TO DISCHARGE WATER FROM THE SUMPS TO OUTSIDE THE ENGINEERING SAFETY FEATURES BUILDING WITH THE INCREASED AIR PRESSURE.
THE SAFETY RELATED CONTAINMENT RECIRCULATION CUBICAL SUMP AIR DRIVEN PUMPS ARE REQUIRED FOLLOWING A LOCA WHEN THE ENGINEERING SAFETY FEATURES BUILDING IS INACCESSIBLE DUE TO HIGH DOSE RATES IN THE BUILDING. THE PLANT IS CURRENTLY IN A REFUELING OUTAGE AND THE NON-SAFETY RELATED CONTAINMENT RECIRCULATION CUBICAL SUMP PUMPS ARE FUNCTIONAL.
THE CAUSE OF THE EVENT IS CURRENTLY UNDER INVESTIGATION. AT THIS TIME, IT IS HYPOTHESIZED THAT THE AIR CHAMBER OF THE PUMPS ARE FLOODED WITH LUBRICATING OIL WHICH REDUCES THEIR CAPABILITIES TO PUMP WATER.
THE RESIDENT INSPECTOR WAS INFORMED.
*** UPDATE ON 5/21/99 @ 0838 BY MARTIN TO GOULD ***
THE DATE BOTH AIR DRIVEN PUMPS WERE DECLARED INOPERABLE WAS 5/20/99 INSTEAD OF 5/19/99 AS REPORTED IN THE INITIAL REPORT.
THE RESIDENT INSPECTOR WAS NOTIFIED. REG 1 RDO (ESELGROTH) WAS INFORMED.
ON 5/16/99 DURING THE 18 MONTH SURVEILLANCE FOR THE SAFETY RELATED CONTAINMENT RECIRCULATION CUBICAL SUMP AIR DRIVEN PUMPS, BOTH PUMPS FAILED TO DISCHARGE WATER FROM THE SUMPS TO OUTSIDE THE ENGINEERING SAFETY FEATURES BUILDING. A REVISION TO THE SURVEILLANCE TO INCREASE THE AIR PRESSURE TO THE PUMPS WAS APPROVED ON 5/19/99. ON 5/19/99, BOTH AIR DRIVEN PUMPS WERE DECLARED INOPERABLE WHEN PUMP DAS*P15A FAILED TO DISCHARGE WATER FROM THE SUMPS TO OUTSIDE THE ENGINEERING SAFETY FEATURES BUILDING WITH THE INCREASED AIR PRESSURE.
THE SAFETY RELATED CONTAINMENT RECIRCULATION CUBICAL SUMP AIR DRIVEN PUMPS ARE REQUIRED FOLLOWING A LOCA WHEN THE ENGINEERING SAFETY FEATURES BUILDING IS INACCESSIBLE DUE TO HIGH DOSE RATES IN THE BUILDING. THE PLANT IS CURRENTLY IN A REFUELING OUTAGE AND THE NON-SAFETY RELATED CONTAINMENT RECIRCULATION CUBICAL SUMP PUMPS ARE FUNCTIONAL.
THE CAUSE OF THE EVENT IS CURRENTLY UNDER INVESTIGATION. AT THIS TIME, IT IS HYPOTHESIZED THAT THE AIR CHAMBER OF THE PUMPS ARE FLOODED WITH LUBRICATING OIL WHICH REDUCES THEIR CAPABILITIES TO PUMP WATER.
THE RESIDENT INSPECTOR WAS INFORMED.
*** UPDATE ON 5/21/99 @ 0838 BY MARTIN TO GOULD ***
THE DATE BOTH AIR DRIVEN PUMPS WERE DECLARED INOPERABLE WAS 5/20/99 INSTEAD OF 5/19/99 AS REPORTED IN THE INITIAL REPORT.
THE RESIDENT INSPECTOR WAS NOTIFIED. REG 1 RDO (ESELGROTH) WAS INFORMED.
Fuel Cycle Facility
Event Number: 35745
Facility: PORTSMOUTH GASEOUS DIFFUSION PLANT
Region: 3 State: OH
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: RICK LARSON
HQ OPS Officer: DICK JOLLIFFE
Region: 3 State: OH
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: RICK LARSON
HQ OPS Officer: DICK JOLLIFFE
Notification Date: 05/20/1999
Notification Time: 12:52 [ET]
Event Date: 05/20/1999
Event Time: 10:40 [EDT]
Last Update Date: 05/20/1999
Notification Time: 12:52 [ET]
Event Date: 05/20/1999
Event Time: 10:40 [EDT]
Last Update Date: 05/20/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
BRENT CLAYTON (R3)
SCOTT MOORE (NMSS)
BRENT CLAYTON (R3)
SCOTT MOORE (NMSS)
- DOE NOTIFIED OF URANIUM BEARING SOLUTION LEAKING FROM A POLYBOTTLE -
At 1040 on 05/20/99, the DOE was notified of an off-normal event classified as a Level 3 Nuclear Criticality Safety Incident that occurred in the X-706 West Annex which is regulated by the DOE and operated by USEC under a Regulatory Oversight Agreement. The Site DOE Manager and the DOE Regulatory Oversight Manager were verbally notified. The notification stated the following:
At 1800 on 05/19/99, plant personnel discovered a small amount of uranium bearing solution leaking from a small diameter storage container (polybottle) in the HEU cylinder cleaning area of the X-705 West Annex. Plant Nuclear Criticality Safety personnel determined the leak to be a loss of geometry control, such that only one of the double contingency controls remained in place.
This event is reportable to the NRC per requirements in the plant's Safety Analysis Report, Section 6.9, Table 1, Criteria P, Miscellaneous: USEC shall notify the NRC of any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made. Such an event may include an onsite fatality or inadvertent release of radioactively contaminated materials.
The licensee notified the NRC Resident Inspector.
At 1040 on 05/20/99, the DOE was notified of an off-normal event classified as a Level 3 Nuclear Criticality Safety Incident that occurred in the X-706 West Annex which is regulated by the DOE and operated by USEC under a Regulatory Oversight Agreement. The Site DOE Manager and the DOE Regulatory Oversight Manager were verbally notified. The notification stated the following:
At 1800 on 05/19/99, plant personnel discovered a small amount of uranium bearing solution leaking from a small diameter storage container (polybottle) in the HEU cylinder cleaning area of the X-705 West Annex. Plant Nuclear Criticality Safety personnel determined the leak to be a loss of geometry control, such that only one of the double contingency controls remained in place.
This event is reportable to the NRC per requirements in the plant's Safety Analysis Report, Section 6.9, Table 1, Criteria P, Miscellaneous: USEC shall notify the NRC of any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made. Such an event may include an onsite fatality or inadvertent release of radioactively contaminated materials.
The licensee notified the NRC Resident Inspector.