Event Notification Report for August 02, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/01/2001 - 08/02/2001
EVENT NUMBERS
38180381813818238183
Other Nuclear Material
Event Number: 38180
Rep Org: NTH CONSULTANTS
Licensee: NTH CONSULTANTS
Region: 3
City: FARMINGTON HILLS State: MI
County:
License #: 21-14894-01
Agreement: N
Docket:
NRC Notified By: JIM CARSONS
HQ OPS Officer: FANGIE JONES
Licensee: NTH CONSULTANTS
Region: 3
City: FARMINGTON HILLS State: MI
County:
License #: 21-14894-01
Agreement: N
Docket:
NRC Notified By: JIM CARSONS
HQ OPS Officer: FANGIE JONES
Notification Date: 08/02/2001
Notification Time: 08:49 [ET]
Event Date: 08/02/2001
Event Time: 07:50 [EDT]
Last Update Date: 08/02/2001
Notification Time: 08:49 [ET]
Event Date: 08/02/2001
Event Time: 07:50 [EDT]
Last Update Date: 08/02/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
JOHN MADERA (R3)
BRIAN SMITH (NMSS)
JOHN MADERA (R3)
BRIAN SMITH (NMSS)
STOLEN TROXLER MOISTURE DENSITY GAUGE
The licensee reported a missing (presumed stolen) Troxler moisture density gauge, model #3401 serial #14236. The gauge was discovered missing from the bed of a pickup where it had been locked in its case and the case cabled to the truck. The gauge contains 2 sources, one of approximately 8 mCi Cs-137 and the other 40 mCi Am-241:Be. The licensee intends to make a police report and is retracing the trucks route from the work site back to the driver's home located in Farmington Hills, MI.
The licensee reported a missing (presumed stolen) Troxler moisture density gauge, model #3401 serial #14236. The gauge was discovered missing from the bed of a pickup where it had been locked in its case and the case cabled to the truck. The gauge contains 2 sources, one of approximately 8 mCi Cs-137 and the other 40 mCi Am-241:Be. The licensee intends to make a police report and is retracing the trucks route from the work site back to the driver's home located in Farmington Hills, MI.
Power Reactor
Event Number: 38181
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: TOM OSELAND
HQ OPS Officer: BOB STRANSKY
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: TOM OSELAND
HQ OPS Officer: BOB STRANSKY
Notification Date: 08/02/2001
Notification Time: 10:07 [ET]
Event Date: 08/02/2001
Event Time: 08:23 [CDT]
Last Update Date: 08/02/2001
Notification Time: 10:07 [ET]
Event Date: 08/02/2001
Event Time: 08:23 [CDT]
Last Update Date: 08/02/2001
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JOHN MADERA (R3)
PAT MADDEN (NRR)
JOSEPH HOLONICH (IRO)
MARK RING (R3)
JAMES DYER (R3)
JOHN MADERA (R3)
PAT MADDEN (NRR)
JOSEPH HOLONICH (IRO)
MARK RING (R3)
JAMES DYER (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
UNUSUAL EVENT DECLARED DUE TO LOSS OF OFFSITE POWER FOLLOWING LIGHTNING STRIKE
At 0823 CDT, the licensee declared an Unusual Event due to a lightning strike on or near the Unit 2 main transformer which caused a fire in the transformer and a loss of offsite power to the unit. Both emergency diesel generators (the Unit 2 and swing EDGs) started and loaded. An automatic reactor scram occurred and all control rods inserted following the scram. The unit is currently in Hot Shutdown with decay heat being removed via the safety/relief valves and reactor vessel water level control being maintained using the safe shutdown makeup pump and the reactor core isolation cooling (RCIC) system.
Offsite firefighting assistance was requested to combat the fire, which has since been extinguished. The licensee is currently in the process of restoring offsite power to the unit. The electrical transient did not significantly affect the operation of Unit 1.
The NRC resident inspector has been informed by the licensee.
HOO NOTE: The NRC senior resident inspector notified the NRC Operations Center of this event at 0933 EDT. The agency entered the monitoring phase of normal mode at 1003 EDT.
* * * UPDATE 1220EDT ON 8/2/01 FROM FOSTER (REGION 3 IRC) TO S. SANDIN * * *
Region 3 has secured from Monitoring at 1120CDT based on current plant conditions and the licensee's on-going restoration of offsite power. Notified IRO(Holonich).
* * * UPDATE 1253EDT ON 8/2/01 FROM CHRISSOTIMOS TO S. SANDIN * * *
Unit 2 exited the Unusual Event at 1147CDT. The following information was provided via fax:
"The Unit 2 and 1/2 [Swing] Emergency Diesel Generators Auto Started on the ESF signal. Group II and III isolations were received as expected. Local Fire Department assisted in fire activities and extinguished transformer fire. RCIC and the Safe Shutdown Makeup Pump were manually initiated to provide level control. Relief valves were manually operated to control pressure. At 1048 CDT Transformer 22 power was restored and is providing loads to Unit 2. Both EDG's have been shutdown. The Illinois Emergency Management Agency has been notified of the Hazmat spill from the transformer fire.
"A courtesy call was also made to the National Response Center for a potential of a Hazmat spill into the Mississippi River [NRC Incident Report # 575186].
"The Unusual Event was terminated at 1147 CDT."
The licensee is in the process of informing state/local agencies and has informed the NRC resident inspector. Notified R3DO(Madera), EO(Madden), IRO(Holonich), EDO(Bergman) and FEMA(Caldwell).
At 0823 CDT, the licensee declared an Unusual Event due to a lightning strike on or near the Unit 2 main transformer which caused a fire in the transformer and a loss of offsite power to the unit. Both emergency diesel generators (the Unit 2 and swing EDGs) started and loaded. An automatic reactor scram occurred and all control rods inserted following the scram. The unit is currently in Hot Shutdown with decay heat being removed via the safety/relief valves and reactor vessel water level control being maintained using the safe shutdown makeup pump and the reactor core isolation cooling (RCIC) system.
Offsite firefighting assistance was requested to combat the fire, which has since been extinguished. The licensee is currently in the process of restoring offsite power to the unit. The electrical transient did not significantly affect the operation of Unit 1.
The NRC resident inspector has been informed by the licensee.
HOO NOTE: The NRC senior resident inspector notified the NRC Operations Center of this event at 0933 EDT. The agency entered the monitoring phase of normal mode at 1003 EDT.
* * * UPDATE 1220EDT ON 8/2/01 FROM FOSTER (REGION 3 IRC) TO S. SANDIN * * *
Region 3 has secured from Monitoring at 1120CDT based on current plant conditions and the licensee's on-going restoration of offsite power. Notified IRO(Holonich).
* * * UPDATE 1253EDT ON 8/2/01 FROM CHRISSOTIMOS TO S. SANDIN * * *
Unit 2 exited the Unusual Event at 1147CDT. The following information was provided via fax:
"The Unit 2 and 1/2 [Swing] Emergency Diesel Generators Auto Started on the ESF signal. Group II and III isolations were received as expected. Local Fire Department assisted in fire activities and extinguished transformer fire. RCIC and the Safe Shutdown Makeup Pump were manually initiated to provide level control. Relief valves were manually operated to control pressure. At 1048 CDT Transformer 22 power was restored and is providing loads to Unit 2. Both EDG's have been shutdown. The Illinois Emergency Management Agency has been notified of the Hazmat spill from the transformer fire.
"A courtesy call was also made to the National Response Center for a potential of a Hazmat spill into the Mississippi River [NRC Incident Report # 575186].
"The Unusual Event was terminated at 1147 CDT."
The licensee is in the process of informing state/local agencies and has informed the NRC resident inspector. Notified R3DO(Madera), EO(Madden), IRO(Holonich), EDO(Bergman) and FEMA(Caldwell).
Fuel Cycle Facility
Event Number: 38182
Facility: PADUCAH GASEOUS DIFFUSION PLANT
Region: 3 State: KY
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: M. C. PITTMAN
HQ OPS Officer: STEVE SANDIN
Region: 3 State: KY
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: M. C. PITTMAN
HQ OPS Officer: STEVE SANDIN
Notification Date: 08/02/2001
Notification Time: 18:10 [ET]
Event Date: 08/02/2001
Event Time: 12:38 [CDT]
Last Update Date: 08/02/2001
Notification Time: 18:10 [ET]
Event Date: 08/02/2001
Event Time: 12:38 [CDT]
Last Update Date: 08/02/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JOHN MADERA (R3)
LARRY CAMPER (NMSS)
JOHN MADERA (R3)
LARRY CAMPER (NMSS)
24-HOUR REPORT INVOLVING A SAFETY SYSTEM ACTUATION DUE TO A VALID SIGNAL
"At 1250 on 08/02/01, the PSS office was notified that a High Autoclave Steam Pressure alarm was received on the C-337A autoclave position 2 west Autoclave Steam Pressure Control System (SPCS). The SPCS system is required to be operable while feeding in mode 5 according to TSR 2.2.3.3. The autoclave was in Mode 5 at the time of the actuation. The indications were checked according to the alarm response procedure and the alarm was determined to be a valid signal. The autoclave was removed from service and the Steam Pressure Control System was declared inoperable by the Plant Shift Superintendent.
"This safety system actuation is reportable to the NRC as required by Safety Analysis Report, section 6.9, table 1, criteria J.2, Safety System actuation due to a valid signal as a 24-hour event notification.
"The NRC Senior Resident Inspector has been notified of this event."
"At 1250 on 08/02/01, the PSS office was notified that a High Autoclave Steam Pressure alarm was received on the C-337A autoclave position 2 west Autoclave Steam Pressure Control System (SPCS). The SPCS system is required to be operable while feeding in mode 5 according to TSR 2.2.3.3. The autoclave was in Mode 5 at the time of the actuation. The indications were checked according to the alarm response procedure and the alarm was determined to be a valid signal. The autoclave was removed from service and the Steam Pressure Control System was declared inoperable by the Plant Shift Superintendent.
"This safety system actuation is reportable to the NRC as required by Safety Analysis Report, section 6.9, table 1, criteria J.2, Safety System actuation due to a valid signal as a 24-hour event notification.
"The NRC Senior Resident Inspector has been notified of this event."
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 38183
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: TIM RIEGER
HQ OPS Officer: STEVE SANDIN
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: TIM RIEGER
HQ OPS Officer: STEVE SANDIN
Notification Date: 08/02/2001
Notification Time: 19:17 [ET]
Event Date: 08/02/2001
Event Time: 15:00 [EDT]
Last Update Date: 09/28/2001
Notification Time: 19:17 [ET]
Event Date: 08/02/2001
Event Time: 15:00 [EDT]
Last Update Date: 09/28/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
CLIFFORD ANDERSON (R1)
HERB BERKOW (NRR)
CLIFFORD ANDERSON (R1)
HERB BERKOW (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNANALYZED CONDITION INVOLVING SEISMIC EVENT DISCOVERED DURING ENGINEERING REVIEW
"On August 2, 2001, at approximately 1500 hours, Engineering notified operations that the Service Water (SW) System may not meet analyzed flow requirements after a seismic event as a result of a system re-alignment change implemented June 4, 2001. The SWS re-alignment change placed an 8 inch non-seismic SW line on the essential SW header. The SWS was originally analyzed for a seismic event with the break of a 10 inch non-seismic SW line. The change evaluation concluded that this configuration was bounding for the alignment. The assessment of the alignment change did not adequately consider the effects of the seismic event. After a review of the change, Engineering judged that the SWS would not meet system design flow requirement after a seismic event with two out of three pumps due to the failure of both non-seismic lines that were aligned as a result of the change. Operations initiated realignment of the 8 inch SW line back to the non-essential header which was completed at 1640 hours. Engineering is performing evaluations but judged that the SWS would have met flow requirements for plant shutdown with three SW pumps operable after a seismic event with no random single failure (three pumps operable)."
The licensee will inform the NRC resident inspector.
**** RETRACTION ON 09/28/01 AT 1002 HOURS BY TIM RIEGER TAKEN BY MACKINNON ****
Upon further assessment, the re-alignment condition is not considered reportable. Additional engineering reviews showed that the alignment to the non-seismic SW lines to the Essential header was not risk significant. Engineering judgement and analysis concluded that the plant design basis events, including the seismic event, would not cause a consequential loss of the non-seismic lines aligned to the Essential header. Therefore, the condition did not significantly degrade plant safety and although at the time was unanalyzed, the condition does not meet reporting requirements. As part of Indian Point 3's corrective action program, the cause and extent of condition of the event is being evaluated and identified corrective actions will be performed. R3DO (John Kinneman) notified.
The NRC Resident Inspector was notified of this retraction by the licensee.
"On August 2, 2001, at approximately 1500 hours, Engineering notified operations that the Service Water (SW) System may not meet analyzed flow requirements after a seismic event as a result of a system re-alignment change implemented June 4, 2001. The SWS re-alignment change placed an 8 inch non-seismic SW line on the essential SW header. The SWS was originally analyzed for a seismic event with the break of a 10 inch non-seismic SW line. The change evaluation concluded that this configuration was bounding for the alignment. The assessment of the alignment change did not adequately consider the effects of the seismic event. After a review of the change, Engineering judged that the SWS would not meet system design flow requirement after a seismic event with two out of three pumps due to the failure of both non-seismic lines that were aligned as a result of the change. Operations initiated realignment of the 8 inch SW line back to the non-essential header which was completed at 1640 hours. Engineering is performing evaluations but judged that the SWS would have met flow requirements for plant shutdown with three SW pumps operable after a seismic event with no random single failure (three pumps operable)."
The licensee will inform the NRC resident inspector.
**** RETRACTION ON 09/28/01 AT 1002 HOURS BY TIM RIEGER TAKEN BY MACKINNON ****
Upon further assessment, the re-alignment condition is not considered reportable. Additional engineering reviews showed that the alignment to the non-seismic SW lines to the Essential header was not risk significant. Engineering judgement and analysis concluded that the plant design basis events, including the seismic event, would not cause a consequential loss of the non-seismic lines aligned to the Essential header. Therefore, the condition did not significantly degrade plant safety and although at the time was unanalyzed, the condition does not meet reporting requirements. As part of Indian Point 3's corrective action program, the cause and extent of condition of the event is being evaluated and identified corrective actions will be performed. R3DO (John Kinneman) notified.
The NRC Resident Inspector was notified of this retraction by the licensee.