Event Notification Report for April 09, 1999
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/08/1999 - 04/09/1999
EVENT NUMBERS
35570355713556435565355663556735577
Power Reactor
Event Number: 35570
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DANIEL MURRAY
HQ OPS Officer: BOB STRANSKY
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DANIEL MURRAY
HQ OPS Officer: BOB STRANSKY
Notification Date: 04/09/1999
Notification Time: 18:46 [ET]
Event Date: 04/09/1999
Event Time: 18:38 [EDT]
Last Update Date: 04/09/1999
Notification Time: 18:46 [ET]
Event Date: 04/09/1999
Event Time: 18:38 [EDT]
Last Update Date: 04/09/1999
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):
JOHN KINNEMAN (R1)
JOHN KINNEMAN (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 98 | Power Operation | 98 | Power Operation |
DISCREPANCIES DISCOVERED IN APPENDIX R PROCEDURES
"A review associated with an Engineering fire protection self-assessment has identified discrepancies in manual actions specified in select Unit 1 post-fire safe shutdown procedures. Steps in these procedures require certain manual actions to be taken that have been determined to be inappropriate. Performing these actions could place Unit 1 in a condition which is outside the design basis of the Fire Protection Program involving Appendix R Safe Shutdown capability. These actions involve manually de-energizing non-essential class 1E power circuits. The intent of these actions is to turn off circuits that are not required for safe shutdown in order to eliminate the potential for circuit faults due to a postulated fire that could trip out an entire AC distribution panel. However, performing these actions would result in de-energizing the power to the diesel building exhaust dampers. It has been determined that the dampers revert to the closed position when their power supply is de-energized. This could have resulted in the emergency diesel generator operating with insufficient ventilation for diesel room cooling. This condition could have prevented the fulfillment of the safety function of the emergency diesel generators needed to satisfy the Appendix R Safe Shutdown requirements. As a result of these procedural deficiencies, the ability to mitigate the consequences of a fire event and to place the plant in a safe shutdown condition cannot be assured.
"A condition report has been written to document these procedural discrepancies. The root cause and corrective actions are being addressed through the corrective action program."
The licensee will inform the NRC resident inspector of this notification.
"A review associated with an Engineering fire protection self-assessment has identified discrepancies in manual actions specified in select Unit 1 post-fire safe shutdown procedures. Steps in these procedures require certain manual actions to be taken that have been determined to be inappropriate. Performing these actions could place Unit 1 in a condition which is outside the design basis of the Fire Protection Program involving Appendix R Safe Shutdown capability. These actions involve manually de-energizing non-essential class 1E power circuits. The intent of these actions is to turn off circuits that are not required for safe shutdown in order to eliminate the potential for circuit faults due to a postulated fire that could trip out an entire AC distribution panel. However, performing these actions would result in de-energizing the power to the diesel building exhaust dampers. It has been determined that the dampers revert to the closed position when their power supply is de-energized. This could have resulted in the emergency diesel generator operating with insufficient ventilation for diesel room cooling. This condition could have prevented the fulfillment of the safety function of the emergency diesel generators needed to satisfy the Appendix R Safe Shutdown requirements. As a result of these procedural deficiencies, the ability to mitigate the consequences of a fire event and to place the plant in a safe shutdown condition cannot be assured.
"A condition report has been written to document these procedural discrepancies. The root cause and corrective actions are being addressed through the corrective action program."
The licensee will inform the NRC resident inspector of this notification.
Power Reactor
Event Number: 35571
Facility: YANKEE ROWE
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: MARK GILMORE
HQ OPS Officer: BOB STRANSKY
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: MARK GILMORE
HQ OPS Officer: BOB STRANSKY
Notification Date: 04/09/1999
Notification Time: 19:13 [ET]
Event Date: 04/09/1999
Event Time: 18:50 [EDT]
Last Update Date: 04/09/1999
Notification Time: 19:13 [ET]
Event Date: 04/09/1999
Event Time: 18:50 [EDT]
Last Update Date: 04/09/1999
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):
JOHN KINNEMAN (R1)
JOHN KINNEMAN (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Decommissioned | 0 | Decommissioned |
NUCLEAR ALERT TELEPHONE SYSTEM INOPERABLE
The licensee reported that the Nuclear Alert telephone, which links the plant to local police departments, is inoperable. FTS2000 and commercial telephone service is unaffected.
The licensee reported that the Nuclear Alert telephone, which links the plant to local police departments, is inoperable. FTS2000 and commercial telephone service is unaffected.
Power Reactor
Event Number: 35564
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: HOLLAND
HQ OPS Officer: CHAUNCEY GOULD
Region: 2 State: SC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: HOLLAND
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 04/09/1999
Notification Time: 05:15 [ET]
Event Date: 04/09/1999
Event Time: 04:28 [EDT]
Last Update Date: 04/09/1999
Notification Time: 05:15 [ET]
Event Date: 04/09/1999
Event Time: 04:28 [EDT]
Last Update Date: 04/09/1999
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):
WALTER RODGERS (R2)
WALTER RODGERS (R2)
| 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 |
PLANT ENTERED 3.0.3 DUE TO BOTH TRAINS OF CONTROL ROOM VENTILATION BEING INOPERABLE.
A SPURIOUS SIGNAL ON THE CHLORINE DETECTOR ON UNIT 1 "B" TRAIN CONTROL ROOM VENTILATION INTAKE WAS RECEIVED WHILE UNIT 2 VENTILATION INTAKE WAS CLOSED. UNIT 2 CONTROL ROOM INTAKE HAD PREVIOUSLY CLOSED ON A SPURIOUS SIGNAL( SEE EVENT 35561) AND IT WAS STILL CLOSED FOR TROUBLESHOOTING. BOTH UNITS CONTROL ROOM VENT SYSTEMS BEING CLOSED RESULTS IN THE INOPERABILITY OF BOTH TRAINS OF CONTROL ROOM VENTILATION, PLACING BOTH UNITS IN TS 3.0.3.
THE RESIDENT INSPECTOR WILL BE NOTIFIED.
*** UPDATE AT 0530 BY HOLLAND TO GOULD ***
THEY EXITED 3.0.3 AT 0526 WHEN THE "B" TRAIN WAS RESTORED TO OPERABLE CONDITION.
THE RESIDENT INSPECTOR WILL BE NOTIFIED.
A SPURIOUS SIGNAL ON THE CHLORINE DETECTOR ON UNIT 1 "B" TRAIN CONTROL ROOM VENTILATION INTAKE WAS RECEIVED WHILE UNIT 2 VENTILATION INTAKE WAS CLOSED. UNIT 2 CONTROL ROOM INTAKE HAD PREVIOUSLY CLOSED ON A SPURIOUS SIGNAL( SEE EVENT 35561) AND IT WAS STILL CLOSED FOR TROUBLESHOOTING. BOTH UNITS CONTROL ROOM VENT SYSTEMS BEING CLOSED RESULTS IN THE INOPERABILITY OF BOTH TRAINS OF CONTROL ROOM VENTILATION, PLACING BOTH UNITS IN TS 3.0.3.
THE RESIDENT INSPECTOR WILL BE NOTIFIED.
*** UPDATE AT 0530 BY HOLLAND TO GOULD ***
THEY EXITED 3.0.3 AT 0526 WHEN THE "B" TRAIN WAS RESTORED TO OPERABLE CONDITION.
THE RESIDENT INSPECTOR WILL BE NOTIFIED.
Power Reactor
Event Number: 35565
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DANIEL MURRAY
HQ OPS Officer: DOUG WEAVER
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DANIEL MURRAY
HQ OPS Officer: DOUG WEAVER
Notification Date: 04/09/1999
Notification Time: 09:14 [ET]
Event Date: 04/09/1999
Event Time: 08:37 [EDT]
Last Update Date: 04/09/1999
Notification Time: 09:14 [ET]
Event Date: 04/09/1999
Event Time: 08:37 [EDT]
Last Update Date: 04/09/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(v) - ENS INOPERABLE
10 CFR Section:
50.72(b)(1)(v) - ENS INOPERABLE
Person (Organization):
JOHN KINNEMAN (R1)
JOHN KINNEMAN (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Standby | 0 | Hot Standby |
| 2 | N | Y | 98 | Power Operation | 98 | Power Operation |
EMERGENCY SIRENS INOPERABLE
At 0837, the control room received a report from the Beaver County Emergency Management Agency (BCEMA 911 center) that the emergency notification sirens for Beaver County were inoperable. The computer that activates the sirens was damaged by a lightning strike. This constitutes a major loss of emergency communications capability as listed in 10CFR50.72.(b)1.v. Crews are working to repair the main (damaged) computer and are also working to place the backup computer in service. They expect to have the emergency sirens returned to service within 1 hour.
The licensee notified the NRC resident inspector.
*** UPDATE ON 4/9/99 @ 1431 BY SHIPE TO GOULD ***
ALL SIRENS WERE RETURNED TO SERVICE AT 1401.
THE RESIDENT INSPECTOR WILL BE INFORMED. R1DO (KINNEMAN) WAS NOTIFIED.
At 0837, the control room received a report from the Beaver County Emergency Management Agency (BCEMA 911 center) that the emergency notification sirens for Beaver County were inoperable. The computer that activates the sirens was damaged by a lightning strike. This constitutes a major loss of emergency communications capability as listed in 10CFR50.72.(b)1.v. Crews are working to repair the main (damaged) computer and are also working to place the backup computer in service. They expect to have the emergency sirens returned to service within 1 hour.
The licensee notified the NRC resident inspector.
*** UPDATE ON 4/9/99 @ 1431 BY SHIPE TO GOULD ***
ALL SIRENS WERE RETURNED TO SERVICE AT 1401.
THE RESIDENT INSPECTOR WILL BE INFORMED. R1DO (KINNEMAN) WAS NOTIFIED.
Other Nuclear Material
Event Number: 35566
Rep Org: MATERIALS TESTING CONSULTANTS
Licensee: MATERIALS TESTING CONSULTANTS
Region: 3
City: GRAND RAPIDS State: MI
County:
License #: 21-15281-02
Agreement: N
Docket:
NRC Notified By: PETE GASEWICZ
HQ OPS Officer: BOB STRANSKY
Licensee: MATERIALS TESTING CONSULTANTS
Region: 3
City: GRAND RAPIDS State: MI
County:
License #: 21-15281-02
Agreement: N
Docket:
NRC Notified By: PETE GASEWICZ
HQ OPS Officer: BOB STRANSKY
Notification Date: 04/09/1999
Notification Time: 12:14 [ET]
Event Date: 04/09/1999
Event Time: 09:00 [EDT]
Last Update Date: 04/09/1999
Notification Time: 12:14 [ET]
Event Date: 04/09/1999
Event Time: 09:00 [EDT]
Last Update Date: 04/09/1999
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):
BRUCE BURGESS (R3)
SCOTT MOORE (NMSS)
BRUCE BURGESS (R3)
SCOTT MOORE (NMSS)
LOST TROXLER MOISTURE/DENSITY GAUGE
A technician, en route to a project site, encountered problems with his pickup truck approximately one mile from the company offices. The technician was transporting a Troxler model 3430 gauge, containing one 8 mCi Cs-137 source and one 40 mCi Am-241/Be source. A second truck was sent to retrieve the technician and his equipment. However, when the gauge was moved to the second truck, it was not properly secured to the bed of the truck, nor was the tailgate raised. Upon arrival at the office, the technician discovered that the gauge had fallen from the truck. The technician immediately retraced the route of travel, but did not find the gauge. The licensee believes that a passing motorist may have picked it up. The gauge was locked inside of its storage case at the time of the loss. The local police department has been contacted by the licensee.
A technician, en route to a project site, encountered problems with his pickup truck approximately one mile from the company offices. The technician was transporting a Troxler model 3430 gauge, containing one 8 mCi Cs-137 source and one 40 mCi Am-241/Be source. A second truck was sent to retrieve the technician and his equipment. However, when the gauge was moved to the second truck, it was not properly secured to the bed of the truck, nor was the tailgate raised. Upon arrival at the office, the technician discovered that the gauge had fallen from the truck. The technician immediately retraced the route of travel, but did not find the gauge. The licensee believes that a passing motorist may have picked it up. The gauge was locked inside of its storage case at the time of the loss. The local police department has been contacted by the licensee.
General Information or Other
Event Number: 35567
Rep Org: ROCHESTER GAS AND ELECTRIC CORP
Licensee: COLTEC INDUSTRIES
Region: 1
City: ROCHESTER State: NY
County:
License #:
Agreement: Y
Docket:
NRC Notified By: WIDAY (FAX)
HQ OPS Officer: CHAUNCEY GOULD
Licensee: COLTEC INDUSTRIES
Region: 1
City: ROCHESTER State: NY
County:
License #:
Agreement: Y
Docket:
NRC Notified By: WIDAY (FAX)
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 04/09/1999
Notification Time: 13:50 [ET]
Event Date: 04/09/1999
Event Time: 00:00 [EDT]
Last Update Date: 04/09/1999
Notification Time: 13:50 [ET]
Event Date: 04/09/1999
Event Time: 00:00 [EDT]
Last Update Date: 04/09/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
JOHN KINNEMAN (R1)
VERN HODGE (FAX) (NRR)
JOHN KINNEMAN (R1)
VERN HODGE (FAX) (NRR)
THE LICENSEE REPORTED A PART 21 DEFECT ON A REPLACEMENT TURBOCHARGER SUPPLIED BY COLTEC INDUSTRIES.
THE LICENSEE REPLACED A TURBOCHARGER(MODEL 730), SUPPLIED BY COLTEC INDUSTRIES, ON THEIR "B" EMERGENCY DIESEL GENERATOR (ALCO MODEL 16-251F) AT GINNA STATION. IT WAS DETERMINED THAT THERE WAS A MANUFACTURING DEFICIENCY IN THE REPLACEMENT TURBOCHARGER WHICH CONSISTED OF A MISSING DRAIN PORT IN THE INTERMEDIATE CASING ON THE TURBINE END WHICH WOULD PREVENT ENGINE LUBRICATING OIL FROM BEING ABLE TO DRAIN BACK TO THE ENGINE SUMP FROM THE TURBOCHARGER SHAFT AND BEARINGS. THIS DEFICIENCY CREATED A CONDITION WHERE ENGINE LUBE OIL WAS BEING DIRECTED INTO THE CYLINDERS THROUGH THE EXHAUST MANIFOLD PIPING, WHICH COULD HAVE RESULTED IN SERIOUS ENGINE DAMAGE.
THE LICENSEE REPLACED A TURBOCHARGER(MODEL 730), SUPPLIED BY COLTEC INDUSTRIES, ON THEIR "B" EMERGENCY DIESEL GENERATOR (ALCO MODEL 16-251F) AT GINNA STATION. IT WAS DETERMINED THAT THERE WAS A MANUFACTURING DEFICIENCY IN THE REPLACEMENT TURBOCHARGER WHICH CONSISTED OF A MISSING DRAIN PORT IN THE INTERMEDIATE CASING ON THE TURBINE END WHICH WOULD PREVENT ENGINE LUBRICATING OIL FROM BEING ABLE TO DRAIN BACK TO THE ENGINE SUMP FROM THE TURBOCHARGER SHAFT AND BEARINGS. THIS DEFICIENCY CREATED A CONDITION WHERE ENGINE LUBE OIL WAS BEING DIRECTED INTO THE CYLINDERS THROUGH THE EXHAUST MANIFOLD PIPING, WHICH COULD HAVE RESULTED IN SERIOUS ENGINE DAMAGE.
Other Nuclear Material
Event Number: 35577
Rep Org: PAYNE FIRM
Licensee: ARVAN INDUSTRIES
Region: 3
City: GREENWOOD State: IN
County:
License #:
Agreement: N
Docket:
NRC Notified By: DAN WOODY
HQ OPS Officer: FANGIE JONES
Licensee: ARVAN INDUSTRIES
Region: 3
City: GREENWOOD State: IN
County:
License #:
Agreement: N
Docket:
NRC Notified By: DAN WOODY
HQ OPS Officer: FANGIE JONES
Notification Date: 04/12/1999
Notification Time: 10:05 [ET]
Event Date: 04/09/1999
Event Time: 00:00 [CST]
Last Update Date: 04/12/1999
Notification Time: 10:05 [ET]
Event Date: 04/09/1999
Event Time: 00:00 [CST]
Last Update Date: 04/12/1999
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 JACOBSON (R3)
FRED COMBS (NMSS)
ROSEMARY HOGAN (IRO)
JOHN JACOBSON (R3)
FRED COMBS (NMSS)
ROSEMARY HOGAN (IRO)
RADIATION DEVICE CONTAINING 1 CURIE OF AMERICIUM POSSIBLY STOLEN
Arvan Industries of Greenwood, Indiana contacted the Payne Firm (Dan Woody acting as representative) late Friday, 4/9/99, for consultation concerning a radiation device containing 1 Ci of Am-241 that is believed stolen. The device is missing from the Arvan Exhaust Greenwood Facility located at 101 Center St., Greenwood, Indiana during ongoing closure activities. The device weighs about 200 pounds, contains a sealed source of 1 Ci of Am-241, and was used to measure the thickness of rolled steel. The device, an Xact Ray Thickness Gauge 3500 Model, serial #48761-1 and source serial #2786LX was manufactured by the Loral Control Systems of Archbald, Pennsylvania. The manufacturer is no longer in business.
There is an ongoing investigation and a written report will be submitted later.
The police have not been contacted at this time. It will probably be reported to the Greenwood, Indiana police or possibly the Indiana Highway police.
NRC HOO notified Mr John Ruyack of the Indiana Dept of Radiation Protection
Arvan Industries of Greenwood, Indiana contacted the Payne Firm (Dan Woody acting as representative) late Friday, 4/9/99, for consultation concerning a radiation device containing 1 Ci of Am-241 that is believed stolen. The device is missing from the Arvan Exhaust Greenwood Facility located at 101 Center St., Greenwood, Indiana during ongoing closure activities. The device weighs about 200 pounds, contains a sealed source of 1 Ci of Am-241, and was used to measure the thickness of rolled steel. The device, an Xact Ray Thickness Gauge 3500 Model, serial #48761-1 and source serial #2786LX was manufactured by the Loral Control Systems of Archbald, Pennsylvania. The manufacturer is no longer in business.
There is an ongoing investigation and a written report will be submitted later.
The police have not been contacted at this time. It will probably be reported to the Greenwood, Indiana police or possibly the Indiana Highway police.
NRC HOO notified Mr John Ruyack of the Indiana Dept of Radiation Protection