Event Notification Report for April 03, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/02/2000 - 04/03/2000
EVENT NUMBERS
36861368573685836859
General Information or Other
Event Number: 36861
Rep Org: PPG ARCHITECTURAL FINISHES, INC
Licensee: PPG ARCHITECTURAL FINISHES, INC
Region: 1
City: PITTSBURGH State: PA
County: ALLEGHENY
License #:
Agreement: N
Docket:
NRC Notified By: JOSEPH KARAS
HQ OPS Officer: FANGIE JONES
Licensee: PPG ARCHITECTURAL FINISHES, INC
Region: 1
City: PITTSBURGH State: PA
County: ALLEGHENY
License #:
Agreement: N
Docket:
NRC Notified By: JOSEPH KARAS
HQ OPS Officer: FANGIE JONES
Notification Date: 04/03/2000
Notification Time: 13:20 [ET]
Event Date: 04/03/2000
Event Time: 00:00 [EDT]
Last Update Date: 05/03/2000
Notification Time: 13:20 [ET]
Event Date: 04/03/2000
Event Time: 00:00 [EDT]
Last Update Date: 05/03/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
VERN HODGE (FAX) (NRR)
VERN HODGE (FAX) (NRR)
10 CFR PART 21 REPORT
"This notification is being made by PPG Architectural Finishes, Inc (PPG) concerning relatively small quantities of a silicon stainless steel enamel coating used inside primary containment supplied to a single utility which is a NRC nuclear power plant licensee. The coating was not appropriately controlled such that its formulation changed from that which was originally supplied. The utility has been informed and is working with PPG. Further investigation is being conducted which may result in the withdrawal or modification of this notification. Written notification in accordance with 10 CFR § 21.2 1(d)(3)(ii) will follow."
* * * UPDATE AT 1640 ON 05/03/00 BY JOSEPH M. KARAS, PPG INDUSTRIES, INC TO JOLLIFFE * * *
Exterior silicone stainless steel enamel coating #8674 qualified for Coating Service Level I Exposure in 1980 by PPG Industries, Inc, Keeler & Long Division, was supplied as a commercial grade item (not included in the supplier's Quality Assurance Program) to Duke Energy Company Nuclear Facilities, Catawba, McGuire and Oconee. This coating is being used inside containment on piping that is contained by mirror insulation which should minimize the potential for paint chip fouling of sump pumps thereby interfering with the operation of Emergency Core Cooling Systems in the event of a DBA incident.
The NRC Operations Officer notified the R2DO Bob Haag and NRR Vern Hodge (by fax).
"This notification is being made by PPG Architectural Finishes, Inc (PPG) concerning relatively small quantities of a silicon stainless steel enamel coating used inside primary containment supplied to a single utility which is a NRC nuclear power plant licensee. The coating was not appropriately controlled such that its formulation changed from that which was originally supplied. The utility has been informed and is working with PPG. Further investigation is being conducted which may result in the withdrawal or modification of this notification. Written notification in accordance with 10 CFR § 21.2 1(d)(3)(ii) will follow."
* * * UPDATE AT 1640 ON 05/03/00 BY JOSEPH M. KARAS, PPG INDUSTRIES, INC TO JOLLIFFE * * *
Exterior silicone stainless steel enamel coating #8674 qualified for Coating Service Level I Exposure in 1980 by PPG Industries, Inc, Keeler & Long Division, was supplied as a commercial grade item (not included in the supplier's Quality Assurance Program) to Duke Energy Company Nuclear Facilities, Catawba, McGuire and Oconee. This coating is being used inside containment on piping that is contained by mirror insulation which should minimize the potential for paint chip fouling of sump pumps thereby interfering with the operation of Emergency Core Cooling Systems in the event of a DBA incident.
The NRC Operations Officer notified the R2DO Bob Haag and NRR Vern Hodge (by fax).
Power Reactor
Event Number: 36857
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MILTON MUNDEN
HQ OPS Officer: STEVE SANDIN
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MILTON MUNDEN
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/03/2000
Notification Time: 10:02 [ET]
Event Date: 04/03/2000
Event Time: 08:57 [EDT]
Last Update Date: 04/03/2000
Notification Time: 10:02 [ET]
Event Date: 04/03/2000
Event Time: 08:57 [EDT]
Last Update Date: 04/03/2000
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):
CAUDLE JULIAN (R2)
CAUDLE JULIAN (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP ON TURBINE TRIP DUE TO STATION SERVICE TRANSFORMER FAULT
"REACTOR TRIP CAUSED BY LOSS OF 'C' STATION SERVICE TRANSFORMER DUE TO A FAULT. THE AUXILIARY FEEDWATER SYSTEM ACTUATED AS DESIGNED."
THE LICENSEE'S PRELIMINARY EVAULATION OF THE TRANSFORMER FAULT INDICATES INSULATION FAILURE. FOLLOWING THE TRIP, NO PRIMARY/SECONDARY SAFETIES OR RELIEFS LIFTED. ALL CONTROL RODS FULLY INSERTED. ALL (3) AFW PUMPS STARTED AS DESIGNED SUPPLYING MAKEUP TO THE STEAM GENERATORS. THE MAIN CONDENSER IS IN SERVICE ACTING AS A HEAT SINK FOR DECAY HEAT REMOVAL. ALL ELECTRICAL LOADS REMAINED ENERGIZED WITH OFFSITE POWER SUPPLIED THROUGH THE RESERVE STATION TRANSFORMER. THE EMERGENCY DIESEL GENERATORS ARE AVAILABLE, IF NEEDED. UNIT 2 WILL REMAIN IN MODE 3 PENDING THE RESULTS OF THE INVESTIGATION INTO THE TRANSFORMER FAULT.
THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.
* * * UPDATE 1052EDT ON 4/3/00 FROM MUNDEN TO S.SANDIN * * *
"AUXILIARY FEEDWATER SYSTEM AUTOMATIC ACTUATION [1014EDT] FOLLOWING SECURING DUE TO LOW-LOW LEVEL IN 'C' STEAM GENERATOR."
THE AFW SYSTEM HAS BEEN SECURED WITH MAIN FEED IN SERVICE USING THE BYPASS VALVES.
THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED R2DO (JULIAN).
"REACTOR TRIP CAUSED BY LOSS OF 'C' STATION SERVICE TRANSFORMER DUE TO A FAULT. THE AUXILIARY FEEDWATER SYSTEM ACTUATED AS DESIGNED."
THE LICENSEE'S PRELIMINARY EVAULATION OF THE TRANSFORMER FAULT INDICATES INSULATION FAILURE. FOLLOWING THE TRIP, NO PRIMARY/SECONDARY SAFETIES OR RELIEFS LIFTED. ALL CONTROL RODS FULLY INSERTED. ALL (3) AFW PUMPS STARTED AS DESIGNED SUPPLYING MAKEUP TO THE STEAM GENERATORS. THE MAIN CONDENSER IS IN SERVICE ACTING AS A HEAT SINK FOR DECAY HEAT REMOVAL. ALL ELECTRICAL LOADS REMAINED ENERGIZED WITH OFFSITE POWER SUPPLIED THROUGH THE RESERVE STATION TRANSFORMER. THE EMERGENCY DIESEL GENERATORS ARE AVAILABLE, IF NEEDED. UNIT 2 WILL REMAIN IN MODE 3 PENDING THE RESULTS OF THE INVESTIGATION INTO THE TRANSFORMER FAULT.
THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.
* * * UPDATE 1052EDT ON 4/3/00 FROM MUNDEN TO S.SANDIN * * *
"AUXILIARY FEEDWATER SYSTEM AUTOMATIC ACTUATION [1014EDT] FOLLOWING SECURING DUE TO LOW-LOW LEVEL IN 'C' STEAM GENERATOR."
THE AFW SYSTEM HAS BEEN SECURED WITH MAIN FEED IN SERVICE USING THE BYPASS VALVES.
THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED R2DO (JULIAN).
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 36858
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: STEVE GHEEN
HQ OPS Officer: STEVE SANDIN
Region: 3 State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: STEVE GHEEN
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/03/2000
Notification Time: 10:43 [ET]
Event Date: 04/03/2000
Event Time: 08:45 [CDT]
Last Update Date: 04/17/2000
Notification Time: 10:43 [ET]
Event Date: 04/03/2000
Event Time: 08:45 [CDT]
Last Update Date: 04/17/2000
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):
THOMAS KOZAK (R3)
THOMAS KOZAK (R3)
| 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 |
HIGH ENERGY LINE BREAK ANALYSES (HELB) REQUIRE DOORS IN AREAS CONTAINING MAIN STEAM LINES NOT BE BLOCKED OR OBSTRUCTED
"DOORS 155/177 OBSTRUCTED BY SCAFFOLDING CAUSING DOORS TO BE PARTIALLY BLOCKED. DUE TO HELB CONSIDERATIONS, DOORS NEED TO BE ABLE TO SWING OPEN FULLY. SCAFFOLDING WAS MOVED AT 0925 CDT."
THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.
* * * RETRACTED AT 1130 EDT ON 4/17/00 BY WILLIAM MATHER TO FANGIE JONES * * *
"Northern States Power Company's Nuclear Analysis Department (NAD) completed calculations based on the doors being blocked and as a result of these calculations is withdrawing the Event Notification #36858." The analysis indicates that there is no significant effect on peak pressure during the analyzed event.
The licensee notified the NRC Resident Inspector. The NRC Operations Officer notified the R3DO (Patrick Hiland).
"DOORS 155/177 OBSTRUCTED BY SCAFFOLDING CAUSING DOORS TO BE PARTIALLY BLOCKED. DUE TO HELB CONSIDERATIONS, DOORS NEED TO BE ABLE TO SWING OPEN FULLY. SCAFFOLDING WAS MOVED AT 0925 CDT."
THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.
* * * RETRACTED AT 1130 EDT ON 4/17/00 BY WILLIAM MATHER TO FANGIE JONES * * *
"Northern States Power Company's Nuclear Analysis Department (NAD) completed calculations based on the doors being blocked and as a result of these calculations is withdrawing the Event Notification #36858." The analysis indicates that there is no significant effect on peak pressure during the analyzed event.
The licensee notified the NRC Resident Inspector. The NRC Operations Officer notified the R3DO (Patrick Hiland).
Research Reactor
Event Number: 36859
Rep Org: GEORGIA INSTITUTE OF TECHNOLOGY
Licensee: GEORGIA INSTITUTE OF TECHNOLOGY
Region: 2
City: ATLANTA State: GA
County: FULTON
License #: R-97
Agreement: Y
Docket: 05000160
NRC Notified By: ROD ICE
HQ OPS Officer: CHAUNCEY GOULD
Licensee: GEORGIA INSTITUTE OF TECHNOLOGY
Region: 2
City: ATLANTA State: GA
County: FULTON
License #: R-97
Agreement: Y
Docket: 05000160
NRC Notified By: ROD ICE
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 04/03/2000
Notification Time: 10:49 [ET]
Event Date: 04/03/2000
Event Time: 09:49 [EDT]
Last Update Date: 04/05/2000
Notification Time: 10:49 [ET]
Event Date: 04/03/2000
Event Time: 09:49 [EDT]
Last Update Date: 04/05/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
CAUDLE JULIAN (R2)
MARVIN MENDONCA NRR (PM)
CAUDLE JULIAN (R2)
MARVIN MENDONCA NRR (PM)
SAFEGUARDS SYSTEM DEGRADATION RELATED TO DETECTION/MONITORING/ALARM FUNCTIONS.. COMPENSATORY MEASURES TAKEN IMMEDIATELY UPON DISCOVERY.
CONTACT THE OPERATIONS CENTER FOR ADDITIONAL INFORMATION.
* * * UPDATE AT 1507 EDT ON 4/5/00 BY ROD ICE TO FANGIE JONES * * *
Normal safeguards systems are restored. Notified R2DO (Steve Cahill) and NRR (Ed Goodwin).
CONTACT THE OPERATIONS CENTER FOR ADDITIONAL INFORMATION.
* * * UPDATE AT 1507 EDT ON 4/5/00 BY ROD ICE TO FANGIE JONES * * *
Normal safeguards systems are restored. Notified R2DO (Steve Cahill) and NRR (Ed Goodwin).