Event Notification Report for April 4, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/03/2000 - 04/04/2000
** EVENT NUMBERS **
36847 36850 36857 36858 36859 36860 36861
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|General Information or Other |Event Number: 36847 |
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| REP ORG: LOUISIANA RADIATION PROTECTION DIV |NOTIFICATION DATE: 03/30/2000|
|LICENSEE: FORMOSA PLASTICS |NOTIFICATION TIME: 16:48[EST]|
| CITY: BATON ROUGE REGION: 4 |EVENT DATE: 03/30/2000|
| COUNTY: STATE: LA |EVENT TIME: [CST]|
|LICENSE#: LA-4042-LO1 AGREEMENT: Y |LAST UPDATE DATE: 04/04/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |KRISS KENNEDY R4 |
| |JOHN GREEVES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: COREY MEAUX | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| AGREEMENT STATE REPORT |
| |
| A 100 mCi Cs-137 source was found at the Southern Scrap Yard in Baton Rouge, |
| LA. The source was part of a level gauge used by Formosa Plastics. The |
| source had not been opened and there was no spread of contamination. The |
| manufacturer of the source, Texas Nuclear Technologies, will recover the |
| source. The source is currently in a roped off area at the scrap yard. The |
| State is still investigating how the source ended up in the scrap yard. |
| |
| * * *UPDATE 0928EDT ON 4/3/00 FROM PAT LARKINS TO S.SANDIN * * * |
| |
| THE FOLLOWING INFORMATION WAS FAXED TO THE NRC OPERATIONS CENTER ON 4/3/00 |
| BY THE NRC OFFICE OF STATE PROGRAMS: |
| |
| "APPROXIMATELY 1220 [HOURS] THURSDAY 3/30/00 LDEQ RECEIVED A CALL FROM THE |
| NATIONAL |
| RESPONSE CENTER DIRECTING US TO SOUTHERN SCRAP LOCATED ON SCENIC HWY IN |
| BATON |
| ROUGE, LA, CONCERNING A SOURCE DISCOVERED ON THEIR YARD. THE ATTACHMENT |
| PLATE ON |
| THE Cs-137 LEVEL GAUGE WAS DAMAGED BY A SHREADER AT SOUTHERN SCRAP. THIS |
| ACTION |
| EXPOSED THE SOURCE LEADING TO ITS DISCOVERY. SOUTHERN SCRAP WAS ABLE TO |
| DETERMINE |
| FROM LABELING THAT THE SOURCE WAS A Cs-137 (100 mCi SOURCE MANUFACTURED IN |
| 1991 BY TN |
| TECHNOLOGY AND BELONGED TO FORMOSA PLASTIC. THE SOURCE WAS A MODEL 5200 |
| LEVEL |
| GAUGE, S/N B2209. AT 1430 [HOURS] A MEETING WAS HELD WITH FORMOSA PLASTIC TO |
| TRY TO |
| DETERMINE HOW THE SOURCE ESCAPED THEIR POSSESSION. AT THIS TIME NO MEANS |
| COULD BE |
| DETERMINED. AT 2000 [HOURS] 3/30/00 A TN TECHNOLOGY REPRESENTATIVE RECOVERED |
| THE |
| SOURCE. FOUR WIPE TEST[S] WERE PERFORMED ON THE SOURCE, ALL RESULTING IN THE |
| SOURCE |
| NOT LEAKING. THERE WAS NO CONTAMINATION OF THE AREA. ON 3/31/00, JIM |
| ALDREDGE |
| CONTACTED LDEQ STATING THAT THE SHUTTER WAS NOT SHEERED OFF AND THE GAUGE |
| WAS |
| RETURNED TO THE LOCKED POSITION. MR ALDREDGE ALSO STATED THAT THE GAUGE WAS |
| TO |
| RETURNED TO FORMOSA PLASTIC ON 3/31/00." |
| |
| NOTIFIED R4DO (JONES) AND NMSS (HICKEY). |
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|Fuel Cycle Facility |Event Number: 36850 |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/31/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 15:10[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/30/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:58[CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/03/2000|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |RONALD GARDNER R3 |
| DOCKET: 0707001 |BRIAN SMITH NMSS |
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| NRC NOTIFIED BY: ERIC WALKER | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| CRITICALITY ACCIDENT ALARM SYSTEM FAILURE DURING A TEST |
| |
| At 1845 on 03-30-2000, during functional testing of C-746Q Criticality |
| Accident Alarm System (CAAS), it was discovered that temperature control |
| system on cluster "AD" was unable to perform the ability to maintain the |
| system above the manufacturer's fourteen degree Fahrenheit recommendation |
| due to failure of a temperature switch. The system was last tested on |
| 12-30-99 and was determined to be functional at that time. In January of |
| this year there were several days were outside ambient temperature dropped |
| below fourteen degrees Fahrenheit and operability of system at those times |
| cannot be reasonably determined. Even though the failure was discovered |
| during testing, it is possible that the system would not have performed its |
| intended safety function if it had been required to since the last |
| surveillance on 12-30-99. |
| |
| This event is reportable under 10 CFR 76.120(c)(2) as an event in which |
| equipment required by the TSR is disabled or fails to function as designed. |
| |
| The NRC Senior Resident Inspector has been notified of this event. |
| |
| * * * Update 1155EDT on 4/3/00 from Underwood to S.Sandin * * * |
| |
| Corrected event date and time. Operations informed the NRC Resident |
| Inspector. Notified R3DO (Kozak). |
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|Power Reactor |Event Number: 36857 |
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| FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 04/03/2000|
| UNIT: [] [2] [] STATE: VA |NOTIFICATION TIME: 10:02[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/03/2000|
+------------------------------------------------+EVENT TIME: 08:57[EDT]|
| NRC NOTIFIED BY: MILTON MUNDEN |LAST UPDATE DATE: 04/03/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Standby |
| | |
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EVENT TEXT
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| 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). |
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|Power Reactor |Event Number: 36858 |
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| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 04/03/2000|
| UNIT: [1] [2] [] STATE: MN |NOTIFICATION TIME: 10:43[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/03/2000|
+------------------------------------------------+EVENT TIME: 08:45[CDT]|
| NRC NOTIFIED BY: STEVE GHEEN |LAST UPDATE DATE: 04/03/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS KOZAK R3 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
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| | |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| 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 0925CDT." |
| |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. |
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|Research Reactor |Event Number: 36859 |
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| FACILITY: GEORGIA INSTITUTE OF TECHNOLOGY |NOTIFICATION DATE: 04/03/2000|
| RXTYPE: 5000 KW RESEARCH HW |NOTIFICATION TIME: 10:49[EDT]|
| COMMENTS: |EVENT DATE: 04/03/2000|
| |EVENT TIME: 09:49[EDT]|
| |LAST UPDATE DATE: 04/03/2000|
| CITY: ATLANTA REGION: 2 +-----------------------------+
| COUNTY: FULTON STATE: GA |PERSON ORGANIZATION |
|LICENSE#: R-97 AGREEMENT: Y |CAUDLE JULIAN R2 |
| DOCKET: 05000160 |MARVIN MENDONCA NRR PM |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ROD ICE | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
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| | |
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| | |
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EVENT TEXT
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| SAFEGUARDS SYSTEM DEGRADATION RELATED TO DETECTION/MONITORING/ALARM |
| FUNCTIONS.. COMPENSATORY MEASURES TAKEN IMMEDIATELY UPON DISCOVERY. |
| |
| CONTACT THE OPERATIONS CENTER FOR ADDITIONAL INFORMATION. |
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|Other Nuclear Material |Event Number: 36860 |
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| REP ORG: GE PLASTICS |NOTIFICATION DATE: 04/03/2000|
|LICENSEE: GE PLASTICS |NOTIFICATION TIME: 13:28[EDT]|
| CITY: MT. VERNON REGION: 3 |EVENT DATE: 03/29/2000|
| COUNTY: STATE: IN |EVENT TIME: [CST]|
|LICENSE#: 13-10455-03 AGREEMENT: N |LAST UPDATE DATE: 04/03/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |THOMAS KOZAK R3 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: LAURA CULLEN | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | |
| | |
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EVENT TEXT
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| MISSING 15 mCi NICKEL-63 SOURCE |
| |
| The licensee discovered that a HP model 5890 Gas Chromatograph (serial # |
| 2541A06448), containing a 15 mCi Ni-63 source, was missing from the excess |
| equipment storage on site. The source is contained within an electron |
| capture detector. A search of the entire site was completed on 3/29/00 |
| without finding the device. |
| |
| A written report will be made within thirty days. |
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|General Information or Other |Event Number: 36861 |
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| REP ORG: PPG ARCHITECTURAL FINISHES |NOTIFICATION DATE: 04/03/2000|
|LICENSEE: PPG ARCHITECTURAL FINISHES |NOTIFICATION TIME: 13:20[EDT]|
| CITY: PITTSBURG REGION: 1 |EVENT DATE: 04/03/2000|
| COUNTY: STATE: PA |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 04/03/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |VERN HODGE (FAX) NRR |
| | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JOSEPH KARAS | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 10 CFR PART 21 REPORT |
| |
| "This notification is being made by PPG Architectural Finishes (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 C.F.R. � 21.2 1(d)(3)(ii) will follow." |
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