U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/13/2000 - 10/16/2000
** EVENT NUMBERS **
37426 37427 37428 37429 37430 37431
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|General Information or Other |Event Number: 37426 |
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| REP ORG: NATIONAL INSTITUTE OF HEALTH |NOTIFICATION DATE: 10/13/2000|
|LICENSEE: NATIONAL INSTITUTE OF HEALTH |NOTIFICATION TIME: 16:04[EDT]|
| CITY: BETHESDA REGION: 1 |EVENT DATE: 10/13/2000|
| COUNTY: STATE: MD |EVENT TIME: [EDT]|
|LICENSE#: 19-00296-10 AGREEMENT: Y |LAST UPDATE DATE: 10/13/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LAWRENCE DOERFLEIN R1 |
| |PATRICIA HOLAHAN NMSS |
+------------------------------------------------+JOSEPH GIITTER IRO |
| NRC NOTIFIED BY: ZOON | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|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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| THE NATIONAL INSTITUTE OF HEALTH REPORTED A MISSING PHOSPHORUS - 32 SOURCE |
| |
| On September 22, 2000 a researcher and Authorized User within the NIH |
| Radiation Safety Program reported to his area health physicist that |
| approximately 600 microcuries of Phosphorus-32 labeled DCTP was missing from |
| a source vial. The source vial of NEN Catalog Number BLU513Z had been first |
| opened the previous day, September 21, 2000, by another researcher who |
| remembered removing only 400 microcuries of the total activity of 1000 |
| microcuries for an experiment. This researcher then replaced the vial into |
| the refrigerator, noting that 30 microliters (600 microcuries) were left. |
| |
| The research laboratory staff distinctly recalled locking the laboratory at |
| the end of that day, in accordance with NIH policy for the security of |
| radioactive materials, and also recalled having to unlock the laboratory the |
| next morning. |
| |
| However, on September 22 at 11 A.M., when a third researcher went to use the |
| remaining P-32 DCTP from the same vial as was used the previous day, the |
| vial was completely empty. |
| |
| The researchers performed extensive contamination surveys to determine if |
| the contents had spilled; no contamination was found. Following notification |
| of the Radiation Safety Branch, the area health physicist performed |
| extensive contamination checks throughout the Department to ensure that the |
| material had not been used to intentionally contaminate anything. Again, no |
| contamination was found. The Authorized User notified the NIH Police of the |
| missing material. |
| |
| The Authorized User contacted everyone within the Department to determine |
| the resolution of the missing P-32. The Department Chief has held meetings |
| with his staff and interviewed all Authorized Users within the Department; |
| to date no one has admitted using the F-32 DCTP. However, it is the belief |
| of everyone involved that the P-32 DCTP was borrowed by another researcher, |
| who is not willing to admit it, for a legitimate research experiment. This |
| is based on the fact that the P-32 compound was within the locked |
| laboratory; therefore, someone with a key to that laboratory, i.e. a member |
| of the Department, is most likely to have used the P-32. |
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|General Information or Other |Event Number: 37427 |
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| REP ORG: ITT INDUSTRIES |NOTIFICATION DATE: 10/13/2000|
|LICENSEE: ITT INDUSTRIES |NOTIFICATION TIME: 16:20[EDT]|
| CITY: ST. GEORGE REGION: 2 |EVENT DATE: 08/18/2000|
| COUNTY: STATE: SC |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 10/13/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |KEN BARR R2 |
| |VERN HODGE NRR |
+------------------------------------------------+DAVE LOVELESS R4 |
| NRC NOTIFIED BY: PATTON (BY FAX) |MONTE PHILLIPS R3 |
| HQ OPS OFFICER: CHAUNCEY GOULD |LAWRENCE DOERFLEIN R1 |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| PART 21 INVOLVING POSSIBLE ITT INDUSTRIES TRANSDUCER FAILURES |
| |
| |
| Since the date of discovery, design alternatives continue to be evaluated. |
| The methods under investigation for corrective action will be mechanical in |
| nature. ITT Conoflow expects to conclude the analysis phase of their |
| investigation by 12/15/00 and currently estimate that replacement units |
| would be available by 2/15/01. |
| |
| Advice to Customers |
| |
| Each site location should analyze their system and corresponding potential |
| for failure with regard to this notification. In the absence of a seismic |
| event resulting in radiation and/or a steam line break, they do not believe |
| this unit will cause an operational problem. |
| |
| Please note that the product qualification was simulated for a ten, (10) |
| year design life. Those units with a service life of ten, (10) years or |
| more should not be considered qualified. |
| |
| Individual customers will be advised by letter when replacement IEEE I/P |
| transducers are available. |
| |
| Nature of the Deviation |
| |
| The nature of the deviation is to the test and performance requirements |
| associated with IEEE 323 and IEEE 344. An inappropriate bonding process was |
| utilized in the manufacture of the IEEE I/P Transducer. This process change |
| began in 1986 and could, during a seismic event involving high radiation |
| and/or high temperature steam, result in the potential failure of the |
| transducer to perform its intended safety function. |
| |
| Product Models involved |
| GT25CA1826 GT65CA1826 GT45CA1826 |
| GT25FA1826 GT45FA1826 GT65FA1826 |
| |
| Identification of the Company |
| |
| ITT Conoflow |
| ITT Conoflow, Division of ITT Grinnell Valve Company |
| ITT Conoflow, Division of ITT Fluid Technology Corporation |
| ITT Conoflow, ITT Industries |
| |
| Location of Components in Use |
| |
| DUKE ENERGY CORPORATION, CATAWBA NUCLEAR STATION |
| |
| FORT CALHOUN STATION |
| |
| KOREA ELECTRIC POWER CORPORATION, KANONAM |
| |
| ERGYTECH INCORPORATED, HOUSTON, TEXAS |
| |
| PONTON INDUSTRIES, INCORPORATED, SANTA FE SPRINGS, CALIFORNIA |
| |
| ONTARIO POWER GENERATION, DNGD, BOWMANVILLE, ONTARIO LIC 3Z8 CANADA |
| |
| COMMONWEALTH EDISON, MAY WOOD, ILLINOIS |
| |
| COPES-VULCAN, INCORPORATED, LAKE CITY, PENNSYLVANIA |
| |
| PETRO-CHEM EQUIPMENT COMPANY, BATON ROUGE, LOUISIANA |
| |
| ASIAM INTERNATIONAL (TAIWAN) INCORPORATED, TAIPEI 105 TAIWAN, R.O.C. |
| |
| NEW YORK POWER AUTHORITY, JA FITZPATRICK NUCLEAR PLANT |
| |
| CONTROL COMPONENTS, INC., RANCHO SANTA MARGARITA, CALIFORNIA |
| |
| NORTHEAST NUCLEAR ENERGY, HARTFORD, CONNECTICUT |
| |
| These companies were also informed. |
| |
| OMAHA PUBLIC POWER DISTRICT, FORT CALHOUN STATION |
| |
| DETROIT EDISON COMPANY |
| |
| ALABAMA POWER COMPANY, SOUTHERN NUCLEAR OPERATING COMPANY |
| |
| GPU NUCLEAR CORPORATION, C/O GPU SERVICE CORPORATION |
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|Power Reactor |Event Number: 37428 |
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| FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 10/13/2000|
| UNIT: [1] [] [] STATE: CA |NOTIFICATION TIME: 22:18[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/13/2000|
+------------------------------------------------+EVENT TIME: 17:14[PDT]|
| NRC NOTIFIED BY: NORTHNESS |LAST UPDATE DATE: 10/13/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVE LOVELESS R4 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
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EVENT TEXT
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| THE PLANT HAD AUTO START OF THE ONE COMPONENT COOLING WATER PUMP |
| |
| During testing of vital bus "F" components,(first and second level |
| undervoltage relays) with the emergency diesel generator 1/3 parallel to the |
| aux. Power(bus "F"), a signal was generated which tripped the aux feeder |
| breaker and that separated bus "F" from the PG&E system or auxiliary power. |
| This event picked up a safety relay which started the third component |
| cooling water(CCW) pump 1/1, which is an ESF component. They do not need |
| three pumps running, so they secured pump 1/2. |
| |
| The NRC Resident Inspector will be notified. |
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|Power Reactor |Event Number: 37429 |
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| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 10/14/2000|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 05:14[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 10/14/2000|
+------------------------------------------------+EVENT TIME: 03:24[CDT]|
| NRC NOTIFIED BY: WILLIAM GREEN |LAST UPDATE DATE: 10/14/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVE LOVELESS R4 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
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EVENT TEXT
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| AUTOMATIC REACTOR SCRAM DUE TO A MAIN GENERATOR TRIP FOR UNKNOWN REASONS |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 0324 [CDT], a reactor scram occurred due to a main generator trip. |
| Group isolations 2, 3[, and] 6 occurred due to low reactor water level. The |
| lowest [reactor water] level recorded was -20 inches on [the] wide range |
| level recorder. Reactor water level recovered, and both reactor [feedwater] |
| pumps tripped on high reactor water level. Group isolations have been |
| verified and reset. [The] 'A' reactor [feedwater] pump has been returned to |
| service and is being used to control water level. [High pressure coolant |
| injection] and [reactor core isolation cooling] did not inject and were not |
| needed to control reactor water level. The plant will be placed in Cold |
| Shutdown. The electrical grid is stable." |
| |
| The licensee stated that all control rods fully inserted and that all |
| systems functioned as required. The licensee also stated that alternate rod |
| insertion initiated as a result of high pressure due to the transient. The |
| highest pressure observed was 1,085 psi. None of the relief valves lifted, |
| and the main steam isolation valves remained open throughout the event. |
| Steam is currently being dumped to the condenser. |
| |
| In addition, the licensee stated that the cause of the main generator trip |
| is currently under investigation. There were no related surveillance or |
| maintenance activities ongoing at the time of the event. |
| |
| The licensee notified the NRC resident inspector. |
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|Power Reactor |Event Number: 37430 |
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| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 10/14/2000|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 18:50[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/14/2000|
+------------------------------------------------+EVENT TIME: 18:30[EDT]|
| NRC NOTIFIED BY: THOMAS O'QUINN |LAST UPDATE DATE: 10/14/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |KEN BARR R2 |
|10 CFR SECTION: |BRUCE BOGER NRR |
|AAEC |BELCHER FEMA |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |JOHN JOLICOEUR RCT |
| |C. MILLER IRO |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| UNUSUAL EVENT DECLARED AT 1830 HOURS DUE TO FIRE IN THE PROTECTED AREA |
| LASTING GREATER THAN 10 MINUTES. |
| |
| "2A" Heater Drain Pump motor fire reported. Fire reported at 1815 hours, |
| the area was secured and the fire was extinguished using carbon dioxide by |
| the onsite fire brigade at 1831 hours. No injuries. Offsite fire |
| department assistance was initially requested by the licensee but was not |
| needed to extinguish the fire. Damage caused by the fire was the top back of |
| the heater drain pump motor. Plant operation was not affected by the fire. |
| Emergency facilities on site were not activated. State and local counties |
| were notified by the licensee. |
| |
| After "2A" Heater Drain Pump tripped "2C" Heater Drain Pump was started. |
| |
| The NRC Residence Inspector was notified of this event by the licensee. |
| |
| * * * UPDATE on 10/14/00 at 1912ET by Schall taken by MacKinnon * * * |
| |
| Unusual Event terminated at 1908 ET. R2DO (Ken Barr), FEMA (Belcher), IRO |
| (C. Miller). |
| |
| The NRC Resident Inspector was notified by the licensee. |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 37431 |
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| FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 10/15/2000|
| UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 01:42[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/14/2000|
+------------------------------------------------+EVENT TIME: 16:40[EDT]|
| NRC NOTIFIED BY: PAUL McINTYRE |LAST UPDATE DATE: 10/15/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KEN BARR R2 |
|10 CFR SECTION: |BRUCE BOGER NRR |
|AAIR 50.72(b)(2)(iv)(A) AIRBORNE RAD RELEASE |JOSEPH GIITTER IRO |
| |ROGER PEDERSON HP |
| |STU BAILEY DOE |
| |MIGUEL CRUZ HHS |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
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EVENT TEXT
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| UNPLANNED, MONITORED, RADIOACTIVE RELEASE OF NOBLE GASES THROUGH THE UNIT |
| VENT DURING ALIGNMENT FOR SAMPLING OF THE REACTOR COOLANT SYSTEM PRESSURIZER |
| STEAM SPACE WHILE ENTERING A REFUELING OUTAGE |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "[Based on preliminary data, the licensee reported that an] airborne |
| radioactive release that may have exceeded the reportability limits in |
| Appendix 'B' of 10 CFR [Part] 20, Table 2. Preliminary results from data |
| available as of 2200 hours on 10/14/00 appear to indicate that the release |
| has exceeded the reportability criterion. Additional review and calculation |
| of preliminary results are in progress to determine the actual release. |
| Followup notification will be made to validate or retract this |
| notification." |
| |
| The licensee reported that this unplanned, monitored, gaseous, offsite |
| release occurred at 1640 on 10/14/00 and that it was terminated within |
| approximately 20 minutes. The weather conditions were very stable at the |
| time. The site boundary dose and noble gas release rate were not available |
| at the time of the event notification. However, the available data |
| indicated the dose at the unit vent. Two radiation monitors exceeded their |
| Trip II setpoints. |
| |
| Plant Stack Other |
| EMF 36 EMF 41 |
| |
| Radiation Monitor Readings 3.63 E3 |
| cpm 2.24 E4 cpm |
| Alarm Setpoints: Trip II |
| 2.71 E3 cpm 4.54 E3 cpm |
| Percent of Technical Specification Limit Not |
| Available Not Available |
| |
| The licensee stated that there is no direct correlation between the |
| radiation monitor setpoints or readings and the technical specification |
| limits. The technical specification limits are based upon dose at the site |
| boundary, and determination of the site boundary dose requires extensive |
| calculations and review. The licensee currently anticipates that this |
| information will be available in the followup notification. At this time, |
| the licensee believes that the release was well below the technical |
| specification limits. The licensee stated that nothing was unusual or |
| misunderstood and that all systems functioned as required. |
| |
| The licensee plans to notify the NRC resident inspector, the States of North |
| Carolina and South Carolina, and the applicable counties (York, Gaston, and |
| Mecklenburg). The licensee does not plan to issue a press release, and |
| media interest is not anticipated at this time. |
| |
| HOO NOTE: At 0735 and 0818 on 10/15/00, representatives from the |
| Environmental Protection Agency (Paul Wagner) and the South Carolina |
| Department of Health and Environmental Control (John Jesse), respectively, |
| called the NRC Operations Center for information regarding this event. |
| (Call the NRC operations officer for contact information.) |
| |
| * * * UPDATE ON 10/15/00 @ 1438 BY FRITZ TO GOULD * * * RETRACTION |
| |
| The Radiation Protection staff have evaluated the release and determined |
| that it did not exceed any limits and also did not meet any reporting |
| requirements of 10 CFR 50.72(b)(2)(iv)(A). Therefore, the licensee is |
| retracting this event. |
| |
| The NRC Resident Inspector will be notified. |
| |
| The following individuals have been notified of this update: |
| Reg 2 RDO Barr NRR EO Boger IRO Giitter DOE Stambaugh EPA(NRC) |
| Crews FEMA Stinederf |
| USDA Conley NMSS Holahan HHS Cruz HP Pederson SCDHEC Jesse |
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