Event Notification Report for June 12, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/09/2000 - 06/12/2000
** EVENT NUMBERS **
37071 37072 37073 37074 37075 37076
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|Power Reactor |Event Number: 37071 |
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| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 06/09/2000|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 15:42[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 06/09/2000|
+------------------------------------------------+EVENT TIME: 13:11[EDT]|
| NRC NOTIFIED BY: ED FIRTH |LAST UPDATE DATE: 06/09/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS MOSLAK R1 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
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EVENT TEXT
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| REACTOR TRIP CAUSED BY GENERATOR AND TURBINE TRIPS |
| |
| "On June 9, 2000, at approximately 1311 hours, an automatic reactor trip |
| occurred due to an automatic turbine trip caused by a main generator trip. |
| The main generator trip was caused by actuation of the generator 86 lockout |
| relays due to a direct trip from the 345 KV Buchanan substation. All |
| primary and secondary systems appear to have responded as required after the |
| automatic reactor trip. The Auxiliary Feed Water system automatically |
| started as result of this trip due to low row steam generator (S/G) level |
| (8%) resulting from S/G water level shrink. The plant is stable in the hot |
| shutdown condition. The cause of this main generator 86 lockout is under |
| investigation. The NRC resident inspector was notified." |
| |
| All control rods fully inserted during the reactor trip. The S/Gs are being |
| fed by auxiliary feedwater and decay heat is being removed by dumping steam |
| to the main condenser. Reactor Coolant Pumps are running. |
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|Fuel Cycle Facility |Event Number: 37072 |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/09/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 15:52[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/09/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:58[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/09/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |DAVID HILLS R3 |
| DOCKET: 0707002 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: K. WILLIAMSON | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| INFORMATION CALL - TRACTOR/TRAILER CARRYING TWO UF6 CYLINDERS STRUCK BY A |
| CAR |
| |
| At 1158 hours, the PORTS PSS was informed that a tractor/trailer carrying 2 |
| empty 10 ton uranium hexaflouride (UF6) cylinders had been struck by a car |
| approximately 10 miles North of Chillicothe, Ohio on State Route 104. The |
| cylinders which contained only residual quantities of UF6 were not damaged |
| and there was no release of radioactive materials. The accident generated |
| media attention and the Ohio EPA was also notified of the incident by the |
| Ohio highway patrol. The Trailer sustained minor damage and will be towed |
| to the Portsmouth Site for repairs. The PORTS NRC Resident has been |
| notified of this incident. |
| |
| This incident is reportable in accordance with the Safety Analysis Report, |
| Section 64 Criteria P, since the media and other government agencies have |
| been notified of this event. |
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|Other Nuclear Material |Event Number: 37073 |
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| REP ORG: CROWE BUTTE RESOURCES |NOTIFICATION DATE: 06/09/2000|
|LICENSEE: CROWE BUTTE RESOURCES |NOTIFICATION TIME: 18:15[EDT]|
| CITY: CRAWFORD REGION: 4 |EVENT DATE: 06/09/2000|
| COUNTY: STATE: NE |EVENT TIME: 12:00[CDT]|
|LICENSE#: SUA-1534 AGREEMENT: Y |LAST UPDATE DATE: 06/09/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN PELLET R4 |
| | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: RHONDA GRANTHAM | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| APPARENT LEAK IN AN EVAPORATION POND LINER. |
| |
| The licensee detected an increase in the level in an evaporation pond |
| underdrain. The level had increased from about 1 inch up to 5 inches. |
| Tests on the water were conducted and the results suggest a leak in the |
| inner pond liner. The outer pond liner is believed to be intact. The |
| licensee intends to find and repair the leak. The pond's level may be |
| reduced to aid in leak detection. |
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|Power Reactor |Event Number: 37074 |
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| FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 06/09/2000|
| UNIT: [3] [] [] STATE: LA |NOTIFICATION TIME: 19:19[EDT]|
| RXTYPE: [3] CE |EVENT DATE: 06/09/2000|
+------------------------------------------------+EVENT TIME: 17:30[CDT]|
| NRC NOTIFIED BY: CHARLES DEDEAUX |LAST UPDATE DATE: 06/09/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN PELLET R4 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| SAFEGUARD SYSTEM DEGRADATION RELATED TO THE VITAL AREA BOUNDARY. IMMEDIATE |
| COMPENSATORY ACTIONS TAKEN UPON DISCOVERY. THE LICENSE NOTIFIED THE NRC |
| RESIDENT INSPECTOR. |
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|Power Reactor |Event Number: 37075 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 06/09/2000|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 20:00[EDT]|
| RXTYPE: [1] GE-2 |EVENT DATE: 06/09/2000|
+------------------------------------------------+EVENT TIME: 18:30[EDT]|
| NRC NOTIFIED BY: FRANK CIGANIK |LAST UPDATE DATE: 06/09/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS MOSLAK R1 |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| LICENSEE MAY HAVE EXCEEDED LICENSED THERMAL POWER LIMIT |
| |
| While reviewing the plants thermal performance, Oyster Creek discovered that |
| the plant was potentially operating above the Technical Specification |
| licensed thermal limit. Based on a comparison of the various inputs to the |
| plant's thermal heat balance, it appears that the total feedwater flow |
| venturi is reading non-conservatively (lower than actual) in comparison to |
| the summation of the individual feedwater strings flows. As a result of |
| this disparity, the plant's Engineering Staff has tentatively concluded that |
| the heat balance is non-conservatively calculating 5 MWth less than actual |
| based on the lower flow reading. |
| |
| The plant's Technical Specification steady-state thermal power limit is 1930 |
| MWth. Oyster Creek has administratively limited thermal power to 1920 MWth |
| until this situation can be fully analyzed. The plant's Engineering Staff is |
| presently developing a plan to confirm this information and initiate the |
| appropriate corrective actions to resolve this disparity. |
| |
| This condition has been determined reportable under the plant's Technical |
| Specifications Section 2.E (24 Hour Notification) which requires |
| notification of the NRC for all Technical Specification violations. The |
| plant's Technical Specifications require maintaining core thermal power less |
| than 1930 MWth under steady-state conditions and the plant might have been |
| operated for prolonged periods at as high as 1935 MWth. The safety |
| significance of this discrepancy is minimal because the plant's licensing |
| bases includes a 2% error margin which was never challenged. |
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|Power Reactor |Event Number: 37076 |
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| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 06/09/2000|
| UNIT: [1] [2] [] STATE: NC |NOTIFICATION TIME: 20:21[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/09/2000|
+------------------------------------------------+EVENT TIME: 16:51[EDT]|
| NRC NOTIFIED BY: DAVE JESTER |LAST UPDATE DATE: 06/09/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES R. OGLE R2 |
|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 Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| ESF ACTUATION - CONTROL BUILDING VENTILATION ISOLATED DUE TO CHLORINE |
| PROTECTION MODE |
| |
| Control Building Ventilation isolated to the Chlorine Protection Mode during |
| maintenance activities on the transfer line between the Chlorine Tank Car |
| and the Chlorination Building. The isolation occurred when maintenance |
| personnel loosened a fitting in the transfer line which allowed the release |
| of residual chlorine. At the time of the isolation, the Chlorine Tank Car |
| was isolated and under clearance. All systems functioned as expected. The |
| Control Building Ventilation System was returned to normal lineup at 1814. |
| |
| The licensee notified the NRC resident inspector. |
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