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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.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| SAFEGUARD SYSTEM DEGRADATION RELATED TO THE VITAL AREA BOUNDARY.  IMMEDIATE  |
| COMPENSATORY ACTIONS TAKEN UPON DISCOVERY.  THE LICENSE NOTIFIED THE NRC     |
| RESIDENT INSPECTOR.                                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37076       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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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