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Event Notification Report for May 15, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           05/12/2000 - 05/15/2000

                              ** EVENT NUMBERS **

36993  36994  36995  36996  36997  36998  36999  37000  37001  

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36993       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 05/12/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 09:34[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        05/11/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        10:55[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  05/12/2000|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |BRENT CLAYTON        R3      |
|  DOCKET:  0707001                              |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TOM WHITE                    |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01, 24 HOUR NOTIFICATION                                     |
|                                                                              |
| INSTRUMENT USED TO DETERMINE URANIUM MASSES WAS FOUND TO BE IN ERROR IN THE  |
| NON-CONSERVATIVE DIRECTION.                                                  |
|                                                                              |
| The calibration factor of an instrument used to determine uranium masses was |
| discovered to be in error.  This error was in the non-conservative direction |
| (approximately 30% off) and resulted in the under reporting of uranium       |
| masses, violating NCSA GEN-010, Requirement 3.1.3.  The purpose of this      |
| requirement is to ensure proper uncomplicated handling/planned expeditious   |
| handling (UH/PEH) classification to ensure safe handling of the item.        |
|                                                                              |
| SAFETY SIGNIFICANCE OF EVENTS:                                               |
|                                                                              |
| Both of the controls relied upon for double contingency are based on         |
| determination of a uranium mass.  Both of these controls were lost;          |
| therefore, double contingency was not maintained.  However, based on         |
| Non-Destructive Analysis recalculation of the measured values using the      |
| correct calibration factor, an unsafe mass of uranium was not involved.      |
|                                                                              |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED OF HOW CRITICALITY COULD OCCUR:      |
|                                                                              |
| In order for a criticality to be possible, a critical mass of uranium would  |
| be needed to be accumulated in an unsafe geometry.                           |
|                                                                              |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):     |
|                                                                              |
| Double contingency for this scenario is established by implementing two      |
| independent controls on mass.                                                |
|                                                                              |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS     |
| LIMIT AND % WORST CASE CRITICAL MASS):                                       |
|                                                                              |
| Each item or group has been verified to be less than the always safe mass    |
| and enrichment could be as much as 100%, in the form of uranyl fluoride.     |
| The process limit of 400 grams is less than half of the worst case mass.     |
|                                                                              |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION   |
| OF THE FAILURES OR DEFICIENCIES:                                             |
|                                                                              |
| Double contingency for this scenario is established by implementing two      |
| controls on mass.                                                            |
|                                                                              |
| Since the measurements were performed with an improperly calibrated          |
| instrument, the reported masses could not be relied upon and double          |
| contingency was not maintained.                                              |
|                                                                              |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED:  |
|                                                                              |
| Access to the identified items is being controlled with ropes and postings   |
| until they can be retagged with the correct uranium masses.  After the       |
| uranium mass has been corrected, the ropes and postings may be removed.      |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the certificate     |
| holder.                                                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   36994       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  JOHNSON CONTROLS                     |NOTIFICATION DATE: 05/12/2000|
|LICENSEE:  AMSTAT INDUSTRIES                    |NOTIFICATION TIME: 10:30[EDT]|
|    CITY:  HOLLAND                  REGION:  3  |EVENT DATE:        05/12/2000|
|  COUNTY:                            STATE:  MI |EVENT TIME:        10:30[EDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  05/12/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |BRENT CLAYTON        R3      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JOE MILBURN                  |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| IN-LINE STATIC DE-IONIZATION GUN MISSING.                                    |
|                                                                              |
| Johnson Controls leased an in-line static de-ionization gun from Amstat      |
| Industries on 04/0 9/99.  While looking for the static de-ionization gun to  |
| return it to Amstat Industries, Johnson Controls discovered that the static  |
| de-ionization gun was missing.  The in-line static de-ionization gun         |
| contains 10 millicuries of Polonium-210 (alpha emitter).   Johnson Controls  |
| did not know when the in-line static de-ionization gun was last seen.  The   |
| in-line static de-ionization gun, model number P2021-8101 was made by NRD,   |
| Grand Island, NY.  The serial number of the source is 110700.                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36995       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  U.S. AIR FORCE                       |NOTIFICATION DATE: 05/12/2000|
|LICENSEE:  U.S. AIR FORCE                       |NOTIFICATION TIME: 14:56[EDT]|
|    CITY:  ELMENDORF AFB            REGION:  4  |EVENT DATE:        11/01/1998|
|  COUNTY:                            STATE:  AK |EVENT TIME:             [YDT]|
|LICENSE#:  42-23539-01AF         AGREEMENT:  N  |LAST UPDATE DATE:  05/12/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHARLES CAIN         R4      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  HICKS (BOLLING AFB)          |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE LICENSEE REPORTED POSSIBLE LOSS OF CHEMICAL AGENT MONITORS (CAM).        |
|                                                                              |
| THE LICENSEE WAS NOTIFIED AT 1030 ON 05/12/00 BY MAJ WISEMAN OF THE 3RD      |
| AMDS/SGPB AT ELMENDORF AFB, ALASKA, OF A RECENT INSPECTION SHOWING A         |
| DISCREPANCY IN DOCUMENTATION FOR THE TRANSFER OF EIGHT AUTOMATIC CHEMICAL    |
| AGENT ALARMS (CONTAINING  250 MICROCURIES EACH OF AMERICIUM-241) IN          |
| NOVEMBER, 1998.  THE TRANSFER OF THESE EIGHT CHEMICAL AGENT DEVICES WAS TO   |
| KELLY AFB, TEXAS, WHERE THE RETURNED PAPERWORK STATED THAT ONLY FIVE DEVICES |
| WERE RECEIVED.  THE LICENSEE IS NOW TRYING TO DETERMINE IF ONLY FIVE DEVICES |
| INSTEAD OF EIGHT WERE RECEIVED AND THE NUMBER 5 WAS A TYPOGRAPHICAL ERROR ON |
| THE RECEIPT FORM.  THE LICENSEE IS CONTINUING THE INVESTIGATION.             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36996       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  COGEMA MINING INC                    |NOTIFICATION DATE: 05/12/2000|
|LICENSEE:  COGEMA MINING INC                    |NOTIFICATION TIME: 15:30[EDT]|
|    CITY:  MILLS                    REGION:  4  |EVENT DATE:        05/09/2000|
|  COUNTY:                            STATE:  WY |EVENT TIME:             [MDT]|
|LICENSE#:  SUA-1341              AGREEMENT:  N  |LAST UPDATE DATE:  05/12/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHARLES CAIN         R4      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+MIKE LAYTON          NMSS    |
| NRC NOTIFIED BY:  VASELIN                      |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SAMPLES COLLECTED AT A MONITOR WELL EXCEEDED TWO OF ITS THREE UPPER CONTROL  |
| LIMITS.                                                                      |
|                                                                              |
| A routine quarterly water sample collected on 05/09/00 from monitor well #M2 |
| exceeded two of its three upper control limits (UCLs).  A confirmation       |
| sample was collected on 05/11/00, which also exceeded two UCLs. Monitor well |
| #M2 was then placed on excursion status as per license section 11.2 and its  |
| sampling frequency increased to weekly.  Well #M2 is a perimeter ore zone    |
| monitor well located approximately 300 feet west of the restored Production  |
| Unit 2 boundary, at the Irigaray Mine, Johnson County, Wyoming.  The nearest |
| community is Linch, Wyoming, approximately 23 miles to the southeast.        |
|                                                                              |
| Analysis data:                                                               |
|                                                                              |
| Date                            Chloride                    Conductivity     |
| Alkalinity                        Uranium                                    |
| Sampled                       mg/l                        mhos/cm2          |
| mg/l                          mg/l U3O8                                      |
| ULC 18.0                          UCL 685                    UCL 131.1       |
| UCL none                                                                     |
| 05/09/00                        19.3                                   814   |
| 94.3                                    <0.4                                 |
| 05/11/00                        19.3                                   799   |
| 96.6                                    <0.4                                 |
|                                                                              |
| Health and Environmental Hazards:                                            |
| None.                                                                        |
|                                                                              |
| Investigative Action:                                                        |
| Conduct further sampling to try to determine the extent and direction of the |
| excursion.                                                                   |
|                                                                              |
| Written Notification:                                                        |
| Written notification will be submitted to NRC Uranium Recovery Branch Chief. |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36997       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  NORTH CAROLINA DIV OF RAD PROTECT    |NOTIFICATION DATE: 05/12/2000|
|LICENSEE:  HUMBOLDT                             |NOTIFICATION TIME: 16:30[EDT]|
|    CITY:  RALEIGH                  REGION:  2  |EVENT DATE:        05/12/2000|
|  COUNTY:                            STATE:  NC |EVENT TIME:        09:15[EDT]|
|LICENSE#:  092-0750-1            AGREEMENT:  Y  |LAST UPDATE DATE:  05/12/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |BRIAN BONSER         R2      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+BRENT CLAYTON        R3      |
| NRC NOTIFIED BY:  ACCATTATO                    |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HUMBOLDT NOTIFIED THE NORTH CAROLINA DIVISION OF RADIATION PROTECTION OF A   |
| MISSING MOISTURE DENSITY GAUGE.                                              |
|                                                                              |
| A HUMBOLDT MOISTURE DENSITY GAUGE, MODEL #5001C, SERIAL #1966, WAS SHIPPED   |
| FROM THE MANUFACTURER IN RALEIGH, NC, TO COPLAY, PA, VIA THEIR CARRIER,      |
| ROADWAY EXPRESS.  AFTER FIVE DAYS THE CUSTOMER NOTIFIED HUMBOLDT THAT THEY   |
| HAD NOT RECEIVED THE GAUGE.  HUMBOLDT THEN CALLED ROADWAY AND FOUND OUT THAT |
| THE GAUGE WAS MISSING IN TRANSIT.  A TRACE WAS PUT OUT BY ROADWAY FOR THE    |
| GAUGE AND THEY BELIEVE IT MAY HAVE BEEN TRANSFERRED TO ANOTHER TRAILER IN    |
| WINSTON-SALEM, NC WHICH WAS SCHEDULED TO GO TO INDIANAPOLIS, IN.  THE        |
| SUSPECTED TRAILER HAS BEEN LOCATED IN INDIANA, AND THEY WILL TAKE IT BACK TO |
| THEIR HUB IN INDIANAPOLIS TO UNLOAD IT TO VERIFY IF THE GAUGE IS THERE.  THE |
| GAUGE CONTAINED 10 MILLICURIES OF CESIUM-137 AND 40 MILLICURIES              |
| AMERICIUM/BERYLLIUM.  THEY ARE ALSO CHECKING OTHER TRAILERS THAT LEFT FROM   |
| THE WINSTON/SALEM, NC HUB.                                                   |
|                                                                              |
| * * * UPDATE ON 5/12/00 @ 2244 BY ACCATTATO TO GOULD * * *                   |
|                                                                              |
| THE  GAUGE WAS  RECOVERED IN INDIANAPOLIS AND HAS BEEN REDIRECTED TO THE     |
| ORIGINAL CUSTOMER.                                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36998       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 05/12/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 18:57[EDT]|
|   RXTYPE: [1] GE-2                             |EVENT DATE:        05/12/2000|
+------------------------------------------------+EVENT TIME:        18:00[EDT]|
| NRC NOTIFIED BY:  DEMONCH                      |LAST UPDATE DATE:  05/13/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN ROGGE           R1      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| PLANT ENTERED A TECH SPEC REQUIRED SHUTDOWN DUE TO THE ELECTROMATIC RELIEF   |
| VALVES AND ASSOCIATED ADS BEING DECLARED INOPERABLE.                         |
|                                                                              |
| While preparing a spare Electromatic Relief Valve for installation in the    |
| upcoming refueling outage, Oyster Creek identified that the valve's          |
| electrical (Patel) connector was not properly sealed.  As such, the          |
| Environmental Qualification of the electrical connectors for these valves    |
| are questionable.  Based on this discovery, Oyster Creek has declared all    |
| the Electromatic Relief Valves (and associated Automatic Depressurization    |
| System) inoperable.                                                          |
|                                                                              |
| During a Small Break LOCA, these valves are required to function in order to |
| depressurize the reactor.  In accordance with the plant's Technical          |
| Specifications, Oyster Creek is in the process of shutting down. The plant   |
| has 24 hours to be <110F and be in Cold Shutdown Condition in the following |
| six hours. This condition is reportable under 10CFR50.72(b)(1)(ii)(B) for    |
| operation of the plant outside design basis.  Testing is being conducted in  |
| parallel with the shutdown in order to determine if the existing             |
| configuration is acceptable for continued operation.                         |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| * * * UPDATE ON 05/13/00 AT 0836 EDT BY PIETRUSKI TAKEN BY MACKINNON * * *   |
|                                                                              |
| After a review of the Electromatic Relief Valve power connectors bench test  |
| for EQ requirements, it has been concluded that there is reasonable          |
| assurance that the Electromatic Relief Valves will perform their function as |
| designed.  The Electromatic Relief Valves are considered operable, the       |
| Limiting Condition of Operation has been exited, and shutdown has been       |
| terminated at 0654 EDT.  Reactor power is currently 75% and plans are to     |
| return to 100% power.                                                        |
|                                                                              |
| The NRC Resident Inspector was notified of this update by the licensee.      |
|                                                                              |
| The NRC Operations Officer notified the R1DO (John Rogge).                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36999       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 05/13/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 16:25[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        05/13/2000|
+------------------------------------------------+EVENT TIME:        13:26[EDT]|
| NRC NOTIFIED BY:  BREADY                       |LAST UPDATE DATE:  05/13/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN ROGGE           R1      |
|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     A          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| At 1325 on 05/13/00, a Reactor Protection System scram signal was received   |
| due to a high Scram Discharge Volume level condition.                        |
|                                                                              |
| The high Scram Discharge Volume level condition occurred as a result of an   |
| Alternate Rod Insertion test signal that was initiated from the Redundant    |
| Reactivity Control System during a planned valve testing activity. The       |
| Alternate Rod Insertion test signal depressurized the scram air header,      |
| causing all control rod scram inlet and outlet valves to open and Scram      |
| Discharge Volume vent and drain valves to close as designed.  Control room   |
| personnel involved in the valve testing activity incorrectly believed that   |
| manipulation of the Alternate Rod Insertion test switches for one second     |
| would allow an Alternate Rod Insertion valve to be tested following planned  |
| maintenance, without depressurizing the scram air header.  Control Room      |
| personnel reset the Redundant Reactivity Control and Reactor Protection      |
| Scram signals in accordance with plant procedures at 1343, after initial     |
| validation of the sequence of events.                                        |
|                                                                              |
| At the time of the event, reactor core reload was in progress in Operational |
| Condition 5.  All control rods were previously verified to be fully inserted |
| in support of core alterations.  'B' and 'D' channel equipment are           |
| considered protected for defense in depth, and planned maintenance is in     |
| progress on 'A' and 'C' channel equipment.  The 'B' Residual Heat Removal    |
| pump remained in service in shutdown cooling throughout the event, and       |
| reactor cavity level and temperature were unaffected. There was no impact to |
| overall plant safety as a result of this event.                              |
|                                                                              |
| The response of the Alternate Rod Insertion valve that was to be tested is   |
| currently being evaluated.  A root cause investigation team has been         |
| assembled, and evaluation of system and personnel performance is in          |
| progress.                                                                    |
|                                                                              |
| The NRC Resident Inspector will be informed.                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37000       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF               REGION:  4  |NOTIFICATION DATE: 05/14/2000|
|    UNIT:  [1] [] []                 STATE:  MS |NOTIFICATION TIME: 20:01[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        05/14/2000|
+------------------------------------------------+EVENT TIME:        15:05[CDT]|
| NRC NOTIFIED BY:  HANKS                        |LAST UPDATE DATE:  05/14/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES CAIN         R4      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| THE LICENSEE DECLARED THE DIVISION 3 EMERGENCY DIESEL GENERATOR (EDG)        |
| INOPERABLE AND THE PLANT ENTERED AN LCO ACTION STATEMENT.                    |
|                                                                              |
| THE DIVISION 3 EDG WAS DECLARED INOPERABLE DUE TO THE SOAK BACK PUMP         |
| (SUPPLIES LUBE OIL TO THE DIESEL SO THAT IT IS READY TO START) TRIP FAILURE. |
| THE CAUSE OF THE FAILURE IS A FAULTY RELAY FOR THE PUMP.  THEY WILL REPLACE  |
| THIS RELAY.  THIS EDG SUPPORTS THE HIGH PRESSURE CORE SPRAY (HPCS) SYSTEM    |
| FOR SAFETY FUNCTIONS.  THE HPCS SYSTEM HAS NOT BEEN DECLARED INOPERABLE AND  |
| THE DIVISION 3 EDG IS STILL FUNCTIONAL.  THE PLANT HAS 12 HOURS TO BE IN     |
| CONDITION 3 AND 36 HOURS TO BE IN CONDITION 4.                               |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37001       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 05/15/2000|
|    UNIT:  [1] [] []                 STATE:  CA |NOTIFICATION TIME: 04:04[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        05/15/2000|
+------------------------------------------------+EVENT TIME:        00:43[PDT]|
| NRC NOTIFIED BY:  STEVE HACKLEMAN              |LAST UPDATE DATE:  05/15/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |CHARLES CAIN         R4      |
|10 CFR SECTION:                                 |JOSE CALVO           NRR     |
|AAEC 50.72 (a) (1) (I)   EMERGENCY DECLARED     |JOSEPH GIITTER       IRO     |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |EACHES               FEMA    |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |JOSEPH HIMES         RCT     |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DUE TO AUXILIARY TRANSFORMER EXPLOSION & FIRE; LOSS OF OFFSITE |
| POWER -                                                                      |
|                                                                              |
| At 0043 PDT on 05/15/00, the licensee declared an Unusual Event due to       |
| auxiliary transformer #1-1 exploding and catching on fire.  This resulted in |
| the loss of offsite power and an automatic trip of Unit 1.  The licensee     |
| called the offsite fire department and they responded to the plant.          |
| Auxiliary transformer #1-1 is located outside the turbine building (north    |
| end).                                                                        |
|                                                                              |
| Three of three Unit 1 emergency diesel generators started and loaded and are |
| supplying emergency power to vital Unit 1 buses.  Auxiliary transformer #1-1 |
| supplies backup power to Unit 1 emergency buses.  The Unit 1 12 KV buses are |
| energized.  Unit 1 reactor coolant pumps are running providing forced        |
| circulation.                                                                 |
|                                                                              |
| Unit 1 automatically tripped from 100% power.  All control rods inserted     |
| completely.  Steam is being dumped to the atmosphere.  Unit 1 has no steam   |
| generator tube leaks and no fuel leaks.  The auxiliary feedwater system      |
| automatically started, as expected.  A #1-2 steam generator code safety      |
| valve failed open for about 25 - 30 minutes about 30 minutes after the       |
| reactor trip.  The valve is now closed.  There was no safety injection       |
| actuation.                                                                   |
|                                                                              |
| Unit 1 is stable in Mode 3 (Hot Standby).                                    |
|                                                                              |
| This event had no effect on Unit 2 which is stable at 100% power.            |
|                                                                              |
| The licensee notified state and local officials and the NRC Resident         |
| Inspector.                                                                   |
|                                                                              |
| At 0143 PDT, the fire is out.  No personnel were injured.                    |
|                                                                              |
| At 0405 CDT, NRC Region 4 entered the Monitoring Phase of Normal NRC         |
| Response Mode.                                                               |
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