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Event Notification Report for July 6, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           07/02/1999 - 07/06/1999

                              ** EVENT NUMBERS **

35887  35888  35889  35890  35891  35892  35893  35894  35895  35896  35897  

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35887       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 07/02/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 00:50[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        07/02/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        00:40[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  07/03/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |JAMES CREED          R3      |
|  DOCKET:  0707002                              |SUSAN SHANKMAN       NMSS    |
+------------------------------------------------+JOSEPH GIITTER       IRO     |
| NRC NOTIFIED BY:  MAY                          |HILAND/CANIANO       R3      |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |LIZ TEN EYCK         NMSS    |
+------------------------------------------------+CANUPP               FEMA    |
|EMERGENCY CLASS:          ALE                   |                             |
|10 CFR SECTION:                                 |                             |
|OADD 76.120(a)(4)        EMERGENCY DECLARED     |                             |
|OCBB 76.120(c)(2)(ii)    EQUIP DISABLED/FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ALERT DECLARED DUE TO CRITICALITY ACCIDENT ALARM SYSTEM BEING DECLARED       |
| INOPERABLE.                                                                  |
|                                                                              |
| THE CERTIFICATEE DISCOVERED THAT THE CRITICALITY ACCIDENT ALARM SYSTEM       |
| (CAAS) FAILED ITS SURVEILLANCE TEST DUE TO THE CALIBRATION SETPOINT BEING    |
| INCORRECT.  THE CORRECT SETPOINT SHOULD BE 5 MR/HR, BUT THE AS-FOUND         |
| SETPOINT WAS 8.57 MR/HR.  DUE TO THIS CONDITION, THE CERTIFICATEE CANNOT     |
| MEET THEIR OPERABILITY REQUIREMENTS FOR THE CAAS, SO ALL OF THE CAAS IS      |
| BEING DECLARED INOPERABLE (BUT FUNCTIONAL) WHICH PUTS THE PLANT AT THE ALERT |
| LEVEL PER THEIR EMERGENCY ACTION LEVEL PROCEDURES.  ALL OF THE AUTOCLAVE     |
| AREAS ARE SHUTDOWN AND PLANT PERSONNEL THAT ARE STAFFING THE FACILITIES ARE  |
| USING ALARMING DOSIMETERS.  THE CASCADES ARE STILL OPERATING AT THIS TIME.   |
| THERE ARE 76 CAAS CLUSTERS AFFECTED BY THIS CONDITION.  THE CERTIFICATEE     |
| BELIEVES THAT THESE INSTRUMENTS HAVE NOT BEEN CALIBRATED CORRECTLY SINCE     |
| ORIGINAL INSTALLATION.  THE CERTIFICATEE HAS NOT YET DETERMINED WHEN THE     |
| CALIBRATION OF THE CAAS CLUSTERS WILL BE COMPLETED.                          |
|                                                                              |
| THE CERTIFICATEE NOTIFIED THE NRC RESIDENT INSPECTOR, DOE SITE               |
| REPRESENTATIVE, DOE OAK RIDGE, OHIO EMA, PIKE COUNTY LEPC AND PIKE COUNTY    |
| EMA.                                                                         |
|                                                                              |
| * * * UPDATE ON 07/02/99 @ 0251 BY MCCRAE TO GOULD * * *                     |
|                                                                              |
| THE CERTIFICATEE IS RESTRICTING ACCESS TO ALL AREAS AFFECTED BY THE          |
| INOPERABLE CAAS MONITORS.  RECOVERY EFFORTS ARE BEING IMPLEMENTED TO         |
| RECALIBRATE THE MONITORS. NONESSENTIAL PERSONNEL ON DAY SHIFT WILL BE SENT   |
| HOME UPON ARRIVAL AT THE SITE.                                               |
|                                                                              |
| THE NRC OPERATIONS OFFICER NOTIFIED THE R3DO (JAMES CREED) AND NMSS EO       |
| (SUSAN SHANKMAN).                                                            |
|                                                                              |
| * * * UPDATE ON 07/02/99 @ 0432 BY CASTLE TO GOULD * * *                     |
|                                                                              |
| THE CERTIFICATEE WILL BE MAKING A PRESS RELEASE AND NOTIFIED DOE.  THIS      |
| ACTION REQUIRES A 4 HOUR NOTIFICATION TO NRC.                                |
|                                                                              |
| WITH THE CAAS CLUSTERS INOPERABLE AND NOT AVAILABLE TO FUNCTION AS DESIGNED, |
| THIS IS  A 24 HOUR NOTIFICATION REQUIREMENT.                                 |
|                                                                              |
| THE NRC OPERATIONS OFFICER NOTIFIED THE R3DO (JAMES CREED),  NMSS EO (SUSAN  |
| SHANKMAN) AND HQ PAO (JOE GILLILAND).                                        |
|                                                                              |
| * * * UPDATE ON 07/03/99 @ 0013 BY FAUST TO GOULD * * *                      |
|                                                                              |
| THE CERTIFICATEE SUCCESSFULLY COMPLETED TWO CAAS CALIBRATIONS, TERMINATED    |
| THE ALERT AT 0010 ON 07/03/99, AND NOTIFIED THE NRC RESIDENT INSPECTOR, SITE |
| DOE REPRESENTATIVE, AND STATE AND LOCAL OFFICIALS.                           |
|                                                                              |
| THE NRC OPERATIONS OFFICER NOTIFIED THE R3DO (JAMES CREED), NMSS EO (SUSAN   |
| SHANKMAN), IRO(JOE GIITTER), FEMA (STINEDURF), DOE (BY FAX), USDA (BY FAX),  |
| HHS (BY FAX), &  EPA/NATIONAL RESPONSE CENTER (BY FAX).                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35888       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CROW BUTTE RESOURCES, INC            |NOTIFICATION DATE: 07/02/1999|
|LICENSEE:  CROW BUTTE RESOURCES, INC            |NOTIFICATION TIME: 12:49[EDT]|
|    CITY:  CRAWFORD                 REGION:  4  |EVENT DATE:        07/02/1999|
|  COUNTY:                            STATE:  NE |EVENT TIME:        10:00[CDT]|
|LICENSE#:  SUA-1534              AGREEMENT:  Y  |LAST UPDATE DATE:  07/02/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LINDA SMITH          R4      |
|                                                |SCOTT MOORE          NMSS    |
+------------------------------------------------+DAN GILLEN           NMSS    |
| NRC NOTIFIED BY:  MIKE GRIFFIN                 |EPA (by fax)                 |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - CROW BUTTE URANIUM LEACH MINE PERIMETER MONITOR WELL PLACED IN EXCURSION   |
| STATUS -                                                                     |
|                                                                              |
| WATER SAMPLES OF THE PERIMETER MONITOR WELL #CM6-6 AT THE CROW BUTTE IN-SITU |
| URANIUM LEACH MINE, CRAWFORD, NE, EXCEEDED THE MULTIPLE UPPER CONTROL LIMITS |
| ON FOUR OF THE FOLLOWING FIVE PARAMETERS MONITORED AND THE WELL WAS PLACED   |
| IN EXCURSION STATUS:                                                         |
|                                                                              |
| PARAMETER (UNITS)                 UPPER LIMIT (MULTIPLE)       UPPER LIMIT   |
| (SINGLE)      LATEST SAMPLE                                                  |
| -----------------------------------                                          |
| -----------------------------------        -------------------------------   |
| ------------------------                                                     |
| CONDUCTIVITY (MHOs)                            2412                         |
| 2894                                 2750                                    |
| CARBONATES (PPM)                                    370                      |
| 444                                   378                                    |
| CHLORIDES (PPM)                                        251                   |
| 301                                   268                                    |
| SULFATES (PPM)                                          461                  |
| 553                                   550                                    |
| SODIUM (PPM)                                              486                |
| 583                                   457                                    |
|                                                                              |
| OPERATORS HAVE REDUCED INJECTION AND INCREASED PRODUCTION IN THE AREA OF THE |
| EXCURSION.  THE MINE IS LOCATED 5 - 6 MILES FROM THE NEAREST TOWN OF         |
| CRAWFORD, NE.  THERE WERE NO SPILLS OR RELEASES OF RADIOACTIVE MATERIAL FROM |
| THE MINE.                                                                    |
|                                                                              |
| THE LICENSEE'S ASSESSMENT OF THIS SITUATION IS THAT RISK IS MINIMAL AND      |
| THERE IS NO ADVERSE IMPACT ON PERSONS, ANIMALS, OR THE ENVIRONMENT.  THE NRC |
| URANIUM MINING EXPERT, DAN GILLEN, AGREES WITH THIS ASSESSMENT AND NO NRC    |
| RESPONSE IS REQUIRED.                                                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35889       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 07/02/1999|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 16:41[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        07/02/1999|
+------------------------------------------------+EVENT TIME:        13:30[EDT]|
| NRC NOTIFIED BY:  HANK STRAHLEY                |LAST UPDATE DATE:  07/02/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAWRENCE DOERFLEIN   R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       15       Power Operation  |15       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - RCIC SYSTEM DECLARED INOPERABLE -                                          |
|                                                                              |
| While performing Reactor Core Isolation Cooling (RCIC) System injection      |
| testing, the licensee declared the RCIC System inoperable due to problems    |
| with the system injection testable check valves. Valve #2ICS*AOV157 did not  |
| indicate open with full flow to the reactor vessel and valve #2ICS*AOV156    |
| continued to indicate open following injection. The licensee declared these  |
| containment isolation valves inoperable and is taking actions to isolate the |
| containment penetration.  The RCIC System injected properly with the         |
| exception of the above noted problem.  Otherwise, the RCIC System operated   |
| properly.  Tech Spec 3.7.4 requires the licensee to restore the RCIC System  |
| to operable status within 14 days.  The High Pressure Core Spray System is   |
| operable.  The licensee will be troubleshooting these valves.                |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35890       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE           REGION:  1  |NOTIFICATION DATE: 07/02/1999|
|    UNIT:  [1] [] []                 STATE:  VT |NOTIFICATION TIME: 16:58[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        07/02/1999|
+------------------------------------------------+EVENT TIME:        16:34[EDT]|
| NRC NOTIFIED BY:  MIKE EMPY                    |LAST UPDATE DATE:  07/02/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAWRENCE DOERFLEIN   R1      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| - PRIMARY CONTAINMENT COULD BE OUTSIDE ITS DESIGN BASIS UNDER CERTAIN        |
| CONDITIONS -                                                                 |
|                                                                              |
| During validation of the Vermont Yankee (VY) Containment Pressurization      |
| System Design Basis Document, the licensee determined that a design analysis |
| which envelopes the design operating conditions of the torus and drywell     |
| does not exist.  Specifically, no design analysis exists which verifies the  |
| ability of the torus-to-drywell and torus-to-reactor building vacuum         |
| breakers to limit depressurization of the containment to less than the       |
| design basis value of - 2 psig (22A1265, Rev. 1).                            |
|                                                                              |
| The specific event in question involves the effects of an inadvertent        |
| drywell spray actuation occurring during conditions when the torus water is  |
| at a minimum temperature 50F (VYAPF 0150.03).                               |
|                                                                              |
| Present design evaluations (VYC-236, Rev 0, "Torus-Reactor Building Vacuum   |
| Breaker Conditions" and VYC-315, Rev 0, "Primary Containment Vacuum")        |
| calculated the resulting torus and containment pressure caused by            |
| inadvertent spray actuation, but used a spray water temperature of 83.7F.   |
| These analyses concluded that vacuum breaker operation was not necessary to  |
| ensure that the containment remained within its external design pressure.    |
| These analyses evaluated this event at normal operating conditions (100F    |
| torus water temperature, 33F service water temperature, and 165F drywell   |
| temperature).  No evaluation has been performed for temperatures below these |
| values.                                                                      |
|                                                                              |
| The General Electric design basis for the VY vacuum breaker sizing is based  |
| on an evaluation for Monticello. This evaluation assumed a minimum spray     |
| water temperature of 50F and assumed that all vacuum breakers operated      |
| within one second.  The VY vacuum breaker design differs from this design    |
| assumption in that operation of the torus-to-reactor building vacuum         |
| breakers requires the opening of air operated valves (AOVs) #SB-16-19-11A &  |
| B as part of the vacuum breaker operation.  These AOVs require more than 5   |
| seconds to operate (VYOPF 4115.01, 03/23/99).  As a result, it cannot be     |
| assured that the vacuum breaker system will function adequately to prevent   |
| the containment from exceeding its design basis external design pressure for |
| low spray water temperature conditions.                                      |
|                                                                              |
| A plant operability evaluation, based on the information included in         |
| VYC-315, Rev 0, has concluded that a minimum drywell spray water temperature |
| of 70F would be required to approach the design basis containment external  |
| pressure limit of - 2.0 psig without effective vacuum breaker operation.  In |
| order to achieve this low spray water temperature, a combination of low      |
| torus water temperature and/or low service water temperature would be        |
| required to exist.  Current operating conditions indicate that the torus     |
| water temperature is being maintained at ~80F and has been maintained at    |
| this temperature during the months of May and June, 1999.  The current       |
| service water temperature of 79F ensures that, in the event of an           |
| inadvertent drywell spray event, spray water temperature will not be lower   |
| than 70F.                                                                   |
|                                                                              |
| This 79F service water temperature corresponds to the maximum 20 year       |
| average for river water temperature.  Based on this temperature, river water |
| temperature would not be anticipated to decrease below 70F until            |
| mid-to-late September, 1999.                                                 |
|                                                                              |
| Based on the current high service water temperature, in combination with     |
| existing torus water temperature, this condition does not effect the         |
| operability of the primary containment or the operability of the primary     |
| containment vacuum breakers.  There is no operability concern providing the  |
| torus water temperature remains above 70F and river water temperature       |
| remains above 33F.                                                          |
|                                                                              |
| The license plans to immediately issue standing orders to plant operators    |
| regarding this situation and to perform necessary design analyses prior to   |
| September, 1999.                                                             |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35891       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 07/02/1999|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 22:13[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        07/02/1999|
+------------------------------------------------+EVENT TIME:        21:30[EDT]|
| NRC NOTIFIED BY:  DAVE WALSH                   |LAST UPDATE DATE:  07/02/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAWRENCE DOERFLEIN   R1      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - Emergency safeguards system transformer radiator bottom oil drain valves   |
| found closed -                                                               |
|                                                                              |
| At 1500 on 07/01/99, Susquehanna Unit 1 was in Condition 4 (Cold Shutdown)   |
| and Unit 2 was at 100% power, when the licensee identified that the radiator |
| bottom drain valves were closed on two of the four emergency safeguards      |
| system (ESS) transformers.  Each transformer provides the preferred offsite  |
| power to one load group and alternate offsite power to another.  The two     |
| affected transformers provided backup to each other.  The drain valves allow |
| oil circulation though the transformer finned coolers.  The drain valves     |
| were opened and the ESS transformers are currently operable.                 |
|                                                                              |
| Per the Susquehanna Tech Spec 3.8.1 Basis, the AC electrical power           |
| distribution system is designed to meet the requirements of 10CFR50,         |
| Appendix A, GDC 17, which requires the AC electrical power system to provide |
| independence and redundancy to ensure an available source of power to ESF    |
| systems.  The class 1E AC distribution system is divided into redundant load |
| groups, so the loss of any one group does not prevent minimum safety         |
| functions from being performed.  Each load group has connections to two      |
| preferred offsite power supplies and a single emergency diesel generator     |
| (EDG) in order to meet this requirement.                                     |
|                                                                              |
| Licensee evaluation of the effects of the drain valves being closed is in    |
| progress.  Initial evaluation has determined that in this configuration,     |
| these transformers would have been able to perform their design function for |
| an indeterminate period of time.  Pending further evaluation, this report is |
| being provided based on conservative interpretation of the existing guidance |
| in that due to the absence of design analysis for this scenario, it could    |
| represent a condition that is potentially outside of design basis, therefore |
| reportable under 10CFR50.72(b)(1)(ii)(B).                                    |
|                                                                              |
| The licensee currently believes that this condition was not safety           |
| significant because Susquehanna is designed for a DBA LOCA/LOOP with a       |
| single failure which they believe is more limiting.  At no time were any ESS |
| buses deenergized due to this condition and the condition was promptly       |
| corrected and does not currently exist.  The EDGs would have been available  |
| to power the subject buses had the transformers failed.                      |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35892       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TROJAN                   REGION:  4  |NOTIFICATION DATE: 07/02/1999|
|    UNIT:  [1] [] []                 STATE:  OR |NOTIFICATION TIME: 22:55[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        07/02/1999|
+------------------------------------------------+EVENT TIME:        18:43[PDT]|
| NRC NOTIFIED BY:  KARL OBERLOH                 |LAST UPDATE DATE:  07/02/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |LINDA SMITH          R4      |
|10 CFR SECTION:                                 |LEDYARD (TAD) MARSH  NRR     |
|AAEC 50.72 (a) (1) (I)   EMERGENCY DECLARED     |BUTCH STINEDURF      FEMA    |
|                                                |JOSEPH GIITTER       IRO     |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Decommissioned   |0        Decommissioned   |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - 5.0 EARTHQUAKE FELT ONSITE AT TROJAN; NO DAMAGE TO PLANT COMPONENTS OR     |
| SYSTEMS -                                                                    |
|                                                                              |
| AT 1843 PDT ON 07/02/99, AN EARTHQUAKE, MEASURING 5.0 ON THE RICHTER SCALE,  |
| OCCURRED AT THE GREY HARBOR AREA OF WASHINGTON STATE, APPROXIMATELY 50 - 60  |
| MILES SOUTHWEST OF SEATTLE, WA.                                              |
|                                                                              |
| TROJAN, WHICH IS LOCATED APPROXIMATELY 70 - 80 MILES FROM THE EPICENTER,     |
| REPORTED THAT THE EARTHQUAKE WAS FELT ONSITE AND THAT THERE WAS NO DAMAGE TO |
| PLANT COMPONENTS OR SYSTEMS.                                                 |
|                                                                              |
| TROJAN IS DECOMMISSIONED BUT STILL HAS SPENT FUEL IN THEIR SPENT FUEL POOL.  |
|                                                                              |
| AT 1905 PDT, THE LICENSEE DECLARED AND TERMINATED AN UNUSUAL EVENT DUE TO    |
| THE EARTHQUAKE BEING FELT ONSITE AND NOTIFIED STATE AND LOCAL OFFICIALS.     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35893       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  FL BUREAU OF RAD CONTROL             |NOTIFICATION DATE: 07/03/1999|
|LICENSEE:  ATC ASSOCIATES, MIAMI, FL            |NOTIFICATION TIME: 18:05[EDT]|
|    CITY:  HOMESTEAD                REGION:  2  |EVENT DATE:        07/02/1999|
|  COUNTY:                            STATE:  FL |EVENT TIME:        22:30[EDT]|
|LICENSE#:  FL 2962-1             AGREEMENT:  Y  |LAST UPDATE DATE:  07/03/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |PAUL FREDRICKSON     R2      |
|                                                |SUSAN SHANKMAN       NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JOHN WILLIAMS, FL BRC        |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - TROXLER MOISTURE DENSITY GAUGE STOLEN FROM A COMPANY TRUCK IN HOMESTEAD,   |
| FL -                                                                         |
|                                                                              |
| A TROXLER MOISTURE DENSITY GAUGE WAS STOLEN FROM A TRUCK OWNED BY ATC        |
| ASSOCIATES,                                                                  |
| MIAMI, FL, BETWEEN 2230 ON 07/02/99 AND 0730 ON 07/03/99.  THE TRUCK WAS AT  |
| THE HOME OF AN                                                               |
| EMPLOYEE IN HOMESTEAD, FL.  THE UNDAMAGED GAUGE, MODEL #3411B, SERIAL        |
| #15140, CONTAINS                                                             |
| SEALED SOURCES OF 6.1 MILLICURIES OF Cs-137 AND 39.3 MILLICURIES OF          |
| Am-241-Be.  AN ATC                                                           |
| REPRESENTATIVE NOTIFIED THE HOMESTEAD POLICE AND THE FL BUREAU OF RADIATION  |
| CONTROL (BRC).  THE HOMESTEAD POLICE ARE PREPARING A PRESS RELEASE WARNING   |
| OF THE DANGER INVOLVED IN HANDLING THE GAUGE AND OFFERING A REWARD FOR THE   |
| RETURN OF THE GAUGE.                                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35894       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 07/05/1999|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 11:51[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        07/05/1999|
+------------------------------------------------+EVENT TIME:        11:30[EDT]|
| NRC NOTIFIED BY:  GORDEN FIEDLER               |LAST UPDATE DATE:  07/05/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAWRENCE DOERFLEIN   R1      |
|10 CFR SECTION:                                 |                             |
|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       22       Power Operation  |22       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT ENTERED 24-HOUR LIMITING CONDITION OF OPERATIONS (LCO) ACTION STATEMENT |
| (A/S)  DUE TO AMBIENT AIR TEMPERATURE EXCEEDING THE EMERGENCY DIESEL         |
| GENERATOR (EDG) TEMPERATURE LIMIT.                                           |
|                                                                              |
| BOTH EMERGENCY DIESEL GENERATORS WERE DETERMINED TO BE OUTSIDE THEIR DESIGN  |
| BASIS DUE TO AMBIENT OUTSIDE AIR TEMPERATURE EXCEEDING 88 DEGREES F.  THE    |
| UNIT ENTERED  A 24-HOUR LCO A/S 3.5.F.1 AND COMMENCED TEMPERATURE MONITORING |
| PER 2.2.8 ATTACHMENT 6.  ONE OF THE EMERGENCY DIESEL GENERATORS WILL BE      |
| TAGGED OUT TO INSTALL A TEMPERATURE MODIFICATION WHICH WILL RAISE THE DESIGN |
| AMBIENT TEMPERATURE LIMIT TO  95 DEGREES F.  BOTH EDGs ARE  STILL AVAILABLE, |
| IF NEEDED.                                                                   |
|                                                                              |
| THE NRC RESIDENT WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE.             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35895       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SURRY                    REGION:  2  |NOTIFICATION DATE: 07/05/1999|
|    UNIT:  [] [2] []                 STATE:  VA |NOTIFICATION TIME: 13:57[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        07/05/1999|
+------------------------------------------------+EVENT TIME:        11:22[EDT]|
| NRC NOTIFIED BY:  DONALD HART                  |LAST UPDATE DATE:  07/05/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PAUL FREDRICKSON     R2      |
|10 CFR SECTION:                                 |LEDYARD (TAD) MARSH  NRR     |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |JOSEPH GIITTER       IRO     |
|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      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DUE TO A LOSS OF COOLANT FLOW SIGNAL.                 |
|                                                                              |
| A loss of coolant flow signal was received from the "A" RCP  which actuated  |
| an automatic reactor trip.  All control rods except 2 inserted into the core |
| as designed as indicated by the rod bottom light indication. Control rods    |
| J13 (outer portion of the core) & F8 (inner portion of the core) initially   |
| did not fully insert however both slowly drifted into the core as indicated  |
| by rod bottom lights. This is believed to be an instrumentation problem and  |
| is being investigated.  The shutdown margin for Unit 2 was determined to be  |
| satisfactory.  Auxiliary Feedwater Pumps (both Turbine and Motor Driven      |
| Pumps) automatically initiated as designed on low low steam generator water  |
| level following the reactor trip.  Reactor Coolant System (RCS) temperature  |
| decreased to 542 degrees F following the trip.  No primary or secondary      |
| safety or power operated relief valves (PORVs) actuated during the event.    |
| No indication of primary to secondary leakage exists. Therefore, no adverse  |
| radiological consequences resulted.  All electrical buses transferred        |
| properly following the trip and all emergency diesel generators and          |
| emergency core cooling systems are operable and available. There were no     |
| radiation releases nor were there any personnel injuries or contamination    |
| involved.  The cause of the loss of coolant flow signal is being             |
| investigated.                                                                |
|                                                                              |
| Unit 2 is at a Tave no load condition of 547 degrees dumping steam to the    |
| main condenser.                                                              |
|                                                                              |
| Unit 1 was not affected by and remains stable at 100% power.                 |
|                                                                              |
| The NRC Resident Inspector was informed by the licensee.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35896       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 07/05/1999|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 15:40[EDT]|
|   RXTYPE: [1] GE-2                             |EVENT DATE:        07/05/1999|
+------------------------------------------------+EVENT TIME:        14:53[EDT]|
| NRC NOTIFIED BY:  ERIC deMONCH                 |LAST UPDATE DATE:  07/05/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAWRENCE DOERFLEIN   R1      |
|10 CFR SECTION:                                 |LEDYARD (TAD) MARSH  NRR     |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |JOSEPH GIITTER       IRO     |
|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                                   
+------------------------------------------------------------------------------+
| TECH SPEC REQUIRED SHUTDOWN DUE TO LOSS OF POWER TO STARTUP TRANSFORMERS FOR |
| APPROXIMATELY 8 MINUTES                                                      |
|                                                                              |
| The units main generator output supplies power to two (2) 230KV "A" & "B"    |
| buses.  The 230KV "A" & "B" buses, in addition to supplying power to the     |
| grid, each have a 230KV/34.5KV step-down transformer energizing the 34.5KV   |
| "A" & "B" buses, respectively.  These 34.5KV buses feed Bank 5 and 6 Startup |
| Transformers using offsite  power when the main generator is offline.  Both  |
| the "A" & "B" 34.5KV  buses deenergized for approximately 8 minutes,         |
| possibly due to a thermal overload trip condition caused by high ambient     |
| temperatures >100 degrees F (the specific location of the 34.5KV loss is     |
| under investigation).  This placed the  unit in Tech Spec 3.7.A.(3) which    |
| states "that one 230KV line must be fully operational and switchgear for     |
| both Startup Transformers to the station are energized to carry power . . .  |
| ." or the unit must be shutdown.  The unit exited the Technical              |
| Specification required Shutdown after approximately 8 minutes when both      |
| 34.5KV buses were reenergized.  The associated 4.16KV safeguard buses        |
| remained energized throughout the transient since they normally receive      |
| power from the Auxiliary Transformer during power operations. Both emergency |
| diesel generators are available, if needed.                                  |
|                                                                              |
| At the present time the licensee said that they are carrying a large amount  |
| of VARS.                                                                     |
|                                                                              |
| The NRC Resident Inspector will be informed of this event notification by    |
| the licensee.                                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35897       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SURRY                    REGION:  2  |NOTIFICATION DATE: 07/06/1999|
|    UNIT:  [] [2] []                 STATE:  VA |NOTIFICATION TIME: 02:44[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        07/06/1999|
+------------------------------------------------+EVENT TIME:        02:04[EDT]|
| NRC NOTIFIED BY:  LISA HILBERT-SEMMES          |LAST UPDATE DATE:  07/06/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PAUL FREDRICKSON     R2      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Hot Shutdown     |0        Intermediate Shut|
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MODE CHANGE INITIATED AS PART OF A TECHNICAL SPECIFICATION REQUIRED          |
| SHUTDOWN                                                                     |
|                                                                              |
| "At 1810 hours on 7-5-99, with Surry Power Station Unit 2 at Hot Shutdown    |
| (HSD) following a reactor trip, the 'A' Cold Leg Loop Stop Valve (Mark       |
| number 2-RC-MOV-2591) was removed from it's backseat in accordance with      |
| station procedure 2-GOP-2.4.  Upon reopening the valve, full open indication |
| was not received.  In accordance with Technical Specification 3.17.1 and     |
| 3.0.1, a 30 hour clock to Cold Shutdown (CSD) LCO was started. The valve was |
| de-energized by opening it's breaker.  A cooldown to CSD was initiated at    |
| 2050 on 7-5-99.  At 0204 on 7-6-99, a review of Station procedures and       |
| 10CFR50.72 determined that a one hour report was required for commencing the |
| RCS cooldown in accordance with the Technical Specification LCO.             |
|                                                                              |
| "There were no radiation releases due to this event, nor were there any      |
| personnel injuries or contamination events.                                  |
|                                                                              |
| "Unit 2 is currently at Intermediate Shutdown with RCS cooldown in progress  |
| in accordance with station procedures.                                       |
|                                                                              |
| "Unit 1 was not affected by this event and remains stable at 100% power and  |
| 824 MWe.                                                                     |
|                                                                              |
| "This event is being reported in accordance with 10CFR50.72(b)(1)(i)(A)."    |
|                                                                              |
| The Licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+