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Event Notification Report for June 21, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/18/1999 - 06/21/1999

                              ** EVENT NUMBERS **

35790  35801  35832  35834  35841  35842  35843  35844  35845  35846  35847  35848 


+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35790       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 06/03/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 14:44[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/02/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        16:30[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  06/18/1999|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |DAVID HILLS          R3      |
|  DOCKET:  0707001                              |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  THOMAS WHITE                 |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)(i)     ACCID MT EQUIP FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THREE SPRINKLER SYSTEMS DECLARED INOPERABLE DUE TO CORRODED HEADS (24-hour   |
| report)                                                                      |
|                                                                              |
| The following text is a portion of a facsimile received from Paducah:        |
|                                                                              |
| "On 06/02/99 at 1630 CDT, the Plant Shift Superintendent (PSS) was notified  |
| that numerous sprinkler heads were corroded, affecting 16 sprinkler systems  |
| in C-337 and one system in C-333, such that the ability of the sprinklers to |
| flow sufficient water was called into question.  Subsequently, these         |
| sprinkler systems were declared inoperable, and TSR-required actions         |
| establishing roving fire patrols were initiated.  This deficiency was        |
| detected during scheduled system inspections conducted by Fire Protection    |
| personnel.  Currently, functionality of the sprinkler heads has not been     |
| fully evaluated by Fire Protection personnel, and the remaining cascade      |
| buildings are currently being inspected, and if necessary, this report will  |
| be updated to identify any additional areas.                                 |
|                                                                              |
| "It has been determined that this event is reportable under                  |
| 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to     |
| function as designed."                                                       |
|                                                                              |
| The NRC resident inspector has been notified of this event.                  |
|                                                                              |
| ******************** UPDATE RECEIVED AT 1022 EDT ON 06/04/99 FROM CAGE TO    |
| TROCINE *******************                                                  |
|                                                                              |
| The following text is a portion of a facsimile received from Paducah:        |
|                                                                              |
| "Two sprinkle heads on system D-1 in C-337 and two sprinkler heads on system |
| 27 in C-335 were identified to also be corroded.  These were identified to   |
| the PSS on 06/03/99 at 1600 CDT and 1601 CDT, respectively, and determined   |
| to require an update to this report by the PSS.                              |
|                                                                              |
| "It has been determined that this event is reportable under                  |
| 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to     |
| function as designed."                                                       |
|                                                                              |
| Paducah personnel notified the NRC resident inspector of this update.  The   |
| NRC operations officer notified the R3DO (Hills) and NMSS EO (Combs).        |
|                                                                              |
| *********** UPDATE RECEIVED AT 2152 EDT ON 06/17/99 FROM WALKER TO POERTNER  |
| ***********                                                                  |
|                                                                              |
| The following text is a portion of a facsimile received from Paducah:        |
|                                                                              |
| "Three sprinkler heads on system C-15 and five sprinkler heads on system B-8 |
| in C-333 were identified to also be corroded.  The PSS was notified of this  |
| condition at 1300 CDT on 06/17/99 and determined that an update to this      |
| report was required."                                                        |
|                                                                              |
| "It has been determined that this event is reportable under                  |
| 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to     |
| function as designed."                                                       |
|                                                                              |
| Paducah personnel notified the NRC resident inspector of this update.  The   |
| NRC operations officer notified the R3DO (Madera).                           |
|                                                                              |
| * * * UPDATE AT 1440 ON 06/18/99 FROM UNDERWOOD TAKEN BY STRANSKY * * *      |
|                                                                              |
| "Two sprinkler heads on system C-15 and one sprinkler head on system B-8 in  |
| C-333 were identified to have corrosion.  The PSS was notified of this       |
| condition at 1350 CDT on 06/18/99.  The area of the fire patrol for system   |
| C-15 was expanded to include the two heads identified as corroded.  The one  |
| head on system B-8 was in the area already being patrolled.  The PSS         |
| determined that an update to this report was required."                      |
|                                                                              |
| The NRC resident inspector has been informed of this update.  The NRC        |
| operations officer notified R3DO (Madera).                                   |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35801       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 06/06/1999|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 18:07[EDT]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        06/06/1999|
+------------------------------------------------+EVENT TIME:        14:40[CDT]|
| NRC NOTIFIED BY:  MIKE MacLENNON               |LAST UPDATE DATE:  06/18/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID HILLS          R3      |
|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  |55       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LIGHTNING STRIKE CAUSED SOME MINOR ALARMS AND PARTIAL GROUP ONE ISOLATIONS   |
|                                                                              |
| "On 06/06/99 at approximately 1440, a lightning strike caused valves         |
| 1-0220-44 and 1-0220-45, Reactor Recirculation sample valves, to close on an |
| invalid signal.  These valves close automatically on a Group 1 isolation,    |
| and therefore this is considered to be an ESF actuation.                     |
|                                                                              |
| "The power change indicated above was also a result of the lightning strike. |
| An emergency load reduction was made in response to a partial loss of        |
| feedwater heaters.  Reactor recirculation flow was manually reduced and      |
| control rods were inserted to reduce the flow control line below 100%.       |
| Miscellaneous other minor alarms were received on both units due to the      |
| lightning strike.                                                            |
|                                                                              |
| "The above sample valves have been reopened, and a load increase to full     |
| power has been initiated at 1635."                                           |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE AT 1115 ON 06/18/99 BY VENCI RECEIVED BY WEAVER * * *           |
|                                                                              |
| On 06/06/99, an ENS notification was made in accordance with                 |
| 10CFR50.72(b)(2)(ii) as an ESF actuation.   A lightning strike caused the    |
| reactor recirculation sample valves, 1-0220-44 and 1-0220-45 to close on an  |
| invalid signal.  These valves close on a Group 1 isolation signal.           |
|                                                                              |
| The subsequent evaluation determined that there were no conditions present   |
| to actuate these valves from a Group 1 signal and the PCI logic circuitry    |
| was not actuated.   Apparently, the lightning strike caused a minor power    |
| disturbance of the instrument bus that resulted in the solenoid valves,      |
| associated with the reactor recirculation sample valves, to lose power.      |
| This caused closure of the 1-0220-44 and 1-0220-45 valves.                   |
|                                                                              |
| Quad Cities experienced an invalid signal with no actuation of ESF logic.    |
| Therefore, this event is being retracted.                                    |
|                                                                              |
| The licensee informed the NRC Resident Inspector.  The NRC Operations        |
| Officer notified the R3DO (Madera).                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35832       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 06/16/1999|
|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 18:57[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        06/16/1999|
+------------------------------------------------+EVENT TIME:        18:15[EDT]|
| NRC NOTIFIED BY:  CHARLIE KOCSIS               |LAST UPDATE DATE:  06/18/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JIMI YEROKUN         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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH HEAD SAFETY INJECTION EXTERNAL LEAKAGE.                                 |
|                                                                              |
| On 06/16/99, operators identified packing leakage from a drain valve in the  |
| high head safety injection system (valve SI-105).  When the leakage was      |
| added to the existing system leakage, the control room ventilation system    |
| exceeded its system design basis calculation assumption for external         |
| recirculation system leakage (0.68 gph).  The control room ventilation       |
| system continues to remain operable per an existing operability              |
| determination (OD 98-16).  Leakage was subsequently reduced, such that total |
| system leakage was within design base limits.                                |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
|                                                                              |
| * * * UPDATE AT 1318 ON 06/18/99 FROM DECLEMENTE TAKEN BY STRANSKY * * *     |
|                                                                              |
| "On 06/16/99, while the plant was in operation, operators identified active  |
| packing leakage from a drain valve in the high head safety injection system  |
| (valve SI-105).  When the leakage is added to the existing system leakage,   |
| the control room ventilation system exceeded its system design basis         |
| calculation assumption for external recirculation system leakage (0.68 gph). |
| The control room ventilation system continues to remain operable per an      |
| existing operability determination (OD 98-16).  Following discovery of the   |
| active packing leak, adjustments were made that reduced leakage.  However,   |
| the subsequent calculated leak rate shows the leak rate still remained       |
| greater than 0.68 gph, specifically 0.683 gph.                               |
|                                                                              |
| "During another test procedure, PT-Q116, packing leakage from valve          |
| SI-MOV-851B, 32 safety injection pump discharge isolation valve was found on |
| 06/18/99.  Total leak rate of systems outside containment likely to contain  |
| radioactive material is 0.689 gph."                                          |
|                                                                              |
| The licensee will inform the NRC Resident Inspector.  The NRC Operations     |
| Officer notified R1DO (Yerokun).                                             |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35834       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 06/16/1999|
|    UNIT:  [1] [2] []                STATE:  GA |NOTIFICATION TIME: 20:57[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        06/16/1999|
+------------------------------------------------+EVENT TIME:        20:00[EDT]|
| NRC NOTIFIED BY:  BARRY COLEMAN                |LAST UPDATE DATE:  06/18/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PHYSICAL SECURITY REPORT                                                     |
|                                                                              |
| Plant access granted inappropriately.  Immediate compensatory measures taken |
| upon discovery.  The licensee notified the NRC resident inspector.           |
|                                                                              |
| Refer to HOO Log for additional details.                                     |
|                                                                              |
| * * * RETRACTION AT 1312 ON 06/18/99 FROM BARNES TAKEN BY STRANSKY * * *     |
|                                                                              |
| The licensee has determined that this event is not reportable, and this      |
| notification is being retracted.  The licensee will inform the NRC Resident  |
| Inspector.  The NRC Operations Officer notified R2DO (Julian).               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35841       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALISADES                REGION:  3  |NOTIFICATION DATE: 06/18/1999|
|    UNIT:  [1] [] []                 STATE:  MI |NOTIFICATION TIME: 01:41[EDT]|
|   RXTYPE: [1] CE                               |EVENT DATE:        06/17/1999|
+------------------------------------------------+EVENT TIME:        22:40[EDT]|
| NRC NOTIFIED BY:  BRUCE HOWARD                 |LAST UPDATE DATE:  06/18/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN MADERA          R3      |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| INFORMATION CALL - A FIRE ON OWNER CONTROLLED PROPERTY                       |
|                                                                              |
| A fire of undetermined origin was discovered by a janitor at 2240 on         |
| 06/17/99 in a temporary office trailer, north of the Palisades Training      |
| Building.  The trailer complex is located one-half mile from the operating   |
| plant.  There was no impact to the Training Building or the plant's          |
| operation, and the plant remained at full power.                             |
|                                                                              |
| The control room was notified after discovery of the blaze.  The control     |
| room dispatched the plant's fire brigade and Covert Fire and Ambulance       |
| department to the scene.  The plant fire brigade began immediate setup of    |
| hoses and began initial fire fighting until the Covert Fire department       |
| arrived, some 15 minutes later.                                              |
|                                                                              |
| The cause of the fire has not been determined.  An investigation will be     |
| initiated.  There were no injuries and no one was in the trailer office at   |
| the time.                                                                    |
|                                                                              |
| A safety inspection of all plant offices and trailers for potential fire     |
| hazards will be conducted on 06/18/99.                                       |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35842       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 06/18/1999|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 05:48[EDT]|
|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        06/18/1999|
+------------------------------------------------+EVENT TIME:        02:50[CDT]|
| NRC NOTIFIED BY:  JIM SPIELER                  |LAST UPDATE DATE:  06/18/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN MADERA          R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ESF ACTUATION - VACUUM BREAKER                                               |
|                                                                              |
| At 0250 CDT,  #2PC001D, the 2D Primary Containment Vacuum Breaker went from  |
| the (normal) closed position to an indicated dual position.  Locally, it was |
| determined that the valve was just cracked open.  The valve is designed to   |
| open when suppression chamber pressure is approximately 0.5 psig greater     |
| than drywell pressure.  When the vacuum breaker opened the aforementioned    |
| differential pressure was approximately 0.2 psid.  The vacuum breaker was    |
| closed by an equipment attendant and then cycled per LOS-PC-M2 "Unit 2       |
| Drywell-Suppression Pool Vacuum Breaker Operability Test for Condition 1, 2  |
| and 3" to verify proper operation.  The valve cycled satisfactorily.         |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| NOTE:  THIS  EVENT IS SIMILAR TO EVENT #35840.                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35843       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  NC DIVISION OF RADIATION PROTECTION  |NOTIFICATION DATE: 06/18/1999|
|LICENSEE:  BARNHILL CONSTRUCTION                |NOTIFICATION TIME: 08:45[EDT]|
|    CITY:  ROBERSON                 REGION:  2  |EVENT DATE:        06/14/1999|
|  COUNTY:  MARTIN                    STATE:  NC |EVENT TIME:        12:00[EDT]|
|LICENSE#:  NC-092-0958-1         AGREEMENT:  Y  |LAST UPDATE DATE:  06/18/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CAUDLE JULIAN        R2      |
|                                                |FRED COMBS           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  MR. JEFFRIES                 |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|NDAM                     DAMAGED GAUGE/DEVICE   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DAMAGED MOISTURE DENSITY GAUGE                                               |
|                                                                              |
| A TROXLER MOISTURE DENSITY GAUGE WAS DAMAGED BY A MOTORIST AT A CONSTRUCTION |
| WORKSITE ALONG HIGHWAY 64 IN MARTIN COUNTY, NC.  THE GAUGE WAS SEVERELY      |
| DAMAGED AS WAS THE SOURCE TUBE, BUT NO CONTAMINATION WAS SPREAD BY THIS      |
| INCIDENT.  THE GAUGE HAS BEEN RETURNED TO TROXLER.  THE GAUGE IS A MODEL     |
| 4640B CONTAINING A 8 mCi Cs-137 SOURCE.                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35844       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ROSEMOUNT NUCLEAR INSTRUMENTS, INC.  |NOTIFICATION DATE: 06/18/1999|
|LICENSEE:  ROSEMOUNT NUCLEAR INSTRUMENTS, INC   |NOTIFICATION TIME: 12:28[EDT]|
|    CITY:  EDEN PRAIRIE             REGION:  3  |EVENT DATE:        06/18/1999|
|  COUNTY:                            STATE:  MN |EVENT TIME:        10:00[CDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  06/18/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |VERN HODGE (via fax) NRR     |
|                                                |                             |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  GERRY HANSON                 |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 10 CFR PART 21 REPORT REGARDING POTENTIAL NEED FOR CAPACITOR REPLACEMENT IN  |
| SPECIFIC TRIP/CALIBRATION SYSTEMS                                            |
|                                                                              |
| The following is text of a letter submitted to the NRC Operations Center via |
| facsimile:                                                                   |
|                                                                              |
| "The purpose of this letter is to inform you that a specific capacitor C25   |
| used in Rosemount Trip/Calibration Systems may require replacement.  This    |
| affects all Rosemount Model 510DU Trip Units (obsolete since 1987) and       |
| certain Rosemount Model 710DU Trip Units.                                    |
|                                                                              |
| "Prior to 1987, there were 10 confirmed random failures of C25 capacitors    |
| used in slave and master trip unit circuit boards.  In 1987, a number of     |
| tests were run on sample capacitors in an attempt to duplicate the failure   |
| modes.  It was found that unless the capacitors were exposed to temperatures |
| and voltages in excess of normal operating conditions, no failures were      |
| induced.  However, introduction of a contaminant such as moisture could      |
| possibly cause this type of failure.  As a precautionary measure, a          |
| component change was instituted on the C25 capacitor beginning with          |
| manufacturer date code 8630.  This change featured an enhanced moisture      |
| seal.  No confirmed failures of the post 8630 date code C25 capacitor have   |
| been identified.  However, Rosemount Nuclear Instruments. Inc is sending     |
| this letter to affected utilities to remind users that the model 710 and 510 |
| trip units with pre-8630 date code C25 capacitors could be susceptible to    |
| this condition.  Failure of the C25 capacitor can cause a low resistance     |
| condition between the power supply input and chassis ground.  This low       |
| resistance can allow over-current conditions to cause failure of the         |
| affected unit.                                                               |
|                                                                              |
| "A letter [enclosed in facsimile] was issued by Rosemount Nuclear            |
| Instruments Inc to the Scram Frequency Reduction Committee of the BWR        |
| Owners' Group in response to a BWROG request for information [enclosed in    |
| facsimile], documenting the change which had been made in 1987.  Since that  |
| time, there have been five additional confirmed C25 failures and fourteen    |
| additional failures possibly related to the C25 capacitor.  Again, all of    |
| these failures occurred in units with C25 capacitors that had date codes of  |
| pre-8630.  The total number of model 510 and 710 trip units shipped with the |
| pre-8630 date code capacitors was 18,164.  We believe that recent failures   |
| may warrant further examination of your 510DU/710DU systems to determine     |
| whether replacement of the pre-8630 date code capacitors is warranted."      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35845       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE               REGION:  4  |NOTIFICATION DATE: 06/19/1999|
|    UNIT:  [] [2] []                 STATE:  AZ |NOTIFICATION TIME: 04:16[EDT]|
|   RXTYPE: [1] CE,[2] CE,[3] CE                 |EVENT DATE:        06/18/1999|
+------------------------------------------------+EVENT TIME:        22:29[MST]|
| NRC NOTIFIED BY:  DAN MARKS                    |LAST UPDATE DATE:  06/19/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN PELLET          R4      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS 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                                   
+------------------------------------------------------------------------------+
| - Auto reactor trip from 100% power due to low DNBR trips due to a failed    |
| control element assembly calculator -                                        |
|                                                                              |
| On 06/18/99, at approximately 2229 MST, Palo Verde Unit 2 experienced a      |
| reactor trip (RPS actuation) from 100% rated thermal power due to low        |
| departure from nucleate boiling ratio (DNBR) trips on all four channels of   |
| the core protection calculators (CPCs).  Unit 2 was at normal temperature    |
| and pressure prior to the trip.                                              |
|                                                                              |
| Prior to the reactor trip, at approximately 2204 MST, a CPC channel 'C'      |
| sensor fail alarm and control element assembly (CEA) withdrawal prohibit     |
| (CWP) alarm were received and cleared about one second later.  While         |
| investigating the alarms, at 2229 MST, all four CPC channel sensor fail      |
| alarms and the CWP alarm were received.  The reactor automatically tripped   |
| six seconds later.  A CEA calculator (CEAC) fail alarm was received on CEAC  |
| #2.  The apparent cause is presently suspected to be the failure of CEAC #2. |
| An investigation has commenced to determine the root cause of the reactor    |
| trip.                                                                        |
|                                                                              |
| All control rods fully inserted into the core.  Four of eight steam bypass   |
| control valves quick opened, per design, directing steam flow to the main    |
| condenser.  No main steam or primary relief valves lifted and none were      |
| required.  There was no loss of heat removal capability or loss of safety    |
| functions associated with this event.  Electrical buses transferred to       |
| offsite power, as designed.  The Shift Manager determined that this event    |
| was an uncomplicated reactor trip.  No significant LCOs have been entered as |
| a result of this event.  No major equipment was inoperable prior to the      |
| event nor contributed to the event, other than the CPCs discussed above.     |
|                                                                              |
| Unit 2 is stable in Mode 3 (hot standby) at normal operating temperature and |
| pressure.  No ESF actuations occurred and none were required.  The event did |
| not result in any challenges to the fission product barrier or result in any |
| releases of radioactive materials.  There were no adverse safety             |
| consequences or implications as a result of this event.  The event did not   |
| adversely affect the safe operation of the plant or health and safety of the |
| public.                                                                      |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35846       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 06/19/1999|
|    UNIT:  [] [] [3]                 STATE:  CT |NOTIFICATION TIME: 10:34[EDT]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        06/19/1999|
+------------------------------------------------+EVENT TIME:        10:01[EDT]|
| NRC NOTIFIED BY:  RAY MARTIN                   |LAST UPDATE DATE:  06/19/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JIMI YEROKUN         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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| -AFW PUMP STARTED DUE TO LOW S/G LEVEL SIGNALS WHILE VENTING A S/G LEVEL     |
| TRANSMITTER-                                                                 |
|                                                                              |
| WITH UNIT 3 IN MODE 5 (COLD SHUTDOWN) IN A REFUELING OUTAGE AND THE #2A      |
| VITAL INSTRUMENT AC BUS INOPERABLE, PLANT TECHNICIANS WERE VENTING AN 'A'    |
| STEAM GENERATOR (S/G) LEVEL TRANSMITTER.  THE 'A' AUXILIARY FEEDWATER (AFW)  |
| PUMP STARTED DUE TO A LOW S/G LEVEL ACTUATION SIGNAL ALONG WITH A LOW S/G    |
| LEVEL SIGNAL DUE TO THE #2A VITAL INSTRUMENT AC BUS BEING INOPERABLE (2 OUT  |
| OF 4 LOGIC ACTUATION SIGNAL).  PLANT OPERATORS STOPPED THE 'A' AFW PUMP AND  |
| RESET IT TO NORMAL WITHIN ONE MINUTE.                                        |
|                                                                              |
| THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT         |
| INSPECTOR.                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35847       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE                   REGION:  2  |NOTIFICATION DATE: 06/19/1999|
|    UNIT:  [] [2] []                 STATE:  SC |NOTIFICATION TIME: 11:58[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE:        06/19/1999|
+------------------------------------------------+EVENT TIME:        10:15[EDT]|
| NRC NOTIFIED BY:  PRESTON GILLESPIE            |LAST UPDATE DATE:  06/19/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       66       Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DUE TO MAIN TURBINE TRIP                              |
|                                                                              |
| The unit experienced an automatic turbine trip/reactor trip due to an        |
| indicated high moisture separator level.  Following the trip, all control    |
| rods inserted and all systems functioned as required. The reactor is         |
| currently stable in Mode 3, with steam generator levels being maintained by  |
| the feedwater system and decay heat being removed via the main condenser.    |
|                                                                              |
| The licensee is investigating the cause of the trip, but reported that       |
| numerous 125VDC ground alarms were received prior to the trip.  The unit had |
| been operating at reduced power because one of the reactor coolant pumps had |
| been secured due to an oil leak.  The NRC resident inspector has been        |
| informed of this event.                                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35848       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 06/19/1999|
|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 22:25[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/19/1999|
+------------------------------------------------+EVENT TIME:        21:00[CDT]|
| NRC NOTIFIED BY:  ROBERT BRINKLEY              |LAST UPDATE DATE:  06/19/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SAFEGUARDS SYSTEM DEGRADATION RELATED TO VITAL AREA BOUNDARY.  COMPENSATORY  |
| MEASURES TAKEN UPON DISCOVERY.  THE LICENSEE WILL INFORM THE NRC RESIDENT    |
| INSPECTOR.  CONTACT THE OPERATIONS CENTER FOR ADDITIONAL DETAILS.            |
+------------------------------------------------------------------------------+