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Event Notification Report for March 4, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/03/1999 - 03/04/1999

                              ** EVENT NUMBERS **

35327  35365  35418  35426  35435  35436  35437  35438  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35327       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 01/29/1999|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 13:57[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        01/29/1999|
+------------------------------------------------+EVENT TIME:        12:03[EST]|
| NRC NOTIFIED BY:  FIELDER                      |LAST UPDATE DATE:  03/03/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID SILK           R1      |
|10 CFR SECTION:                                 |                             |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE PLANT ENTERED A 14 DAY LCO DUE TO HPCI BEING DECLARED INOPERABLE.        |
|                                                                              |
| THE HPCI SYSTEM WAS ISOLATED AND DECLARED INOPERABLE DUE TO A SUSPECTED      |
| PROBLEM WITH STEAMLINE FLOW SWITCH TRIP SETPOINT.  IT WAS DETERMINED THERE   |
| WAS A POSSIBILITY THAT THE SETSCREW INTERNAL TO THE BARTON DIFFERENTIAL      |
| PRESSURE SWITCH HAD NOT BEEN TIGHTEN AFTER PERFORMANCE OF THE LAST           |
| CALIBRATION.  THIS CONDITION COULD CAUSE EXCESSIVE DRIFT.                    |
|                                                                              |
| A SECOND CONCERN IS THE SWITCH'S RESPONSE DURING A SEISMIC EVENT MAY BE      |
| AFFECTED WITH A LOOSE SCREW.  HPCI WAS ISOLATED TO MAINTAIN PRIMARY          |
| CONTAINMENT INTEGRITY AND A MAINTENANCE REQUEST HAS BEEN SUBMITTED.  THIS    |
| CONCERN MAY ALSO BE APPLICABLE TO OTHER SAFETY RELATED SYSTEMS AND THEY WILL |
| BE CHECKED TO ENSURE THE SETSCREW IS APPROPRIATELY TIGHTENED.  RCIC IS       |
| OPERABLE.                                                                    |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
|                                                                              |
| * * * RETRACTED AT 1021 EST ON 3/3/99 BY KEN GRACIA TO FANGIE JONES * * *    |
|                                                                              |
| The licensee has determined that the as-found trip setting for the steamline |
| flow switch was satisfactory.  Also, the as-found setting of the steamline   |
| flow switch was greater than the indication that occurs when the HPCI        |
| turbine is initiated and was greater than the indication that occurs during  |
| HPCI turbine operation.  The HPCI system was operable before the             |
| surveillance and was returned to service within the Technical Specification  |
| timeframe for HPCI.  The steamline flow switch was replaced because its      |
| performance, based on previous calibrations, was degrading.  The steamline   |
| flow switch was, in fact, operable and therefore, there was no violation of  |
| Technical Specifications.                                                    |
|                                                                              |
| The instrument plate screw(s) protrude through the instrument scale because  |
| that feature is a calibration convenience only.  The seismic qualification   |
| of the steamline flow switch was not affected by the screws that did         |
| protrude through the scale plate.                                            |
|                                                                              |
| Therefore, this event notification is retracted as not reportable.           |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| The NRC Operations Officer notified the R1DO (Michael Modes).                |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35365       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 02/11/1999|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 23:56[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        02/11/1999|
+------------------------------------------------+EVENT TIME:        22:49[EST]|
| NRC NOTIFIED BY:  DAVID JENKINS                |LAST UPDATE DATE:  03/03/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS DECKER        R2      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE DUE TO     |
| INABILITY TO ESTABLISH REFERENCE FLOW CONDITIONS.                            |
|                                                                              |
| HPCI SYSTEM WAS DECLARED INOPERABLE DUE TO INABILITY TO ESTABLISH REFERENCE  |
| FLOW CONDITIONS DURING PERFORMANCE OF THE QUARTERLY OPERABILITY TEST.  THESE |
| CONDITIONS ARE NORMALLY ESTABLISHED AT 2,500 REVOLUTIONS/MINUTE AND 4,550    |
| GALLONS/MINUTE.  DURING THIS PERFORMANCE OF THE TEST, A FLOW OF 4,450        |
| GALLONS/MINUTE WAS OBTAINED WITH REFERENCE TURBINE SPEED.                    |
|                                                                              |
| THE HPCI SYSTEM IS A SINGLE TRAIN EMERGENCY CORE COOLING SYSTEM.             |
| ACCORDINGLY, EMERGENCY HIGH PRESSURE INJECTION IS NOT AVAILABLE AT THIS      |
| TIME.  THE HIGH PRESSURE REACTOR CORE ISOLATION COOLING (RCIC) REMAINS       |
| OPERABLE, AND THE AUTOMATIC DEPRESSURIZATION SYSTEM  (BACKUP SYSTEM FOR      |
| HPCI) ALSO REMAINS OPERABLE.  PLANT TECHNICAL SPECIFICATIONS SECTION 3.5     |
| ALLOWS CONTINUED OPERATION FOR 14 DAYS WITH HPCI SYSTEM INOPERABLE.          |
|                                                                              |
| ENGINEERING AND MAINTENANCE PERSONNEL ARE WORKING TO DETERMINE THE CAUSE OF  |
| THIS EVENT.  ONCE THE CAUSE IS UNDERSTOOD, A CORRECTIVE ACTION PLAN WILL BE  |
| DEVELOPED.                                                                   |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE.       |
|                                                                              |
| * * * RETRACTED AT 1123 EST ON 3/3/99 BY STEVE TABOR TO FANGIE JONES * * *   |
|                                                                              |
| The licensee has determined that the HPCI system was capable of performing   |
| its design basis function.  The declaration on inoperability was             |
| conservative based on initial indications.  However, after a calibration     |
| check of the flow instrumentation, which indicated the need for calibration, |
| the flow instrument was calibrated.  The HPCI flow test was performed again  |
| with satisfactory results, showing that no flow degradation had occurred.    |
| Thus, this event notification is retracted.                                  |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| The NRC Operations Officer notified the R2DO (Claude Julian).                |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35418       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA                    REGION:  1  |NOTIFICATION DATE: 02/27/1999|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 13:37[EST]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        02/27/1999|
+------------------------------------------------+EVENT TIME:        11:39[EST]|
| NRC NOTIFIED BY:  DOUGLAS GOMEZ                |LAST UPDATE DATE:  03/03/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RICHARD BARKLEY      R1      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       70       Power Operation  |70       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CONTAINMENT VENTILATION ISOLATION DURING I&C WORK ON RADIATION MONITOR       |
|                                                                              |
| "During Instrument and Control (I/C) activities on radiation channel R-12,   |
| an unexpected Containment Ventilation Isolation (CVI) occurred. The planning |
| activities for this maintenance recognized the potential of generating a CVI |
| signal and directed the technicians to install a jumper to prevent the       |
| actuation. Even with the jumper installed an unexpected CVI occurred when    |
| the R-12 drawer was deenergized. The CVI was therefore due to maintenance    |
| activities and was not the result of an actual high radiation condition.     |
|                                                                              |
| "No plant system other than the containment ventilation monitoring system    |
| was affected by this event. The plant is stable at approximately 70% power   |
| with a plant coastdown in progress.                                          |
|                                                                              |
| "This event is reportable under lOCFR50.72(b)(2)(ii), 'Any condition that    |
| results in a manual or automatic actuation an Engineered Safety Feature.'"   |
|                                                                              |
| The NRC resident inspector has been informed of this notification.           |
|                                                                              |
| * * * RETRACTED AT 0905 EST ON 3/3/99 BY KEVIN McLAUGHLIN TO FANGIE JONES *  |
| * *                                                                          |
|                                                                              |
| The licensee, RG&E, is retracting this event notification.  RG&E has         |
| confirmed that the Containment Ventilation Isolation (CVI) signal that was   |
| generated on 02/27/99 was an invalid actuation and involved only the system  |
| equivalent to the reactor building ventilation system.  Further evaluation   |
| confirmed that the CVI signal was due to a temporary electrical jumper that  |
| was connected, but did not make adequate electrical contact with the         |
| terminal board.  The CVI was not in response to any radiation condition.     |
|                                                                              |
| The NRC Resident Inspector was notified of this retraction by the licensee.  |
|                                                                              |
| The NRC Headquarters Operations Officer notified the R1DO (Michael Modes).   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35426       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 03/01/1999|
|    UNIT:  [1] [2] []                STATE:  GA |NOTIFICATION TIME: 20:18[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/01/1999|
+------------------------------------------------+EVENT TIME:        19:29[EST]|
| NRC NOTIFIED BY:  BUTLER                       |LAST UPDATE DATE:  03/03/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROBERT HAAG          R2      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Shutdown     |0        Hot Shutdown     |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BOTH MAIN AND BACKUP PROMPT NOTIFICATION SYSTEMS WERE OUT OF SERVICE.        |
|                                                                              |
| THE NOAA WEATHER RADIO SIGNALS WERE NOT BEING RECEIVED AT HATCH FOR          |
| APPROXIMATELY 6 MINUTES.  IT APPEARS THAT DUE TO A LOOSE WIRE ON THE         |
| MICROPHONE, NOAA HAD NOT RECORDED ANYTHING ON THE TAPE THAT IS TRANSMITTED   |
| TO THE LICENSEE.  THE PROBLEM WAS CORRECTED AT 1935.                         |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED.                                     |
|                                                                              |
| * * * UPDATE 1200 EST 3/3/99 FROM BARRY COLEMAN TO S.SANDIN * * *            |
|                                                                              |
| THE LICENSEE IN RESPONSE TO PUBLIC INQUIRIES REGARDING INADVERTENT RADIO     |
| TEST SIGNALS NOTIFIED BOTH STATE AND LOCAL AGENCIES.  ALSO,  A LOCAL TV      |
| STATION CONTACTED THE LICENSEE BASED ON PUBLIC INTEREST.  NOTIFIED           |
| R2DO(CAUDLE JULIAN).                                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35435       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS                   REGION:  2  |NOTIFICATION DATE: 03/03/1999|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 17:01[EST]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        03/03/1999|
+------------------------------------------------+EVENT TIME:        16:13[EST]|
| NRC NOTIFIED BY:  MACKENZIE                    |LAST UPDATE DATE:  03/03/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| GREATER THAN 20% OF THE SIRENS ARE OUT OF SERVICE                            |
|                                                                              |
| DUE TO SEVERE WEATHER IN THE AREA OF THE SITE MORE THAN 20% OF THE           |
| LICENSEE'S SIRENS ARE INOPERABLE.  THE PLANT HAD RECEIVED A SEVERE STORM     |
| WARNING WITH HIGH WINDS FROM THE WEATHER SERVICE AT 1400.  REPAIR EFFORTS    |
| WILL BE INITIATED IMMEDIATELY.                                               |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED ALONG WITH STATE AND LOCAL           |
| AGENCIES.                                                                    |
|                                                                              |
| ***UPDATE ON 3/3/99 @ 2006 BY HOLBROOK TO GOULD ***                          |
|                                                                              |
| THE NUMBER OF INOPERABLE SIRENS IS 5 OUT OF 62 WHICH IS WITHIN THE 20% LIMIT |
| AS OF 1813.                                                                  |
| THE RESIDENT INSPECTOR WILL BE INFORMED.                                     |
|                                                                              |
| REG 2 RDO(JULIAN) WAS NOTIFIED.                                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35436       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  AUTOMATIC SWITCH CO.                 |NOTIFICATION DATE: 03/03/1999|
|LICENSEE:  AUTOMATIC SWITCH CO.                 |NOTIFICATION TIME: 15:51[EST]|
|    CITY:  FLORHAM PARK             REGION:  1  |EVENT DATE:        03/03/1999|
|  COUNTY:                            STATE:  NJ |EVENT TIME:             [EST]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  03/03/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MICHAEL MODES        R1      |
|                                                |VERN HODGES          NRR     |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  YAOUANC(FAX)                 |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC SWITCH CO (ASCO) REPORTED A MANUFACTURING DEFICIENCY .             |
|                                                                              |
| CERTAIN PUMP AND AMPLIFIER ASSEMBLIES USED IN ASCO GENERAL CONTROLS          |
| HYDRAMOTOR ACTUATORS COULD HAVE A MANUFACTURING DEFICIENCY WHICH MAY AFFECT  |
| THE OPERATION OF THE ACTUATORS.  ASCO WAS ALERTED TO THIS PROBLEM UPON       |
| EXAMINATION OF A HYDRAMOTOR ACTUATOR, THAT WAS RECENTLY RETURNED TO ASCO     |
| FROM NINE MILE POINT 2 AFTER IT HAD FAILED DURING THE POST INSTALLATION      |
| TESTING.  THIS CONDITION MAY RESULT IN THE FAILURE OF THE ACTUATOR PISTON TO |
| RETRACT WHEN THE HYDRAMOTOR IS POWERED, OR THE ACTUATOR PISTON RETURNING TO  |
| THE SPRING EXTENDED POSITION WHILE THE HYDRAMOTOR IS POWERED. THEY ARE       |
| CONTINUING THE INVESTIGATION AND WILL PROVIDE A COMPLETE LIST OF POTENTIALLY |
| AFFECTED ACTUATORS, ALONG WITH THEIR PURCHASERS.                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35437       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 03/03/1999|
|    UNIT:  [1] [] []                 STATE:  CA |NOTIFICATION TIME: 20:31[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/03/1999|
+------------------------------------------------+EVENT TIME:        15:01[PST]|
| NRC NOTIFIED BY:  MAGRUDER                     |LAST UPDATE DATE:  03/03/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PHIL HARRELL         R4      |
|10 CFR SECTION:                                 |ELINOR ADENSAM       NRR     |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |JOSEPH GIITTER       IRO     |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP           |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUXILIARY OFFSITE POWER TRIPPED DURING MAINTENANCE WORK DUE TO A PROCEDURAL  |
| DISCREPANCY.                                                                 |
|                                                                              |
| THE AUXILIARY OFFSITE POWER TRIP RESULTED IN THE AUTO START AND LOADING OF   |
| THE 1-2 DIESEL GENERATOR ON A BUS UNDERVOLTAGE SIGNAL.  THE OPERATING RHR    |
| PUMP TRIPPED, BUT WAS MANUALLY RESTARTED WITHIN 39 SEC, WITHOUT ANY          |
| NOTICEABLE TEMPERATURE INCREASE OCCURRING IN THE PRIMARY SYSTEM.  THE TRIP   |
| OF THE OFFSITE POWER OCCURRED DURING MAIN TURBINE WORK WHICH CAUSED A THRUST |
| BEARING TRIP SIGNAL.  THE THRUST BEARING TRIP WAS NOT CUT OUT AT THE TIME,   |
| THUS THE INITIATION OF A UNIT TRIP SIGNAL OCCURRED, TRIPPING OFFSITE         |
| AUXILIARY POWER.                                                             |
|                                                                              |
| ONE OF THE THREE VITAL BUSES WAS ALIGNED WITH ITS STARTUP FEEDER BREAKER IN  |
| THE TEST POSITION FOR PLANNED TESTING.  WHEN AUXILIARY POWER TRIPPED, THE    |
| BUS COULD THEREFORE NOT TRANSFER TO OFFSITE STARTUP POWER AND THE DIESEL     |
| GENERATOR STARTED ON BUS UNDERVOLTAGE.  THE RUNNING RHR PUMP WAS SHED FROM   |
| THE BUS DURING THE TRANSFER.  THE OTHER TWO BUSES SUCCESSFULLY TRANSFERRED   |
| TO THE STARTUP POWER SOURCE.                                                 |
|                                                                              |
| THE VITAL BUS ON THE DIESEL WAS TRANSFERRED AT 1549 PST TO THE STARTUP POWER |
| SOURCE AND THE DIESEL WAS SECURED AT 1551 PST.  ALL OFFSITE POWER SOURCES    |
| WERE RESTORED AT 1800 PST.                                                   |
|                                                                              |
| THE PROCEDURE DISCREPANCY WILL BE CORRECTED.                                 |
|                                                                              |
| THE RESIDENT INSPECTOR WAS INFORMED.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35438       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA                  REGION:  2  |NOTIFICATION DATE: 03/04/1999|
|    UNIT:  [] [2] []                 STATE:  SC |NOTIFICATION TIME: 01:15[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/04/1999|
+------------------------------------------------+EVENT TIME:        00:28[EST]|
| NRC NOTIFIED BY:  BILL RUDD                    |LAST UPDATE DATE:  03/04/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| IMPROVED TECHNICAL SPECIFICATION REVIEW FOUND SUSPECT SURVEILLANCE           |
|                                                                              |
| The licensee identified a suspect surveillance during a programatic review   |
| of  Improved Technical Specifications Surveillances.  The surveillance       |
| involved the timers for the hydrogen skimmer suction isolation valves.  The  |
| acceptance criteria in the surveillance procedure was higher than allowed by |
| the acceptance criteria of the Updated Final Safety Analysis Report Table    |
| 7-15.  The licensee entered LCO 3.0.3 due to both trains being out of        |
| tolerance.  The licensee exited LCO 3.0.3 at 0059 EST after one of the       |
| timers was recalibrated and that train was declared operable.                |
|                                                                              |
| The licensee also verified unit 1 hydrogen skimmer suction valve timers were |
| in specification.  One of unit 1's valves was out of specification and will  |
| be reported as a 30 day written report.                                      |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+