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Event Notification Report for April 3, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/31/2000 - 04/03/2000

                              ** EVENT NUMBERS **

36737  36825  36849  36850  36851  36852  36853  36854  36855  36856  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36737       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 02/28/2000|
|    UNIT:  [] [2] []                 STATE:  CT |NOTIFICATION TIME: 23:29[EST]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        02/28/2000|
+------------------------------------------------+EVENT TIME:        23:09[EST]|
| NRC NOTIFIED BY:  STEVEN BAKER                 |LAST UPDATE DATE:  03/31/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JIM TRAPP            R1      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |97       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TECH SPEC REQUIRED SHUTDOWN - BACKLEAKAGE FROM THE S/G TO THE AUXILIARY      |
| FEEDWATER SYSTEM.                                                            |
|                                                                              |
| Check valve leakage from the # 1 Steam Generator caused a rise in            |
| temperature in the discharge piping of the "A" auxiliary feedwater pump.     |
| The maximum allowed temperature is 190 degrees F.  The maximum temperature   |
| reached was 300 degrees F.  The licensee entered Tech Spec 3.0.3 at 1209 and |
| started slowly lowering power.    Injection with the "A" AFW pump reduced    |
| the temperature in the line below the limit.  The licensee is waiting to     |
| determine if the check valve has reseated.                                   |
|                                                                              |
| The licensee notified the NRC resident inspector, the town of Waterford and  |
| the state of Connecticut.                                                    |
|                                                                              |
| * * * UPDATE 0026 2/29/2000 FROM JOHN CLAIR TAKEN BY BOB STRANSKY * * *      |
|                                                                              |
| TS 3.0.3 was exited at 2338 2/28/2000. The unit is returning to rated power. |
| The NRC resident inspector will be informed of this update by the licensee.  |
| Notified R1DO (Trapp).                                                       |
|                                                                              |
| * * * RETRACTION 0833 3/31/2000 FROM KENNETH TRUSDALE TAKEN BY STRANSKY * *  |
| *                                                                            |
|                                                                              |
| "This call is to retract a call made on 2/28/2000 under 10 CFR 50.72         |
| regarding entry into Tech Spec Action Statement 3.0.3, as the plant was in a |
| condition prohibited by the Tech Specs. The original notification was made   |
| because the Shift Manager had indication that the auxiliary feedwater piping |
| temperature was above normal, and he did not have enough information or      |
| guidance at that time to determine that the auxiliary feedwater system was   |
| operable. As operability was indeterminate, the Shift Manager conservatively |
| assumed the auxiliary feedwater system was inoperable, which is a condition  |
| prohibited by the plant Technical Specifications. Subsequent research and    |
| investigation determined that the auxiliary feedwater system was operable    |
| throughout the event and the plant was not in a condition prohibited by the  |
| Technical Specifications.                                                    |
|                                                                              |
| "As the plant was not in a condition prohibited by the Technical             |
| Specifications, there was no requirement to enter Action Statement 3.0.3.    |
| The notification made on 2/28/2000 is withdrawn."                            |
|                                                                              |
| The NRC resident inspector has been informed of this retraction by the       |
| licensee. Notified R1DO (Evans).                                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36825       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 03/23/2000|
|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 13:11[EST]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        03/23/2000|
+------------------------------------------------+EVENT TIME:        12:00[EST]|
| NRC NOTIFIED BY:  DENNIS CORNAX                |LAST UPDATE DATE:  03/31/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LOUIS MANNING        R1      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| C-3 DEFECTS DETECTED DURING EDDY CURRENT INSPECTION OF STEAM GENERATORS      |
|                                                                              |
| Indian Point 2 is conducting eddy current testing of 100% of the steam       |
| generator (SG) tubes.  With about 90% of the inspection complete, SG-21 and  |
| SG-24 tubes have defects in greater than 1% of the tubes inspected.  SG-22   |
| and SG-23 have defects in much less than 1% of the tubes inspected.  The     |
| majority of the defects are at the support plate intersections and in row 2  |
| U-bends.  There are 41 indications in SG-21, 40 at the support plate and 1   |
| in the U-bend.  There are 39 indications in SG-24, 36 at the support plate   |
| and 3 in the U-bend.  In accordance with Technical Specification 4.13, these |
| defects result in a C-3 classification.  The testing will continue until     |
| 100% of the tubes are inspected.                                             |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
|                                                                              |
| UPDATE ON 3/31/2000 BY LAMB, RECEIVED BY WEAVER * * *                        |
|                                                                              |
| This report is being made as a follow up to previously reported event number |
| 36825.  At approximately 1500 today, the tube at Row 2 Column 69 in steam    |
| generator 24 failed the three delta pressure requirement during in-situ      |
| pressure testing being performed in accordance with NEI 97-06 guidelines to  |
| meet Technical Specification requirements.  The three delta pressure value   |
| was calculated to be 5118 psi, and with uncertainties applied, the test      |
| pressure was specified at 5173 psi.  Shortly after achieving 5173 psi for    |
| the required two seconds specified in the test, pressure was noted to        |
| rapidly drop indicating leakage.  No leakage was observed at a steam line    |
| test pressure of 2841 psi.  Therefore, that performance criterion was met.   |
|                                                                              |
| The licensee notified the NRC resident inspector.  The operations center     |
| notified the R1DO (Evans).                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36849       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  FLORIDA BUREAU OF RADIATION CONTROL  |NOTIFICATION DATE: 03/31/2000|
|LICENSEE:  J. B. COXWELL CONTRACTING, INC.      |NOTIFICATION TIME: 07:31[EST]|
|    CITY:  JACKSONVILLE             REGION:  2  |EVENT DATE:        03/31/2000|
|  COUNTY:                            STATE:  FL |EVENT TIME:             [EST]|
|LICENSE#:  FL 2904-1             AGREEMENT:  Y  |LAST UPDATE DATE:  03/31/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CAUDLE JULIAN        R2      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JERRY EAKINS                 |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - STOLEN MOISTURE/DENSITY GAUGE                       |
|                                                                              |
| The Florida Bureau of Radiation Control reported the theft of a Troxler      |
| Model 3430 moisture/density gauge (Serial Number 2904-1) from a state        |
| licensee. The theft occurred sometime between 0000 and 0600 on 3/31/2000     |
| from the parking lot of a motel in Jacksonville, FL. The gauge was stored in |
| its case, which was chained to the bed of a pickup truck. The chain was cut, |
| and both the gauge and case were taken. The theft has been reported to the   |
| Jacksonville Police Department. The state has requested that the licensee    |
| post a reward for the return of the gauge, and is helping the licensee to    |
| prepare a press release regarding this incident.                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36850       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 03/31/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 15:10[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        03/31/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:             [CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  03/31/2000|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |RONALD GARDNER       R3      |
|  DOCKET:  0707001                              |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC WALKER                  |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBB 76.120(c)(2)(ii)    EQUIP DISABLED/FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CRITICALITY ACCIDENT ALARM SYSTEM FAILURE DURING A TEST                      |
|                                                                              |
| At 1845 on 03-30-2000, during functional testing of C-746Q Criticality       |
| Accident Alarm System (CAAS), it was discovered that temperature control     |
| system on cluster "AD"  was unable to perform the ability to maintain the    |
| system above the manufacturer's fourteen degree Fahrenheit recommendation    |
| due to failure of a temperature switch.  The system was last tested on       |
| 12-30-99 and was determined to be functional at that time. In January of     |
| this year there were several days were outside ambient temperature dropped   |
| below fourteen degrees Fahrenheit and operability of system at those times   |
| cannot be reasonably determined.  Even though the failure was discovered     |
| during testing, it is possible that the system would not have performed its  |
| intended safety function if it had been required to since the last           |
| surveillance on 12-30-99.                                                    |
|                                                                              |
| This event is reportable under 10 CFR 76.120(c)(2) as an event in which      |
| equipment required by the TSR is disabled or fails to function as designed.  |
|                                                                              |
| The NRC Senior Resident Inspector has been notified of this event.           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36851       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS                   REGION:  2  |NOTIFICATION DATE: 03/31/2000|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 15:40[EST]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        03/31/2000|
+------------------------------------------------+EVENT TIME:        14:48[EST]|
| NRC NOTIFIED BY:  MAURICE GRIFFIN              |LAST UPDATE DATE:  03/31/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| A CONTRACT EMPLOYEE WAS INAPPROPRIATELY GRANTED UNESCORTED ACCESS.  ACCESS   |
| HAS BEEN SUSPENDED PENDING FURTHER INVESTIGATION.  THE LICENSEE WILL NOTIFY  |
| THE NRC RESIDENT INSPECTOR.  ADDITIONAL DETAILS ARE AVAILABLE FROM THE NRC   |
| OPERATIONS CENTER.                                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36852       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FT CALHOUN               REGION:  4  |NOTIFICATION DATE: 04/01/2000|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 11:02[EST]|
|   RXTYPE: [1] CE                               |EVENT DATE:        04/01/2000|
+------------------------------------------------+EVENT TIME:        09:20[CST]|
| NRC NOTIFIED BY:  LARRY LEES                   |LAST UPDATE DATE:  04/01/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KRISS KENNEDY        R4      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TECH SPEC REQUIRED SHUTDOWN DUE TO EMERGENCY FEEDWATER STORAGE TANK LEVEL    |
| DECREASING BELOW TECH SPEC LIMIT                                             |
|                                                                              |
| THE PLANT ENTERED ABNORMAL OPERATING PROCEDURE (AOP) 30, "EMERGENCY FILL OF  |
| EMERGENCY FEEDWATER STORAGE TANK," AS A RESULT OF THE EMERGENCY FEEDWATER    |
| STORAGE TANK LEVEL FALLING BELOW TECH SPEC LOW LIMIT OF 91%.  THIS RESULTED  |
| IN ENTRY INTO TECH SPEC 2.0.1 WHICH DIRECTS PLACING THE PLANT IN HOT         |
| SHUTDOWN WITHIN 6 HOURS, LESS THAN 300 DEGREES F IN ANOTHER 6 HOURS AND IN   |
| COLD SHUTDOWN IN 30 HOURS.  AT THE TIME OF ENTRY INTO THIS TECH SPEC THE     |
| PLANT WAS ALREADY IN HOT SHUTDOWN.  ACTIONS TO REFILL THE EMERGENCY          |
| FEEDWATER STORAGE TANK WERE TAKEN BY OPENING THE CONDENSATE FILL LINE AND    |
| EMERGENCY FILLING.  FILLING WAS IN PROGRESS BEFORE GOING BELOW 91%, HOWEVER, |
| SYSTEM DEMAND WAS GREATER THAN THE MAKEUP ABILITY OF THE DEMINERALIZED WATER |
| SOURCE (STEAM GENERATOR WATER SUPPLY SWAPOVER).  LEVEL WAS ABOVE 91% AT      |
| 0944CST AT WHICH TIME AOP 30 AND TECH SPEC 2.0.1 WERE EXITED.                |
|                                                                              |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36853       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 04/01/2000|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 21:04[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        04/01/2000|
+------------------------------------------------+EVENT TIME:        17:38[EST]|
| NRC NOTIFIED BY:  TOM PLUMPTON                 |LAST UPDATE DATE:  04/01/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHELE EVANS        R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       26       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR SCRAM                                                                |
|                                                                              |
| During a planned power reduction, the recombiner was removed from service.   |
| The recombiner bypass valve shut, reason unknown, isolating all off gas      |
| flow.  Vacuum decayed as a result.  The main turbine was manually tripped,   |
| followed by an automatic reactor scram.                                      |
|                                                                              |
| Three rods did not indicate fully inserted immediately after the trip, but   |
| were later verified to be full in.  The recirculating pumps are running and  |
| steam is being dumped to the main condenser (vacuum was restored) to remove  |
| decay heat.                                                                  |
|                                                                              |
| The licensee informed the NRC resident inspector and will make a press       |
| release.                                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36854       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 04/01/2000|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 22:28[EST]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        04/01/2000|
+------------------------------------------------+EVENT TIME:        19:15[EST]|
| NRC NOTIFIED BY:  KEVIN DAHM                   |LAST UPDATE DATE:  04/01/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RONALD GARDNER       R3      |
|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     M/R        Y       23       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR SCRAM                                                                |
|                                                                              |
| On Saturday 4/1/2000, at 1200 hours, control room operators commenced a      |
| planned unit shutdown in preparation for refueling outage number 7.   At     |
| 1815 hours, the 'A' Reactor Recirculation Pump exhibited speed fluctuations  |
| and was tripped.  The crew conducted an evaluation to determine existing     |
| procedure guidance for operation at low power and low flow in a single loop  |
| configuration, and conservatively decided to shut down the reactor.  At 1915 |
| hours, the Reactor Operator placed the Reactor Mode Switch in Shutdown       |
| inserting a manual scram from 23% reactor power.  All control rods fully     |
| inserted.   All systems operated as expected, no safety/relief valves opened |
| and no ECCS systems initiated/actuated.                                      |
|                                                                              |
| The lowest reactor water level observed was 163 inches, normal operating     |
| band is 196 inches, all level three isolations (173 inches) came in as       |
| expected.  At present, reactor water level is operating in normal operating  |
| band and is being maintained on the startup level control valve.   No steam  |
| leaks noted.                                                                 |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36855       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY                   REGION:  2  |NOTIFICATION DATE: 04/02/2000|
|    UNIT:  [1] [2] []                STATE:  AL |NOTIFICATION TIME: 07:25[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        04/02/2000|
+------------------------------------------------+EVENT TIME:        05:05[CDT]|
| NRC NOTIFIED BY:  BILL ARENS                   |LAST UPDATE DATE:  04/02/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+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          N       0        Refueling        |0        Refueling        |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 1 HOUR SECURITY REPORT                                                       |
|                                                                              |
| UNESCORTED PROTECTED AREA ACCESS GRANTED INAPPROPRIATELY.  IMMEDIATE         |
| COMPENSATORY MEASURES TAKEN.  THE LICENSEE WILL INFORM THE NRC RESIDENT      |
| INSPECTOR.                                                                   |
|                                                                              |
| CONTACT THE HEADQUARTERS OPERATIONS CENTER FOR ADDITIONAL DETAILS.           |
|                                                                              |
| * * * UPDATE 0955EDT ON 4/2/00 FROM VINCE MURPHY TO S.SANDIN * * *           |
|                                                                              |
| THE LICENSEE PROVIDED ADDITIONAL SPECIFIC INFORMATION.  A REVIEW WILL BE     |
| PERFORMED ON MONDAY 4/3 TO DETERMINE REPORTABILITY.  NOTIFIED R2DO (JULIAN). |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36856       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS                   REGION:  2  |NOTIFICATION DATE: 04/02/2000|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 09:38[EDT]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        04/02/2000|
+------------------------------------------------+EVENT TIME:        09:17[EDT]|
| NRC NOTIFIED BY:  STAN LOWE                    |LAST UPDATE DATE:  04/02/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |JOHN ZWOLINSKI       NRR     |
|AAEC 50.72 (a) (1) (I)   EMERGENCY DECLARED     |CHARLES MILLER       IRO     |
|                                                |CEGIELSKI            FEMA    |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO LOSS OF THE EMERGENCY RESPONSE FACILITY        |
| INFORMATION SYSTEM (ERFIS) FOR GREATER THAN 4 HOURS                          |
|                                                                              |
| AT 0917EDT THE LICENSEE DECLARED AN UNUSUAL EVENT BASED ON EMERGENCY ACTION  |
| LEVEL (EAL) 6-2-1, "INABILITY OF ERFIS TO PERFORM ITS INTENDED FUNCTION FOR  |
| A CONTINUOUS PERIOD OF 4 HOURS."  BOTH THE "A" AND "B" PLANT PROCESS         |
| COMPUTERS WHICH SUPPLY INPUT DATA TO ERFIS WOULD NOT REBOOT FOR REASONS      |
| UNKNOWN.  ADDITIONAL INFORMATION TECHNOLOGY (IT) STAFF HAS BEEN BROUGHT IN   |
| TO RESOLVE THE FAILURE.  THE LICENSEE HAS IMPLEMENTED MONITORING ON          |
| REDUNDANT EQUIPMENT IN ACCORANCE WITH TECH SPEC REQUIREMENTS.  THE UNIT IS   |
| CURRENTLY STABLE AT 100% POWER.                                              |
|                                                                              |
| THE LICENSEE INFORMED STATE AND COUNTY AGENCIES AND WILL INFORM THE NRC      |
| RESIDENT INSPECTOR.                                                          |
|                                                                              |
| * * * UPDATE AT 1644 ON 4/2/00, BY LOWE RECEIVED BY WEAVER * * *             |
|                                                                              |
| The licensee terminated the Unusual Event at 1630 after having repaired and  |
| tested the ERFIS system.  The licensee informed the NRC resident inspector   |
| as well as state and county agencies.  The Operations Center notified the    |
| RDO (Julian), EO (Zwolinski) and FEMA (Cegielski).                           |
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