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Event Notification Report for January 26, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/25/2000 - 01/26/2000

                              ** EVENT NUMBERS **

36558  36620  36621  36622  36623  36624  36625  36626  36627  36628  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36558       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 01/03/2000|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 16:14[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        01/03/2000|
+------------------------------------------------+EVENT TIME:        14:45[EST]|
| NRC NOTIFIED BY:  M ABRAMSKI                   |LAST UPDATE DATE:  01/25/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JIMI YEROKUN         R1      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP           |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE.                  |
|                                                                              |
| During Technical Specification required surveillance testing an oil leak was |
| detected on a fitting in the HPCI hydraulic governor control system (EGR     |
| actuator).  It was determined that had this leak developed during accident   |
| conditions, the HPCI system may not have been able to perform it's intended  |
| function for the duration of time required.  The licensee entered the        |
| appropriate Technical Specification for declaring HPCI inoperable (7 day     |
| Limiting Condition of Operation).  All other Emergency Core Cooling Systems  |
| and the Reactor Core Isolation Cooling system are fully operable if needed.  |
| The licensee is preparing to repair the HPCI hydraulic governor control      |
| system oil leak.                                                             |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
|                                                                              |
| * * * RETRACTED AT 1412 EST ON 1/25/00 BY JAMES COSTEDIO TO FANGIE JONES * * |
| *                                                                            |
|                                                                              |
| The licensee has performed an engineering evaluation  of the reported oil    |
| leak and determined that the amount of oil expected to be lost as a result   |
| would not have resulted in inadequate oil level.  HPCI would have been able  |
| to perform its intended function for the duration of time required.          |
| Therefore, this event notification has been retracted.                       |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| The R1DO (John Rogge) has been notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36620       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUMMER                   REGION:  2  |NOTIFICATION DATE: 01/24/2000|
|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 22:37[EST]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        01/24/2000|
+------------------------------------------------+EVENT TIME:        22:15[EST]|
| NRC NOTIFIED BY:  HENRY MANOS                  |LAST UPDATE DATE:  01/26/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KERRY LANDIS         R2      |
|10 CFR SECTION:                                 |                             |
|AENS 50.72(b)(1)(v)      ENS INOPERABLE         |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| MORE THAN 25% OF THE OFFSITE WARNING SIRENS LOST DUE TO ICE STORMS           |
|                                                                              |
| The licensee reported the loss of more than 25% of the offsite warning       |
| sirens due to ice storms passing through the local area.  The licensee will  |
| be contacting the power suppliers of the sirens to take action to recover    |
| them.                                                                        |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE AT 1315 EST ON 1/26/00 BY BLAIR WILSON TO FANGIE JONES * * *    |
|                                                                              |
| Greater than 75 % of the emergency sirens (86 %) have been restored to       |
| service, this is the last update as the minimum number operable is met.  The |
| NRC Resident Inspector has been notified.                                    |
|                                                                              |
| The R2DO (Caudle Julian) has been informed.                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36621       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 01/25/2000|
|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 06:44[EST]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        01/25/2000|
+------------------------------------------------+EVENT TIME:        06:10[EST]|
| NRC NOTIFIED BY:  CORNAX                       |LAST UPDATE DATE:  01/25/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN ROGGE           R1      |
|10 CFR SECTION:                                 |                             |
|AUNA 50.72(b)(1)(ii)(A)  UNANALYZED COND OP     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       99       Power Operation  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BROKEN WINDOW IN A HIGH ENERGY LINE BREAK DOOR PLACES THE PLANT IN AN        |
| UNANALYZED CONDITION                                                         |
|                                                                              |
| A Broken Window in a High Energy Line Break Door which is located between    |
| the Main Feed Regulating  Valve Room and the Auxiliary Boiler Feed Pump Room |
| places the plant in an unanalyzed condition.  Maintenance is fabricating a   |
| metal replacement part to cover the opening.  The Door is supposed to remain |
| closed at all times when the plant is above 350 degrees F.                   |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36622       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS                   REGION:  2  |NOTIFICATION DATE: 01/25/2000|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 07:32[EST]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        01/25/2000|
+------------------------------------------------+EVENT TIME:        07:07[EST]|
| NRC NOTIFIED BY:  JAMES BRIGGS                 |LAST UPDATE DATE:  01/25/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KERRY LANDIS         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       95       Power Operation  |95       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| EMERGENCY RESPONSE ORGANIZATION (ERO) ABILITY REDUCED BY HEAVY SNOW STORM    |
|                                                                              |
|                                                                              |
| The plant is operating at 95% power.  Unusually heavy snow has reduced the   |
| ability of the ERO organization to respond to the site in a timely manner.   |
| Plant equipment is operating normally.  The licensee is trying to get        |
| vehicles that can be used to transport essential personnel to their EOF and  |
| the TSC if they are needed.                                                  |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
|                                                                              |
| * * * UPDATE AT 1725 EST ON 1/25/00 BY MIKE WEBER TO FANGIE JONES * * *      |
|                                                                              |
| Weather conditions have improved and the roads are cleared such that ERO     |
| manning can be accomplished in required time.  The licensee notified the NRC |
| Resident Inspector.                                                          |
|                                                                              |
| The R2DO (Caudle Julian) has been informed.                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36623       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ROBINSON                 REGION:  2  |NOTIFICATION DATE: 01/25/2000|
|    UNIT:  [2] [] []                 STATE:  SC |NOTIFICATION TIME: 08:45[EST]|
|   RXTYPE: [2] W-3-LP                           |EVENT DATE:        01/25/2000|
+------------------------------------------------+EVENT TIME:        07:50[EST]|
| NRC NOTIFIED BY:  BAUCOM                       |LAST UPDATE DATE:  01/26/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KERRY LANDIS         R2      |
|10 CFR SECTION:                                 |                             |
|AESS 50.72(b)(1)(v)      EMERGENCY SIREN INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| LOSS OF AC POWER TO 23 OF 45 EMERGENCY SIRENS DUE TO SNOW AND ICE.           |
|                                                                              |
| Due to recent accumulation of snow and ice, sporadic power outages have      |
| occurred in the area.  This has resulted in "loss of AC power" indications   |
| for 23/45 Public Warning Sirens per their remote siren monitoring system.    |
| This is considered a loss of off-site response capability .  Actions are     |
| being initiated to restore operability.  Local surrounding counties will be  |
| notified of this condition.                                                  |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
|                                                                              |
| * * * UPDATE AT 1509 EST ON 1/25/00 BY PETER YANDOW TO FANGIE JONES * * *    |
|                                                                              |
| Power outages continue to be a problem in the Darlington, Lee, and           |
| Chesterfield counties affecting the public warning sirens.  A total of 31 of |
| 45 have been out-of-service, but restorations have brought the number down   |
| to 26 of 45 out-of-service.  The NRC Resident Inspector has been notified.   |
|                                                                              |
| The R2DO (Caudle Julian) has been informed.                                  |
|                                                                              |
| * * * UPDATE AT 1533 EST ON 1/26/00 BY PETER YANDOW TO FANGIE JONES * * *    |
|                                                                              |
| Greater than 75 % of the emergency sirens (only 9 of 45 remain               |
| out-of-service) have been restored to service, this is the last update as    |
| the minimum number operable is met.  The NRC Resident Inspector has been     |
| notified.                                                                    |
|                                                                              |
| The R2DO (Caudle Julian) has been informed.                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36624       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEQUOYAH                 REGION:  2  |NOTIFICATION DATE: 01/26/2000|
|    UNIT:  [] [2] []                 STATE:  TN |NOTIFICATION TIME: 04:29[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/26/2000|
+------------------------------------------------+EVENT TIME:        00:39[EST]|
| NRC NOTIFIED BY:  JEFF EPPERSON                |LAST UPDATE DATE:  01/26/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 2 ENTERED TECH SPEC 3.0.3 DUE TO BOTH TRAINS SAFETY INJECTION           |
| INOPERABLE                                                                   |
|                                                                              |
| "AT 0039 EST ON 1/26/2000 BOTH TRAINS OF THE SAFETY INJECTION PUMPS (SIPs)   |
| OF SEQUOYAH UNIT 2 WERE RENDERED INOPERABLE.  THE '2A' SAFETY INJECTION PUMP |
| AND ITS ROOM COOLER WERE TAGGED OUT UNDER THE SITES TAGOUT PROCEDURE FOR     |
| MAINTENANCE.  EITHER OF THESE COMPONENTS [SI PUMP OR ITS ASSOCIATED ROOM     |
| COOLER] BEING TAGGED MADE THE PUMP INOPERABLE.  WHILE THE '2A' SI PUMP WAS   |
| INOPERABLE, MAINTENANCE WORKERS MISTAKENLY DRAINED THE OIL  FROM THE '2B'    |
| SAFETY INJECTION PUMP MOTOR BEARING FOR A PERIOD OF TIME WHICH MADE IT       |
| INOPERABLE AND UNAVAILABLE.  THIS OIL CHANGING EVOLUTION REQUIRED            |
| APPROXIMATELY 30 MINUTES TO ACCOMPLISH.  THE SIMULANTEOUS INOPERABILITY OF   |
| BOTH UNIT 2 SI PUMPS REQUIRED ENTRY INTO TECHNICAL SPECIFICATION LCO 3.0.3   |
| ACTION.  IMMEDIATE STEPS WERE INITIATED TO RESTORE OPERABILITY TO '2B' SI    |
| PUMP.  AT 0316 EST ON 1/26/2000 THE '2B' SI PUMP WAS DECLARED OPERABLE WHEN  |
| THE PUMP WAS SUCCESSFULLY RUN.  LCO 3.0.3 ACTION WAS THEN EXITED.  AN        |
| INVESTIGATION INTO THE CAUSE OF THIS EVENT WILL BE CONDUCTED."               |
|                                                                              |
| MAINTENANCE WORKERS WERE TAKING A SAMPLE OF THE BEARING OIL FOR ANALYSIS     |
| WHICH IS USUALLY ACCOMPLISHED THROUGH DRAINING.                              |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WILL BE INFORMED.                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36625       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 01/26/2000|
|    UNIT:  [1] [] []                 STATE:  GA |NOTIFICATION TIME: 07:42[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        01/26/2000|
+------------------------------------------------+EVENT TIME:        06:48[EST]|
| NRC NOTIFIED BY:  FRANK GORLEY                 |LAST UPDATE DATE:  01/26/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |WILLIAM BATEMAN      NRR     |
|ACCS 50.72(b)(1)(iv)     ECCS INJECTION         |FRANK CONGEL         IRO     |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 1 EXPERIENCED AN AUTOMATIC REACTOR SCRAM ON LOW REACTOR VESSEL WATER    |
| LEVEL DUE TO A FEEDWATER (FW) CONTROL FAILURE                                |
|                                                                              |
| AT APPROXIMATELY 0648 EST ON 1/26/2000 CONTROL ROOM OPERATORS RESPONDED TO A |
| FEEDWATER CONTROL FAILURE ALARM.  WHILE INVESTIGATING, FEEDWATER PUMP SPEED  |
| DECREASED CAUSING REACTOR VESSEL WATER LEVEL (RVWL)TO DROP FROM ITS NORMAL   |
| OPERATING LEVEL OF 37.5" TO APPROXIMATELY -45".  AT 0"  AN AUTOMATIC REACTOR |
| SCRAM AND GROUP 2 ENGINEERED SAFEGUARDS FEATURES (ESF) ACTUATION OCCURRED,   |
| AS EXPECTED.  ALL CONTROL RODS FULLY INSERTED.  AT -38" BOTH THE HIGH        |
| PRESSURE COOLANT INJECTION (HPCI) AND REACTOR CORE ISOLATION COOLING (RCIC)  |
| SYSTEM RECEIVED A START SIGNAL.  HPCI INJECTED UNTIL THE HPCI PUMP TRIPPED   |
| AT ITS RVWL SETPOINT OF 51.5".  THE FW PUMPS TRIPPED AT 58" WITH RVWL SWELL  |
| CAUSING LEVEL TO REACH 100".  FOLLOWING THE LEVEL TRANSIENT OPERATORS HAD    |
| DIFFICULTY IN ESTABLISHING THE LO-LO SET RANGE FOR PRESSURE CONTROL.         |
| NORMALLY, ONE OF THE FOUR SAFETY RELIEF VALVES USED FOR PRESSURE CONTROL,    |
| i.e.,  "H", "A", "G", OR "C" SRV, IS OPENED ELECTRICALLY FROM THE CONTROL    |
| ROOM WHICH THEN ESTABLISHES THE LOWER PRESSURE CONTROL.  TEN OF THE ELEVEN   |
| SRVs FAILED TO OPEN IN RESPONSE TO CONTROL ROOM SWITCH POSITIONING.  THE     |
| LAST SRV ATTEMPTED, THE "B" SRV, OPENED.  UNIT 1 IS CURRENTLY STABLE IN HOT  |
| SHUTDOWN REJECTING DECAY HEAT TO THE TORUS WITH BOTH TRAINS OF SUPPRESSION   |
| POOL COOLING IN SERVICE.  EFFORTS ARE UNDERWAY TO RESTORE THE MAIN CONDENSER |
| AS A HEAT SINK.  UNIT 1 INTENDS TO COOLDOWN TO INVESTIGATE AND RESOLVE THE   |
| PROBLEM WITH THE SRVs.  THERE IS NO INDICATION THAT THE SRV MECHANICAL       |
| SAFETY OR ADS FUNCTION IS IMPAIRED AT THIS TIME.  DURING THE TRANSIENT,      |
| REACTOR COOLANT SYSTEM (RCS) TEMP AND PRESSURE DECREASED FROM THEIR NORMAL   |
| AT POWER VALUES OF 532 DEGREES F AND 1035 PSIG TO AN OBSERVED MINIMUM OF 480 |
| DEGREES F AND 871 PSIG.  BOTH ARE CURRENTLY  AT 510 DEGREES F AND 977 PSIG.  |
| THERE IS NO INDICATION THAT THE 100 DEGREES F/ HR COOLDOWN RATE WAS          |
| EXCEEDED.                                                                    |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36626       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 01/26/2000|
|    UNIT:  [1] [2] [3]               STATE:  CT |NOTIFICATION TIME: 11:06[EST]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        01/26/2000|
+------------------------------------------------+EVENT TIME:        09:47[EST]|
| NRC NOTIFIED BY:  STEVE LAWHEAD                |LAST UPDATE DATE:  01/26/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN ROGGE           R1      |
|10 CFR SECTION:                                 |WILLIAM BATEMAN      NRR     |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |FRANK CONGEL         IRO     |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO STATE/LOCAL AGENCIES INVOLVING ERRONEOUS EMERGENCY   |
|                                                                              |
| "At 0947 on January 26, 2000 a notification to offsite emergency response    |
| agencies was made in error. The notification indicated that a General        |
| Emergency had been declared at Millstone. No emergency conditions currently  |
| exists at the site. The notification occurred during testing of the primary  |
| notification system. The cause of the condition is being investigated at     |
| this time. Backup means of notification is available in the event that a     |
| bonafide emergency condition arises prior to the restoration of the primary  |
| notification system.                                                         |
|                                                                              |
| "Retractions of the event notification were issued to appropriate State and  |
| local agencies. Millstone emergency management personnel have also been in   |
| contact with representatives of these agencies."                             |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36627       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  SOLIDSTATE CONTROLS, INC.            |NOTIFICATION DATE: 01/26/2000|
|LICENSEE:  SOLIDSTATE CONTROLS, INC.            |NOTIFICATION TIME: 16:11[EST]|
|    CITY:  COLUMBUS                 REGION:  3  |EVENT DATE:        01/21/2000|
|  COUNTY:                            STATE:  OH |EVENT TIME:             [EST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  01/26/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MONTE PHILLIPS       R3      |
|                                                |JOHN ROGGE           R1      |
+------------------------------------------------+CAUDLE JULIAN        R2      |
| NRC NOTIFIED BY:  W. G. HAMPTON                |GAIL GOOD            R4      |
|  HQ OPS OFFICER:  FANGIE JONES                 |VERN HODGE (fax)     NRR     |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 10 CFR 21 - POTENTIAL DEFECT INVOLVING STATIC SWITCH CONTROL ASSEMBLY AND    |
| REGULATED RECTIFIER CONTROL ASSEMBLY USED IN AN UNINTERRUPTIBLE POWER        |
| SYSTEM                                                                       |
|                                                                              |
| This reports a potential for a defect in Static Switch Control assemblies    |
| and Regulated Rectifier Control assemblies used in Uninterruptible Power     |
| Systems manufactured under the Solidstate Controls, Inc., 10CFR50 Appendix B |
| Program.                                                                     |
|                                                                              |
| Each of the plants has been notified of this report and requested to return  |
| the affected assemblies for replacement.  The following plants have affected |
| components:  Indian Point 2, Catawba, Oconee, Arkansas Nuclear One,          |
| Waterford 3, Crystal River, Diablo Canyon, Sequoyah, and Surry.              |
|                                                                              |
| The problem is associated with a component part - Unijunction Transistor,    |
| part number 03-650007-00, that has been found to sometimes cause random,     |
| sporadic transfers of the static switch due to a higher level of sensitivity |
| to noise spikes on the input line or cause the regulated rectifier to output |
| a higher DC voltage.  This increase in sensitivity will not cause the system |
| to drop power to the load, if the alternate source is not available the      |
| static switch will not transfer, continuing to protect the load.             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36628       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  METROPOLITAN DISTRICT                |NOTIFICATION DATE: 01/26/2000|
|LICENSEE:  METROPOLITAN DISTRICT                |NOTIFICATION TIME: 18:23[EST]|
|    CITY:  HARTFORD                 REGION:  1  |EVENT DATE:        01/26/2000|
|  COUNTY:                            STATE:  CT |EVENT TIME:             [EST]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  01/26/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN ROGGE           R1      |
|                                                |                             |
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| NRC NOTIFIED BY:  EARL DELANO                  |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
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|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
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                                   EVENT TEXT                                   
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| REQUIRED REPORT - EXPLOSION IN SHREDDER, NO DAMAGE TO SOURCE IN LEVEL        |
| DETECTOR                                                                     |
|                                                                              |
| The operating procedures require notification of the NRC of any explosion in |
| the trash shredders, even if no damage occurs to the source in the level     |
| measuring device.  It has been determined that small gas welding bottle that |
| contained acetylene caused an explosion in the shredder at Metropolitan      |
| District.  The source was not damaged.  Local authorities were informed and  |
| the fire department made the determination of the probable cause.            |
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