United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 1999

Event Notification Report for April 22, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/21/1999 - 04/22/1999

                              ** EVENT NUMBERS **

35494  35611  35612  35613  35614  35615  35616  35617  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35494       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 03/20/1999|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 20:20[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        03/20/1999|
+------------------------------------------------+EVENT TIME:        18:57[EST]|
| NRC NOTIFIED BY:  ERIC OLSON                   |LAST UPDATE DATE:  04/21/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JACK MCFADDEN        R1      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| RCIC INOPERABLE                                                              |
|                                                                              |
| The licensee declared Reactor Core Isolation Cooling (RCIC) inoperable       |
| because of a problem found during a surveillance.  Relay 13A-k30 contacts 1  |
| - 7 were found to have a high resistance.  These contacts close to provide   |
| the 'A' channel input to the RCIC high level shutdown.  A high resistance    |
| across these contacts may prevent the actuating relay (13A-k38) from         |
| energizing,  and thereby prevent a shutdown of RCIC on a high reactor vessel |
| water level.  The RCIC high water level shutdown requires both channels 'A'  |
| and 'B' signals be present to occur.                                         |
|                                                                              |
| The licensee entered a 14 day LCO because of this condition.   Repair        |
| efforts are in progress.  RCIC remains available for use in the event of an  |
| emergency.                                                                   |
|                                                                              |
| The licensee will inform the NRC resident inspector.                         |
|                                                                              |
| * * * UPDATE at 1903 on 04/21/99 by MIKE ENGLAND to JOLLIFFE * * *           |
|                                                                              |
| After further evaluation of this event, the licensee determined that the     |
| as-found condition of the RCIC System did not affect its operability since   |
| the last surveillance test.  NUREG-1022, Rev 1, Section 3.2.2, Item 3,       |
| discusses this instance.  Therefore, the RCIC System was not inoperable due  |
| to the above problem.  Thus, the licensee desires to retract this report.    |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The NRC Operations        |
| Officer notified the R1DO MOHAMED SHANBAKY.                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35611       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 04/20/1999|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 19:21[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        04/20/1999|
+------------------------------------------------+EVENT TIME:        18:32[EDT]|
| NRC NOTIFIED BY:  RAY McKINLEY                 |LAST UPDATE DATE:  04/22/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MOHAMED SHANBAKY     R1      |
|10 CFR SECTION:                                 |CURT COWGILL         R1      |
|ACCS 50.72(b)(1)(iv)     ECCS INJECTION         |R. BLOUGH/D. FLOREK  R1      |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |ART BURRITT          SRI     |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |WILLIAM BATEMAN      NRR     |
|                                                |CHARLES MILLER       IRO     |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| - AUTO REACTOR SCRAM FROM 100% POWER DUE TO LOSS OF MAIN FEEDWATER; ECCS     |
| INJECTION -                                                                  |
|                                                                              |
| AT 1832 ON 04/20/99, WITH UNIT 1 AT 100% POWER, ALL EIGHT CONDENSATE SYSTEM  |
| DEEP BED DEMINERALIZER OUTLET MOTOR OPERATED VALVES FAILED CLOSED POSSIBLY   |
| DUE TO A COMPUTER MALFUNCTION.  THE DEMINERALIZER BYPASS VALVES TRIPPED DUE  |
| TO THERMAL OVERLOADS AND FAILED TO OPEN, CAUSING ALL THREE STEAM DRIVEN MAIN |
| FEEDWATER PUMPS TO TRIP.  THE REACTOR VESSEL WATER LEVEL DROPPED FROM A      |
| NORMAL LEVEL OF +35 INCHES TO +12.5 INCHES, CAUSING THE REACTOR TO           |
| AUTOMATICALLY SCRAM FROM 100% POWER DUE TO LOW REACTOR VESSEL WATER LEVEL.   |
| ALL CONTROL RODS INSERTED COMPLETELY; HOWEVER, ROD #30-39 INSERTED SLOWLY.   |
| NO SAFETY/RELIEF VALVES LIFTED.  STEAM IS BEING DUMPED TO THE MAIN           |
| CONDENSER.                                                                   |
|                                                                              |
| REACTOR VESSEL WATER LEVEL FURTHER DROPPED TO -38 INCHES, CAUSING THE HIGH   |
| PRESSURE COOLANT INJECTION (HPCI)  AND THE REACTOR CORE ISOLATION COOLING    |
| (RCIC) SYSTEMS TO ACTUATE AND INJECT INTO THE REACTOR VESSEL.  THE REDUNDANT |
| REACTIVITY CONTROL SYSTEM INITIATED TO TRIP THE CIRCUIT BREAKERS FOR THE     |
| REACTOR RECIRCULATION PUMPS.  PRIMARY CONTAINMENT ISOLATION SYSTEM GROUPS    |
| 1B, 2A, 2B, 2C, 3, 6A, 6B, 6C, 7B, AND 8B ISOLATED.  THE DIVISION 'A'        |
| ATWS/RPT CIRCUIT BREAKER FOR THE 'A' RECIRC MOTOR GENERATOR SET FAILED TO    |
| TRIP, AS REQUIRED.  SMOKE WAS OBSERVED TO BE COMING FROM THE BREAKER.  THE   |
| BREAKER WAS MANUALLY TRIPPED FROM THE CONTROL ROOM AND THE SMOKING STOPPED.  |
| THE 'A' AND 'B' RECIRC MOTOR GENERATOR SET DRIVE MOTOR CIRCUIT BREAKERS ALSO |
| FAILED TO TRIP ON THE 13 kV BUS FAST TRANSFER.  THE BREAKERS WERE MANUALLY   |
| TRIPPED.                                                                     |
|                                                                              |
| REACTOR VESSEL WATER LEVEL DROPPED TO A LOW LEVEL OF -75 INCHES ABOUT 40     |
| SECONDS INTO THE EVENT (TOP OF ACTIVE FUEL IS  -161 INCHES).  THE HPCI AND   |
| RCIC SYSTEMS RECOVERED REACTOR VESSEL WATER LEVEL TO +25 INCHES, AT WHICH    |
| TIME CONTROL ROOM OPERATORS MANUALLY SECURED THE HPCI SYSTEM.  THE RCIC      |
| SYSTEM IS MAINTAINING REACTOR VESSEL WATER LEVEL AT +25 INCHES WITH REACTOR  |
| PRESSURE AT 875 PSIG AT AN INJECTION RATE OF 300 GPM.                        |
|                                                                              |
| PLANT OPERATORS ENCOUNTERED A PROBLEM WITH THE AUXILIARY STEAM SYSTEM AND    |
| THE MECHANICAL VACUUM PUMP.  THEY MANUALLY CLOSED THE MAIN STEAM ISOLATION   |
| VALVES.  THEY ARE CONTROLLING REACTOR VESSEL WATER LEVEL WITH THE RCIC       |
| SYSTEM AND REACTOR COOLANT SYSTEM PRESSURE WITH THE HPCI SYSTEM.             |
|                                                                              |
| UNIT 1 IS STABLE IN OPERATIONAL CONDITION 3 (HOT SHUTDOWN) AND COOLING DOWN  |
| TO COLD SHUTDOWN.  PRIMARY CONTAINMENT PARAMETERS ARE NORMAL.  THERE WAS NO  |
| RELEASE OF RADIOACTIVE MATERIAL.  RELEASE RATES ARE NORMAL.  THIS EVENT HAD  |
| NO IMPACT ON UNIT 2 WHICH IS IN OPERATIONAL CONDITION 5 IN A REFUELING       |
| OUTAGE.                                                                      |
|                                                                              |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND IS INVESTIGATING THIS   |
| EVENT.  THEY PLAN TO ISSUE A PRESS RELEASE.                                  |
|                                                                              |
| *** UPDATE ON 4/21/99 @ 0418 BY HUNTER TO GOULD ***                          |
|                                                                              |
| THE REACTOR IS IN OPCON 3 AT 350 PSIG CONTINUING TO COLD SHUTDOWN.           |
| CONDENSER VACUUM IS BEING REESTABLISHED IN ORDER TO RE-OPEN THE MSIVs AND    |
| SECURE HPCI FROM PRESSURE CONTROL MODE.  FEEDWATER SYSTEM IS BEING           |
| REPRESSURIZED TO REESTABLISH NORMAL FEED AND SECURE RCIC FROM LEVEL CONTROL  |
| MODE.                                                                        |
|                                                                              |
| ALSO THE "1A" AND "1B" MG SET DRIVE MOTOR BREAKERS DID NOT TRIP DURING THE   |
| TRANSIENT SINCE PLANT LOADS WERE PREVIOUSLY TRANSFERRED BY A REACTOR         |
| OPERATOR PRIOR TO THE TURBINE TRIP.  THE BREAKERS, THEREFORE, OPERATED AS    |
| DESIGNED.                                                                    |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
|                                                                              |
| THE REG 1 RDO(SHANBAKY) WAS NOTIFIED.                                        |
|                                                                              |
| *** UPDATE ON 4/22/99 @ 0220 BY HUNTER TO GOULD ***                          |
|                                                                              |
| THE UNIT IS IN COLD SHUTDOWN AS OF 2214 ON 4/21/99.   RESOLUTION OF          |
| EQUIPMENT PROBLEMS WHICH RESULTED IN THE SHUTDOWN ARE IN PROGRESS.           |
| ACTIVITIES ARE ALSO IN PROGRESS FOR PLANT STARTUP.                           |
|                                                                              |
| ALL CONTROL RODS INCLUDING 30-39 WENT FULL IN WITHIN THE REQUIRED TECHNICAL  |
| SPECIFICATION TIME.  ROD 30-39 POSITION INDICATION WAS LOST FOR              |
| APPROXIMATELY TWO MINUTES AFTER THE SCRAM, THEN THE "00" FULL IN POSITION    |
| INDICATION BECAME AVAILABLE AND REMAINED AVAILABLE THROUGHOUT THE SHUTDOWN.  |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE INFORMED.  THE REG 1 RDO(SHANBAKY) WAS        |
| INFORMED.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35612       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  MA DEPT OF PUBLIC HEALTH RCP         |NOTIFICATION DATE: 04/21/1999|
|LICENSEE:  AEA TECHNOLOGIES QSA, INC            |NOTIFICATION TIME: 15:00[EDT]|
|    CITY:  BURLINGTON               REGION:  1  |EVENT DATE:        04/21/1999|
|  COUNTY:                            STATE:  MA |EVENT TIME:        14:00[EDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  04/21/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MOHAMED SHANBAKY     R1      |
|                                                |FREDERICK COMBS      NMSS    |
+------------------------------------------------+JOSEPH GIITTER       IRO     |
| NRC NOTIFIED BY:  KEN TRAEGDE                  |DONNA MARIE PEREZ    IP      |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |LEN WERT             R2      |
+------------------------------------------------+DALE POWERS          R4      |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - SHIPMENT OF 8 Ir-192 SOURCES (866 CURIES TOTAL) FROM BURLINGTON, MA,       |
| OVERDUE IN MEXICO -                                                          |
|                                                                              |
| AT 1500 EDT ON 04/21/99, KEN TRAEGDE, MA DEPARTMENT OF PUBLIC HEALTH         |
| RADIATION CONTROL PROGRAM (RCP), BOSTON, MA, REPORTED THAT ON 04/16/99, AEA  |
| TECHNOLOGY QSA, INC, BURLINGTON, MA, SHIPPED A MODEL #855 SOURCE CHANGER     |
| LOADED WITH EIGHT Ir-192 SOURCES (TOTALING 866 CURIES) VIA FEDERAL EXPRESS   |
| TO VICONT SA DE CV, TALUCA, MEXICO.  THE UNDAMAGED PACKAGE HAS A TRANSPORT   |
| INDEX OF 1.4 (NORMAL READINGS OF 1.4 MR/HR AT ONE METER AND 55 MR/HR AT THE  |
| SURFACE) AT THE TIME OF SHIPMENT.                                            |
|                                                                              |
| THE SHIPMENT WAS SCHEDULED TO ARRIVE IN MEXICO ON 04/17/99.  AS OF 1400 EDT  |
| ON 04/21/99, THE RECEIVER HAD RECEIVED THE SHIPPING PAPERS BUT NOT THE       |
| CONTAINER.  THE SHIPPER AND FEDERAL EXPRESS HAVE LAUNCHED A FULL SEARCH FOR  |
| THE PACKAGE.  THE FEDEX HAZARDS MATERIAL INVESTIGATION TEAM HAS CONDUCTED A  |
| PHYSICAL SEARCH OF EXPRESS DEPOS IN BOSTON, MEMPHIS, LOS ANGELES, AND        |
| MEXICO.                                                                      |
|                                                                              |
| LICENSE NUMBERS ARE:  SU-1485, 12-8361, 52-0243, 54-0237, 58-0242.           |
|                                                                              |
| CONTACT THE NRC OPERATIONS OFFICER FOR TELEPHONE NUMBERS.                    |
|                                                                              |
| THE NRC OPERATIONS OFFICER NOTIFIED THE DOT NATIONAL RESPONSE CENTER         |
| (GAUTHIER), REPORT NUMBER 481132.                                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35613       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 04/21/1999|
|    UNIT:  [1] [2] []                STATE:  TX |NOTIFICATION TIME: 18:03[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/21/1999|
+------------------------------------------------+EVENT TIME:        10:15[CDT]|
| NRC NOTIFIED BY:  KLAY KLIMPLE                 |LAST UPDATE DATE:  04/21/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DALE POWERS          R4      |
|10 CFR SECTION:                                 |                             |
|HFIT 26.73               FITNESS FOR DUTY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| - FITNESS FOR DUTY REPORT -                                                  |
|                                                                              |
| AT 1015 CDT ON 04/21/99, A PLANT EMPLOYEE WAS DETERMINED TO BE UNDER THE     |
| INFLUENCE OF ALCOHOL DURING A RANDOM TEST.  THE EMPLOYEE'S ACCESS            |
| AUTHORIZATION TO THE PLANT HAS BEEN TERMINATED.  REFER TO THE HOO LOG FOR    |
| ADDITIONAL DETAILS.                                                          |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35614       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 04/21/1999|
|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 22:16[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        04/21/1999|
+------------------------------------------------+EVENT TIME:        21:17[EDT]|
| NRC NOTIFIED BY:  PHIL SANTINI                 |LAST UPDATE DATE:  04/21/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MOHAMED SHANBAKY     R1      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       99       Power Operation  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - UNIT 2 OUTSIDE ITS PLANT DESIGN BASIS FOR 30 SECONDS DUE TO A FAILED       |
| TRANSFER SWITCH -                                                            |
|                                                                              |
| DURING A SURVEILLANCE TEST, DC CONTROL POWER TRANSFER SWITCH #EDD-2 FAILED   |
| TO TRANSFER TO THE EMERGENCY POWER SUPPLY FOR 480-VOLT BUS 2A..  PLANT       |
| OPERATORS RESTORED DC CONTROL POWER TO 480-VOLT BUS 2A FROM ITS NORMAL POWER |
| SUPPLY IN APPROXIMATELY 30 SECONDS.                                          |
|                                                                              |
| THIS LOSS OF DC CONTROL POWER TO 480-VOLT BUS 2A PLACED UNIT 2 OUTSIDE ITS   |
| PLANT DESIGN BASIS FOR 30 SECONDS.                                           |
|                                                                              |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35615       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA                    REGION:  1  |NOTIFICATION DATE: 04/21/1999|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 22:30[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        04/21/1999|
+------------------------------------------------+EVENT TIME:        20:00[EDT]|
| NRC NOTIFIED BY:  DOUG PETERSON                |LAST UPDATE DATE:  04/21/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MOHAMED SHANBAKY     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       2        Startup          |2        Startup          |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - INADVERTENT TDAFW PUMP START DURING A MOVATS TEST -                        |
|                                                                              |
| During the restoration of motor operated valve #MOV-3505A from Motor         |
| Operated Valve Analysis and Test System (MOVATS) test #M-64.1.2, the turbine |
| driven auxiliary feedwater (TDAFW) pump inadvertently started.   A system    |
| engineer standing near the TDAFW pump called the control room and reported   |
| that the pump was running.  The control operator isolated the TDAFW system   |
| discharge to the steam generators with the discharge air operated valves,    |
| and the control room foreman directed the auxiliary operator to close the    |
| manual isolation valve which secured the steam to the TDAFW pump.            |
|                                                                              |
| This resulted in a 2F cooldown of the reactor coolant system (RCS) during   |
| the approximate 1 minute run of the TDAFW pump.                              |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35616       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 04/21/1999|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 23:19[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        04/21/1999|
+------------------------------------------------+EVENT TIME:        20:25[EDT]|
| NRC NOTIFIED BY:  CURT WOLTON                  |LAST UPDATE DATE:  04/22/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MOHAMED SHANBAKY     R1      |
|10 CFR SECTION:                                 |                             |
|AMED 50.72(b)(2)(v)      OFFSITE MEDICAL        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - POTENTIALLY CONTAMINATED INDIVIDUAL TRANSPORTED TO OFFSITE MEDICAL         |
| FACILITY -                                                                   |
|                                                                              |
| AT 2025 ON 04/21/99, A WORKER RECEIVED AN INJURY TO HIS HAND.  THE INJURY    |
| WAS SERIOUS ENOUGH THAT THE EMERGENCY MEDICAL TECHNICIAN AND HEALTH PHYSICS  |
| TECHNICIAN DID NOT REMOVE THE WORKERS GLOVE BEFORE TRANSPORTING HIM TO THE   |
| POTTSTOWN HOSPITAL FOR TREATMENT.  THE HEALTH PHYSICS TECHNICIAN             |
| SUBSEQUENTLY DETERMINED THAT THE INDIVIDUAL WAS NOT CONTAMINATED.            |
|                                                                              |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35617       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 04/22/1999|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 03:00[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        04/22/1999|
+------------------------------------------------+EVENT TIME:        01:31[CDT]|
| NRC NOTIFIED BY:  PFEFFER                      |LAST UPDATE DATE:  04/22/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MELVYN LEACH         R3      |
|10 CFR SECTION:                                 |                             |
|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                                   
+------------------------------------------------------------------------------+
| THE PLANT HAD A REACTOR SCRAM ON LOW REACTOR WATER LEVEL.                    |
|                                                                              |
| THE PLANT HAD A REACTOR SCRAM FROM 100% POWER DUE TO A LOW REACTOR WATER     |
| LEVEL.  CAUSE OF THE LOW REACTOR WASTER LEVEL IS UNKNOWN AND BEING           |
| INVESTIGATED.  ALL RODS FULLY INSERTED, NO ECCS INJECTION OCCURRED, AND NO   |
| SAFETY RELIEF VALVES LIFTED.  PLANT DID HAVE GROUP 2 AND GROUP 3 ISOLATIONS. |
| THE GROUP 3 ISOLATION HAS BEEN RESET, AND  PRESENTLY  THEY ARE IN PROGRESS   |
| OF RESETTING THE GROUP 2 ISOLATION.  THE MAIN CONDENSER IS THE HEAT SINK.    |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE INFORMED.                                     |
+------------------------------------------------------------------------------+