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Event Notification Report for April 23, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/22/1999 - 04/23/1999

                              ** EVENT NUMBERS **

35600  35611  35612  35617  35618  35619  35620  35621  35622  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35600       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 04/17/1999|
|    UNIT:  [] [] [3]                 STATE:  IL |NOTIFICATION TIME: 11:58[EDT]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        04/17/1999|
+------------------------------------------------+EVENT TIME:        09:59[CDT]|
| NRC NOTIFIED BY:  DAVE SLAGER                  |LAST UPDATE DATE:  04/23/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN JACOBSON        R3      |
|10 CFR SECTION:                                 |                             |
|ADEG 50.72(b)(1)(ii)     DEGRAD COND DURING OP  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          Y       99       Power Operation  |99       Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FAILURE OF A PRIMARY CONTAINMENT AIR SAMPLE RETURN ISOLATION VALVE TO MEET   |
| MAXIMUM INSERVICE TEST STROKE-TIME REQUIREMENTS                              |
|                                                                              |
| While performing quarterly valve stroke-time testing on Unit 3, a primary    |
| containment air sample return isolation valve exceeded its specified maximum |
| stroke-time limit.  The sample return line was isolated in accordance with   |
| Technical Specification 3.7.D for primary containment isolation valves, and  |
| this action satisfied the 4-hour limiting condition for operation action     |
| statement requirements.  The second in-line primary containment isolation    |
| system valve remains operable.                                               |
|                                                                              |
| The licensee stated that no other valves failed to meet the maximum          |
| stroke-time limits.  The licensee also stated that, during a test that was   |
| performed last month, the valve in question was identified as being in the   |
| 'Alert' time range for inservice test timing requirements and that it was    |
| being tested per the required increased testing frequency.  Corrective       |
| actions are being initiated, and troubleshooting activities are in           |
| progress.                                                                    |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
|                                                                              |
| *** UPDATE ON 4/23/99 @ 0443 BY GADBOIS TO GOULD ***  RETRACTION             |
|                                                                              |
| UPON FURTHER REVIEW, IT WAS DETERMINED THAT THIS EVENT DID NOT CONSTITUTE A  |
| REPORTABLE CONDITION SINCE THE PENETRATION HAD A OPERABLE REDUNDANT VALVE    |
| WHICH COULD HAVE ISOLATED THE CONTAINMENT PENETRATION.  THEREFORE, THEY ARE  |
| RETRACTING THIS EVENT.                                                       |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED.                                     |
|                                                                              |
| THE REG 3 RDO(LEACH) WAS NOTIFIED.                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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:  04/22/1999|
|  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        |                             |
|NOCM                     COMM ASST BRIEF        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   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 OF THE MA DEPARTMENT OF PUBLIC HEALTH   |
| RADIATION CONTROL PROGRAM (RCP) LOCATED IN BOSTON, MA, REPORTED THAT ON      |
| 04/16/99, AEA TECHNOLOGY QSA, INC., LOCATED IN BURLINGTON, MA, SHIPPED A     |
| MODEL #855 SOURCE CHANGER LOADED WITH 8 Ir-192 SOURCES (TOTALING 866 CURIES) |
| VIA FEDERAL EXPRESS TO VICONT S.A. DE C.V. LOCATED IN TOLUCA, MEXICO.  THE   |
| UNDAMAGED PACKAGE HAD A TRANSPORT INDEX OF 1.4 (NORMAL READINGS OF 1.4 mR/HR |
| AT 1 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 RECIPIENT (VICONT S.A. DE C.V.) HAD RECEIVED THE SHIPPING   |
| PAPERS BUT NOT THE CONTAINER.  THE SHIPPER AND FEDERAL EXPRESS HAVE LAUNCHED |
| A FULL SEARCH FOR THE PACKAGE.  THE FEDERAL EXPRESS HAZARDS MATERIAL         |
| INVESTIGATION TEAM HAS CONDUCTED A PHYSICAL SEARCH OF EXPRESS DEPOTS IN      |
| BOSTON, MEMPHIS, LOS ANGELES, AND MEXICO.                                    |
|                                                                              |
| THE LICENSE NUMBERS ARE:  SU-1485, 12-8361, 52-0243, 54-0237, AND 58-0242.   |
|                                                                              |
| CONTACT THE NRC OPERATIONS OFFICER FOR APPLICABLE TELEPHONE NUMBERS.         |
|                                                                              |
| THE NRC OPERATIONS OFFICER NOTIFIED THE DOT NATIONAL RESPONSE CENTER         |
| (GAUTHIER); REPORT NUMBER 481132.                                            |
|                                                                              |
| *********************************** UPDATE AT 1345 ON 04/22/99 BY JONES      |
| ***********************************                                          |
|                                                                              |
| The NRC entered the Monitoring Phase of Normal Mode at 1345 on 04/22/99.     |
| The NRC operations officer notified, the R1DO (Shanbaky), Region 1 (Miller), |
| IRO (Congel and Giitter), NMSS (Paperiello), RCT (Weinstein), PAO (Gagner),  |
| EDO's office (name unknown), and Chairman's office (Holian).  The RCT        |
| notified  FEMA (Dan Rishe), DOE (Thomas Yates), EPA (Ms. Reddy), USDA (Bob   |
| Conley), HHS/CDC (James Raab), and DOT (Rick Boyle).                         |
|                                                                              |
|                                                                              |
|                                                                              |
| *********************************** UPDATE AT 1600 ON 04/22/99 BY JONES      |
| ***********************************                                          |
|                                                                              |
| A Commissioner's Assistants Briefing was conducted at 1600 on 04/22/99. The  |
| following notifications were made (* office did not participate):  IRO (Joe  |
| Giitter, Erick Weinstein), Chairman Jackson (Dan Gillen), Commissioner Dicus |
| (Joel Lubenau), Commissioner Diaz (Patrick Castleman), Commissioner          |
| McGaffigan (Janet Schlueter), Commissioner Merrifield (JohnThoma), EDO (*),  |
| DEDE (*), NMSS (Don Cool, Carl Paperiello), NMSS EO (Fred Combs), R1DO       |
| (Mohamed Shanbaky), PAO (Joe Gilland), CAO (Thomas Madden), SECY (Andrew     |
| Bates), SP (Paul Lohaus), IP (Ron Hauber), R1 (Felicia Hinson, Jim Wiggins,  |
| etc), and R2 (Doug Collins, Chuck Hosey, Rich Woodruff).  The briefer was    |
| Fred Combs of NMSS.                                                          |
|                                                                              |
| 1610 Played back tape of briefing for EDO (Dan Martin) and DEDE (Jocelyn     |
| Mitchell).                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35618       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 04/22/1999|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 06:32[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        04/22/1999|
+------------------------------------------------+EVENT TIME:        01:45[CDT]|
| NRC NOTIFIED BY:  WELLER                       |LAST UPDATE DATE:  04/22/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MELVYN LEACH         R3      |
|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          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE LICENSEE DECLARED HPCI INOPERABLE AND ENTERED AN LCO ACTION STATEMENT.   |
|                                                                              |
| THE HPCI SYSTEM WAS DECLARED INOPERABLE FROM 0145 TO 0236 DUE TO MOISTURE IN |
| THE TURBINE STEAM INLET LINE.  A HPCI TURBINE INLET HIGH DRAIN POT LEVEL     |
| ANNUNCIATION WAS  RECEIVED AT 0145.  RCIC WAS VERIFIED OPERABLE.  THE        |
| STEAMLINE MANUAL DRAIN VALVE WAS OPENED AND THE DRAIN LINE ANNUNCIATOR       |
| CLEARED AT 0236.  HPCI WAS DECLARED OPERABLE AND PLACED IN STANDBY.          |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35619       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS           REGION:  1  |NOTIFICATION DATE: 04/22/1999|
|    UNIT:  [1] [2] []                STATE:  MD |NOTIFICATION TIME: 14:36[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        04/21/1999|
+------------------------------------------------+EVENT TIME:             [EDT]|
| NRC NOTIFIED BY:  BRUCE MONTGOMERY             |LAST UPDATE DATE:  04/22/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MOHAMED SHANBAKY     R1      |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - VOLUNTARY FITNESS-FOR-DUTY REPORT -                                        |
|                                                                              |
| A licensed operator was determined to be just below the limit by random      |
| test.  The employee's access to the plant was terminated.  Refer to the HOO  |
| Log for additional details.                                                  |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   35620       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  U.S. ARMY (ACALA)                    |NOTIFICATION DATE: 04/22/1999|
|LICENSEE:  U.S. ARMY (ACALA)                    |NOTIFICATION TIME: 17:22[EDT]|
|    CITY:  ROCK ISLAND              REGION:  3  |EVENT DATE:        04/22/1999|
|  COUNTY:                            STATE:  IL |EVENT TIME:             [CDT]|
|LICENSE#:  12-00722-06           AGREEMENT:  Y  |LAST UPDATE DATE:  04/22/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MOHAMED SHANBAKY     R1      |
|                                                |MELVYN LEACH         R3      |
+------------------------------------------------+FREDERICK COMBS      NMSS    |
| NRC NOTIFIED BY:  GAVIN ZIGLER                 |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|IBAC 30.50(b)(1)(i)      ACCESS DENIED >24 HRS  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DAMAGED VIAL CONTAINING 0.8 CURIES OF TRITIUM                                |
|                                                                              |
| During repair activities at Fort Drum, New York, in the arms room, an M224   |
| range indicator was apparently damaged.  The illuminator was checked working |
| prior to the maintenance and noted not to be working later.  The contained   |
| vial of tritium, 0.8 Ci, used in the illuminator is assumed to be broken.    |
| The device has been double bagged and the area secured until the results of  |
| surveys are obtained.  Survey results were sent off site as lab facilities   |
| are not available on site.  Investigation of the event is ongoing, and no    |
| further information is available at this time.                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35621       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER            REGION:  2  |NOTIFICATION DATE: 04/22/1999|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 19:02[EDT]|
|   RXTYPE: [3] B&W-L-LP                         |EVENT DATE:        04/22/1999|
+------------------------------------------------+EVENT TIME:        18:08[EDT]|
| NRC NOTIFIED BY:  BILL BANDHAUGER              |LAST UPDATE DATE:  04/22/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LEN WERT             R2      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POSSIBLE OVERLOAD OF ESF TRANSFORMER IN AN ABNORMAL OPERATING PROCEDURE      |
| FOUND                                                                        |
|                                                                              |
| While investigating a previous LER concerned with backfeed the following was |
| discovered:                                                                  |
|                                                                              |
| "During a scenario involving a Loss of Off-Site Power resulting from a loss  |
| of the BEST and Startup transformers, the Crystal River Unit 3 abnormal      |
| operating procedures could have caused an overload of the safety-related     |
| Engineered Safeguards 4160V to 480V transformer.  Assuming a single failure  |
| of the 'B' side diesel generator, power could have been unavailable to both  |
| trains of 480V Engineered safeguards loads.                                  |
|                                                                              |
| "This condition is considered reportable per 10 CFR 50.72(b)(l)(ii)(B) and   |
| 10 CFR 50.73(a)(2)(ii)(B) as a condition outside of the design basis of the  |
| plant.                                                                       |
|                                                                              |
| "Loads have been identified which can be administratively maintained off     |
| during this scenario to avoid the overload condition, and therefore, the     |
| transformer is operable."                                                    |
|                                                                              |
| This is under investigation, and further actions will be forthcoming.        |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35622       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 04/23/1999|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 04:33[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        04/23/1999|
+------------------------------------------------+EVENT TIME:        02:14[CDT]|
| NRC NOTIFIED BY:  WELLER                       |LAST UPDATE DATE:  04/23/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MELVYN LEACH         R3      |
|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          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HPCI SYSTEM DECLARED INOPERABLE AND PLANT ENTERED LCO ACTION STATEMENT       |
|                                                                              |
| THE HPCI SYSTEM WAS DECLARED INOPERABLE FROM 0214 TO 0220 DUE TO MOISTURE IN |
| THE TURBINE STEAM INLET LINE.  A 14-DAY LCO ACTION STATEMENT WAS ENTERED,    |
| AND RCIC WAS VERIFIED OPERABLE.  HPCI TURBINE INLET HIGH DRAIN POT LEVEL     |
| ANNUNCIATION WAS RECEIVED  DUE TO STROKING MO-2036 (TURBINE STEAM SUPPLY     |
| VALVE) AS PART OF THE REACTOR SHUTDOWN PROCEDURE AT REACTOR PRESSURE OF 500  |
| PSIG.  THE STEAM LINE MANUAL DRAIN VALVE WAS OPENED, AND THE ANNUNCIATOR     |
| CLEARED AT 0220.  HPCI DECLARED OPERABLE AND IN STANDBY.  THE 14-DAY LCO     |
| ACTION STATEMENT WAS ALSO EXITED AT 0220.                                    |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED.                                     |
+------------------------------------------------------------------------------+