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Event Notification Report for January 3, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/30/1999 - 01/03/2000

                              ** EVENT NUMBERS **

36396  36487  36539  36544  36548  36549  36550  36551  36552  36553  36554  36555 


!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   36396       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  PRINCETON MEDICAL CENTER             |NOTIFICATION DATE: 11/04/1999|
|LICENSEE:  PRINCETON MEDICAL CENTER             |NOTIFICATION TIME: 14:30[EST]|
|    CITY:  PRINCETON                REGION:  1  |EVENT DATE:        11/04/1999|
|  COUNTY:                            STATE:  NJ |EVENT TIME:        09:15[EST]|
|LICENSE#:  29-06750-01           AGREEMENT:  N  |LAST UPDATE DATE:  12/30/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MOHAMED SHANBAKY     R1      |
|                                                |JOSIE PICCONE        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  EDWARD BACZA                 |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33(a)            MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POTENTIAL MISADMINISTRATION INVOLVING DISLODGED BRACHYTHERAPY SOURCE         |
|                                                                              |
| AT APPROXIMATELY 0915EST AN ELDERLY FEMALE PATIENT NOTIFIED HOSPITAL STAFF   |
| THAT A BRACYTHERAPY SOURCE (Cs-137 - 21.8 MILLIGRAM RADIUM EQUIVALENT) HAD   |
| BECOME DISLODGED.  HOSPITAL STAFF CONTACTED THE PHYSICIAN THAT HAD INSERTED  |
| THE SOURCE AND WAS INSTRUCTED TO RELOCATE THE APPLICATOR TO THE FOOT OF THE  |
| BED.  THE HOSPITAL PHYSICIST ESTIMATES THAT THE SOURCE WAS IN THE VICINITY   |
| OF THE PATIENT'S THIGH FOR APPROXIMATELY 15 MINUTES AND AT THE FOOT THE BED  |
| FOR ANOTHER 18 MINUTES BEFORE BEING PLACED IN A LEAD PIG.  THE ATTENDING     |
| PHYSICIAN DOES NOT INTEND ANY ADDITIONAL EXPOSURE SINCE THE SOURCE REMAINED  |
| IN PLACE FOR 18.45 OF THE 22.79 HOURS PRESCRIBED.  NO ADVERSE HEALTH         |
| CONSEQUENCES ARE EXPECTED.                                                   |
|                                                                              |
|                                                                              |
| * * * UPDATE AT 0900 ON 12/30/99 BY BACZA, TAKEN BY WEAVER * * *             |
|                                                                              |
| THE LICENSEE REQUESTED THIS EVENT BE RETRACTED.   REGIONAL INSPECTORS        |
| CONDUCTED AN INVESTIGATION OF THIS EVENT AND DETERMINED THAT NO              |
| MISADMINISTRATION HAD OCCURRED.                                              |
| HOO NOTIFIED RDO (BELLAMY).                                                  |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36487       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND           REGION:  3  |NOTIFICATION DATE: 12/04/1999|
|    UNIT:  [] [2] []                 STATE:  MN |NOTIFICATION TIME: 01:17[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        12/03/1999|
+------------------------------------------------+EVENT TIME:        22:30[CST]|
| NRC NOTIFIED BY:  MICHAEL T. MURPHY            |LAST UPDATE DATE:  12/30/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GEOFFREY WRIGHT      R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ACTUATION OF TWO UNIT 2 AUXILIARY BUILDING NORMAL RADIATION MONITORS DURING  |
| PERFORMANCE OF VENTILATION SYSTEM SURVEILLANCE TESTING                       |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 2230 [CST] during normal Unit 1 [and] 2 [reactor coolant system]         |
| sampling, a [high] radiation and [emergency safety feature (ESF)] actuation  |
| signal was received on [radiation monitors] 2R-30 and 2R-37 ([auxiliary      |
| building] normal exhaust monitors).  Normal exhaust was off, and [the        |
| auxiliary] building special ventilation system was in operation while        |
| performing [surveillance procedure] SP-1172, Monthly Ventilation System      |
| Operation.  Alarm response procedures were completed for high radiation on   |
| 2R-30 [and 2R-]37.  [The] duty chemist was informed, the sample was secured, |
| and 2R-30 [and 2R-]37 levels [then] returned normal.  At 2255 [CST,] the     |
| actuating signals were reset, and all equipment returned to normal."         |
|                                                                              |
| The licensee stated that all systems functioned as required in response to   |
| the high radiation and ESF actuation signal.  The cause of the ESF signal is |
| under investigation.  At the time of this event notification, both units     |
| were operating at 100% power.                                                |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * UPDATE AT 1251 ON 12/30/99 BY DALE JOHNSON TO JOLLIFFE * * *           |
|                                                                              |
| The licensee desires to retract this event because the regulation does not   |
| require reporting of an actuation of the Auxiliary Building Special          |
| Ventilation System if it was started by an invalid start signal.  The        |
| licensee determined that the actuation in this instance was initiated by an  |
| invalid start signal.                                                        |
|                                                                              |
| The licensee plans to notify the NRC Resident Inspector.                     |
|                                                                              |
| The NRC Operations Officer notified the R3DO Bruce Burgess.                  |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36539       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 12/25/1999|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 07:45[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        12/25/1999|
+------------------------------------------------+EVENT TIME:        07:00[EST]|
| NRC NOTIFIED BY:  BRIAN SULLIVAN               |LAST UPDATE DATE:  12/30/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RICHARD CONTE        R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOW SWITCHGEAR ROOM TEMPERATURE DUE TO DEGRADED HEATING, VENTILATION, AND    |
| AIR  CONDITIONING (HVAC) COMPONENTS IN CONJUNCTION WITH COLD WEATHER         |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "[The] 'A' switchgear room temperature [was] outside the [final safety       |
| analysis report] design temperature limit of 60F.  [The] temperature        |
| decreased to 59F due to degraded [heating, ventilation, and air             |
| conditioning (HVAC)] components.  No known operability issues have been      |
| identified."                                                                 |
|                                                                              |
| The licensee stated that the temperature in the 'A' switchgear room has      |
| returned to 60F but that cold weather is expected again tonight.  The       |
| licensee is currently in the process of repairing the degraded HVAC          |
| components.                                                                  |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * UPDATE AT 1045 ON 12/30/99 BY MANTENFEL, TAKEN BY WEAVER * * *         |
|                                                                              |
| An engineering evaluation determined that the equipment remained operable at |
| the as found temperature.  The licensee is retracting this event.  The NRC   |
| resident will be informed.  The Operations center notified the RDO           |
| (Bellamy).                                                                   |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36544       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 12/29/1999|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 06:15[EST]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        12/29/1999|
+------------------------------------------------+EVENT TIME:        04:20[CST]|
| NRC NOTIFIED BY:  DARYL NOHR                   |LAST UPDATE DATE:  12/30/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE BURGESS        R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       90       Power Operation  |80       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HPCI INOPERABLE                                                              |
|                                                                              |
| During QCOS 2300-28 'HPCI Turning Gear Logic Functional Test'  the HPCI      |
| turning gear failed to engage.  The test was stopped and HPCI was placed on  |
| the turning gear from a normal standby lineup and removed from the turning   |
| gear using QCOP 2300-13 'HPCI Turning Gear Operation'.   Per analysis the    |
| HPCI turbine must be able to be remotely placed on the turning gear.  Since  |
| HPCI  failed to go on gear during the logic test it was declared inoperable  |
| at 0420.   A 14 day LCO was centered per Tech Spec 3.5.A action 3.           |
|                                                                              |
| The Licensee will notify the NRC resident inspector.                         |
|                                                                              |
| * * * UPDATE AT 1839 ON 12/30/99 BY TONY SCOTT TO JOLLIFFE * * *             |
|                                                                              |
| The licensee desires to retract this event due to the test method being used |
| during the test.  During the test, the HPCI turning gear would have          |
| functioned, as required.                                                     |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| The NRC Operations Officer notified the R3DO Bruce Burgess.                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36548       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE                   REGION:  2  |NOTIFICATION DATE: 12/30/1999|
|    UNIT:  [] [2] []                 STATE:  GA |NOTIFICATION TIME: 05:53[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        12/30/1999|
+------------------------------------------------+EVENT TIME:        04:56[EST]|
| NRC NOTIFIED BY:  LEE MANSFIELD                |LAST UPDATE DATE:  12/30/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHRIS CHRISTENSEN    R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     M/R        N       0        Startup          |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR TRIP FROM MODE TWO                                                   |
|                                                                              |
| "Plant Vogtle Unit 2 was in a reactor startup following repair of a          |
| Feedwater Heater. During withdrawal of Control Bank B to 85 steps, Control   |
| Bank B rod B6 became misaligned from its bank by Digital Rod position        |
| indication System (DRPI) indication and the demand step counters. The Rod    |
| Control System Malfunction abnormal operating procedure was entered and the  |
| reactor was manually tripped at 0456 hours EST due to a misalignment of      |
| greater than 12 steps between DRPI and the demand step counters. All rods    |
| inserted as expected during the trip and no other anomalies were noted. The  |
| reactor is currently stable in Mode 3."                                      |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36549       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 12/30/1999|
|    UNIT:  [1] [2] []                STATE:  MI |NOTIFICATION TIME: 17:42[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        12/30/1999|
+------------------------------------------------+EVENT TIME:        16:55[EST]|
| NRC NOTIFIED BY:  DEAN BRUCK                   |LAST UPDATE DATE:  12/30/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE BURGESS        R3      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP           |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - Unit 1 and 2 valves have the potential to experience pressure locking      |
| under post-LOCA conditions -                                                 |
|                                                                              |
| Motor operated valves ICM-305 and ICM-306, for both units, have been         |
| identified as having the potential to experience pressure locking under      |
| post-LOCA conditions. These valves are the ECCS suction valves from the      |
| recirculation sump that are opened to supply water to the Residual Heat      |
| Removal (RHR) pump suction, which in turn supplies flow to the suction of    |
| the safety injection and charging pumps.  Calculations performed during a    |
| review of Generic Letter 95-07 determined that the valve operators are       |
| potentially incapable of opening the valves under pressure locking           |
| conditions, which result from the post LOCA temperature rise.                |
|                                                                              |
| Additionally, Units 1 and 2 IMO-330 and IMO-331, the RHR to upper            |
| containment spray shutoff valves, have been determined to experience the     |
| same post-LOCA pressure locking problem. These valves provide isolation of   |
| RHR flow to the upper containment spray headers, and are opened during the   |
| recirculation phase of an accident if upper spray is needed.                 |
|                                                                              |
| Design changes are being developed to modify the valves to eliminate the     |
| potential for pressure locking.                                              |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36550       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 12/30/1999|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 17:53[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        12/30/1999|
+------------------------------------------------+EVENT TIME:        16:00[CST]|
| NRC NOTIFIED BY:  BILL GREEN                   |LAST UPDATE DATE:  12/30/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GARY SANBORN         R4      |
|10 CFR SECTION:                                 |RICHARD WESSMAN      NRR     |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |JOSEPH GIITTER       IRO     |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - TS REQUIRED PLANT SHUTDOWN DUE TO 23 GPD REACTOR EQUIPMENT COOLING SYSTEM  |
| LEAK -                                                                       |
|                                                                              |
| AT 1600 CST ON 12/30/99, THE LICENSEE DECLARED THE REACTOR EQUIPMENT COOLING |
| (REC) SYSTEM INOPERABLE DUE TO THE REC SYSTEM LEAK RATE BEING APPROXIMATELY  |
| 3 INCHES OF SURGE TANK LEVEL PER DAY (APPROXIMATELY 23 GALLONS PER DAY).     |
| THIS LEAK RATE DOES NOT ALLOW THE REC SYSTEM TO REMAIN OPERABLE 30 DAYS      |
| POST-LOCA AS REQUIRED BY THE UFSAR, SECTION X-6, PAGE X-6-8.  TECH SPEC LCO  |
| 3.7.3, CONDITION B, REQUIRES THE PLANT TO BE IN MODE 3 IN 12 HOURS AND MODE  |
| 4 IN 36 HOURS.                                                               |
|                                                                              |
| ONE OF TWO EDGs (#2 EDG) AND THE 'B' SERVICE WATER BOOSTER PUMP ARE          |
| INOPERABLE.                                                                  |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36551       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA                  REGION:  2  |NOTIFICATION DATE: 12/30/1999|
|    UNIT:  [] [2] []                 STATE:  SC |NOTIFICATION TIME: 20:07[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        12/30/1999|
+------------------------------------------------+EVENT TIME:        18:21[EST]|
| NRC NOTIFIED BY:  BOB WHITE                    |LAST UPDATE DATE:  01/02/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHRIS CHRISTENSEN    R2      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - AUTO REACTOR TRIP FROM 100% POWER FOR UNKNOWN REASONS -                    |
|                                                                              |
| AT 1821 ON 12/30/99, UNIT 2 AUTO TRIPPED FROM 100% POWER FOR UNKNOWN REASONS |
| CAUSING A MAIN TURBINE TRIP.  THE MAIN FEEDWATER SYSTEM ISOLATED AND THE     |
| AUXILIARY FEEDWATER SYSTEM AUTOSTARTED.  ALL CONTROL RODS INSERTED           |
| COMPLETELY.  STEAM IS BEING DUMPED TO THE MAIN CONDENSER.  INTERMEDIATE      |
| RANGE MONITOR N-35 APPEARED UNDERCOMPENSATED, REQUIRING A MANUAL RESET OF    |
| THE SOURCE RANGES.                                                           |
|                                                                              |
| UNIT 2 IS STABLE IN MODE 3 (HOT STANDBY).                                    |
|                                                                              |
| THE LICENSEE IS INVESTIGATING THE CAUSE OF THE TRIP.                         |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
|                                                                              |
| * * * UPDATE AT 1616 ON 01/02/00 BY GARY HAMILTON TO JOLLIFFE * * *          |
|                                                                              |
| THE CAUSE OF THE REACTOR TRIP WAS A MAIN TURBINE TRIP ABOVE THE P-9          |
| PERMISSIVE INTERLOCK (WITH REACTOR POWER BELOW 50% POWER, THE REACTOR        |
| REMAINS AT POWER IF THE MAIN TURBINE TRIPS).  THE MAIN TURBINE TRIPPED DUE   |
| TO TWO WIRES SHORTING TOGETHER ON AN ELECTRICAL CONNECTOR OF THE ELECTRIC    |
| TRIP SOLENOID VALVE IN THE MAIN TURBINE CONTROL CIRCUITRY.                   |
|                                                                              |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR.                            |
|                                                                              |
| THE NRC OPERATIONS OFFICER NOTIFIED THE R2DO CHRIS CHRISTENSEN.              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36552       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 12/30/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 21:45[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        12/30/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        11:30[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  12/30/1999|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |BRUCE BURGESS        R3      |
|  DOCKET:  0707001                              |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC WALKER                  |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)(i)     ACCID MT EQUIP FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NOTE:  THIS EVENT IS A CONTINUATION OF EVENT #35790.                         |
|                                                                              |
| At 1130 CST on 12/30/99, the Plant Shift Superintendent (PSS) was notified   |
| that during walkdowns of the High Pressure Fire Water System in C-337, a     |
| total of 13 corroded sprinkler heads were discovered in System B-2.  The     |
| system was declared inoperable and actions were taken as required by the     |
| technical safety requirement.  The PSS determined that an update to this     |
| event report is required.                                                    |
|                                                                              |
| The NRC Resident Inspector has been notified of this event.                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36553       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 12/31/1999|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 03:11[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        12/31/1999|
+------------------------------------------------+EVENT TIME:        01:11[EST]|
| NRC NOTIFIED BY:  DOUG AMTSFIELD               |LAST UPDATE DATE:  12/31/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |RANDY BLOUGH         R1      |
|10 CFR SECTION:                                 |RICHARD WESSMAN      NRR     |
|AAEC 50.72 (a) (1) (I)   EMERGENCY DECLARED     |JOSEPH GIITTER       IRO     |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |KEN CYBOCH           FEMA    |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT - MAIN TRANSFORMER FAILURE                                     |
|                                                                              |
| A main transformer insulator failure led to a catastrophic failure of the    |
| main transformer.  This in turn led to a turbine trip and reactor scram.     |
| The plant response to the transient was normal and the plant is now stable   |
| in mode 3.  Decay heat is being removed by dumping steam to the main         |
| condenser.  Reactor vessel water level is being maintained by the condensate |
| and feed systems.  Offsite power was maintained throughout the event and no  |
| safety related equipment has been damaged.  The event occurred at 0111 and   |
| the Unusual Event was declared at 0255.  The Reactor Recirculation Pump      |
| EOC-RPT (End of Cycle Recirc Pump Trip) breakers tripped as expected due to  |
| the turbine stop valve and turbine control valve closures.                   |
|                                                                              |
| The unusual event was declared because of the potential impact of the        |
| failure on other plant components in the vicinity of the transformer.  The   |
| licensee has notified the resident inspector.                                |
|                                                                              |
| * * * UPDATE AT 0431 ON 12/31/99 BY AMTSFIELD, RECEIVED BY WEAVER * * *      |
|                                                                              |
| The unusual event was terminated at 0400.  Damage was limited to the main    |
| transformer phase 'B' insulator with only ancillary damage to surrounding    |
| equipment and no damage to safety related equipment.  The licensee has       |
| notified state and local governments of the event and a press release will   |
| be issued.                                                                   |
|                                                                              |
| The operations center notified R1 (Blough); IRO (Giitter); EO (Wessman);     |
| FEMA (CYBOCH)                                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36554       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND        REGION:  1  |NOTIFICATION DATE: 12/31/1999|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 11:09[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP            |EVENT DATE:        12/31/1999|
+------------------------------------------------+EVENT TIME:             [EST]|
| NRC NOTIFIED BY:  MARK JANES                   |LAST UPDATE DATE:  12/31/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROBERT SUMMERS       R1      |
|10 CFR SECTION:                                 |JOHN DAVIDSON        NMSS    |
|NINF                     INFORMATION ONLY       |RICHARD ROSANO       NRR     |
|                                                |JOHN WHITE           R1      |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| NON-CREDIBLE BOMB THREAT.                                                    |
|                                                                              |
| CONTACT THE NRC OPERATIONS CENTER FOR ADDITIONAL DETAILS.                    |
|                                                                              |
| LICENSEE WILL NOTIFY THE NRC RESIDENT.                                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36555       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD             REGION:  3  |NOTIFICATION DATE: 12/31/1999|
|    UNIT:  [1] [] []                 STATE:  IA |NOTIFICATION TIME: 13:13[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        12/31/1999|
+------------------------------------------------+EVENT TIME:        11:33[CST]|
| NRC NOTIFIED BY:  BRUCE ROWLAND                |LAST UPDATE DATE:  12/31/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE BURGESS        R3      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PHYSICAL SECURITY EVENT -                                                    |
|                                                                              |
| MINIMUM SECURITY PERSONNEL STAFFING REQUIREMENTS NOT MET FOR 22 MINUTES.     |
| COMPENSATORY MEASURES IMMEDIATELY TAKEN UPON DISCOVERY.  THE LICENSEE PLANS  |
| TO NOTIFY THE NRC RESIDENT INSPECTOR.  CONTACT THE NRC OPERATIONS OFFICER    |
| FOR ADDITIONAL DETAILS.                                                      |
+------------------------------------------------------------------------------+