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Event Notification Report for March 2, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/01/2000 - 03/02/2000

                              ** EVENT NUMBERS **

36657  36739  36740  36741  36742  36743  36744  36745  36746  36747  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36657       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 02/03/2000|
|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 16:08[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        02/03/2000|
+------------------------------------------------+EVENT TIME:        11:14[CST]|
| NRC NOTIFIED BY:  VERN CARLSON                 |LAST UPDATE DATE:  03/01/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CLAUDE JOHNSON       R4      |
|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       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BOTH TRAINS OF POST ACCIDENT H2 ANALYZERS DECLARED ADMINISTRATIVELY          |
| INOPERABLE.                                                                  |
|                                                                              |
| During an ongoing review of calculations for "Normal and Accident Gamma and  |
| Beta Doses for Mechanical Equipment Qualifications"  it was discovered that  |
| an inaccurate assumption was made concerning the operation of the            |
| Containment and Drywell post accident hydrogen monitoring system.  This      |
| inaccurate assumption could lead to the sample isolation valves receiving    |
| more radiation exposure than assumed in the calculations curing a design     |
| bases accident.  This extra radiation exposure could cause deterioration of  |
| the valve seats and prevent them from sealing properly.  With the valves     |
| leaking the indicated hydrogen concentrations could be non-conservatively    |
| low leading to improper actions during an accident.  This condition affects  |
| both safety trains of the post accident hydrogen analyzers.  The actual      |
| affect is still indeterminate however both trains have been conservatively   |
| declared administratively inoperable.  The system is still in a standby      |
| lineup and is expected to continue to perform its function during the early  |
| stages of an accident.  Engineering is continuing to evaluate the actual     |
| affect of the increased radiation exposure on the equipment.  The NRC        |
| Resident Inspector will be informed of this event by the licensee.           |
|                                                                              |
| * * * UPDATE AT 1713 ON 3/1/2000, BY FELTNER RECEIVED BY WEAVER * * *        |
|                                                                              |
| On 2/3/2000, (event notification 36657), River Bend Station reported that    |
| the Containment and Drywell hydrogen monitor system had been conservatively  |
| declared inoperable.  The inoperability was based on the impact of an        |
| inadequate assumption in a post accident dose calculation for the system     |
| sample valves.  This could have lead to more post accident radiation         |
| exposure than determined in the original calculation, which may have lead to |
| failure of the sample valves to properly seat.   At the time of the original |
| report. the actual affect of the condition on the valves was indeterminate   |
| and the system was declared inoperable. Engineering re-evaluated the         |
| condition as documented in a revision to calculation PR(c) 547. This         |
| calculation found that the original assumption in the calculation did not    |
| impact system operability.  The calculation states that the potential doses  |
| due to plateout in the system would be negligible when compared to the       |
| airborne beta doses, and therefore the doses presented in the original       |
| calculation conservatively represent dose expected following a design basis  |
| accident.   Based on this the system it was determined to be operable, and   |
| the condition not reportable.  The licensee notified the NRC resident        |
| inspector.  The NRC Operations Center notified the RDO (Cain).               |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36739       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 03/01/2000|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 06:27[EST]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        03/01/2000|
+------------------------------------------------+EVENT TIME:        05:30[EST]|
| NRC NOTIFIED BY:  MIKE PHILIPPON               |LAST UPDATE DATE:  03/01/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JIM CREED, IAT       R3      |
|10 CFR SECTION:                                 |MIKE JORDAN, DO      R3      |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |DICK ROSANO, IAT     NRR     |
|                                                |CHRIS GRIMES, EO     NRR     |
|                                                |MIKE WEBER, IAT      NMSS    |
|                                                |BRIAN SMITH, EO      NMSS    |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       97       Power Operation  |97       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - OVERDUE SHIPMENT OF NEW FUEL -                                             |
|                                                                              |
| The licensee reported that a shipment of new fuel from General Electric was  |
| due to arrive onsite at 0500 on 03/01/00.  The shipper (Kindrick Trucking    |
| Company) was contacted and the shipment was located in Canton, Ohio, at 0550 |
| on 03/01/00.  The new expected arrival time is 0900 on 03/01/00.  The        |
| licensee notified the NRC Resident Inspector.                                |
|                                                                              |
| * * * UPDATE AT 0955 ON 03/01/00 BY PAT FALLON TO JOLLIFFE * * *             |
|                                                                              |
| General Electric notified the licensee that the reason for the delay was     |
| that a tarp on the nuclear fuel truck blew off and is being recovered and    |
| reinstalled on the truck.  Estimated time of arrival onsite now is 1300 on   |
| 03/01/00.  The licensee plans to notify the NRC Resident Inspector.  The NRC |
| Operations Officer notified R3 IAT Jim Creed, R3DO Mike Jordan, NRR IAT Dick |
| Rosano, NRR EO Chris Grimes, NMSS IAT Mike Weber, NMSS EO Brian Smith, and   |
| IRO Frank Congel.                                                            |
|                                                                              |
| * * * UPDATE AT 1254 ON 3/1/2000 BY COSEO TAKEN BY WEAVER * * *              |
|                                                                              |
| The licensee is retracting this event.                                       |
|                                                                              |
| "10 CFR 73.67(g)(3) states that each licensee, either shipper or receiver,   |
| who arranges for the physical protection of special nuclear material of low  |
| strategic significance while in transit or who takes delivery of such        |
| material free on board (f.o.b.) the point at which it is delivered to a      |
| carrier for transport shall: conduct immediately a trace investigation of    |
| any shipment that is lost or unaccounted for after the estimated arrival     |
| time and notify the NRC Operations Center within one hour after the          |
| discovery of the loss of the shipment and within one hour after recovery of  |
| or accounting for such lost shipment in accordance with the provisions of 10 |
| CFR 73.71. In accordance with a General Electric (GE) letter to Detroit      |
| Edison, dated August 12, 1992, GE stated that they are responsible for       |
| in-transit physical protection of fuel shipments from Wilmington to the      |
| Fermi 2 site. Therefore, the notification to the NRC regarding lost or       |
| unaccounted for special nuclear material of low strategic significance while |
| in transit should have been completed by GE.                                 |
|                                                                              |
| "However, further evaluation of the event revealed that communication        |
| between GE and the truck driver regarding the trucks location and problem,   |
| did occur. Therefore, the truck was never lost or unaccounted for by GE. The |
| delay in the estimated arrival time was apparently due to problems with the  |
| truck during the transit. Based on the above information and the fact that   |
| the shipment was never lost or unaccounted for, the reporting requirements   |
| of 10 CFR 73.71 do not apply in this event. Therefore, Detroit Edison is     |
| retracting the 1-hour notification."                                         |
|                                                                              |
| The licensee notified the NRC resident inspector and the Operations Center   |
| notified the RDO (Jordan), EO (Smith), IRO (Congel).                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   36740       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  FL BUREAU OF RADIATION CONTROL       |NOTIFICATION DATE: 03/01/2000|
|LICENSEE:  HALIFAX MEDICAL CENTER               |NOTIFICATION TIME: 08:58[EST]|
|    CITY:  DAYTONA BEACH            REGION:  2  |EVENT DATE:        01/31/2000|
|  COUNTY:                            STATE:  FL |EVENT TIME:        12:00[EST]|
|LICENSE#:  FL-194-3              AGREEMENT:  Y  |LAST UPDATE DATE:  03/01/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LEN WERT             R2      |
|                                                |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  CHARLIE ADAMS                |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|LADM 35.33(a)            MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - MEDICAL MISADMINISTRATION EVENT IN AN AGREEMENT STATE -                    |
|                                                                              |
| On 01/31/00, during the second of three applicator treatments of 3.43 curies |
| of Ir-192 at Halifax Medical Center, Daytona Beach, FL, the hospital         |
| therapist switched the location numbers and the patient was treated at a     |
| location of 898 mm instead of 989 mm. The result was that the majority of    |
| the dose went to the wrong treatment site.  The maximum dose received was    |
| 1600 Rads.  The doctor and the patient have been notified.  No damage to the |
| patient is expected.  The patient has since completed the full course of     |
| treatments which were compensated for the error.  A written report has been  |
| filed with Florida.  This incident is still under investigation by Florida.  |
| Florida Incident Number FL00-018.                                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36741       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  US ARMY (ACALA)                      |NOTIFICATION DATE: 03/01/2000|
|LICENSEE:  US ARMY (ACALA)                      |NOTIFICATION TIME: 10:36[EST]|
|    CITY:  ROCK ISLAND              REGION:  3  |EVENT DATE:        02/17/2000|
|  COUNTY:                            STATE:  IL |EVENT TIME:        12:00[CST]|
|LICENSE#:  12-00722-06           AGREEMENT:  Y  |LAST UPDATE DATE:  03/01/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MIKE JORDAN          R3      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TIM MOHS                     |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|IBAD 30.50(b)(1)(ii)     MATL >5X LOWEST LIMIT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - M1A1 COLLIMATOR WAS OVERPRESSURIZED AND RUPTURED -                         |
|                                                                              |
| On 02/17/00, while the Third Army Corp Maintenance Unit from Fort            |
| Wainwright, AK, was performing a purge for Fort Hood units during training   |
| at Fort Irwin, CA, an M1A1 collimator containing 10 curies of tritium was    |
| overpressurized and ruptured.  The M1A1 collimator was double bagged but not |
| reported to the Fort Irwin Radiation Safety Officer.  On 02/29/00, when the  |
| military van containing the M1A1 collimator was being readied for shipment   |
| back to Fort Wainwright, the broken M1A1 collimator was noted and surveyed.  |
| The survey came back contaminated (as high as 255,000 dpm).  The military    |
| van is being held at Army/Marine Base, Yermo Annex, Barstow, CA, by Fort     |
| Hood personnel.  Results are pending.  The two individuals who performed the |
| purge are being bioassayed.  Results are pending.  Further investigation of  |
| what happened and surveys to determine contamination status are ongoing.     |
| Army Incident #00-12.                                                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   36742       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ALLEGHENY GENERAL HOSPITAL           |NOTIFICATION DATE: 03/01/2000|
|LICENSEE:  ALLEGHENY GENERAL HOSPITAL           |NOTIFICATION TIME: 11:38[EST]|
|    CITY:  PITTSBURGH               REGION:  1  |EVENT DATE:        03/01/2000|
|  COUNTY:  ALLEGHENY                 STATE:  PA |EVENT TIME:        10:30[EST]|
|LICENSE#:  37-0131704            AGREEMENT:  N  |LAST UPDATE DATE:  03/01/2000|
|  DOCKET:  03033730                             |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JIM TRAPP            R1      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+FRANK CONGEL         IRO     |
| NRC NOTIFIED BY:  JOE OCH                      |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AMERICIUM-241 SEALED SOURCE DISCOVERED TO BE MISSING FROM ALLEGHENY GENERAL  |
| HOSPITAL LOCATED IN PITTSBURGH, PENNSYLVANIA.                                |
|                                                                              |
| At approximately 1030 on 03/01/00, representatives at Allegheny General      |
| Hospital located in Pittsburgh, Pennsylvania, discovered that a              |
| 14-millicurie, americium-241, sealed source was missing from a stationary    |
| gamma camera.  The licensee reported that the source was last seen at 1130   |
| on 02/29/00.                                                                 |
|                                                                              |
| The licensee stated that the source is a relatively low level source with    |
| longevity which is used to mark images.  It is about the size of a pencil    |
| eraser, and it is typically glued into a holder on the gamma camera.         |
|                                                                              |
| The licensee currently believes that the source may have become dislodged    |
| from the holder and that it may have fallen to the floor.  If that occurred, |
| the source may have been placed in the trash when the room was cleaned the   |
| on the evening of 02/29/00.  The licensee's investigation is ongoing, and    |
| surveys are underway.                                                        |
|                                                                              |
| The licensee plans to notify the state inspector.  (Call the NRC operations  |
| officer for a licensee contact telephone number.)                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36743       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUMMER                   REGION:  2  |NOTIFICATION DATE: 03/01/2000|
|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 13:06[EST]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        03/01/2000|
+------------------------------------------------+EVENT TIME:        12:15[EST]|
| NRC NOTIFIED BY:  PHILIP ROSE                  |LAST UPDATE DATE:  03/01/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OUTSIDE DESIGN BASIS - NON CONSERVATIVE LIMITING CONDITION FOR OPERATION     |
|                                                                              |
| On March 1, 2000, at 1215 hours, resulting from evaluations performed in     |
| response to the McGuire Station Notification (02/04/2000, event # 36659),    |
| Virgil C. Summer Nuclear Station has determined that a condition outside of  |
| design basis may have existed during past plant operation.                   |
|                                                                              |
| The specific condition is a deficiency in the current Limiting Condition for |
| Operation for Engineered Safety Feature Actuation System (ESFAS)             |
| instrumentation.  For one inoperable channel (in the Emergency Feedwater     |
| suction swap over on low suction pressure, RWST [Reactor Water Storage Tank] |
| swap over to RB [Reactor Building] Sump on low level, and/or Containment     |
| Spray actuation on High-3 pressure) the Technical Specification (TS) action  |
| is to place the channel in bypass with no Allowed Outage Time (AOT) limit.   |
| These are energize to actuate functions. At this point the actuation logic   |
| changes from 2 out of 4 to 2 out of 3.                                       |
|                                                                              |
| Because of the indefinite period of time that this condition is permitted to |
| remain in effect, this condition cannot be considered a single failure       |
| during a design basis accident.  During a design basis accident, a single    |
| failure involving a loss of power to the opposite train instrumentation,     |
| while one or more of these functions were in bypass, would prevent the       |
| safety function from automatically occurring.  Manual operator action is     |
| specified in the station Emergency Operating Procedures.                     |
|                                                                              |
| Currently all four channels for each of the above functions are OPERABLE.    |
| Therefore, Summer  is not operating with a single failure vulnerability at   |
| this time.  A preliminary PRA [Probability Risk Assessment] assessment shows |
| the change in Core Damage Frequency to be 2.4 E-8 for placing one channel    |
| from each of these functions in bypass indefinitely.                         |
|                                                                              |
| Administrative controls have been developed to limit the AOT for these       |
| particular channels to be in bypass until such time as a TS change request   |
| can be submitted and approved.                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36744       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 03/01/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 13:20[EST]|
|   RXTYPE: [1] GE-2                             |EVENT DATE:        03/01/2000|
+------------------------------------------------+EVENT TIME:        10:58[EST]|
| NRC NOTIFIED BY:  TRITRUSKI                    |LAST UPDATE DATE:  03/01/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JIM TRAPP            R1      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       24       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR MANUALLY SCRAMMED DUE TO A LOSS OF 3 OF 5 RECIRCULATION PUMPS.       |
|                                                                              |
| STARTUP TRANSFORMER "A" WAS BEING USED TO FEED ELECTRICAL POWER TO 4.16 kV   |
| NON- VITAL BUS "A" AND  VITAL BUS  "C".  EARLIER IN THE DAY THE REACTOR HAD  |
| BEEN TAKEN OFF LINE SO THAT AUXILIARY TRANSFORMER "M1A" COULD BE PLACED BACK |
| IN SERVICE.  AUXILIARY TRANSFORMER "M1A" WAS REPAIRED OVER THE PAST FEW      |
| WEEKS.  WHEN AUXILIARY TRANSFORMER BREAKER "1A" WAS CLOSED TO TRANSFER       |
| STATION ELECTRICAL LOADS FROM THE STARTUP TRANSFORMER  TO  THE "M1A"         |
| AUXILIARY TRANSFORMER,   STARTUP TRANSFORMER "A"  BREAKER "S1A" OPENED AS    |
| EXPECTED BUT "1A" BREAKER DID NOT CLOSE. THE FAILURE OF BREAKER "1A" TO      |
| CLOSE RESULTED IN  A LOSS OF ELECTRICAL POWER TO  BOTH NON-VITAL BUS "A" AND |
| VITAL BUS "C".                                                               |
|                                                                              |
| THE LOSS OF NON- VITAL BUS "A" CAUSED THREE OF FIVE REACTOR RECIRCULATION    |
| PUMPS TO TRIP.  THE OPERATORS MANUALLY SCRAMMED THE REACTOR IN ACCORDANCE    |
| WITH PROCEDURES.  ALL CONTROL RODS FULLY INSERTED INTO THE CORE.  LOSS OF    |
| ELECTRICAL POWER TO VITAL BUS "C" CAUSED A LOSS OF POWER TO 1/2 OF THE       |
| REACTOR PROTECTION SYSTEM.  THIS RESULTED IN  VITAL BUS EMERGENCY DIESEL     |
| GENERATOR #1 TO AUTOMATICALLY START  AND LOAD ONTO THE BUS. THE MAIN STEAM   |
| ISOLATION VALVES  CLOSED WHEN REACTOR VESSEL PRESSURE DECREASED BELOW 850    |
| PSIG.                                                                        |
|                                                                              |
| AT THE PRESENT TIME THE ISOLATION CONDENSER IS BEING USED TO COOL THE        |
| REACTOR VESSEL DOWN. WHEN REACTOR PRESSURE DROPS BELOW 100 PSIG THE MAIN     |
| STEAM ISOLATION VALVES CAN BE REOPENED.  OFFSITE POWER HAS BEEN RESTORED TO  |
| NON- VITAL BUS "A" AND VITAL BUS "C" VIA STARTUP TRANSFORMER "A."  EMERGENCY |
| DIESEL GENERATOR # 1 IS BEING PROPERLY SECURED.  DURING THIS INCIDENT BOTH   |
| NON-VITAL BUS "B" AND VITAL BUS "D" REMAINED IN SERVICE.                     |
|                                                                              |
| THE LICENSEE IS INVESTIGATING WHY "1A" BREAKER DID NOT CLOSE.                |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVEN BY THE LICENSEE.        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36745       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 03/01/2000|
|    UNIT:  [] [2] []                 STATE:  AR |NOTIFICATION TIME: 13:56[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        03/01/2000|
+------------------------------------------------+EVENT TIME:        12:35[CST]|
| NRC NOTIFIED BY:  LARRY MCLERRAN               |LAST UPDATE DATE:  03/01/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES CAIN         R4      |
|10 CFR SECTION:                                 |                             |
|AUNA 50.72(b)(1)(ii)(A)  UNANALYZED COND OP     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNANALYZED CONDITION - USING THE AUXILIARY FEEDWATER PUMP TO FEED THE STEAM  |
| GENERATORS VIA THE MAIN FEEDWATER SYSTEM IS UNANALYZED.                      |
|                                                                              |
| ANO engineering has determined that using the Auxiliary Feedwater pump to    |
| feed S/Gs via the Main Feedwater system is unanalyzed.  The ability of the   |
| Main Feedwater Block valves to shut and isolate the affected S/G on a Main   |
| Steam Line Break has not been fully evaluated.  Preliminary evaluation       |
| indicates that the valves may not shut under worst case conditions (low      |
| voltage supplied to the MOV and high D/P across the valves).  This condition |
| is only applicable during low power operations with Auxiliary Feedwater      |
| feeding via the Main Feedwater piping.                                       |
|                                                                              |
| Auxiliary Feedwater is not an Engineered Safety Feature at ANO Unit 2.  The  |
| plant has a separate Emergency Feedwater system which is not affected by     |
| this problem.                                                                |
|                                                                              |
| The licensee will notify the NRC resident inspector.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   36746       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  RESTON HOSPITAL CENTER               |NOTIFICATION DATE: 03/01/2000|
|LICENSEE:  RESTON HOSPITAL CENTER               |NOTIFICATION TIME: 14:22[EST]|
|    CITY:  RESTON                   REGION:  2  |EVENT DATE:        02/28/2000|
|  COUNTY:                            STATE:  VA |EVENT TIME:        08:00[EST]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  03/01/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LEN WERT             R2      |
|                                                |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  DR. FRUMAN                   |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOST I-125 SEED                                                              |
|                                                                              |
| A 0.401 mCi I-125 seed was lost on 2/28/2000, at Reston Hospital Center in   |
| Reston, VA.  The technician working with the seed believes the seed was lost |
| in the hot lab while preparing the seeds for use.  The hot lab was searched  |
| but the seed could not be found.  The technician frisked herself prior to    |
| leaving the hot lab, so the licensee does not believe the seed is outside of |
| the lab.                                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36747       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE               REGION:  4  |NOTIFICATION DATE: 03/01/2000|
|    UNIT:  [] [2] []                 STATE:  AZ |NOTIFICATION TIME: 19:25[EST]|
|   RXTYPE: [1] CE,[2] CE,[3] CE                 |EVENT DATE:        03/01/2000|
+------------------------------------------------+EVENT TIME:        07:49[MST]|
| NRC NOTIFIED BY:  DAN LARKIN                   |LAST UPDATE DATE:  03/01/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES CAIN         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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FITNESS FOR DUTY EVENT                                                       |
|                                                                              |
| A LICENSED OPERATOR TESTED POSITIVE FOR ALCOHOL DURING A FOR CAUSE TEST.     |
| THE OPERATOR'S PROTECTED AREA ACCESS HAS BEEN SUSPENDED.  CONTACT THE        |
| OPERATIONS CENTER FOR ADDITIONAL DETAILS.                                    |
|                                                                              |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+