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Event Notification Report for June 7, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/04/1999 - 06/07/1999

                              ** EVENT NUMBERS **

35686  35687  35790  35791  35792  35793  35794  35795  35796  35797  35798  35799 
35800  35801  35802  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35686       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 05/06/1999|
|    UNIT:  [] [] [3]                 STATE:  CT |NOTIFICATION TIME: 18:44[EDT]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        05/06/1999|
+------------------------------------------------+EVENT TIME:        18:00[EDT]|
| NRC NOTIFIED BY:  MARTIN                       |LAST UPDATE DATE:  06/04/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES LINVILLE       R1      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| VALVE FAILED LOCAL LEAK RATE TEST (LLRT).                                    |
|                                                                              |
| VALVE 3QSS*V4 IS A CHECK VALVE IN THE QUENCH SPRAY SYSTEM, AND THE CAUSE OF  |
| THE LLRT FAILURE IS UNKNOWN AND BEING INVESTIGATED, BUT MOST LIKELY MAY BE   |
| DUE TO VALVE DEGRADATION.  WHEN THE RESULTS OF ITS LLRT WERE ADDED TO THE    |
| OTHER CATEGORY "C" VALVES' RESULTS, THE TOTAL LEAKAGE EXCEEDED TECHNICAL     |
| SPECIFICATION ALLOWABLE LIMITS OF 43 SCFH (TOTAL MEASURED CATEGORY "C" WAS   |
| 335 SCFH); HOWEVER, THE TOTAL LEAKAGE OF EVERYTHING STILL DID NOT EXCEED THE |
| 0.6 La VALUE.  CORRECTIVE ACTION WILL BE TO REPAIR THE VALVE PRIOR TO        |
| STARTUP.                                                                     |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED ALONG WITH STATE, LOCAL AND OTHER    |
| GOVERNMENT AGENCIES.                                                         |
|                                                                              |
| * * * UPDATE 1134 5/13/99 FROM STEVE LAWHEAD TAKEN BY STRANSKY * * *         |
|                                                                              |
| Local leak rate testing of valve SIL*V6 (RHS Loop 1 Cold Leg Check Valve)    |
| found the leakage to be excessive.  This leakage, when combined with the     |
| other known leakage, caused TS LCO 3.6.1.2.b to be exceeded.  The TS         |
| requires a combined leakage rate of less than 0.6 La for all penetrations    |
| and valves subject to Type B and C tests, when pressurized to Pa.  The NRC   |
| resident inspector has been informed of this update.  Notified R1DO          |
| (Cowgill).                                                                   |
|                                                                              |
| * * * RETRACTION 1633 EDT ON 6/4/99 BY DALE BRODSKY TO FANGIE JONES * * *    |
|                                                                              |
| These conditions were conservatively reported as conditions outside the      |
| unit's design basis.                                                         |
|                                                                              |
| "A review has determined that the Combined Type B and C Leakage limit of     |
| 0.60 La and the Enclosure Building (Secondary Containment) Bypass Leakage    |
| limit of 0.042 La, (based upon ANSI/ANS 56.8-1994 and NUREG 1022, Rev. 1)    |
| should be based upon the As-Found limit measured on a Minimum Pathway        |
| Leakage Rate basis. Using this basis the measured total as-found leakage     |
| does not exceed either limit.                                                |
|                                                                              |
| "These conditions are not reportable pursuant to 10 CFR 50.72(b)(1)(ii)(B)   |
| as conditions outside the design basis, or pursuant to 10 CFR 50.72(b)(2)(i) |
| as events or conditions that may have resulted in an unanalyzed conditions   |
| and therefore, the Immediate Notification for these conditions is            |
| retracted."                                                                  |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The Headquarters          |
| Operations Officer notified the R1DO (Ronald Bellamy).                       |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35687       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 05/06/1999|
|    UNIT:  [] [2] []                 STATE:  AL |NOTIFICATION TIME: 20:33[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        05/06/1999|
+------------------------------------------------+EVENT TIME:        16:14[CDT]|
| NRC NOTIFIED BY:  NACOSTE                      |LAST UPDATE DATE:  06/04/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+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     M/R        Y       23       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE REACTOR WAS MANUALLY SCRAMMED FROM 23.5% POWER.                          |
|                                                                              |
| DURING STARTUP FOLLOWING A REFUELING OUTAGE, THE UNIT EXPERIENCED A STEAM    |
| LEAK ON THE INLET SIDE OF THE OFFGAS PREHEATER  (ASME CLASS 2 PIPING).       |
| TECHNICAL REQUIREMENTS MANUAL (TMR) SECTION  3.4.3 REQUIRES THAT THE         |
| AFFECTED COMPONENT BE ISOLATED IMMEDIATELY, REQUIRING THAT THE MAIN STEAM    |
| ISOLATION VALVES (MSIVs) BE CLOSED.  THE MAIN TURBINE WAS TRIPPED FROM 23.5  |
| % POWER IN ANTICIPATION OF THE INSERTION OF A MANUAL SCRAM WHICH OCCURRED AT |
| 1614 CST.  THE MANUAL SCRAM CAUSED REACTOR VESSEL WATER LEVEL TO GO BELOW    |
| THE LOW SETPOINT LEVEL, WHICH GENERATED A REDUNDANT SCRAM SIGNAL AND         |
| INITIATED THE PCIS ISOLATIONS OF GROUPS 2 (PRIMARY CONTAINMENT), 3 (RWCU), 6 |
| (SECONDARY CONTAINMENT), AND 8 (TIP SYSTEM).  ALL RODS FULLY INSERTED, NO    |
| ECCS INJECTION OCCURRED, AND NO RELIEF VALVES LIFTED.  THE MSIVs WERE CLOSED |
| AT 1632.                                                                     |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT.                           |
|                                                                              |
| * * * RETRACTED AT 1434 EDT ON 6/4/99 BY CHRIS VAUGHN TO FANGIE JONES * * *  |
|                                                                              |
| This event is retracted after review and determination that as a planned     |
| manual reactor trip, it was not reportable under 10CFR50.72.2.ii per NUREG   |
| 1022.                                                                        |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The Headquarters          |
| Operations Officer notified the R2DO (Kenneth Barr).                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35790       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 06/03/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 14:44[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/02/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        16:30[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  06/04/1999|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |DAVID HILLS          R3      |
|  DOCKET:  0707001                              |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  THOMAS WHITE                 |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)(i)     ACCID MT EQUIP FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THREE SPRINKLER SYSTEMS DECLARED INOPERABLE DUE TO CORRODED HEADS (24-hour   |
| report)                                                                      |
|                                                                              |
| The following text is a portion of a facsimile received from Paducah:        |
|                                                                              |
| "On 06/02/99 at 1630 CDT, the Plant Shift Superintendent (PSS) was notified  |
| that numerous sprinkler heads were corroded, affecting 16 sprinkler systems  |
| in C-337 and 1 system in C-333, such that the ability of the sprinklers to   |
| flow sufficient water was called into question.  Subsequently, these         |
| sprinkler systems were declared inoperable, and TSR-required actions         |
| establishing roving fire patrols were initiated.  This deficiency was        |
| detected during scheduled system inspections conducted by Fire Protection    |
| personnel.  Currently, functionality of the sprinkler heads has not been     |
| fully evaluated by Fire Protection personnel, and the remaining cascade      |
| buildings are currently being inspected, and if necessary, this report will  |
| be updated to identify any additional areas.                                 |
|                                                                              |
| "It has been determined that this event is reportable under                  |
| 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to     |
| function as designed."                                                       |
|                                                                              |
| The NRC resident inspector has been notified of this event.                  |
|                                                                              |
| ******************** UPDATE RECEIVED AT 1022 EDT ON 06/04/99 FROM CAGE TO    |
| TROCINE *******************                                                  |
|                                                                              |
| The following text is a portion of a facsimile received from Paducah:        |
|                                                                              |
| "Two sprinkle heads on system D-1 in C-337 and two sprinkler heads on system |
| 27 in C-335 were identified to also be corroded.  These were identified to   |
| the PSS on 06/03/99 at 1600 CDT and 1601 CDT, respectively, and determined   |
| to require an update to this report by the PSS.                              |
|                                                                              |
| "It has been determined that this event is reportable under                  |
| 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to     |
| function as designed."                                                       |
|                                                                              |
| Paducah personnel notified the NRC resident inspector of this update.  The   |
| NRC operations officer notified the R3DO (Hills) and NMSS EO (Combs).        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35791       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 06/04/1999|
|    UNIT:  [] [2] []                 STATE:  FL |NOTIFICATION TIME: 05:48[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        06/04/1999|
+------------------------------------------------+EVENT TIME:        03:13[EDT]|
| NRC NOTIFIED BY:  JACK BREEN                   |LAST UPDATE DATE:  06/04/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KENNETH BARR         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        Y       48       Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - MANUAL REACTOR TRIP FROM 48% POWER DUE TO 4 CONTROL RODS DROPPING INTO THE |
| CORE -                                                                       |
|                                                                              |
| AT 0313 ON 06/04/99, WHILE PERFORMING TROUBLESHOOTING ACTIVITIES ON UNIT 2   |
| CONTROL ELEMENT DRIVE SYSTEM FOLLOWING A CONTROL ROD DROPPING INTO THE       |
| REACTOR CORE ON 06/02/99 (REFER TO EVENT #35785), FOUR CONTROL ELEMENT       |
| ASSEMBLIES (SHUTDOWN GROUP 'B' - SUBGROUP 21) FELL INTO THE REACTOR CORE FOR |
| UNKNOWN REASONS.  CONTROL ROOM OPERATORS MANUALLY TRIPPED UNIT 2 FROM 48%    |
| POWER.  ALL CONTROL RODS INSERTED INTO THE CORE COMPLETELY.  STEAM IS BEING  |
| DUMPED INTO THE MAIN CONDENSER.  UNIT 2 IS STABLE IN MODE 3 (HOT STANDBY).   |
|                                                                              |
| THE LICENSEE IS CONTINUING TO INVESTIGATE THE CAUSE(S) OF THE DROPPED        |
| CONTROL RODS.                                                                |
|                                                                              |
| THIS EVENT HAD NO EFFECT ON UNIT 1 WHICH IS OPERATING  AT 100% POWER.        |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   35792       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  U.S. AIR FORCE                       |NOTIFICATION DATE: 06/04/1999|
|LICENSEE:  U.S. AIR FORCE                       |NOTIFICATION TIME: 09:34[EDT]|
|    CITY:  Washington D.C.          REGION:  1  |EVENT DATE:        06/04/1999|
|  COUNTY:                            STATE:  DC |EVENT TIME:        06:30[EDT]|
|LICENSE#:  42-23539-01AF         AGREEMENT:  N  |LAST UPDATE DATE:  06/04/1999|
|  DOCKET:  03028641                             |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |RONALD BELLAMY       R1      |
|                                                |KENNETH BARR         R2      |
+------------------------------------------------+LINDA HOWELL         R4      |
| NRC NOTIFIED BY:  MAJOR MITCH HICKS            |FRED COMBS           NMSS    |
|  HQ OPS OFFICER:  LEIGH TROCINE                |CHARLES MILLER       IRO     |
+------------------------------------------------+FRANK CONGEL         IRO     |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|IBDB 30.50(b)(4)(ii)     DAMAGED LNM/CONTAINER  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF TWO 500- ÁCi STRONTIUM-90 SOURCES DUE TO A HELICOPTER CRASH IN       |
| FAYETTEVILLE, NORTH CAROLINA (24-HOUR REPORT)                                |
|                                                                              |
| A representative from Bolling Air Force Base (located in Washington D.C.)    |
| reported that a helicopter from Hurlburt Field (located in Mary Esther,      |
| Florida) crashed at 2300 on 06/02/99 while performing a night training       |
| exercise at Pope Air Force Base (located in Fayetteville, North Carolina).   |
| Each helicopter blade contained an in-flight blade inspection system (IBIS)  |
| source with 500 ÁCi of Strontium-90, and it is currently believed that the   |
| helicopter had four blades.  Two of the four IBIS sources have been          |
| identified and recovered by the pope Air Force Base Accident Response Team.  |
| These devices have been bagged and will be checked for contamination.        |
| Pending the completion of the crash investigation, the licensee plans to     |
| search for the remaining IBIS sources with survey equipment.                 |
|                                                                              |
| This event was reported to Bolling Air Force Base at 0630 on 06/04/99.       |
|                                                                              |
| Five individuals survived the crash, and there was one fatality.             |
|                                                                              |
| The limit referenced in 10 CFR Part 20, Appendix C, for Strontium-90 is 0.1  |
| ÁCi.                                                                         |
|                                                                              |
| The licensee plans to notify the NRC Region 4 Office.  (Call the NRC         |
| Operations Center for a licensee contact telephone number.)                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35793       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE           REGION:  1  |NOTIFICATION DATE: 06/04/1999|
|    UNIT:  [1] [] []                 STATE:  VT |NOTIFICATION TIME: 12:35[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        06/04/1999|
+------------------------------------------------+EVENT TIME:        09:50[EDT]|
| NRC NOTIFIED BY:  MITCH McCLUSKIE              |LAST UPDATE DATE:  06/04/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RONALD BELLAMY       R1      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP           |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| ALTERNATE COOLING SYSTEM DECLARED INOPERABLE                                 |
|                                                                              |
| "Following a question raised by an NRC Resident Inspector at VY, an Event    |
| Report was submitted due to a lack of sufficient analysis to determine if    |
| procedural guidance was adequate for operation of the Alternate Cooling      |
| System (ACS).  VY declared the ACS inoperable at 2110 on 6/3/99 and entered  |
| a 7 day LCO [3.5.d.3] per the plant Technical Specifications.  Based on      |
| further evaluation, Operations and Engineering Personnel concluded that      |
| current VY procedures may not provide the specific information necessary to  |
| ensure that ACS Design Bases 1 & 2 above, would have been met.  Engineering  |
| and Licensing evaluations of ACS design and performance requirements         |
| continue.                                                                    |
|                                                                              |
| "VY is currently developing procedural enhancements that will ensure that    |
| the operating crews are provided with the guidance necessary to ensure that  |
| ACS would be operated in the manner necessary to achieve its safety design   |
| bases.  It is expected that the necessary procedural guidance will be        |
| developed and issued prior to the                                            |
| expiration of the cited 7 day LCO."                                          |
|                                                                              |
| The licensee notified the NRC Resident Inspector and the State of Vermont.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35794       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ARKANSAS DEPT OF HEALTH RAD CONTROL  |NOTIFICATION DATE: 06/04/1999|
|LICENSEE:  AQUATERRA, INC.                      |NOTIFICATION TIME: 12:51[EDT]|
|    CITY:  El DORADO                REGION:  4  |EVENT DATE:        06/02/1999|
|  COUNTY:                            STATE:  AR |EVENT TIME:        18:00[CDT]|
|LICENSE#:  LA-5382-L01           AGREEMENT:  Y  |LAST UPDATE DATE:  06/04/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LINDA HOWELL         R4      |
|                                                |FRED COMBS           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  DAVID SNELLINGS              |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT                                                       |
|                                                                              |
| "Abstract:  A Troxler gauge Model 3411 B (Serial # 9816) was run over and    |
| damaged by a bulldozer at a construction site near El Dorado, Arkansas.  The |
| gauge contained approximately 9 millicuries of Cesium-137 and 44 millicuries |
| of Americium-241: beryllium.  The outer case of the gauge was damaged and    |
| the source rod was bent.  The licensee was working under reciprocity with a  |
| Louisiana Radioactive Material License (LA-5382-L01).  The licensee was able |
| to retrieve the gauge, assess the damage and return the gauge to the storage |
| location.  A leak test was performed and Troxler Labs was notified.  A       |
| health physicist from the Arkansas Dept. of Health investigated the incident |
| on June 3, 1999.  It was noted during investigation that the shutter was     |
| partially opened resulting in doserate of 50 mR/hour at contact.  Further    |
| investigation is on going.                                                   |
|                                                                              |
| "Arkansas License No:  ARK-REC-232; Reciprocity Licensee: AQUATERRA, INC.,   |
| LA-5382L01, of PORT ALLEN, LA"                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   35795       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  NORTH COUNTRY HOSPITAL               |NOTIFICATION DATE: 06/04/1999|
|LICENSEE:  NORTH COUNTRY HOSPITAL               |NOTIFICATION TIME: 14:25[EDT]|
|    CITY:  Newport                  REGION:  1  |EVENT DATE:        02/04/1999|
|  COUNTY:  Orleans                   STATE:  VT |EVENT TIME:             [EDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  06/04/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |RONALD BELLAMY       R1      |
|                                                |FRED COMBS           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  LARRY LABOR                  |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33(a)            MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MEDICAL MISADMINISTRATION AT NORTH COUNTRY HOSPITAL LOCATED IN NEWPORT,      |
| VERMONT                                                                      |
|                                                                              |
| On 02/04/99, a medical misadministration occurred at North Country Hospital  |
| located in Newport, Vermont.  The physician prescribed a diagnostic test     |
| involving 10 ÁCi of Iodine-131, and a 305-ÁCi dose of Iodine-131 was         |
| administered.  Subsequent review of the dose by a radiologist determined     |
| that the literature search showed support for the dose received, and the     |
| licensee stated that there were no anticipated adverse health affects.  The  |
| patient subsequently went to a tertiary medical center and received an       |
| ablation therapy, and the 305-ÁCi dose of Iodine-131 that was administered   |
| on 02/04/99 at North Country Hospital was subtracted from the ablation dose  |
| administered at the tertiary medical center.   At this time, the licensee    |
| does not plan to notify the patient.                                         |
|                                                                              |
| A Region 1 inspector (Thompson) was informed by the licensee on 06/03/99.    |
| (Call the NRC Operations Center for a licensee contact telephone number.)    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35796       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUMMER                   REGION:  2  |NOTIFICATION DATE: 06/04/1999|
|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 16:03[EDT]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        06/04/1999|
+------------------------------------------------+EVENT TIME:        13:58[EDT]|
| NRC NOTIFIED BY:  JIM PROPER                   |LAST UPDATE DATE:  06/04/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KENNETH BARR         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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR TRIP DUE TO SPURIOUS SIGNAL DURING POWER RANGE CALIBRATION           |
|                                                                              |
| During the performance of power range calibration of N42, with a trip signal |
| in, a spurious signal from N43 was received which completed the 2 of 4       |
| coincidence for a reactor trip on high flux.  The reactor tripped, all rods  |
| inserted and all systems functioned as required.                             |
|                                                                              |
| This event is being investigated and the plant will remain in Hot Standby    |
| until the cause is determined and corrected.  The plant is presently stable  |
| with auxiliary feedwater supplying water to the steam generators and the     |
| steam dumps exhausting to the main condenser.                                |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35797       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 06/04/1999|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 17:04[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        06/04/1999|
+------------------------------------------------+EVENT TIME:        15:05[CDT]|
| NRC NOTIFIED BY:  DAVE DEES                    |LAST UPDATE DATE:  06/04/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LINDA HOWELL         R4      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO EXCESSIVE CHLORINE IN DISCHARGE                  |
|                                                                              |
| The licensee notified the Kansas Department of Health and Environment due to |
| exceeding the residual limit of 0.2 ppm chlorine in the Circulating Water    |
| discharge.  The highest observed reading was 1.6 ppm.  A mechanical failure  |
| in the sodium hypochlorite feed pump is suspected.  An investigation is in   |
| progress and the system is isolated until corrected.                         |
|                                                                              |
| The licensee notified the NRC Resident Inspector as well as the State of     |
| Kansas and local county authorities.                                         |
|                                                                              |
| * * * UPDATE AT 2243 EDT ON 6/4/99 BY STEVE HEDGES TO FANGIE JONES * * *     |
|                                                                              |
| After subsequent evaluation of sodium hypochlorite release volumes, the      |
| licensee determined that the release limits of 40 CFR 302 of 100 pounds was  |
| exceeded.  The calculated release was 1694 pounds.  The licensee notified    |
| the National Response Center (report # 486-281).                             |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The Headquarters          |
| Operations Officer notified the R4DO (Linda Howell).                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35798       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND        REGION:  1  |NOTIFICATION DATE: 06/04/1999|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 18:02[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP            |EVENT DATE:        06/04/1999|
+------------------------------------------------+EVENT TIME:        17:17[EDT]|
| NRC NOTIFIED BY:  JOHN SCHORK                  |LAST UPDATE DATE:  06/04/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RONALD BELLAMY       R1      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR BUILDING EMERGENCY COOLING SYSTEM OPERABLE BUT DEGRADED              |
|                                                                              |
| "At 1717 hours on June 4, 1999, GPU Nuclear determined that a condition that |
| is outside the plant design basis may exist at TMI-1 due to potential        |
| degraded performance of the Reactor Building [RB] Emergency Cooling System.  |
| Measurements of indirect system performance parameters for the TMI-1 Reactor |
| Building Emergency Cooling System indicate that the air flow through the     |
| system may be less than that assumed in the plant design basis.              |
|                                                                              |
| "Specifically, air flow in the RB Normal Cooling system, that utilizes duct  |
| work and a flow damper common to both the RB Normal cooling system and the   |
| RB Emergency Cooling System, has been found to be below previous air flow    |
| measurements. The air flow reduction may be indicative of a reduced air flow |
| that would occur in the RB Emergency Cooling system if it was called upon to |
| function in the event of a design basis accident. The design basis flow for  |
| the RB Emergency Cooling System is 25,000 CFM with the RB cooling fans in    |
| slow speed. Engineering judgement is that the current flow rate may be below |
| 25,000 CFM if the system was called upon to function, hence the              |
| identification of a condition outside the plant design basis.                |
|                                                                              |
| "Engineering judgement is that: the Reactor Building Emergency Cooling       |
| System remains operable but may be degraded. The judgement that the system   |
| is operable with degraded air flow is based on the difference between        |
| conservative assumptions in environmental temperatures in the plant design   |
| basis analysis and current environmental conditions and in view of the fact  |
| that the environmental conditions within the Reactor Building in the design  |
| basis accident should enhance the current potential degraded system air      |
| flow. A formal internal justification of continued operation (JCO) will be   |
| prepared to document the basis for the engineering judgement and will be     |
| provided to the site NRC resident inspectors office.                         |
|                                                                              |
| "Because GPU Nuclear has classified this condition as being potentially      |
| outside the design basis of the plant, GPU Nuclear is notifying the NRC      |
| Operations Center in accordance with 10 CFR 50.72(b)(1)(ii)(b). This         |
| notification will be followed with a 30 day LER in accordance with 10 CFR    |
| 50.73.                                                                       |
|                                                                              |
| "GPU Nuclear will document this condition in its 10 CFR 50 Appendix B        |
| corrective action program and this potential non-conformance is being        |
| addressed in accordance with the guidance provided in NRC Generic Letter     |
| 91-18, Rev 1."                                                               |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35799       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 06/04/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 19:05[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/04/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        07:25[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  06/04/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |DAVID HILLS          R3      |
|  DOCKET:  0707002                              |WAYNE HODGES         NMSS    |
+------------------------------------------------+CHARLES MILLER       IRO     |
| NRC NOTIFIED BY:  RICK LARSON                  |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01 24 HOUR REPORT                                            |
|                                                                              |
| "ON 6/4/99 AT 0725 HRS. OPERATIONS PERSONNEL DISCOVERED THAT REQUIREMENT #5  |
| OF NUCLEAR CRITICALITY SAFETY ANALYSIS (NCSA) PLANT_003.A01 WAS NOT BEING    |
| MET.  THE REQUIREMENT, MONITORING SURGE DRUM PRESSURE ONCE EACH SHIFT WAS    |
| BEING PERFORMED WITH THE INSTALLED PRESSURE INDICATOR WHICH WAS ISOLATED ON  |
| 5/20/99 TO ALLOW MAINTENANCE TO CALIBRATE.  WHEN THE INDICATOR COULD NOT BE  |
| CALIBRATED IT WAS LEFT ISOLATED AND OPERATIONS WAS NOT MADE AWARE THAT OF    |
| THIS CONDITION.  SINCE THE LINE WAS VALVED OFF THE DRUM PRESSURE WAS NOT     |
| MEASURED AS REQUIRED, THIS IS A LOSS OF A SINGLE CONTROL (CONCENTRATION) OF  |
| THE DOUBLE CONTINGENCY PROGRAM.  THE SECOND CONTROL (MODERATION) WAS         |
| MAINTAINED THROUGHOUT THE EVENT.  THE PRESSURE INDICATOR WAS VALVED IN AT    |
| 0905 HRS. ON 6/4/99.  PREVIOUS MAINTENANCE IN THE CASCADE REGARDING SURGE    |
| DRUM CALIBRATION MAY HAVE RESULTED IN A SIMILAR SITUATION.                   |
|                                                                              |
| "THE 'X'  BANK SURGE DRUM WAS EVACUATED AND TAGGED OUT OF SERVICE FOR        |
| MAINTENANCE.                                                                 |
| THEREFORE, THE SURGE DRUM IS CONSIDERED EMPTY.  ON 5/20/99 MAINTENANCE       |
| VALVED OFF THE DRUM TO DO WORK ON THE PRESSURE SENSOR.  THE DRUM REMAINED    |
| VALVED OFF UNTIL 6/4/99.  WHEN THE DRUM WAS VALVED BACK IN THE DRUM WAS      |
| STILL EVACUATED.  THIS INDICATED THAT THE NCSA PRESSURE LIMIT WAS NEVER      |
| EXCEEDED (i.e., WET AIR IN-LEAKAGE DID NOT OCCUR), THEREFORE, THE SAFETY     |
| SIGNIFICANCE OF THIS EVENT IS LOW AND A CRITICALITY WAS NOT POSSIBLE.        |
|                                                                              |
| "FOR CRITICALITY TO OCCUR THE SURGE DRUM WOULD HAVE TO HAVE MATERIAL IN IT   |
| AND THE MATERIAL WOULD NAVE TO BE MODERATED BY WET AIR IN-LEAKAGE.  THIS WAS |
| EXPECTED TO OCCUR IN THIS CASE BECAUSE THE DRUM WAS HOLDING ITS PRESSURE     |
| BEFORE MAINTENANCE CALIBRATED THE PRESSURE SENSOR, AND THE FACT THAT OTHER   |
| SURGE DRUMS IN THE SAME ROOM WERE OPERATING AND THE ROOM TEMPERATURE WAS     |
| GREATER THAN 140■F.                                                          |
|                                                                              |
| "THE ESTIMATED AMOUNT OF MATERIAL IN THE DRUM IS LESS THAN 600 gms. U-235 (A |
| SAFE MASS AT 10% ENRICHMENT) DUE TO THE FACT THAT THE DRUM WAS EVACUATED     |
| PRIOR TO MAINTENANCE.  WHEN THE PRESSURE SENSOR WAS VALVED BACK INTO THE     |
| DRUM, THE DRUM WAS STILL AT A VACUUM (NOTE: THE NCSA PRESSURE LIMIT ON THE   |
| DRUM IS 17 psia).  THE MAXIMUM ENRICHMENT IN THIS DRUM IS 10%.  THE FORM OF  |
| THE MATERIAL IS EITHER UF6 OR UO2F2.                                         |
|                                                                              |
| "THE MAINTENANCE PROCEDURE REQUIRES THE PRESSURE INDICATOR TO BE ISOLATED    |
| FOR CALIBRATION.  THIS WAS DONE ON 5/20/99.  WHEN THE SENSOR COULD NOT BE    |
| CALIBRATED, THE LINE WAS LEFT VALVED OFF AND OPERATIONS DID NOT KNOW THIS.   |
| THE NCSA REQUIRES THE PRESSURE ON THE DRUM TO BE MONITORED AND RECORDED EACH |
| SHIFT, OPERATIONS WAS READING THE MT&E SENSOR INSTALLED.  HOWEVER, SINCE THE |
| LINE WAS VALVED OFF THE DRUM PRESSURE WAS NOT MEASURED AS REQUIRED.          |
|                                                                              |
| "THE RESIDENT NRC INSPECTOR HAS BEEN NOTIFIED."                              |
|                                                                              |
| * * * UPDATE AT 2120 EDT ON 6/4/99 BY ERIC SPAETH TO FANGIE JONES * * *      |
|                                                                              |
| Clarification:  the normal pressure indicator is read in the control room.   |
| That indicator is still not calibrated and a local calibrated pressure gauge |
| was valved in for indication on 6/4/99 and is read locally each shift.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35800       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER            REGION:  2  |NOTIFICATION DATE: 06/05/1999|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 01:27[EDT]|
|   RXTYPE: [3] B&W-L-LP                         |EVENT DATE:        06/04/1999|
+------------------------------------------------+EVENT TIME:        23:55[EDT]|
| NRC NOTIFIED BY:  WILLIAM KISNER               |LAST UPDATE DATE:  06/05/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KENNETH BARR         R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       85       Power Operation  |85       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LIVE TURTLE FOUND IN INTAKE STRUCTURE                                        |
|                                                                              |
| The licensee notified the Florida Department of Environmental Protection     |
| regarding the discovery of a live Loggerhead Turtle on the intake bar racks. |
| The turtle was removed and transported to the mariculture center.  The NRC   |
| resident inspector has been informed of this notification by the licensee.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35801       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 06/06/1999|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 18:07[EDT]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        06/06/1999|
+------------------------------------------------+EVENT TIME:        14:40[CDT]|
| NRC NOTIFIED BY:  MIKE MacLENNON               |LAST UPDATE DATE:  06/06/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID HILLS          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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |55       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LIGHTNING STRIKE CAUSED SOME MINOR ALARMS AND PARTIAL GROUP ONE ISOLATIONS   |
|                                                                              |
| "On 6/6/99 at approximately 1440 hours, a lightning strike caused valves     |
| 1-0220-44 and 1-0220-45, Reactor Recirculation sample valves, to close on an |
| invalid signal.  These valves close automatically on a Group One isolation,  |
| and therefore this is considered to be an ESF actuation.                     |
|                                                                              |
| "The power change indicated above was also a result of the lightning strike. |
| An emergency load reduction was made in response to a partial loss of        |
| feedwater heaters.  Reactor recirculation flow was manually reduced and      |
| control rods were inserted to reduce the flow control line below 100%.       |
| Miscellaneous other minor alarms were received on both units due to the      |
| lightning strike.                                                            |
|                                                                              |
| "The above mentioned sample valves have been reopened, and a load increase   |
| to full power has been initiated as of 1635 hours."                          |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35802       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 06/06/1999|
|    UNIT:  [] [2] []                 STATE:  FL |NOTIFICATION TIME: 21:14[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        06/06/1999|
+------------------------------------------------+EVENT TIME:        18:45[EDT]|
| NRC NOTIFIED BY:  ALAN HALL                    |LAST UPDATE DATE:  06/06/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KENNETH BARR         R2      |
|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     A          N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| WITH THE REACTOR SHUTDOWN, AN AUTOMATIC REACTOR TRIP WAS GENERATED           |
|                                                                              |
| "At 1845 EDT, an inadvertent partial opening of the 2B MSIV occurred,        |
| causing a steam generator pressure transient that resulted in an Reactor     |
| Protection System Asymmetrical Steam Generator Pressure Transient.  The      |
| plant was in Mode 3, all control element assemblies were fully inserted, the |
| trip circuit breakers were closed, and opened as expected in response to the |
| trip signal.  Investigation proceeding."                                     |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+