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Event Notification Report for May 24, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           05/21/1999 - 05/24/1999

                              ** EVENT NUMBERS **

35644  35744  35746  35749  35750  35751  35752  35753  35754  35755  35756  35757 
35758  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35644       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 04/27/1999|
|    UNIT:  [1] [2] []                STATE:  CA |NOTIFICATION TIME: 22:14[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/27/1999|
+------------------------------------------------+EVENT TIME:        18:45[PDT]|
| NRC NOTIFIED BY:  RODERTO ARROYO               |LAST UPDATE DATE:  05/21/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID GRAVES         R4      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       50       Power Operation  |50       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF A SAFEGUARDS SYSTEM DEGRADATION RELATED TO A VITAL AREA         |
| BARRIER                                                                      |
|                                                                              |
| Security personnel discovered a safeguard system degradation related to the  |
| vital area barrier.  Immediate compensatory actions were taken upon          |
| discovery.  (Contact the NRC Operations Officer for additional details and   |
| for a licensee contact telephone number.)                                    |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE AT 1746 ON 05/26/99 BY JOHN HUBBLE TO JOLLIFFE * * *            |
|                                                                              |
| The licensee is retracting this event since adequate compensatory measures   |
| were already in place when this degradation was discovered.  (Contact the    |
| NRC Operations Officer for additional details.)                              |
|                                                                              |
| The licensee plans to notify the NRC Resident Inspector.                     |
|                                                                              |
| The NRC Operations Officer notified the R4DO Gary Sanborn.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35744       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 05/20/1999|
|    UNIT:  [] [] [3]                 STATE:  CT |NOTIFICATION TIME: 10:23[EDT]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        05/20/1999|
+------------------------------------------------+EVENT TIME:        10:14[EDT]|
| NRC NOTIFIED BY:  BRADSKY                      |LAST UPDATE DATE:  05/21/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PETER ESELGROTH      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        Refueling        |0        Refueling        |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
|  - FAILURE OF BOTH SAFETY RELATED CONTAINMENT CUBICAL SUMP AIR DRIVEN PUMPS  |
| -                                                                            |
|                                                                              |
| ON 5/16/99 DURING THE 18 MONTH SURVEILLANCE FOR THE SAFETY RELATED           |
| CONTAINMENT RECIRCULATION CUBICAL SUMP AIR DRIVEN PUMPS, BOTH PUMPS FAILED   |
| TO DISCHARGE WATER FROM THE SUMPS TO OUTSIDE THE ENGINEERING SAFETY FEATURES |
| BUILDING.  A REVISION TO THE SURVEILLANCE TO INCREASE THE AIR PRESSURE TO    |
| THE PUMPS WAS APPROVED ON 5/19/99.  ON 5/19/99, BOTH AIR DRIVEN PUMPS WERE   |
| DECLARED INOPERABLE WHEN PUMP DAS*P15A FAILED TO DISCHARGE WATER FROM THE    |
| SUMPS TO OUTSIDE THE ENGINEERING SAFETY FEATURES BUILDING WITH THE INCREASED |
| AIR PRESSURE.                                                                |
|                                                                              |
| THE SAFETY RELATED CONTAINMENT RECIRCULATION CUBICAL SUMP AIR DRIVEN PUMPS   |
| ARE REQUIRED FOLLOWING A LOCA WHEN THE ENGINEERING SAFETY FEATURES BUILDING  |
| IS INACCESSIBLE DUE TO HIGH DOSE RATES IN THE BUILDING.  THE PLANT IS        |
| CURRENTLY IN A REFUELING OUTAGE AND THE NON-SAFETY RELATED CONTAINMENT       |
| RECIRCULATION CUBICAL SUMP PUMPS ARE FUNCTIONAL.                             |
|                                                                              |
| THE CAUSE OF THE EVENT IS CURRENTLY UNDER INVESTIGATION.  AT THIS TIME, IT   |
| IS HYPOTHESIZED THAT THE AIR CHAMBER OF THE PUMPS ARE FLOODED WITH           |
| LUBRICATING OIL WHICH REDUCES THEIR CAPABILITIES TO PUMP WATER.              |
|                                                                              |
| THE RESIDENT INSPECTOR WAS INFORMED.                                         |
|                                                                              |
| *** UPDATE ON 5/21/99 @ 0838 BY MARTIN TO GOULD ***                          |
|                                                                              |
| THE DATE BOTH AIR DRIVEN PUMPS WERE DECLARED INOPERABLE WAS 5/20/99 INSTEAD  |
| OF 5/19/99 AS REPORTED IN THE INITIAL REPORT.                                |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.  REG 1 RDO (ESELGROTH) WAS INFORMED.    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35746       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 05/20/1999|
|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 14:23[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        12/01/1975|
+------------------------------------------------+EVENT TIME:        12:00[EDT]|
| NRC NOTIFIED BY:  TOM McKEE                    |LAST UPDATE DATE:  05/21/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PETER ESELGROTH      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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - COMPONENT COOLING WATER PIPING IS RUN INSIDE A CRANE WALL (NOT MISSILE     |
| PROTECTED) -                                                                 |
|                                                                              |
| During a 10CFR50.54(f) review of the UFSAR, the licensee discovered a        |
| certain component cooling water (CCW) piping run inside a crane wall (i.e.,  |
| not missile protected from LOCA generated missiles by the crane wall) [DER   |
| 99-0840].  After searching plant records, the licensee has not located any   |
| initial engineering documentation justifying the running of piping inside    |
| the crane wall.  Based on this review, the licensee has concluded that the   |
| CCW piping may have been outside the system design basis stated in the UFSAR |
| since original operation of the plant in December 1975.  The licensee        |
| believes that the design requirement (i.e., protected from LOCA generated    |
| missiles) for the system was restored in March 1986 based on the NRC Safety  |
| Evaluation for Generic Safety Issue A-2.  The Safety Evaluation Report (SER) |
| states, in part, that "dynamic effects associated with postulated pipe       |
| breaks in the primary coolant system of this facility need not be a design   |
| basis."                                                                      |
|                                                                              |
| The licensee has declared the CCW piping operable based on the 1986 SER and  |
| is continuing to reconcile the design basis of this issue using the          |
| 10CFR50.59 process.                                                          |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35749       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  L.A. COUNTY DEPT OF HEALTH SERVICES  |NOTIFICATION DATE: 05/21/1999|
|LICENSEE:  KAISER PERMANENTE MED CARE PROGRAM   |NOTIFICATION TIME: 11:15[EDT]|
|    CITY:  LOS ANGELES              REGION:  4  |EVENT DATE:        04/23/1999|
|  COUNTY:                            STATE:  CA |EVENT TIME:        12:00[PDT]|
|LICENSE#:  0372-19               AGREEMENT:  Y  |LAST UPDATE DATE:  05/21/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GARY SANBORN         R4      |
|                                                |LARRY CAMPER         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  STEPHEN DOERFLER             |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THERAPEUTIC MEDICAL MISADMINISTRATION AT KAISER PERMANENTE MEDICAL CARE      |
| PROGRAM OF SOUTHERN CALIFORNIA.                                              |
|                                                                              |
| A PATIENT WAS SCHEDULED FOR THREE THERAPEUTIC TREATMENTS FOR CANCER OF THE   |
| CERVIX USING THE HIGH DOSE RATE AFTERLOADER.  PRIOR TO THE INITIATION OF THE |
| FIRST TREATMENT ON 04/23/99, THE AUTHORIZED USER MADE A "LAST MINUTE" CHANGE |
| IN THE TREATMENT PLAN WITH RESPECT TO THE SOURCE TRAVEL DISTANCE.  AFTER THE |
| CHANGE WAS MADE, THE SETUP CALLED FOR THE SOURCE TO BEGIN AT 989             |
| MILLIMETERS.  THE PHYSICIST, HOWEVER, SET UP THE UNIT SO THAT THE SOURCE     |
| BEGAN ITS TRAVEL AT 889 MILLIMETERS.  PRIOR TO INITIATION OF THE TREATMENT,  |
| THE AUTHORIZED USER, PHYSICIST, AND TECHNOLOGIST SIGNED OFF ON THIS          |
| TREATMENT PLAN.  THE PATIENT WAS THEN TREATED.  THE SOURCE TRAVEL DISTANCE   |
| WAS 100 MILLIMETERS SHORTER THAN THE TREATMENT PLAN REQUIRED, AND DIFFERENT  |
| FROM THAT INTENDED.  IT WAS NOT NOTED DURING OR AFTER COMPLETION OF THIS     |
| TREATMENT.                                                                   |
|                                                                              |
| THE SECOND TREATMENT OCCURRED ON 04/30/99.  A SECOND PHYSICIST, WITHOUT      |
| VERIFYING THE ACCURACY OF THE FIRST TREATMENT, SET UP THE SECOND TREATMENT   |
| USING THE SAME PARAMETERS, A TRAVEL DISTANCE OF 894 MILLIMETERS.  THE        |
| AUTHORIZED USER, PHYSICIST, AND TECHNOLOGIST SIGNED OFF ON THE SECOND        |
| TREATMENT PLAN.  THE TREATMENT WAS ADMINISTERED TO A DIFFERENT LOCATION THAN |
| INTENDED.  THE ERROR WAS NOT NOTED PRIOR TO,  DURING, OR AFTER THIS          |
| TREATMENT.                                                                   |
|                                                                              |
| THE THIRD TREATMENT PERFORMED ON 05/07/99 BY A THIRD PHYSICIST WHO SET UP    |
| THE PARAMETERS CORRECTLY, AS PLANNED (TRAVEL DISTANCE OF 994 MILLIMETERS)    |
| WAS COMPLETED WITHOUT INCIDENT.                                              |
|                                                                              |
| THE THIRD PHYSICIST PERFORMED A CHART REVIEW ON 05/11/99 AND FOUND THE ERROR |
| IN THE 04/23/99 AND 04/30/99 TREATMENTS AND NOTIFIED THE RADIATION THERAPY   |
| ADMINISTRATOR AND CHIEF OF SERVICE.                                          |
|                                                                              |
| THE REGIONAL RADIATION SAFETY OFFICER (RSO) WAS NOTIFIED ON 05/17/99 BY THE  |
| SITE RSO IN VIOLATION OF THE REQUIRED 4 HOUR NOTIFICATION TIME.              |
|                                                                              |
| THE PATIENT AND HIS REFERRING PHYSICIAN WERE NOTIFIED OF THIS INCIDENT ON    |
| 05/18/99.                                                                    |
|                                                                              |
| A COMPLETE INVESTIGATION OF THESE INCIDENTS, INCLUDING A DOSE ASSESSMENT,    |
| AND THE DEVELOPMENT OF AN ACTION PLAN TO PREVENT FURTHER OCCURRENCES WILL BE |
| MADE.                                                                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35750       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 05/21/1999|
|    UNIT:  [] [2] []                 STATE:  AR |NOTIFICATION TIME: 13:38[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        05/21/1999|
+------------------------------------------------+EVENT TIME:        09:39[CDT]|
| NRC NOTIFIED BY:  WAYNE AHO                    |LAST UPDATE DATE:  05/21/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GARY SANBORN         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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CONTROL ROOM ISOLATION & EMERGENCY VENTILATION/FILTRATION SYSTEM (CREVS)     |
| ACTUATION                                                                    |
|                                                                              |
| A Health Physics Technician was transporting a spent fuel pool purification  |
| filter in the vicinity of the radiation detectors for the CREVS system.  The |
| filter had a contact reading of 131 mrem/hour, and 45.4 mrem/hour at 30 cm.  |
| The actuated radiation detector, #2RITS-8750-1B, has a setpoint of 140       |
| counts per minute.,  This filter was placed near the detector, causing the   |
| actuation.                                                                   |
|                                                                              |
| This is not the normal transport path for contaminated filters.  The filter  |
| was triple-bagged, but developed a leak during transport.  The Health        |
| Physics Technician decided to place the filter in a barrel that is normally  |
| used for torn protective clothing, to prevent the spread of contamination.   |
| This barrel is in the vicinity of the control room ventilation radiation     |
| detectors.                                                                   |
|                                                                              |
| At 1035 CDT, the control room ventilation system was returned to normal.     |
|                                                                              |
| Unit 1 was unaffected by this event.                                         |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35751       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS                   REGION:  2  |NOTIFICATION DATE: 05/21/1999|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 13:53[EDT]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        05/21/1999|
+------------------------------------------------+EVENT TIME:        10:16[EDT]|
| NRC NOTIFIED BY:  MARK ELLINGTON               |LAST UPDATE DATE:  05/21/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ANN BOLAND           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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INADVERTENT START OF THE 'B' CONTAINMENT SPRAY PUMP DUE TO AN INVALID START  |
| SIGNAL                                                                       |
|                                                                              |
| While performing the test of the Sequencer Block Circuit and Containment Fan |
| Cooler, Train 'B' (#OST- 1095) with the plant at 100% power, a maintenance   |
| technician placed multimeter leads on the wrong terminal points.  These      |
| terminal points were adjacent to the desired points. This caused an          |
| inadvertent start of the 'B' Containment Spray Pump.  This invalid actuation |
| was the result of an invalid signal generated by the maintenance technician. |
| Investigation indicates that no other components actuated.                   |
|                                                                              |
| The pump was aligned in standby and no flow was admitted to containment.     |
| The pump operated for approximately two minutes with adequate recirculation  |
| flow before it was secured.  No equipment damage occurred and the 'B'        |
| Containment Spray system is currently operable.  The licensee has            |
| conservatively determined that the pump start constitutes an ESF actuation.  |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35752       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 05/21/1999|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 15:02[EDT]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        05/21/1999|
+------------------------------------------------+EVENT TIME:        10:14[EDT]|
| NRC NOTIFIED BY:  STEVE MAREK                  |LAST UPDATE DATE:  05/21/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       15       Power Operation  |15       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24 hour License Condition 2.C.(9) report concerning non-compliance with the  |
| approved fire protection program.                                            |
|                                                                              |
| During a design calculation review, plant engineering department personnel   |
| discovered that cable routing for safety/relief valve (SRV) 'G' is not in    |
| compliance with Appendix R design assumptions for cable separation.  The SRV |
| is used in the dedicated shutdown procedure to control reactor pressure and  |
| to depressurize the plant so that a cold shutdown condition can be achieved  |
| within 10 hours after plant shutdown (UFSAR commitment).  An hourly fire     |
| watch has been established in the affected zone, pending an evaluation by    |
| engineering department personnel.                                            |
|                                                                              |
| The NRC Resident Inspector has been notified of this event notification by   |
| the licensee.                                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35753       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 05/21/1999|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 22:40[EDT]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        05/21/1999|
+------------------------------------------------+EVENT TIME:        20:46[CDT]|
| NRC NOTIFIED BY:  RON RUSTICK                  |LAST UPDATE DATE:  05/22/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - UNIT 1 SCRAMMED FROM 100% POWER DUE TO A SCRAM DISCHARGE VOLUME HIGH LEVEL |
| SIGNAL -                                                                     |
|                                                                              |
| AT 2046 CDT ON 05/21/99, UNIT 1 RECEIVED A 'B' HALF SCRAM SIGNAL DUE TO A    |
| SCRAM DISCHARGE VOLUME HIGH LEVEL SIGNAL.  APPROXIMATELY 45 SECONDS LATER,   |
| UNIT 1 RECEIVED A FULL SCRAM SIGNAL DUE TO A SCRAM DISCHARGE VOLUME HIGH     |
| LEVEL SIGNAL.  THE REACTOR SCRAMMED FROM 100% POWER DUE TO A VALID SCRAM     |
| DISCHARGE VOLUME HIGH LEVEL SIGNAL POSSIBLY DUE TO A LEAKING VALVE ON A      |
| SCRAM DISCHARGE VOLUME HYDRAULIC CONTROL UNIT.                               |
|                                                                              |
| ALL CONTROL RODS INSERTED COMPLETELY.  NO SAFETY/RELIEF VALVES LIFTED.       |
| DECAY HEAT IS BEING DISSIPATED VIA THE STEAM JET AIR EJECTORS AND AUXILIARY  |
| LOADS.  UNIT 1 PRIMARY CONTAINMENT ISOLATION SYSTEM GROUP 2 (STANDBY GAS     |
| TREATMENT SYSTEM) AND GROUP 3 (REACTOR WATER CLEANUP SYSTEM) ACTUATED.  UNIT |
| 1 IS STABLE IN OPERATIONAL CONDITION 3 (HOT SHUTDOWN).  THE LICENSEE IS      |
| INVESTIGATING THE CAUSE OF THE SCRAM DISCHARGE VOLUME HIGH LEVEL SIGNALS.    |
|                                                                              |
| THIS EVENT HAD NO EFFECT ON UNIT 2 WHICH IS OPERATING AT 100% POWER.         |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
|                                                                              |
| * * * UPDATE AT 0800 EDT ON 5/22/99 BY RON RUSTICK TO FANGIE JONES * * *     |
|                                                                              |
| In review of the event it was noted that the Unit 1 diesel generator         |
| auto-started on the transfer of auxiliary power, an ESF actuation.           |
|                                                                              |
| It is also believed that a reactor water cleanup system relief valve lifted, |
| pressurizing the reactor building drain tank and forcing backflow to fill up |
| the scram discharge volume causing the reactor scram.                        |
|                                                                              |
| The licensee informed the NRC Resident Inspector.  The Headquarters          |
| Operations Officer informed the R3DO (Brent Clayton).                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35754       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 05/22/1999|
|    UNIT:  [2] [3] []                STATE:  PA |NOTIFICATION TIME: 01:56[EDT]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        05/21/1999|
+------------------------------------------------+EVENT TIME:        22:20[EDT]|
| NRC NOTIFIED BY:  JIM KOVALCHICK               |LAST UPDATE DATE:  05/22/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PETER ESELGROTH      R1      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PRIMARY CONTAINMENT ISOLATION SYSTEM ACTUATION DUE TO UNEXPECTED POWER LOSS  |
|                                                                              |
| "At 2220 [EDT] on 5/21/99 two of four 4 kVolt emergency electrical buses on  |
| Unit 2 and Unit 3 fast transferred to the alternate offsite feed when the    |
| normal offsite feed unexpectedly deenergized during switching operations.    |
| The momentary power loss that occurred during the fast transfer unexpectedly |
| deenergized control logics that resulted in the following invalid Primary    |
| Containment Isolation System Isolation actuations:                           |
|                                                                              |
| Unit 2                                                                       |
| a) Outboard isolation of Drywell Instrument Nitrogen System                  |
| b) Outboard isolation of Reactor Water Cleanup System                        |
| c) Outboard isolation of Drywell Sump System                                 |
|                                                                              |
| Unit 3                                                                       |
| a) Inboard isolation of Drywell Instrument Nitrogen System                   |
| b) Inboard isolation of Drywell Sump System                                  |
| c) Full Reactor Water Cleanup System isolation                               |
| d) Inboard isolation Containment Atmosphere Sampling System                  |
|                                                                              |
| "The cause of the loss of feed is under investigation.  Both units remain at |
| 100 % power."  Power has been restored to the normal offsite feed, but the   |
| busses are not being transferred back until the cause of the loss of power   |
| is determined.                                                               |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35755       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD                REGION:  3  |NOTIFICATION DATE: 05/22/1999|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 05:10[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        05/22/1999|
+------------------------------------------------+EVENT TIME:        03:15[CDT]|
| NRC NOTIFIED BY:  DENNIS HIGINBOLHAM           |LAST UPDATE DATE:  05/22/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM 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  |
|2     N          Y       60       Power Operation  |60       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PROCESS COMPUTER OUT-OF-SERVICE FOR PLANNED MAINTENANCE                      |
|                                                                              |
| The Plant Process Computer was placed out-of-service for modification to a   |
| inverter power supply and temporary power was not available.  This also      |
| placed the Safety Parameter Display System (SPDS) and the ability to link to |
| the Emergency Response Data System (ERDS) out-of-service.                    |
|                                                                              |
| Preparations for full restoration is in progress and it is expected to be    |
| complete by 0600 CDT.                                                        |
|                                                                              |
| The licensee plans to notify the NRC Resident Inspector.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35756       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK            REGION:  4  |NOTIFICATION DATE: 05/22/1999|
|    UNIT:  [] [2] []                 STATE:  TX |NOTIFICATION TIME: 09:40[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        05/22/1999|
+------------------------------------------------+EVENT TIME:        07:15[CDT]|
| NRC NOTIFIED BY:  GREGORY BRYAN                |LAST UPDATE DATE:  05/22/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GARY SANBORN         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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE 'A' SAFEGUARDS BUS DEENERGIZED CAUSING THE DIESEL GENERATOR TO START AND |
| REENERGIZE IT                                                                |
|                                                                              |
| The Train 'A' Safeguards 6.9 kV electrical bus experienced a lockout relay   |
| actuation (due to a neutral ground overcurrent).  The diesel generator       |
| (2-01) started and energized the bus.  The Blackout Sequencer actuated and   |
| restored the safeguards equipment on the affected bus.  The ESF equipment    |
| that actuated included the 'A' Train Control Room HVAC, motor driven         |
| Auxiliary Feedwater Pump, turbine driven Auxiliary Feedwater Pump ( 'A'      |
| Train only), and the Blackout Sequencer.                                     |
|                                                                              |
| The unit entered the abnormal procedure to respond to the loss of the normal |
| power supply to the Train 'A' Bus and restore from the Blackout Sequencer.   |
|                                                                              |
|                                                                              |
| The cause of the relay actuation is under investigation and the diesel       |
| generator will continue to power the bus  until it is determined what caused |
| the actuation.                                                               |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35757       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  MEAD PAPER CORPORATION               |NOTIFICATION DATE: 05/22/1999|
|LICENSEE:  MEAD PAPER CORPORATION               |NOTIFICATION TIME: 12:01[EDT]|
|    CITY:  CHILLICOTHE              REGION:  3  |EVENT DATE:        05/22/1999|
|  COUNTY:                            STATE:  OH |EVENT TIME:        07:10[EDT]|
|LICENSE#:  34-06188-09           AGREEMENT:  N  |LAST UPDATE DATE:  05/22/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |BRENT CLAYTON        R3      |
|                                                |CHARLEY HAUGHNEY     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JIM SEGELHORST, RSO          |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - OHMART DENSITY GAUGE (20 MILLICURIES Cs-137 SOURCE) IN A FIRE AT A PAPER   |
| PLANT -                                                                      |
|                                                                              |
| AT 0710 ON 05/22/99, A FIRE OCCURRED IN A WOOD CHIP CONVEYOR, POSSIBLY DUE   |
| TO A SEIZED BEARING, AT THE MEAD PAPER CORPORATION FACILITY IN CHILLICOTHE,  |
| OH.  THE LOCAL FIRE DEPARTMENT WAS CALLED AND RESPONDED TO THE FIRE, WHICH   |
| WAS EXTINGUISHED WITHIN APPROXIMATELY 15 MINUTES.  A OHMART DENSITY          |
| GAUGE(MODEL #SH1-00PS), WHICH IS INSTALLED IN THE AREA OF THE FIRE, HAD ITS  |
| OUTER CASE CHARRED AND SLIGHTLY DAMAGED.  THE GAUGE, WHICH CONTAINS A 20     |
| MILLICURIE CESIUM-137 RADIATION SOURCE, APPEARS NOT TO BE DAMAGED.           |
|                                                                              |
| JIM SEGELHORST, MEAD PAPER CORPORATION RADIATION SAFETY OFFICER (RSO)        |
| MEASURED THE SOURCE AND OBTAINED NORMAL READINGS AT A DISTANCE OF            |
| APPROXIMATELY ONE FOOT.  THE RSO BARRICADED THE AREA AROUND THE GAUGE TO     |
| ISOLATE IT FROM PERSONNEL.   A OHMART REPRESENTATIVE IS ON HIS WAY TO THE    |
| SITE AND PLANS TO TAKE POSSESSION OF THE GAUGE AROUND 1500 AND SHIP IT BACK  |
| TO THE MANUFACTURER.  NO PERSONNEL WERE EXPOSED TO RADIATION.                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35758       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 05/23/1999|
|    UNIT:  [2] [] []                 STATE:  PA |NOTIFICATION TIME: 09:30[EDT]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        05/23/1999|
+------------------------------------------------+EVENT TIME:        08:53[EDT]|
| NRC NOTIFIED BY:  CAMERON CAMPBELL             |LAST UPDATE DATE:  05/23/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PETER ESELGROTH      R1      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| SAFETY PARAMETER DISPLAY SYSTEM OUT OF SERVICE DUE TO PLANNED MAINTENANCE    |
|                                                                              |
| The safety parameter display system (SPDS) was placed out of service due to  |
| planned computer maintenance.  Outage on the plant monitoring system         |
| computer will disable SPDS for up to 24 hours.  Operators are taking         |
| compensatory measures for monitoring parameters.                             |
|                                                                              |
| The licensee has notified the NRC resident inspector.                        |
|                                                                              |
| ******************** UPDATE AT 2049 ON 05/23/99 FROM SCOTT PABIS TO LEIGH    |
| TROCINE ********************                                                 |
|                                                                              |
| The planned computer maintenance outage has been completed, and SPDS was     |
| returned to service at 2026.                                                 |
|                                                                              |
| The licensee plans to notify the NRC resident inspector of this update.  The |
| NRC operations officer notified the R1DO (Eselgroth).                        |
+------------------------------------------------------------------------------+