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Event Notification Report for April 13, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/12/1999 - 04/13/1999

                              ** EVENT NUMBERS **

35576  35577  35578  35579  35580  35581  35582  35583  35584  35585  35586  

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35576       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 04/12/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 07:46[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        04/12/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        01:15[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  04/12/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |BRUCE BURGESS        R3      |
|  DOCKET:  0707002                              |FRED COMBS           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  J. B. HALCOMB                |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| VALID ACTUATION OF A 'Q' SAFETY SYSTEM - 24 HOUR REPORT                      |
|                                                                              |
| "At 0115 hrs, on 04/12/99, Operations Personnel in the X-344 facility,       |
| received a steam shutdown alarm on Autoclave #2 during a cylinder heating    |
| (Mode II).  The steam shutdown was caused by the actuation of the High       |
| Condensate Level Shutoff System ('Q' system).  Investigation of the alarm    |
| and completion of 'as found' testing gave indication that the alarm was      |
| caused by an actual high condensate level condition, which cleared after the |
| steam shutdown occurred. The cylinder in this autoclave was disconnected and |
| the autoclave was declared 'inoperable' by the Plant Shift Superintendent.   |
| Testing of the High Condensate Level Shutoff System will be performed by     |
| Maintenance and Engineering personnel. Autoclave #2 will remain              |
| out-of-service pending an Engineering Evaluation and Resolution of the alarm |
| condition."                                                                  |
|                                                                              |
| Portsmouth personnel notified the NRC Resident Inspector and the onsite DOE  |
| representative.                                                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   35577       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  PAYNE FIRM                           |NOTIFICATION DATE: 04/12/1999|
|LICENSEE:  ARVAN INDUSTRIES                     |NOTIFICATION TIME: 10:05[EDT]|
|    CITY:  GREENWOOD                REGION:  3  |EVENT DATE:        04/09/1999|
|  COUNTY:                            STATE:  IN |EVENT TIME:             [CST]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  04/12/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN JACOBSON        R3      |
|                                                |FRED COMBS           NMSS    |
+------------------------------------------------+ROSEMARY HOGAN       IRO     |
| NRC NOTIFIED BY:  DAN WOODY                    |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| RADIATION DEVICE CONTAINING 1 CURIE OF AMERICIUM POSSIBLY STOLEN             |
|                                                                              |
| Arvan Industries of Greenwood, Indiana contacted the Payne Firm (Dan Woody   |
| acting as representative) late Friday, 4/9/99, for consultation concerning a |
| radiation device containing 1 Ci of Am-241 that is believed stolen.  The     |
| device is missing from the Arvan Exhaust Greenwood Facility located at 101   |
| Center St., Greenwood, Indiana during ongoing closure activities.  The       |
| device weighs about 200 pounds, contains a sealed source of 1 Ci of Am-241,  |
| and was used to measure the thickness of rolled steel.  The device, an Xact  |
| Ray Thickness Gauge 3500 Model, serial #48761-1 and source serial #2786LX    |
| was manufactured by the Loral Control Systems of Archbald, Pennsylvania.     |
| The manufacturer is no longer in business.                                   |
|                                                                              |
| There is an ongoing investigation and a written report will be submitted     |
| later.                                                                       |
|                                                                              |
| The police have not been contacted at this time.  It will probably be        |
| reported to the Greenwood, Indiana police of possibly the Indian Highway     |
| police.                                                                      |
|                                                                              |
| NRC HOO notified Mr John Ruyack of the Indiana Dept of Radiation Protection  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35578       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 04/12/1999|
|    UNIT:  [1] [] []                 STATE:  GA |NOTIFICATION TIME: 11:48[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        04/12/1999|
+------------------------------------------------+EVENT TIME:        10:15[EDT]|
| NRC NOTIFIED BY:  COLEMAN                      |LAST UPDATE DATE:  04/12/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WALTER RODGERS       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          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SCRAM PILOT AIR HEADER INADVERTENTLY ISOLATED WHICH RESULTED IN A REACTOR    |
| SCRAM. NO CONTROL ROD MOVEMENT BECAUSE ALL CONTROL RODS WERE ALREADY FULLY   |
| INSERTED.                                                                    |
|                                                                              |
| The licensee received a full Reactor Protection System actuation from Scram  |
| Discharge Volume High Water Level. No control rod movement due to the fact   |
| that all the control rods were already fully inserted into the core. The     |
| licensee was performing a clearance to perform work on an air valve          |
| associated with the Main Steam Isolation Valves.  The Scram Pilot air header |
| was inadvertently isolated when the air line going to the Main Steam         |
| Isolation Valves was isolated.                                               |
|                                                                              |
| The work involved a valve on the air supply line to the outboard MSIVs.  The |
| P&ID was inadequate because it was not evident that the isolation valve used |
| also isolated the scram pilot air header.                                    |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35579       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 04/12/1999|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 15:10[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        04/12/1999|
+------------------------------------------------+EVENT TIME:        14:00[CDT]|
| NRC NOTIFIED BY:  PEDERSON                     |LAST UPDATE DATE:  04/12/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN JACOBSON        R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT DECLARED HPCI INOPERABLE DUE TO THE LOSS OF THE EMERGENCY SERVICE      |
| WATER TO ONE OF TWO VENTILATION UNITS.                                       |
|                                                                              |
| THE EMERGENCY SERVICE WATER WAS LOST AS A RESULT OF THE FAILURE OF #13       |
| EMERGENCY SERVICE WATER PUMP TO START,  WHICH PUT HPCI OUT OF SERVICE AND    |
| THE PLANT IN A 24 HR TO SHUTDOWN LCO ACTION STATEMENT.  WHEN THEY ATTEMPTED  |
| TO START #13 EMERGENCY SERVICE WATER PUMP,  THE MOTOR WOULD HUM BUT THE      |
| IMPELLER WOULD NOT TURN AND THAT RESULTED IN THE TRIP OF THE PUMP BREAKER.   |
| THEY MANUALLY TRIED TO TURN THE IMPELLER , WHICH SEEMED STUCK INITIALLY, BUT |
| THEY FINALLY GOT IT TO TURN FREELY.   THERE MAY HAVE BEEN SOME TYPE OF       |
| DEBRIS THAT WAS CAUSING THE IMPELLER NOT TO TURN.   CURRENTLY THEY ARE       |
| PERFORMING OPERABILITY CHECKS ON THE PUMP SO THAT THE LCO CAN BE EXITED.     |
| DURING THIS EVENT THE NORMAL SERVICE WATER WAS AVAILABLE.                    |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
|                                                                              |
| *** UPDATE ON 4/12/99 @ 1618 BY PEDERSON TO GOULD ***                        |
|                                                                              |
| HPCI OPERABLE AFTER RESTORATION OF THE #13 EMERGENCY SERVICE WATER SYSTEM.   |
| LCO EXITED AT 1507 CDT.                                                      |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
|                                                                              |
| REG 3 RDO(JACOBSON) WAS INFORMED.                                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35580       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  COOPER ENERGY SERVICES               |NOTIFICATION DATE: 04/12/1999|
|LICENSEE:  COOPER ENERGY SERVICES               |NOTIFICATION TIME: 15:55[EDT]|
|    CITY:  GROVE CITY               REGION:  1  |EVENT DATE:        04/12/1999|
|  COUNTY:                            STATE:  PA |EVENT TIME:             [EDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  04/12/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DAN HOLODY           R1      |
|                                                |WALTER RODGERS       R2      |
+------------------------------------------------+JOHN JACOBSON        R3      |
| NRC NOTIFIED BY:  BILLIG (FAX)                 |LINDA SMITH          R4      |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |VERN HODGE           NRR     |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THIS PART 21 IS CONCERNED WITH A POTENTIAL DEFECT IN A COMPONENT ON THE      |
| DSRV-16-4 ENTERPRISE DIESEL GENERATOR SYSTEM.  THE POTENTIAL PROBLEM IS WITH |
| A CONNECTING ROD ASSEMBLIES BUILT SINCE SEPT 1986 THAT USE OR HAVE BEEN      |
| CONVERTED TO USE PRESTRESSED FASTENERS TO ATTACH THE ROD BOX TO THE MASTER   |
| ROD.  THESE NEW ROD ASSEMBLIES (P/N 1A-7802) COME ASSEMBLED WITH PRESTRESSED |
| FASTENERS THAT ARE SUSPECTED TO BE OF INCORRECT LENGTH.  THE PLANTS INVOLVED |
| ARE VOGTLE (ENGINE S/N 76021-4) AND PERRY (ENGINE S/N 75051-2).              |
|                                                                              |
| IN ADDITION,  UTILITIES WITH DSRV-4 ENGINES WHO HAVE PURCHASED REPLACEMENT   |
| P/N 1A-6280 OR 1A-6281 CONNECTING ROD ASSEMBLIES (WITH BOLTS) SINCE SEPT.,   |
| 1986 AND HAVE SUBSEQUENTLY CONVERTED THESE TO PRESTRESSED FASTENERS (OR      |
| PLANNING TO CONVERT) COULD ALSO BE AFFECTED.  THE FOLLOWING SITES MAY BE     |
| AFFECTED GRAND GULF (ENGINE S/N 74033-6), HARRIS (ENGINE S/N 74046-9),       |
| CATAWBA (ENGINE S/N 75017-20), PERRY (ENGINE S/N 75051-4), COMANCHE PEAK     |
| (76001-4), AND VOGTLE (ENGINE S/N 76021-4).                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35581       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER            REGION:  2  |NOTIFICATION DATE: 04/12/1999|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 16:12[EDT]|
|   RXTYPE: [3] B&W-L-LP                         |EVENT DATE:        04/12/1999|
+------------------------------------------------+EVENT TIME:        13:48[EDT]|
| NRC NOTIFIED BY:  SIMON                        |LAST UPDATE DATE:  04/12/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WALTER RODGERS       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       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| KEMPS RIDLEY SEA TURTLE FOUND ALIVE AT THE PLANT'S INTAKE AREA.              |
|                                                                              |
| THE TURTLE WAS TRANSPORTED TO THE MARICULTURE CENTER FOR OVERNIGHT           |
| OBSERVATION.  FLORIDA DEPARTMENT OF ENVIRONMENT HAS BEEN NOTIFIED.           |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35582       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEQUOYAH                 REGION:  2  |NOTIFICATION DATE: 04/12/1999|
|    UNIT:  [] [2] []                 STATE:  TN |NOTIFICATION TIME: 16:45[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/12/1999|
+------------------------------------------------+EVENT TIME:        15:48[EDT]|
| NRC NOTIFIED BY:  HARRIS                       |LAST UPDATE DATE:  04/12/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WALTER RODGERS       R2      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       65       Power Operation  |65       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TWO CONTAINMENT ISOLATION VALVES ON SAME PENETRATION DECLARED INOPERABLE     |
| PLACING PLANT IN 3.0.3 LCO ACTION STATEMENT.                                 |
|                                                                              |
| THE INBOARD AND OUTBOARD CONTAINMENT ISOLATION VALVES ON THE GLYCOL SYSTEM   |
| WERE DECLARED INOPERABLE.  THIS CONDITION OCCURRED DURING A TAGGING ACTIVITY |
| FOR MAINTENANCE.  IT WAS NOTICED THAT THE RED AND GREEN LIGHTS FOR THESE     |
| VALVES WERE BOTH ON.  ENTERING 3.0.3 GIVES THEM ONE HOUR TO REPAIR AND 6     |
| HOURS TO BE IN HOT S/B.  THEY ARE CURRENTLY TROUBLESHOOTING AND COMMENCING   |
| REPAIR.  THEY ONLY NEED TO RETURN ONE OF THE VALVES TO OPERABLE CONDITION SO |
| THAT IT CAN BE ISOLATED WOULD ALLOW THEM TO EXIT 3.0.3.  THE BASIS FOR BEING |
| OUTSIDE THE DESIGN BASIS IS THAT THEY HAVE A PENETRATION WHICH CAN NOT BE    |
| ISOLATED.                                                                    |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED.                                     |
|                                                                              |
| *** UPDATE ON 4/12/99 @ 1756 BY SIMONS TO GOULD *** RETRACTION               |
|                                                                              |
| THE LICENSEE SUCCESSFULLY COMPLETED A VALVE STROKE TEST ON ONE VALVE AFTER   |
| COMPLETION OF THE ADJUSTMENT OF THE VALVE LIMIT SWITCH.  THE VALVE WAS       |
| DECLARED OPERABLE AND THEN ISOLATED WITH POWER REMOVED.  BASED ON THESE      |
| FACTS UNIT 2 WAS NEVER OUTSIDE DESIGN BASIS.  UPON FURTHER REVIEW, ENTRY IN  |
| 3.0.3 WAS NOT REQUIRED, LCO 3.6.1.1 WAS THE CORRECT TS THEY SHOULD HAVE      |
| ENTERED.  THE LICENSEE IS THEREFORE RETRACTING THIS EVENT.                   |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
|                                                                              |
| THE REG 2 RDO(RODGERS) WAS INFORMED.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35583       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 04/12/1999|
|    UNIT:  [1] [2] []                STATE:  AR |NOTIFICATION TIME: 16:59[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        04/12/1999|
+------------------------------------------------+EVENT TIME:        12:30[CDT]|
| NRC NOTIFIED BY:  REHM                         |LAST UPDATE DATE:  04/12/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LINDA SMITH          R4      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE PLANT HAD AN AUTOMATIC ACTUATION OF THE UNITS 1 & 2 CONTROL ROOM         |
| EMERGENCY AIR RECIRCULATION FAN (VSF-9).                                     |
|                                                                              |
| THE ACTUATION OF VSF-9 WAS DUE TO EXCEEDING THE ACTUATION SETPOINT OF 154    |
| CPM FOR THE UNIT 1 CONTROL ROOM SUPPLY VENTILATION RADIATION MONITOR         |
| (2RITS-8001A).  THE EVOLUTION WHICH CAUSED THE BACKGROUND RADIATION LEVELS   |
| TO EXCEED THE RADIATION MONITOR SETPOINT WAS TRANSPORTING  A MULTI-ASSEMBLY  |
| SEALED BASKET (MSB) CONTAINED IN THE MSB TRANSFER CASK (MTC) FROM THE SPENT  |
| FUEL POOL AREA (ELEV 404) TO THE RAILROAD BAY (ELEV 354).  PRIOR TO          |
| COMMENCING THIS EVOLUTION, THE CONTROL ROOM VENTILATION SUPPLY WAS ISOLATED  |
| AND IN RECIRCULATION MODE USING 2VSF-9 (UNIT 2 CONTROL ROOM EMERGENCY AIR    |
| RECIRCULATION FAN).  UNITS 1 AND 2 SHARE A COMMON VENTILATION SYSTEM.  THE   |
| 2RITS-8001A IS LOCATED OUTSIDE OF THE CONTROL ROOM, ADJACENT TO THE SPENT    |
| FUEL POOL AREA.  THE MOVEMENT OF THE MTC NEAR 2RITS-8001A RESULTED IN        |
| INCREASED BACKGROUND RADIATION LEVELS ABOVE THE RADIATION MONITOR ACTUATION  |
| SETPOINT.  HOWEVER, THERE WAS NO INCREASE IN THE CONTROL ROOM VENTILATION    |
| ACTIVITY LEVELS DUE TO THE CONTROL ROOM VENTILATION SYSTEM SUPPLY BEING      |
| ISOLATED.  FIVE MINUTES FOLLOWING THE ACTUATION, THE RADIATION MONITOR       |
| INDICATED 300 CPM.  THE MONITOR PRESENTLY INDICATES THE NORMAL INDICATION OF |
| 90 CPM.  THE RVSF WAS SECURED 2 MINUTES FOLLOWING THE ACTUATION OF VSF-9.    |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35584       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 04/12/1999|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 17:26[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        04/12/1999|
+------------------------------------------------+EVENT TIME:        17:00[EDT]|
| NRC NOTIFIED BY:  FALLACARA                    |LAST UPDATE DATE:  04/12/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAN HOLODY           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       80       Power Operation  |80       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MOTOR CONTROL CENTER (MCC) ENCLOSURE BLOWOUT PANELS OBSTRUCTED.              |
|                                                                              |
| DURING A PLANT WALKDOWN, IT WAS DISCOVERED THAT THE MCC ENCLOSURE BLOWOUT    |
| PANELS WERE OBSTRUCTED BY STEEL CHANNELS ON D8/D9 AND THE D7 SEEMED TO BE    |
| STUCK.  THE ENCLOSURES WERE DEGRADED, BUT STILL OPERABLE UNDER CURRENT       |
| WEATHER CONDITIONS.                                                          |
| THEY WILL REMOVE ANY OBSTRUCTIONS TO THESE BLOWOUT PANELS.                   |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35585       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA                    REGION:  1  |NOTIFICATION DATE: 04/12/1999|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 19:48[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        04/12/1999|
+------------------------------------------------+EVENT TIME:        16:00[EDT]|
| NRC NOTIFIED BY:  MICKLOW                      |LAST UPDATE DATE:  04/12/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAN HOLODY           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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE LICENSEE DETERMINED THAT THE CHEVRON MOISTURE SEPARATORS WERE INSTALLED  |
| BACKWARDS.                                                                   |
|                                                                              |
| THIS CONDITION WAS DISCOVERED DURING MAINTENANCE OF THE CONTAINMENT          |
| RECIRCULATING FAN COOLERS.  THE CHEVRON MOISTURE SEPARATORS EFFECTIVENESS IN |
| REMOVING MOISTURE IN THIS CONDITION IS UNANALYZED, AND MAY DEGRADE THE       |
| CAPABILITY OF ALL 4 CONTAINMENT RECIRC FAN UNITS.  THE UNITS ARE NOT         |
| REQUIRED IN THE PRESENT MODE.   IT HAS NOT YET BEEN DETERMINED HOW LONG THE  |
| SEPARATORS HAVE BEEN INSTALLED BACKWARDS, BUT THEY ARE INVESTIGATING.        |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE INFORMED.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35586       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 04/13/1999|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 05:55[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        04/13/1999|
+------------------------------------------------+EVENT TIME:        04:27[EDT]|
| NRC NOTIFIED BY:  CHRIS HYNES                  |LAST UPDATE DATE:  04/13/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAN HOLODY           R1      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO ROD CONTROL URGENT FAILURE ALARM                  |
|                                                                              |
| During a planned plant shutdown, with the reactor already subcritical,       |
| control bank 'A' group 2 did not move as rods were being inserted.  As a     |
| result, the rod control system received an "Urgent Alarm" which inhibited    |
| manual control rod motion.  The licensee performed a manual trip and all     |
| rods fully inserted.  The problem is being investigated.                     |
|                                                                              |
| Heat removal was and is by steam dump to the main condenser with feedwater   |
| from the main feedwater system.                                              |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+