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. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021