U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/02/97 - 06/03/97 ** EVENT NUMBERS ** 32427 32428 32429 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32427 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 06/02/97 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 06:41 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/02/97 | +------------------------------------------------+EVENT TIME: 06:05[EDT]| |NRC NOTIFIED BY: KEN HOFFMAN |LAST UPDATE DATE: 06/02/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES HOSEY RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | |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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION 3.0.3 ENTRY DUE TO BOTH TRAINS OF CONTROL ROOM AREA | | VENTILATION BEING INOPERABLE | | | | AS A RESULT OF AN AUXILIARY VENTILATION BOUNDARY DOOR BEING OPEN WITHOUT | | CONTINGENCY ACTIONS BEING IN PLACE, THE UNIT ENTERED THE ACTION STATEMENT | | FOR TECHNICAL SPECIFICATION 3.0.3 DUE TO BOTH TRAINS OF THE CONTROL ROOM | | AREA VENTILATION SYSTEM BEING INOPERABLE. THE DOOR WAS OPENED IN ORDER TO | | FACILITATE A BATTERY REPLACEMENT. THE DOOR WAS CLOSED WITHIN APPROXIMATELY | | 10 MINUTES, AND THE ACTION STATEMENT FOR TECHNICAL SPECIFICATION 3.0.3 WAS | | EXITED. IN ADDITION, BOTH TRAINS OF THE AUXILIARY BUILDING VENTILATION | | SYSTEM WERE INOPERABLE AT THE SAME TIME. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32428 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/02/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 07:48 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/01/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 22:25[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/02/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JOHN JACOBSON RDO | | DOCKET: 0707002 |DON COOL, NMSS EO | +------------------------------------------------+STUART RUBIN, AEOD IRD | |NRC NOTIFIED BY: KEITH VANDERPOOL | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - STEAM SHUTDOWN OF AUTOCLAVE WHILE HEATING A 48-INCH UF6 CYLINDER - | | | | AT 2225 ON 06/01/97, WHILE HEATING A 48-INCH UF6 CYLINDER IN AUTOCLAVE #4, | | THE OPERATOR AT X-344A RECEIVED AN AUDIBLE AND VISUAL ALARM INDICATING A | | STEAM SHUTDOWN OF THE AUTOCLAVE. AT 2230, AUTOCLAVE #4 WAS SHUT DOWN AND | | DECLARED INOPERABLE. | | | | A LARGE AMOUNT OF CONDENSATE WAS REMOVED FROM THE DRAIN LINE INDICATING | | THAT A VALID SAFETY SYSTEM ACTUATION HAD OCCURRED DUE TO A POTENTIAL DRAIN | | LINE PLUG OR RESTRICTION. AN INVESTIGATION REVEALED THAT BOTH HIGH LEVEL | | CONDENSATE ALARMS WERE ACTIVATED CAUSING THE STEAM TO SHUT DOWN. THERE WAS | | NO RELEASE OF HAZARDOUS MATERIALS OR RADIOLOGICAL CONTAMINATION EXPOSURE | | ASSOCIATED WITH THIS ACTIVATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32429 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 06/02/97 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 12:55 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 06/02/97 | +------------------------------------------------+EVENT TIME: 11:11[CDT]| |NRC NOTIFIED BY: LARRY HENRY |LAST UPDATE DATE: 06/02/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |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 STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 EXPERIENCED AN AUTOMATIC REACTOR TRIP FROM 100% POWER DUE TO A ROD | | CONTROL CABINET FAILURE. | | | | WHILE OPERATING AT 100% REACTOR POWER, OPERATORS RECEIVED A NON-URGENT THEN | | AN URGENT ROD CONTROL FAILURE ALARM FOLLOWED BY AN AUTOMATIC REACTOR TRIP | | FROM NEGATIVE RATE. ALL RODS FULLY INSERTED. NONE OF THE PRIMARY OR | | SECONDARY POWER-OPERATED RELIEF VALVES OR SAFETY RELIEF VALVES LIFTED. | | | | UNIT 1 IS CURRENTLY STABLE IN MODE 3 WITH DECAY HEAT BEING REMOVED VIA THE | | STEAM GENERATORS TO THE MAIN CONDENSER USING THE MOTOR-DRIVEN AUXILIARY | | FEEDWATER PUMP TO MAINTAIN STEAM GENERATOR WATER LEVEL. THE TURBINE-DRIVEN | | AUXILIARY FEEDWATER PUMP AUTOMATICALLY STARTED AS EXPECTED AND HAS SINCE | | BEEN SECURED. OFFSITE POWER IS STABLE, AND ALL SAFETY-RELATED EQUIPMENT | | (INCLUDING THE EMERGENCY DIESEL GENERATORS) IS AVAILABLE. THE LICENSEE IS | | TROUBLESHOOTING TO IDENTIFY AND CORRECT THE ROD CONTROL PROBLEM. THE | | PRELIMINARY INDICATION IS THAT ONE OF THE FOUR ROD CONTROL CABINETS LOST | | POWER. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE LICENSEE WAS NOT | | CERTAIN WHETHER A PRESS RELEASE WOULD BE ISSUED. | +------------------------------------------------------------------------------+