U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/31/98 - 04/01/98 ** EVENT NUMBERS ** 33952 33994 33995 33996 33997 33998 33999 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33952 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 03/24/98 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 11:16 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 03/24/98 | +------------------------------------------------+EVENT TIME: 09:33[CST]| |NRC NOTIFIED BY: CAROL BARAJAS |LAST UPDATE DATE: 03/31/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MIKE JORDAN RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 99 POWER OPERATION | 99 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION ENTRY AFTER SCRAM DISCHARGE VOLUME BARTON LEVEL | | SWITCHES WERE DECLARED INOPERABLE. | | | | AT 0933 CST ON 03/24/98, THE LICENSEE INITIATED A SHUTDOWN OF UNIT 3 AFTER | | ENTERING TECHNICAL SPECIFICATION 3.1.A.2, TABLE 3.1.A-1, ACTION 11, AT 0746 | | CST ON 03/24/98, WHICH REQUIRES THE UNIT TO BE IN HOT SHUTDOWN WITHIN 12 | | HOURS. THIS IS DUE TO THE SCRAM DISCHARGE VOLUME BARTON LEVEL SWITCHES | | POSSIBLY BEING INOPERABLE DUE TO NON-CONSERVATIVE SETPOINTS. THERE ARE | | FOUR BARTON LEVEL SWITCHES IN QUESTION; TWO OF EACH INPUT INTO A REACTOR | | PROTECTION SYSTEM (RPS) CHANNEL (TWO TO RPS 'A' AND TWO TO RPS 'B'). | | REACTOR PROTECTION SYSTEM CHANNEL 'A' WAS PLACED IN A TRIP CONDITION AT | | 0840 CST ON 03/24/98 PER TECHNICAL SPECIFICATION 3.1.A.2 AFTER BOTH RPS | | CHANNELS WERE DECLARED INOPERABLE. THE LICENSEE IS VERIFYING THE AS-FOUND | | DATA ON THE SCRAM DISCHARGE VOLUME LEVEL SWITCHES. THE SCRAM DISCHARGE | | VOLUME LEVEL SWITCHES' CALCULATION FROM 1991 MAY BE IN ERROR IN THE | | NON-CONSERVATIVE DIRECTION. THE 41-GALLON SCRAM DISCHARGE VOLUME TRIP | | SETPOINT (MEASURED IN MILLIAMPS) MAY BE SET LESS CONSERVATIVELY THAN IT | | SHOULD HAVE BEEN SET. | | | | ALL EMERGENCY CORE COOLING SYSTEMS AND THE EMERGENCY DIESEL GENERATORS ARE | | FULLY OPERABLE IF NEEDED. THE ELECTRICAL GRID IS STABLE. | | | | THE LICENSEE FOUND OUT ABOUT THIS PROBLEM FROM A TELEPHONE CONVERSATION | | WITH QUAD CITIES. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE AT 0129 ON 03/31/98 FROM DAN DALY ENTERED BY JOLLIFFE * * * | | | | LICENSEE INVESTIGATION OF TECHNICAL SPECIFICATION OPERABILITIES DETERMINED | | THAT THE SWITCHES MET ALL TECHNICAL SPECIFICATION REQUIREMENTS. ALTHOUGH A | | POWER REDUCTION OF UNIT 3 HAD BEEN INITIATED, NOTIFICATION TO THE NRC WAS | | NOT REQUIRED DUE TO THE SWITCHES BEING OPERABLE. THEREFORE, THIS | | OCCURRENCE DID NOT MEET THE REPORTING REQUIREMENTS SPECIFIED BY 10CFR50.72 | | AS A TECHNICAL SPECIFICATION REQUIRED PLANT SHUTDOWN. THEREFORE, THE | | LICENSEE DESIRES TO RETRACT THIS EVENT. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS OFFICER NOTIFIED THE R3DO (BRUCE BURGESS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33994 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 03/31/98 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 10:51 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/18/98 | +------------------------------------------------+EVENT TIME: 06:14[EST]| |NRC NOTIFIED BY: DENNIS MAY |LAST UPDATE DATE: 03/31/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL RULAND RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 86 POWER OPERATION | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CORE SPRAY PUMP INOPERABLE DUE TO EXTRA INSTALLED WASHERS IN CIRCUIT | | BREAKER - | | | | AT 0614 ON 03/18/98, WITH THE PLANT AT 86% POWER, A ROVING FIRE WATCH | | STANDER NOTIFIED THE CONTROL ROOM THAT HE HEARD AN UNUSUAL NOISE IN A | | SWITCHGEAR ROOM. AFTER INVESTIGATION, THE LICENSEE DECLARED THE CIRCUIT | | BREAKER AND THE 'B' CORE SPRAY PUMP INOPERABLE. TECH SPEC LCO A/S 3.5.A.2 | | REQUIRES THE LICENSEE TO RESTORE THE CORE SPRAY PUMP TO OPERABLE STATUS | | WITHIN 7 DAYS OR TO SHUT THE PLANT DOWN. MAINTENANCE ACTIVITY HAD BEEN | | RECENTLY PERFORMED ON THIS BREAKER. THE LICENSEE REMOVED THE BREAKER, | | DISASSEMBLED IT, AND DETERMINED THAT TWO EXTRA WASHERS HAD BEEN INSTALLED | | INSIDE THE BREAKER DURING THE RECENT MAINTENANCE ACTIVITY. THE LICENSEE | | REMOVED THE WASHERS, REINSTALLED THE BREAKER, SATISFACTORILY TESTED IT, | | DECLARED THE BREAKER AND THE 'B' CORE SPRAY PUMP OPERABLE, AND EXITED THE | | ACTION STATEMENT. THE LICENSEE DETERMINED THAT THIS ANOMALY DID NOT EXIST | | ON OTHER SIMILAR BREAKERS IN THE PLANT. THE LICENSEE PLANS TO REVISE THE | | MAINTENANCE PROCEDURE, AS NECESSARY, TO CORRECT THIS PROBLEM. | | | | ON 03/20/98, THE LICENSEE SHUT THE PLANT DOWN TO BEGIN A SCHEDULED | | REFUELING OUTAGE. | | | | AT 0945 ON 03/31/98, THE LICENSEE DETERMINED THIS EVENT TO BE REPORTABLE | | TO THE NRC. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND PLANS TO SUBMIT A | | LICENSEE EVENT REPORT TO THE NRC ON THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33995 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 03/31/98 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 13:44 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 03/31/98 | +------------------------------------------------+EVENT TIME: 12:55[EST]| |NRC NOTIFIED BY: FALLACARA |LAST UPDATE DATE: 03/31/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL RULAND RDO | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | QUESTIONABLE SEISMIC OPERABILITY OF RESIDUAL HEAT REMOVAL QUADRANT COOLERS | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "DURING THE PERFORMANCE OF DETAILED EVALUATIONS TO DETERMINE APPROPRIATE | | ACTIONS TO RESOLVE AN OUT-LIER CONDITION RELATING TO THE VIBRATION | | ISOLATION SUPPORT FEET IDENTIFIED IN THE INITIAL PHASES OF THE A-46 | | PROGRAM, THE SEISMIC OPERABILITY OF [RESIDUAL HEAT REMOVAL] QUADRANT | | COOLERS VAC 204A, B, C, AND D IS JUDGED TO BE QUESTIONABLE. THE ASPECT | | RATIO (HEIGHT TO WIDTH) OF THE EQUIPMENT AND LACK OF TOP SUPPORT COULD | | RESULT IN POTENTIALLY SIGNIFICANT ROCKING MOTION DURING A SEISMIC EVENT | | WHICH IN TURN COULD LEAD TO FAILURE OF THE SUPPORT FEET." | | | | THE UNIT IS CURRENTLY IN A 24-HOUR TO COLD SHUTDOWN LIMITING CONDITION FOR | | OPERATION. IF CORRECTIVE MEASURES CANNOT BE IMPLEMENTED WITHIN 12 HOURS, | | THE LICENSEE PLANS TO COMMENCE A UNIT SHUTDOWN. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33996 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/31/98 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 13:51 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/31/98 | +------------------------------------------------+EVENT TIME: 12:55[EST]| |NRC NOTIFIED BY: LONG |LAST UPDATE DATE: 03/31/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL RULAND RDO | |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 +------------------------------------------------------------------------------+ | THE LICENSEE HAS CONCLUDED THE ABILITY OF THE ELECTRICAL TUNNEL EXHAUST | | FANS TO AUTOMATICALLY START AND COOL THE CABLE SPREADING ROOM IS NOT | | ASSURED. | | | | ENGINEERING HAS CONCLUDED THAT THE ABILITY OF THE ELECTRICAL TUNNEL | | VENTILATION SYSTEM EXHAUST FANS TO AUTOMATICALLY START AND COOL THE CABLE | | SPREADING ROOM DURING DESIGN BASIS EVENTS IS NOT ASSURED. THE THERMOSTATS | | WHICH CONTROL THE ELECTRICAL TUNNEL EXHAUST FANS ARE LOCATED IN THE | | ELECTRICAL TUNNEL. A LOSS OF CABLE SPREADING ROOM VENTILATION WOULD OCCUR | | UNDER ANY OF THE FOLLOWING ACCIDENTS: DESIGN BASIS EVENT, LOSS OF OFFSITE | | POWER, SAFETY INJECTION, OR LOSS OF MOTOR CONTROL CENTER 39. THE | | THERMOSTATS IN THE ELECTRICAL TUNNEL MAY NOT START THE ELECTRICAL TUNNEL | | EXHAUST FANS SOON ENOUGH WHEN THE TEMPERATURES IN THE CABLE SPREADING ROOM | | BECOME ELEVATED. THIS COULD POTENTIALLY PLACE THE PLANT OUTSIDE DESIGN | | BASIS. INITIAL CORRECTIVE ACTION WILL BE TO KEEP TUNNEL EXHAUST FANS IN | | SERVICE AND ESTABLISH A SPECIAL LOG TO MONITOR TEMPERATURE LOCALLY ONCE A | | SHIFT. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33997 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/31/98 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 16:13 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/31/98 | +------------------------------------------------+EVENT TIME: 15:55[EST]| |NRC NOTIFIED BY: VAIL |LAST UPDATE DATE: 03/31/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL RULAND RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | A POSTULATED SINGLE FAILURE CAN COMPROMISE BOTH REDUNDANT SAFEGUARDS | | DIVISIONS DUE TO CIRCUIT MISCOORDINATION. | | | | MOTOR CONTROL CENTERS (MCC) "EF3" (aka 2-3NE) AND "FE3" (aka 2A-3NE) SUPPLY | | LOW PRESSURE COOLANT INJECTION (LPCI) VALVES FOR THE S1 AND S2 TRAINS, | | RESPECTIVELY. SINCE THESE LOADS HAVE BEEN DEEMED TO BE CRITICAL IN NATURE, | | PROVISIONS WERE INCORPORATED INTO THE PLANT'S DESIGN SO THAT BACKUP | | ELECTRIC POWER WOULD BE MADE AVAILABLE AUTOMATICALLY IN THE EVENT OF THE | | LOSS OF THE NORMAL SUPPLY TO THESE MCCs. THIS FEATURE WAS IMPLEMENTED VIA | | THE USE OF AUTOMATIC BUS TRANSFER SWITCHES (ABT). EACH ABT HAS A NORMAL | | SUPPLY FROM ONE SAFEGUARDS TRAIN AND AN EMERGENCY SUPPLY FROM THE REDUNDANT | | SAFEGUARDS TRAIN. | | | | NORMAL SUPPLY TO MCC "EF3" (S1) IS FROM MCC "E3" (aka 2-3 IN THE S1 TRAIN), | | AND THE EMERGENCY OR ALTERNATE SUPPLY IS FROM MCC "F3" (aka 2A-3 IN THE S2 | | TRAIN). SIMILARLY, THE NORMAL SUPPLY TO MCC "FE3" (S2 TRAIN) IS FROM MCC | | "F3"(S2 TRAIN), AND ITS EMERGENCY SUPPLY IS FROM MCC "E3" (S1 TRAIN). THE | | FOUR MOLDED CASE CIRCUIT BREAKERS (MCCB), LOCATED ON MCCs "E3" AND "F3," | | TWO EACH, THAT SUPPLY THE TWO ABTs EACH HAVE A CONTINUOUS CURRENT RATING OF | | 300 AMPS. THE SUPPLY TO MCC "E3" (S1) IS DERIVED FROM THE LOAD CENTER (LC) | | BUS 12E (S1), AND THE SUPPLY TO MCC "F3" (S2) IS DERIVED FROM LC BUS 12F | | (S2). THE LC BREAKER SUPPLYING MCC "E3" (S1) HAS A LONG TIME TRIP SETPOINT | | OF 300A, AND THAT SUPPLYING MCC "F3" (S2) HAS A 313.5A SETPOINT. | | | | THE FOUR 300A MCCBs WHICH SUPPLY MCCs "EF3" AND "FE3" ARE SIGNIFICANTLY | | LARGER THAN THE REMAINING CIRCUIT BREAKERS ON MCCs "E3" AND "F3". WHEN THE | | LONG TIME TRIP SETPOINTS WERE ESTABLISHED FOR THE TWO LC BREAKERS SUPPLYING | | MCCs "E3" AND "F3," IT WAS REALIZED THAT IF THE LC BREAKERS WERE | | COORDINATED WITH THE DOWNSTREAM MCCs "EF3" AND "FE3", THEN THE CABLES | | SUPPLYING MMCs "E3" AND "F3" WOULD NOT BE PROPERLY PROTECTED. THEREFORE, A | | DECISION WAS TAKEN TO PROTECT THE CABLES WITH THE KNOWLEDGE THAT THE | | UPSTREAM LC BREAKERS WOULD NOT COORDINATE WITH THE MCC BREAKERS. | | | | THIS RESULTS IN A CONDITION WHEREBY AN ELECTRICAL OVERLOAD/FAULT ON EITHER | | MCC "EF3" OR "FE3" COULD CAUSE ITS RESPECTIVE NORMAL SOURCE LC BREAKER TO | | CLEAR THE OVERLOAD/FAULT VERSUS CLEARING THE OVERLOAD/FAULT AT THE | | RESPECTIVE MCC "E3" OR "F3". BECAUSE OF THE RESULTANT OVER TRIPPING | | CONDITION, THE CLEARING OF THE OVERLOAD/FAULT AT THE LC CAUSES THE LOSS OF | | ALL SAFEGUARDS LOADS ON THE RESPECTIVE MCC "E3" OR "F3" BEYOND THOSE | | ACTUALLY OVERLOADED OR FAULTED. THEN, WITH THE ABT SENSING NO VOLTAGE, IT | | TRANSFERS TO THE OTHER TRAIN. GIVEN THE ORIGINAL OVERLOAD/FAULT CONDITION | | HAS NOT BEEN RECTIFIED, THIS COULD IMPACT THE REDUNDANT SAFEGUARDS TRAIN IN | | THE SAME MANNER. | | | | DURING THE SYSTEMATIC EVALUATION PROGRAM (SEP), THE SUBJECT ABTs WERE | | EVALUATED DUE TO CONCERNS ABOUT TRANSFERRING FAULTS FROM ONE TRAIN INTO | | ANOTHER. RESOLUTION OF SEP TOPIC VI-7.C.1, INDEPENDENCE OF REDUNDANT | | ONSITE POWER SYSTEMS, DID ALLOW FOR THE USE OF THE ATBs, BUT IT WAS | | PREDICATED UPON HAVING PROTECTED DEVICE COORDINATION. AS INDICATED ABOVE, | | THE MCC MCCBs ARE NOT COORDINATED WITH THE UPSTREAM LC CIRCUIT BREAKERS. | | | | IN THE EVENT OF A POSTULATED LOCA AND POSTULATING A SINGLE FAILURE OF MCC | | "EF3" OR "FE3", IT IS POSSIBLE THAT ALL SAFETY-RELATED LOADS ON REACTOR | | BUILDING MCCs "E3" AND "F3", WHICH ARE REDUNDANT TO EACH OTHER, COULD BE | | LOST DUE TO THE MISCOORDINATION OF THE ELECTRICAL PROTECTIVE DEVICES AND | | THE CONSEQUENTIAL TRIPPING OF THE UPSTREAM LOAD CENTER CIRCUIT BREAKERS. IN | | ADDITION TO COMPROMISING THE LPCI SYSTEM, THIS WOULD ALSO COMPROMISE THE | | CORE SPRAY SYSTEM TOO. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. STATE AND | | LOCAL AGENCIES WERE NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33998 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/31/98 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 17:03 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/31/98 | +------------------------------------------------+EVENT TIME: 16:45[EST]| |NRC NOTIFIED BY: SMITH |LAST UPDATE DATE: 03/31/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL RULAND RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | |FEMA, DOE, DOA, HHS FAX | | |EPA, DOT(VIA NRC) FAX | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE CONNECTICUT DEPARTMENT OF ENVIRONMENTAL | | PROTECTION OF A HYDRAULIC OIL SPILL ON THE SITE ACCESS ROAD. | | | | APPROXIMATELY 12-15 GALLONS OF HYDRAULIC OIL FROM A CONSTRUCTION BACK HOE | | SPILLED ONTO THE SITE ACCESS ROAD. THE SPILL WAS CONTAINED AND CLEANED UP | | BY THE ONSITE FIRE PROTECTION PEOPLE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33999 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/01/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 02:57 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/31/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 10:30[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/01/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |BRUCE BURGESS RDO | | DOCKET: 0707002 |LARRY CAMPER/NMSS EO | +------------------------------------------------+RICHARD BARRETT/AEOD IRD | |NRC NOTIFIED BY: ERICK SPAETH | | |HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NRC BULLETIN 91-01 RESPONSE, 24-HOUR REPORT | | | | WHILE NUCLEAR CRITICALITY SAFETY (NCS) DEPARTMENT PERSONNEL WERE PERFORMING | | A WALKDOWN OF THE X-333 PROCESS BUILDING, THEY DISCOVERED 3 NCS APPROVAL | | (NCSA) REQUIREMENTS THAT WERE NOT BEING MAINTAINED. 1) AT A BOUNDARY | | CONTROL STATION, A BOTTLE OF LIQUID WAS FOUND IN A DRY ACTIVE WASTE DRUM. | | THIS IS A VIOLATION OF CONTROL "B" (MODERATION). 2) AT A MAINTENANCE | | STORAGE AREA, A CONTAMINATED VALVE WAS NOT SPACED THE MINIMUM OF 2 FEET | | FROM A PIECE OF CONTAMINATED PROCESS PIPING. THIS IS A VIOLATION OF | | CONTROL "B" (INTERACTION). 3) AT A PROCESS STORAGE AREA, 3 CONTAINERS OF | | PROCESS COMPONENTS WERE DISCOVERED WITHOUT THE LIDS PROPERLY SECURED WHILE | | UNATTENDED. THIS IS A VIOLATION OF CONTROL "A" (MODERATION). IN EACH | | CASE, THE SECOND CONTROL WAS MET RESULTING IN THE LOSS OF 1 OF 2 CONTROLS. | | THE VIOLATIONS WERE IMMEDIATELY CORRECTED IN EACH CASE. | | | | THERE WAS NO LOSS OF HAZARDOUS OR RADIOACTIVE MATERIAL OR RADIOACTIVE OR | | RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THESE EVENTS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND THE ONSITE DEPARTMENT | | OF ENERGY REPRESENTATIVE. | +------------------------------------------------------------------------------+