U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/16/97 - 04/17/97 ** EVENT NUMBERS ** 32107 32134 32160 32161 32162 32163 32164 32165 32166 32167 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32107 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/08/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 17:08 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/07/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:30[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/16/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |JOHN MADERA RDO | | DOCKET: 0707001 |JOHN GREEVES EO | +------------------------------------------------+STUART RUBIN IRD | |NRC NOTIFIED BY: UNDERWOOD | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED ON 4/7/97 THAT A SAFETY SYSTEM COMPONENT WAS | | REPLACED BY A COMPONENT WHICH DID NOT MEET ENGINEERING AND CONFIGURATION | | CONTROL REQUIREMENTS OF A "Q" (SAFETY SYSTEM) COMPONENT. | | | | THE COMPONENT IN QUESTION WAS A COMPRESSED GAS CYLINDER USED TO SUPPLY | | NITROGEN TO THE CRITICALITY ACCIDENT ALARM SYSTEM(CAAS) HORNS AS A BACK-UP | | TO THE PRIMARY PLANT AIR SUPPLY TO THE HORNS. THE NITROGEN CYLINDER IS | | WITHIN THE "Q" BOUNDARY OF THE CAAS AND IS REQUIRED TO BE CONTROLLED AS A | | "Q" COMPONENT. THE CYLINDER HAD BEEN REPLACED ON 4/5/97 AND WHEN THE | | DISCREPANCY WAS DISCOVERED, THE CAAS CLUSTER IN QUESTION(C-333 CLUSTER Z) | | WAS IMMEDIATELY DECLARED INOPERABLE. SINCE THERE IS NO TOTAL OVERLAPPING | | CAAS COVERAGE IN THE BUILDING FOR THIS CLUSTER, THE REQUIRED TSR LCO | | ACTIONS WERE INITIATED. THE CYLINDER WAS REPLACED WITH ONE WHICH MEETS THE | | "Q" SPECIFICATIONS AND THE BUILDING WAS RETURNED TO SERVICE. THE RESIDENT | | INSPECTOR WAS NOTIFIED. | | | | ***UPDATE ON 4/16/97 @ 1522 BY BOREN TO GOULD*** | | | | THE LICENSEE IS RETRACTING THIS EVENT SINCE LICENSEE ENGINEERING COMPLETED | | AN OPERABILITY EVALUATION WHICH CONCLUDED THAT THE NON-Q NITROGEN CYLINDER | | INSTALLED IN THE C-333 CAAS CLUSTER "Z" WAS EQUIVALENT TO THE "Q" NITROGEN | | CYLINDER WHICH SHOULD HAVE BEEN INSTALLED. THUS, THE CAAS CLUSTER WAS | | OPERABLE AND THIS CONDITION IS NOT REPORTABLE. THE LICENSEE INFORMED THE | | NRC RESIDENT INSPECTOR. THE HOO NOTIFIED R3DO BRUCE BURGESS. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32134 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 04/11/97 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 14:42 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/11/97 | +------------------------------------------------+EVENT TIME: 13:00[CDT]| |NRC NOTIFIED BY: HENNIG |LAST UPDATE DATE: 04/16/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |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 +------------------------------------------------------------------------------+ | LICENSEE DETERMINED THAT THE ALARM SETPOINT OF 105 AMPS FOR THE P15A HIGH | | HEAD SI PUMP MOTOR PROTECTIVE RELAY WAS NON-CONSERVATIVE. | | | | "DURING AN EXTENSIVE REVIEW OF A 10 CFR 50.59 SAFETY EVALUATION FOR THE | | RESETTING OF THE P15A HIGH HEAD SI PUMP MOTOR PROTECTIVE RELAYING, IT WAS | | DETERMINED THAT THE EVALUATION WAS IN ERROR IN ALLOWING THE ALARM PORTION | | OF THE RELAY TO BE SET ABOVE THE MAXIMUM FULL LOAD CURRENT TIMES THE | | SERVICE FACTOR. FULL LOAD (85 AMPS) TIMES SERVICE FACTOR (1.15) EQUALS | | 97.75 AMPS. HOWEVER, THE ALARM WAS SET TO 105 AMPS. THIS WOULD PREVENT | | THE RECEIPT OF AN OPERATOR ANNUNCIATOR PROVIDING INDICATION OF PUMP | | OPERATION OUTSIDE IT'S DESIGN BASIS. THE RELAYING WAS RESET ON FEB 6, 1997 | | AND UNIT 1 WAS SHUTDOWN FOR AN EXTENDED MAINTENANCE OUTAGE ON FEB 18, 1997. | | THE RELAYING FOR UNIT 2 HAD ALSO BEEN RESET ON FEB 6, 1997 BUT SINCE THE | | UNIT WAS DEFUELED THE CONDITION IS NOT REPORTABLE FOR UNIT 2. BOTH UNIT 1 | | AND 2 P15A HIGH HEAD SI PUMPS HAVE BEEN DECLARED INOPERABLE. AS CORRECTIVE | | ACTION THE RELAYS WILL BE RECALIBRATED OR MODIFIED TO ENSURE PROTECTION AND | | ALARMS ARE PROVIDED FOR DESIGN CONDITIONS BEFORE LEAVING COLD SHUTDOWN." | | THE LICENSEE INITIATED THE 50.59 EVALUATION IN RESPONSE TO AN EVENT WHICH | | OCCURRED DURING TESTING ON FEB 5, 1997 (SEE EVENT #31737). THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE ON 4/16/97 @ 1459 BY JAECKLE TO GOULD*** | | | | THE LICENSEE IS RETRACTING THIS EVENT BECAUSE SYSTEM DESIGN & OPERATION IS | | EXPECTED TO PREVENT OPERATION OUTSIDE THE DESIGN BASIS AND THE PUMP WAS NOT | | OPERATED OR TESTED IN A CONDITION OUTSIDE THE DESIGN BASIS. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED R3DO BRUCE BURGESS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32160 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: US ARMY ROCK ISLAND ARSENAL |NOTIFICATION DATE: 04/16/97 | | CITY: REGION: 4 |NOTIFICATION TIME: 11:07 [ET]| | COUNTY: STATE: LA |EVENT DATE: 04/08/97 | |LICENSE#: 12-00722-06 AGREEMENT: Y |EVENT TIME: 11:20[CDT]| | DOCKET: |LAST UPDATE DATE: 04/16/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BRUCE BURGESS, R3 RDO | | | | +------------------------------------------------+BILL JONES, R4 RDO | |NRC NOTIFIED BY: MOHS, ROCK ISLAND ARSENAL | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TRITIUM SOURCE ON A HOWITZER SPILLED ONTO THE GROUND AT FORT POLK, LA - | | | | WHILE BEING TOWED FROM ONE LOCATION TO ANOTHER AT FORT POLK, LA, AN M-198 | | HOWITZER OVERTURNED BREAKING A 6 INCH X 6 INCH X 4 INCH M-18 UPPER LEVEL | | FIRE CONTROL VIAL AND A 75 MILLICURIE TRITIUM SOURCE WHICH SPILLED ONTO | | THE GROUND. WIPES OF THE HOWITZER SITE MOUNT MEASURED LESS THAN 4500 DPM. | | THE 5 TIMES ANNUAL-LIMIT-OF-INTAKE LIMIT OF 0.4 CURIE WAS NOT EXCEEDED. | | THE HOWITZER WAS MOVED TO A SECURED AREA AND QUARANTINED. THE RADIATION | | PROTECTION OFFICER SCOOPED UP APPROXIMATELY 2 GALLONS OF CONTAMINATED DIRT | | AND DISPOSED OF IT AS RADIOACTIVE WASTE. NO PERSONNEL WERE CONTAMINATED. | | THE LICENSEE IS CONTINUING TO INVESTIGATE THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32161 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/16/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 11:32 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/16/97 | +------------------------------------------------+EVENT TIME: 11:15[EDT]| |NRC NOTIFIED BY: P. SCHMIDTKNECHT |LAST UPDATE DATE: 04/16/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN RDO | |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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MOST OF THE COATING IN THE TORUS IS UNQUALIFIED WHICH COULD AFFECT THE | | OPERABILITY OF THE LOW PRESSURE COOLANT INJECTION AND CORE SPRAY SYSTEMS | | DURING A DESIGN BASIS LOSS OF COOLANT ACCIDENT. | | | | LICENSEE ENGINEERING PERSONNEL DETERMINED THAT AN UNQUALIFIED COATING | | (PAINT) OF THE TORUS MAY NOT REMAIN INTACT DURING A DESIGN BASIS LOSS | | OF COOLANT ACCIDENT. THE COATING MIGHT PEEL OFF AND CLOG THE SUCTION | | STRAINERS FOR THE FOUR LOW PRESSURE COOLANT INJECTION PUMPS AND THE TWO | | CORE SPRAY PUMPS. DURING THE LAST TWO REFUELING OUTAGES (#15 IN 1995 | | AND #14 IN 1993), A VISUAL INSPECTION OF THE TORUS HAD NOT DETECTED ANY | | DETERIORATION OF THE TORUS COATING. LICENSEE ENGINEERING PERSONNEL ARE | | EVALUATING THIS PROBLEM. AT THE PRESENT TIME, THIS EVENT POSES NO THREAT | | TO UNIT 1. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL AUTHORITIES AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32162 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/16/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 12:50 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/15/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 19:30[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/16/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |BRUCE BURGESS RDO | | DOCKET: 0707001 |FRED COMBS, NMSS EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: HALICKS | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PADUCAH BUILDINGS C-333 AND C-337 DID NOT HAVE FIRE SPRINKLER BRANCH LINES | | CONNECTED TO THE FIRE WATER SUPPLY LINE. | | | | DURING AN INSPECTION OF FIRE SPRINKLER PIPING ON THE GROUND FLOOR OF | | BUILDING C-337 (CASCADE FACILITY), SEVENTEEN LOCATIONS WERE IDENTIFIED | | WHERE BRANCH LINES WERE INSTALLED, BUT WERE NEVER CONNECTED TO THE FIRE | | WATER SUPPLY. THESE BRANCHES ARE BELIEVED TO HAVE BEEN INSTALLED IN 1976 | | AS A PART OF A VENTILATION SYSTEM IMPROVEMENT PROJECT. THE REASON FOR THE | | BRANCHES NOT BEING CONNECTED IS UNKNOWN AT THIS TIME. THE DISCREPANCIES | | WERE DISCOVERED DURING DETAILED WALKDOWNS OF EACH SYSTEM BY PLANT FIRE | | PROTECTION PERSONNEL. FOLLOWING THE DISCOVERIES IN BUILDING C-337, | | AN INVESTIGATION WAS INITIATED IN BUILDING C-333 (PROCESS BUILDING) | | FOR SIMILAR PROBLEMS. AN ADDITIONAL TWELVE LOCATIONS WERE IDENTIFIED | | WHERE BRANCH PIPING WAS INSTALLED BUT NOT CONNECTED TO THE FIRE WATER | | SYSTEM SUPPLY. THE AFFECTED SPRINKLER SYSTEMS WERE DECLARED INOPERABLE | | AND AN HOURLY FIRE PATROL WAS INITIATED FOR THE AFFECTED AREAS AS REQUIRED | | BY TSR 2.4.4.5. AS A COMPENSATORY ACTION FOR THE REMAINING TWO MAJOR | | PROCESS BUILDINGS, C-331 AND C-335, HOURLY FIRE PATROL WERE INITIATED FOR | | POTENTIALLY AFFECTED AREAS OF THOSE BUILDINGS. DETAILED WALKDOWNS | | ARE CURRENTLY BEING CONDUCTED ON ALL PROCESS BUILDING SPRINKLER SYSTEMS | | TO ENSURE THAT ALL EXISTING DISCREPANCIES ARE IDENTIFIED AND CORRECTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32163 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 04/16/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 14:36 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/16/97 | +------------------------------------------------+EVENT TIME: 14:25[EDT]| |NRC NOTIFIED BY: BROOKS |LAST UPDATE DATE: 04/16/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CERTAIN NONNUCLEAR SAFETY CABLES MAY NOT MEET CABLE SEPARATION CRITERIA - | | | | ALL OF THE 59 NONNUCLEAR SAFETY (NNS) CABLES INSPECTED ARE 120 VOLT OR LESS | | AND ARE USED FOR INDICATION, ANNUNCIATION, CONTROL POWER AND INTERLOCKS, | | SIGNAL INPUTS FROM INSTRUMENTATION, OR RELAYING. THE INDICATION, | | ANNUNCIATION, AND SIGNAL INPUTS ARE LOW LEVEL AND CANNOT GENERATE ENOUGH | | ENERGY TO CAUSE DAMAGING SHORT CIRCUITS WITHIN THESE CABLES. THE POWER | | FEEDS ARE PROVIDED FROM SAFETY CLASS ELECTRICAL (SCE) BUSES AND BREAKERS | | (CRP-9-46, DC-1C, AND DC-2C) AND HAVE SCE BREAKERS UPSTREAM TO PROVIDE | | BACKUP SHORT CIRCUIT PROTECTION. ANY SHORT CIRCUIT IN THESE CABLES WILL BE | | ISOLATED PRIOR TO CABLE DAMAGE. | | | | IN ADDITION, THE CONTROL POWER AND INTERLOCKS ARE PROTECTED BY AT LEAST | | TWO DEVICES SUCH AS A BREAKER AND FUSE, TWO BREAKERS IN SERIES, OR A FUSE | | AND CONTROL POWER TRANSFORMER. FOR A POSTULATED FIRE IN THE CABLE VAULT | | THAT MAY AFFECT BOTH DIVISIONAL SYSTEMS, THE ALTERNATE SHUTDOWN SYSTEM IS | | AVAILABLE TO SAFELY SHUT THE PLANT DOWN. | | | | FOR CABLES THAT CROSS OVER SI AND SII DIVISIONS IN OTHER AREAS OF THE | | PLANT, ADEQUATE FIRE BARRIERS ARE INSTALLED BETWEEN FIRE AREAS OR | | SUFFICIENT SEPARATION DISTANCE EXISTS BETWEEN SI AND SII DIVISIONS TO | | ASSURE THAT A FIRE IN ONE AREA WILL NOT PROPAGATE. ANY POSTULATED DAMAGE | | WILL BE CONFINED TO NNS TRAY AND ONLY ONE DIVISIONAL SYSTEM. A FAULTED NNS | | CABLE MAY AFFECT THE AVAILABILITY OF BOTH TRAINS OF RHR SERVICE WATER SINCE | | BOTH GROUPS OF CABLES SHARE A COMMON TRAY. EXCEPT FOR TWO CABLES, UPS-1A | | FEEDER AND TORUS TEMPERATURE RECORDER INPUTS, ALL IDENTIFIED CABLES WERE | | INSTALLED DURING ORIGINAL CONSTRUCTION. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32164 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 04/16/97 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 17:06 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 04/16/97 | +------------------------------------------------+EVENT TIME: 15:15[CDT]| |NRC NOTIFIED BY: HARRINGTON |LAST UPDATE DATE: 04/16/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE TURBINE DRIVEN AUXILIARY FEEDWATER PUMP MAY NOT BE ABLE TO MAINTAIN A | | CONSTANT SPEED DURING A MAIN STEAM LINE BREAK ACCIDENT. | | | | A LICENSEE ENGINEERING REEVALUATION OF THE LICENSEE'S RESPONSE TO NRC | | BULLETIN 80-04 DETERMINED THAT THE AUXILIARY FEEDWATER (AFW) SYSTEM | | RESPONSE TO A MAIN STEAM LINE BREAK WOULD NOT BE AS ORIGINALLY ANTICIPATED. | | THE LICENSEE'S ORIGINAL ANALYSIS CONCLUDED THAT THERE WAS SUFFICIENT NET | | POSITIVE SUCTION HEAD (NPSH) AND THAT THERE WAS SUFFICIENT SYSTEM | | RESISTANCE WITH 2 AND 3 AFW PUMP OPERATION TO PREVENT THE AFW PUMPS FROM | | REACHING THEIR RUNOUT FLOW. THE REEVALUATION DETERMINED THAT THE MOTOR | | DRIVEN AFW PUMPS COULD TRIP ON LOW DISCHARGE PRESSURE AND THAT THE TURBINE | | DRIVEN AFW PUMP COULD EITHER TRIP OR CONTINUE TO OPERATE AT A LOWER SPEED. | | | | THE ORIGINAL ANALYSIS ASSUMED THAT THE TURBINE DRIVEN AFW PUMP WOULD | | CONTINUE TO OPERATE AT A CONSTANT SPEED THROUGHOUT THE EVENT. THIS | | ASSUMPTION IS BEING QUESTIONED SINCE A FAULT IN ONE STEAM GENERATOR | | COULD CAUSE A COOLDOWN AND DEPRESSURIZE THE INTACT STEAM GENERATOR. | | WITH LESS STEAM PRESSURE, THE TURBINE DRIVEN AFW PUMP MAY NOT BE | | ABLE TO MAINTAIN THE ASSUMED 3600 RPM. A REANALYSIS OF THE ORIGINAL | | SYSTEM CURVES CALCULATED LESS SYSTEM RESISTANCE THAN ORIGINALLY ASSUMED. | | AS A RESULT, THE SYSTEM RESISTANCE WILL NO LONGER SUPPLY SUFFICIENT BACK | | PRESSURE TO KEEP THE AFW PUMPS FROM TRIPPING ON LOW DISCHARGE PRESSURE | | DURING TWO PUMP OPERATION. | | | | A SIMILAR EVENT WAS DESCRIBED IN LER 97-01 CONCERNING INADEQUATE NPSH | | REQUIREMENTS FOR THE AFW PUMPS DURING A MAIN STEAM LINE BREAK EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |IRRETRIEVABLE WELL LOGGING SOURCE | |EVENT NUMBER: 32165 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: PROTECHNICS LOGGING SERVICE |NOTIFICATION DATE: 04/16/97 | | CITY: REGION: 4 |NOTIFICATION TIME: 19:07 [ET]| | COUNTY: LEA STATE: NM |EVENT DATE: 04/16/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 14:30[MDT]| | DOCKET: |LAST UPDATE DATE: 04/16/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BILL JONES RDO | | |CHARLEY HAUGHNEY EO | +------------------------------------------------+ | |NRC NOTIFIED BY: REYNOLDS | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |EIRR 39.77(c) WELL LOGGING SOURCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TEXACO PLANS TO FISH FOR A STUCK RADIOACTIVE WELL LOGGING TOOL. | | | | A 200ęCi AMERICIUM-241 SOURCE WELL LOGGING TOOL IS STUCK 4,460 FT BELOW THE | | SURFACE. THE API WELL NUMBER IS 30-025-03078. THE LEGAL DESCRIPTION IS | | UNIT LETTER "F", SECTION 6, TOWNSHIP 18, SOUTH RANGE 35 EAST, LEA COUNTY, | | NEW MEXICO. THE LICENSEE PLANS TO START FISHING ON 04/17/97. THE WELL | | LOGGING TOOL IS OWNED BY PROTECHNICS LOGGING SERVICES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32166 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/16/97 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 21:01 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/16/97 | +------------------------------------------------+EVENT TIME: 20:52[EDT]| |NRC NOTIFIED BY: MELVIN |LAST UPDATE DATE: 04/16/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED A CONDITION WHERE VOIDING WOULD OCCUR IN THE | | RECIRCULATION SPRAY PUMPS SUCTION LINES. | | | | THE LICENSEE DETERMINED THAT VOIDING WOULD OCCUR IN THE SUCTION LINES OF | | THE RECIRCULATION SPRAY PUMPS WHEN ASSUMING A SATURATED SUMP MODEL, WHICH | | IS CONSIDERED IN THE LICENSING BASIS. IN THIS CONDITION, THE CONTAINMENT | | RECIRCULATION SPRAY SYSTEM WOULD NOT BE CAPABLE OF SUPPLYING THE MINIMUM | | VOLUME OF COOLING WATER CREDITED IN THE CONTAINMENT ANALYSIS. THIS | | HISTORICAL CONDITION IS BEING REPORTED AS A LOSS OF SAFETY FUNCTION OF | | THE CONTAINMENT RECIRCULATION SPRAY SYSTEM. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL AUTHORITIES AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32167 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 04/16/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 21:49 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 04/16/97 | +------------------------------------------------+EVENT TIME: 19:45[CDT]| |NRC NOTIFIED BY: MATTSON |LAST UPDATE DATE: 04/16/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT SEVERAL WELDS ON A CONTAINMENT PENETRATION | | ANCHOR FRAME WERE OUTSIDE OF UFSAR STRESS LIMITS. | | | | INITIAL LICENSEE EVALUATION INDICATED THAT THE STRESSES ON SEVERAL WELDS | | ON A CONTAINMENT PENETRATION ANCHOR FRAME EXCEEDED OPERABILITY LIMITS | | SPECIFIED IN THE UFSAR. THE ANCHOR FRAME PROVIDES SUPPORT FOR THE | | CONTAINMENT PENETRATION AND THE UNIT 2 "B" LOW PRESSURE COOLANT INJECTION | | LINE. THIS FRAME IS USED TO MAINTAIN CONTAINMENT INTEGRITY AND THE | | INTEGRITY OF THE LOW PRESSURE COOLANT INJECTION PIPING. | | | | THE LICENSEE WILL REPAIR THE ANCHOR FRAME PRIOR TO RESTARTING UNIT 2. | | | | THE LICENSEE IS EVALUATING THE CORRESPONDING UNIT 3 ANCHOR FRAMES. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+