U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/08/95 - 02/09/95 ** EVENT NUMBERS ** 28224 28349 28351 28352 28353 28354 28355 28356 28357 28358 28359 28360 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28224 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 01/09/95 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 14:50 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 01/09/95 | +------------------------------------------------+EVENT TIME: 14:25[EST]| |NRC NOTIFIED BY: ED BURCHFIELD |LAST UPDATE DATE: 02/08/95 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR BLOWDOWN OF BOTH STEAM GENERATORS THROUGH A SINGLE COMMON | | HEADER STEAM LINE BREAK. | | | | THE LICENSEE HAS RECENTLY DETERMINED THAT THERE IS A POSSIBILITY THAT BOTH | | STEAM GENERATORS ON ANY OF THE THREE UNITS COULD BLOW DOWN FROM A STEAM | | LINE BREAK ON CERTAIN STEAM LINES COMMON TO THE GENERATORS. THE COMMON | | STEAM HEADERS INVOLVE AUXILIARY STEAM AND THE STEAM SUPPLY LINES TO THE | | TURBINE DRIVEN EMERGENCY FEEDWATER PUMPS (TDEFWP). | | | | IMMEDIATE CORRECTIVE ACTIONS HAVE BEEN TAKEN TO CLOSE ONE OF THE TWO STEAM | | SUPPLY VALVES FROM THE STEAM GENERATORS TO THE COMMON STEAM HEADERS (AUX | | STEAM AND TDEFWP). THIS ACTION ELIMINATES THE POTENTIAL BLOWDOWN OF BOTH | | STEAM GENERATORS FROM A SINGLE LINE BREAK. | | | | THIS CONDITION IS CURRENTLY CONSIDERED AN UNREVIEWED SAFETY QUESTION BY THE | | LICENSEE. A CONFERENCE CALL TOOK PLACE TODAY BETWEEN REPRESENTATIVES FROM | | THE NRC REGION II, NRR, THE NRC RESIDENT INSPECTOR AND THE LICENSEE | | CONCERNING THIS ISSUE. LONG TERM CORRECTIVE ACTIONS AND ANALYSIS ARE STILL | | IN PROGRESS. | | | | THE LICENSEE STATES THAT ISOLATING A STEAM SOURCE TO THE TURBINE DRIVEN | | EMERGENCY FEEDWATER PUMP DOES NOT PLACE THEM INTO ANY TECH SPEC OPERABILITY | | CONDITIONS. | | | | ***UPDATE AT 10:22 ON 02/08/95 BY PATTERSON TO GOULD*** THE LICENSEE IS | | RETRACTING THIS EVENT. UPON THE COMPLETION OF THEIR REVIEW, THE LICENSEE | | HAS CONCLUDED THAT NO EVIDENCE INDICATES THAT THERE IS AN UNREVIEWED SAFETY | | QUESTION ON THIS ISSUE. THE LICENSEE IS PERFORMING AN ENGINEERING ANALYSIS | | TO DETERMINE THE SAFEST CONFIGURATION FOR THE STEAM LINES IN QUESTION. THE | | RI HAS BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28349 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 02/07/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 18:37 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 02/07/95 | +------------------------------------------------+EVENT TIME: 16:15[CST]| |NRC NOTIFIED BY: HASTY/DORWICK |LAST UPDATE DATE: 02/08/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BOB DEFAYETTE RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |NLCO TECH SPEC LCO A/S | | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR CORE ISOLATION COOLING (RCIC) DECLARED INOPERABLE. ALL OTHER | | EMERGENCY CORE COOLING SYSTEMS ARE FULLY OPERABLE. | | | | LICENSEE WAS PERFORMING PREPLANNED MAINTENANCE TO REPACK RCIC STEAM SUPPLY | | DRAIN POT VALVE PACKING WHEN THEY DISCOVERED THAT THEY WERE UNABLE TO | | DEPRESSURIZED RCIC PIPING TO REPACK THE VALVE. LICENSEE HAD ISOLATED RCIC | | PIPING BY CLOSING BOTH OF ITS INBOARD ISOLATION VALVES (CONTAINMENT | | ISOLATION VALVES) SO THEY COULD DEPRESSURIZE THE PIPE AND THEN REPACK THE | | VALVE. LICENSEE ENTERED TECH SPEC 3.7.3 (14 DAYS TO GET RCIC OPERABLE OR | | SHUTDOWN) AND TECH SPEC 3.6.3 (PRIMARY CONTAINMENT ISOLATION - 4 HOURS TO | | ISOLATE OR SHUTDOWN). LICENSEE MET TECH SPEC 3.6.3 BY SHUTTING RCIC | | OUTBOARD ISOLATION VALVE AND THEN DEENERGIZING THE VALVE ACTUATOR. ALL | | OTHER ECCS SYSTEMS ARE FULLY OPERABLE IF NEEDED. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | ****UPDATE @ 1930EST 02/08/95 BY HASTY TAKEN BY MACKINNON**** | | | | LICENSEE COMMENCING A TECH SPEC SHUTDOWN TO REPAIR RCIC STEAM INLET INBOARD | | VALVE (1E51-F063) OR REPAIR RCIC STEAM INLET INBOARD BYPASS VALVE | | (1E51-F076). ONE OF THESE VALVES IS LEAKING BY AND SINCE THEY ARE IN | | CONTAINMENT THEY CANNOT BE WORKED ON UNLESS THE PLANT IS SHUT DOWN. UNIT 1 | | SHOULD BE SHUT DOWN BETWEEN 0000 CST AND 0200 CST ON 02/09/95. UNIT 1 | | SHOULD BE DOWN BETWEEN 6 AND 14 DAYS TO REPAIR THE LEAKING RCIC VALVE AND | | PERFORM OTHER ASSIGNED TASKS. LICENSEE SAID THAT ALL THEIR ECCS SYSTEMS AND | | THEIR EDGs ARE FULLY OPERABLE IF NEEDED. R3DO (DEFAYETTE) NOTIFIED. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28351 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 02/08/95 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 10:55 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/08/95 | +------------------------------------------------+EVENT TIME: 08:15[EST]| |NRC NOTIFIED BY: WALSH |LAST UPDATE DATE: 02/08/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICK KEIMIG RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD THE ISOLATION OF A NORMALLY OPEN PRIMARY CONTAINMENT | | ISOLATION VALVE DUE TO PERSONNEL ERROR. | | | | THIS OCCURRED WHEN A PLANT OPERATOR, WHO WAS REMOVING TWO FANS FROM SERVICE | | FOR SCHEDULED MAINTENANCE, INADVERTENTLY OPENED THE WRONG 120 VAC BREAKER. | | THIS ACTION ISOLATED POWER TO CONTAINMENT INSTRUMENT GAS PURGE TO THE TIP | | INDEXER ISOLATION VALVE, "SV-22661", CAUSING THE VALVE TO CLOSE. THE | | LICENSEE STATES THAT THIS OCCURRENCE HAS BEEN CLASSIFIED AS AN INVALID | | ACTUATION OF ESF. THE INVALID ACTION DOES NOT, HOWEVER, MEET THE REPORTING | | EXCEPTIONS DESCRIBED IN 10CFR50.72(b)(2)(ii). THE ISOLATION WAS RESET | | WITHIN 10 MINS. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28352 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 02/08/95 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 11:08 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/08/95 | +------------------------------------------------+EVENT TIME: 09:00[EST]| |NRC NOTIFIED BY: MCCORKLE |LAST UPDATE DATE: 02/08/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FLOYD CANTRELL RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED A CONDITION ON 2/8/95 THAT COMPONENT COOLING WATER | | LINE CONTAINMENT PENETRATION WAS INOPERABLE BETWEEN REFUELING OUTAGES 8 & | | 9. | | | | THIS OCCURRED WHEN THEY IDENTIFIED A CRACKED WELD (CRACK FOUND 12/02/94) ON | | A COMPONENT COOLING WATER LINE WHICH PENETRATES CONTAINMENT DURING THEIR | | REFUELING OUTAGE #9. THIS LINE SUPPLIES COOLING TO THE EXCESS LETDOWN HEAT | | EXCHANGER. THE LEAK WAS DISCOVERED AT A WELD LOCATION INSIDE THE | | CONTAINMENT VESSEL AND WAS CAUSED BY STRESS CORROSION CRACKING DUE TO HIGH | | NITRATE LEVELS, STAGNANT FLOW CONDITIONS AND HIGH TEMPERATURES. AS A RESULT | | OF THE CRACKING, TWO CONTAINMENT PENETRATIONS DID NOT MEET DESIGN BASIS | | REQUIREMENTS OF CONTAINMENT ISOLATIONS BETWEEN "2EOC8"(REFUEL OUTAGE 8) | | AUGUST 93 AND "2EOC9"(REFUEL OUTAGE 9) MID NOV 94. SINCE THE LEAKAGE COULD | | NOT BE QUANTIFIED, THESE PENETRATIONS WERE NOT CAPABLE OF MAINTAINING | | CONTAINMENT INTEGRITY WHEN COUPLED WITH A SIGNAL FAILURE. CONTAINMENT | | INTEGRITY FUNCTIONS OF THESE PENETRATIONS WAS THEREFORE PAST INOPERABLE. | | THE PENETRATION LEAKAGE CHARACTERISTICS OF THESE PENETRATIONS WILL BE | | QUANTIFIED DURING "2EOC10". THE WELD WAS REMOVED AND REPLACED AND THE | | REMAINING PIPING WELDS WERE 100% ULTRASONIC TESTED PRIOR TO REENTERING MODE | | 4 DURING STARTUP(1/6/95). THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28353 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 02/08/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 15:05 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 02/07/95 | +------------------------------------------------+EVENT TIME: 20:26[CST]| |NRC NOTIFIED BY: DALY |LAST UPDATE DATE: 02/08/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BOB DEFAYETTE RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 96 POWER OPERATION | 96 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR RECIRCULATION PUMPS INCREASED IN SPEED FOR UNKNOWN REASON CAUSING | | REACTOR THERMAL POWER TO INCREASE TO 103.7% OF THEIR ADMINISTRATIVE POWER | | LIMIT. | | | | BOTH REACTOR RECIRCULATION PUMP SPEED INCREASED UNEXPECTEDLY CAUSING AN | | INCREASE IN REACTOR POWER TO >102% OF THEIR ADMINISTRATIVE LIMIT (LIMIT IS | | 2450 MEGAWATTS THERMAL). A 3% ADMINISTRATIVE LIMIT WAS PLACED ON THE CORE | | THERMAL POWER DUE TO FEEDWATER FLOW AND TEMPERATURE MEASUREMENT | | INACCURACIES. THIS 3% DERATE IS CONSIDERED CONSERVATIVE. MAXIMUM POWER | | ACHIEVED WAS CALCULATED VIA HAND HEAT BALANCE FROM STRIP CHART INFORMATION | | TO BE 2541 MEGAWATTS THERMAL (103.7% OF ADMINISTRATIVE LIMIT OF 2450 | | MEGAWATTS THERMAL). REACTOR THERMAL POWER WAS > THAN 2450 MEGAWATTS THERMAL | | FOR LESS THAN 15 MINUTES. OPERATOR ACTION OF MANUALLY DECREASING | | RECIRCULATION PUMP SPEED TERMINATED THE EVENT. INVESTIGATION OF THE CAUSE | | OF THE RECIRCULATION PUMP SPEED INCREASING IS IN PROGRESS. OPERATOR HAD | | BUMPED UP RECIRCULATION PUMP SPEED TO INCREASE REACTOR POWER AND A LITTLE | | WHILE LATER THE RECIRCULATION PUMPS INCREASED SPEED FOR AN UNKNOWN REASON. | | LICENSEE SAID THAT THEY DID NOT SEE ANY INCREASE IN OFFGAS LEVELS AND THAT | | THIS EVENT DID NOT CAUSE ANY FUEL FAILURE. THIS EVENT WAS REPORTED UNDER | | SECTION "C" OF THEIR OPERATING LICENSEE. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28354 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 02/08/95 | |UNIT: [ ] [2] [3] STATE: CA |NOTIFICATION TIME: 15:53 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 02/08/95 | +------------------------------------------------+EVENT TIME: 11:49[PST]| |NRC NOTIFIED BY: PETE CHAMPION |LAST UPDATE DATE: 02/08/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY YANDELL RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 94 POWER OPERATION | 94 POWER OPERATION | | 3 | N Y 97 POWER OPERATION | 97 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INCOMPLETE SCREENING OF EMPLOYMENT RECORDS. INDIVIDUAL DID NOT ENTER | | PROTECTED AREA. IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. SEE | | HOO LOG BOOK FOR FURTHER DETAILS. RESIDENT INSPECTOR WILL BE INFORMED BY | | THE LICENSEE. | | | | LICENSEE HAD SIMILAR EVENT ON 01/31/95, EVENT # 28309. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28355 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 02/08/95 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 15:45 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 02/08/95 | +------------------------------------------------+EVENT TIME: 15:30[EST]| |NRC NOTIFIED BY: D CORNAX |LAST UPDATE DATE: 02/08/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICK KEIMIG 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SOME FLOOR COATING IN CONTAINMENT FOUND CRACKED AND LIFTED. | | | | FLOOR COATING IN CONTAINMENT FOUND CRACKED AND LIFTED. THE FLOOR COATING | | WAS APPLIED AT THE END OF THEIR LAST REFUELING OUTAGE WHICH WAS IN MARCH OF | | 1993. THE FLOOR COATING BEFORE IT WAS APPLIED WAS RESEARCHED FOR | | TEMPERATURE AND OTHER AFFECTS WHICH WOULD CAUSE IT TO DEGRADE. THIS | | CONDITION SEEMS TO BE OUTSIDE THE DESIGN BASIS OF THE PLANT AS DESCRIBED IN | | THEIR UPDATED FINAL SAFETY ANALYSIS REPORT. AN EVALUATION OF THE | | CONSEQUENCES OF THE CRACKS AND LIFTED FLOOR COATING IS BEING PERFORMED. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28356 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 02/08/95 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 18:05 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 02/08/95 | +------------------------------------------------+EVENT TIME: 15:44[EST]| |NRC NOTIFIED BY: DAVID MOHRE |LAST UPDATE DATE: 02/08/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICK KEIMIG 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EMERGENCY CORE COOLING PUMP SUCTION LINE COULD HAVE BEEN BLOCKED BY A TEST | | FLANGE THAT WAS STORED NEAR THE SUCTION FLANGE. | | | | THE FOLLOWING TEXT IS FROM A FACSIMILE SENT BY THE LICENSEE. | | | | "ON 02/08/95, ENGINEERING DETERMINED THAT THE PLANT WAS IN AN UNANALYZED | | CONDITION THAT COULD SIGNIFICANTLY COMPROMISE PLANT SAFETY. THIS IS DUE TO | | AN EMERGENCY CORE COOLING PUMP SUCTION LINE THAT COULD HAVE BEEN BLOCKED BY | | A TEST FLANGE THAT WAS STORED NEAR THE SUCTION FLANGE. THE TEST FLANGE WAS | | STORED BY BOLTING IT TO THE TOP OF THE PUMP SUCTION FLANGE LOCATED IN THE | | VAPOR CONTAINMENT SUMP. IT IS BELIEVED THAT THIS TEST FLANGE WAS STORED IN | | THIS CONFIGURATION WHILE THE PLANT WAS IN OPERATION. THE SUCTION LINE IS A | | BACKUP TO THE INTERNAL RECIRCULATION SYSTEM AND USED ONLY IF THE INTERNAL | | RECIRCULATION SYSTEM SUSTAINS A PASSIVE FAILURE DURING ACCIDENT MITIGATION. | | THE ENGINEERING EVALUATION THAT CONCLUDED THIS FINDING WAS PROMPTED BY A | | QUESTION FROM THE RESIDENT NRC INSPECTOR." | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 28357 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SYNCOR |NOTIFICATION DATE: 02/08/95 | | CITY: SEAFORD REGION: 1 |NOTIFICATION TIME: 18:48 [ET]| | COUNTY: STATE: DE |EVENT DATE: 02/08/95 | |LICENSE#: 073015801MD AGREEMENT: N |EVENT TIME: 05:00[EST]| | DOCKET: |LAST UPDATE DATE: 02/08/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |RICK KEIMIG RDO | | |JOE HOLONICH (NMSS) EO | +------------------------------------------------+ | |NRC NOTIFIED BY: TARA DOMITER | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |IBBF 30.50(b)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FUME HOOD FAILED FOR UNKNOWN REASON. | | | | AT 0500 EST A FUME HOOD FAILED FOR UNKNOWN REASON AT SYNCOR FACILITY | | LOCATED AT BOX 367, SEAFORD, DELAWARE. FUME HOOD WILL NOT BE REPAIRED UNTIL | | THE MORNING OF 02/09/95. VIALS CONTAINING A TOTAL OF 20 MILLICURIES OF | | IODINE-131 AND 20 MILLICURIES OF XENON-133 WERE INSIDE THE FUME HOOD WHEN | | IT FAILED. THE VIALS WERE TRANSFERRED TO A SMALLER VENTILATION UNIT. NO | | RELEASE OCCURRED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28358 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/08/95 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 19:08 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/08/95 | +------------------------------------------------+EVENT TIME: 18:50[EST]| |NRC NOTIFIED BY: M RANIERI |LAST UPDATE DATE: 02/08/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICK KEIMIG RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE DISCOVERED THAT THEIR SERVICE WATER PUMP MOTOR COULD OVER HEAT | | DURING VARIOUS PLANT ACCIDENT SCENARIOS. | | | | LICENSEE CONDUCTED FULL FLOW TESTING OF THEIR INTAKE STRUCTURE VENTILATION | | EXHAUST FANS IN SEPTEMBER 1994 (LAST DOCUMENTED TEST PERFORMED ON THESE | | EXHAUST BEFORE 09/94 WAS BACK IN 1974). THE DESIGN EXHAUST FLOW RATE OF | | EACH EXHAUST FAN IS SUPPOSED TO BE 30,000 CUBIC FEET PER MINUTE (cfm). THE | | TEST RESULTS TAKEN BACK IN SEPTEMBER 1994 SHOWED THAT EXHAUST FAN # 1 FLOW | | RATE WAS 13,000cfm, EXHAUST FAN # 2 WAS 17,000cfm, AND EXHAUST FAN # 3 WAS | | 21,000cfm. LAST WEEK LICENSEE RECEIVED RESULTS BACK THAT THE INTAKE | | STRUCTURE WOULD REQUIRE EXHAUST FANS TO GENERATE 38,000cfm TO KEEP THE | | SERVICE WATER PUMP MOTOR WINDINGS BELOW 115 DEGREES F (ABOVE THIS | | TEMPERATURE WINDINGS MIGHT FAIL). LICENSEE ASSUMED THAT THE HIGHEST FLOW | | EXHAUST FAN WOULD FAIL WHEN IT WAS NEEDED. FROM THE TEST DATA GIVEN ABOVE | | AND THE ASSUMPTION THAT THE HIGHEST FLOW EXHAUST FAN FAILS THE INTAKE | | STRUCTURE VENTILATION SYSTEM WOULD ONLY GENERATE 30,000cfm. LICENSEE PLANS | | TO INCREASE THE cfm OUTPUT OF THE EXHAUST FANS BY PERFORMING FAN BLADE | | ADJUSTMENT AND CHANGE OUT THE EXHAUST FANS MOTORS. IF THIS DOESN'T CORRECT | | THE INSUFFICIENT EXHAUST FAN FLOW RATE THEN LICENSEE WILL REPLACE THE | | EXHAUST FANS. LICENSEE NOTIFIED THE STATE OF THIS EVENT. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28359 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 2 |NOTIFICATION DATE: 02/09/95 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 02:42 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 02/09/95 | +------------------------------------------------+EVENT TIME: 00:50[CST]| |NRC NOTIFIED BY: EHRHARDT |LAST UPDATE DATE: 02/09/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FLOYD CANTRELL RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE PLANT HAD ONE OF ITS EMERGENCY SIRENS TO ACTIVATE INADVERTENTLY. | | | | THE LICENSEE WAS NOTIFIED THAT ONE OF ITS EMERGENCY SIRENS ACTUATED | | AUTOMATICALLY FOR NO APPARENT REASON. THE CAUSE OF THE ACTUATION IS UNKNOWN | | AND BEING INVESTIGATED. THE SIREN WAS SECURED WITHIN 10 MIN. THE RI WAS | | INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28360 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 02/09/95 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 03:25 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 02/09/95 | +------------------------------------------------+EVENT TIME: 00:28[CST]| |NRC NOTIFIED BY: KNIGHT |LAST UPDATE DATE: 02/09/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FLOYD CANTRELL 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A REACTOR SCRAM FROM 100% DUE TO A TURBINE TRIP. | | | | THE TURBINE TRIP WAS CAUSED BY A RELAY SENSING FOR AN ELECTRICAL FAULT IN | | THE MAIN GENERATOR FIELD. IT IS NOT KNOWN AT THIS TIME WHETHER OR NOT THE | | SENSED FAULT WAS VALID. A FOLLOWUP INVESTIGATION WILL DETERMINE THE CAUSE. | | ALL RODS FULLY INSERTED DURING THE SCRAM AND NO SAFETY RELIEF VALVE LIFTING | | WAS NOTED. PCIS GROUPS 2, 3, 6 AND 8 INITIATED AS EXPECTED DUE TO LOW | | REACTOR WATER LEVEL CAUSED BY THE SCRAM. WATER LEVEL WAS RECOVERED, USING | | THE FEEDWATER AND CRD SYSTEM, TO NORMAL RANGE. THE TURBINE TRIP CAUSED A | | RECIRCULATION PUMP TRIP ACTUATION. STANDBY GAS TREATMENT ACTUATION ALSO | | OCCURRED DUE TO LOW REACTOR WATER LEVEL. THE CONTROL ROOM EMERGENCY | | VENTILATION SYSTEM RECEIVED AN ACTUATION SIGNAL, BUT WAS ALREADY RUNNING AT | | THE TIME OF THE SCRAM DUE TO A SURVEILLANCE THAT WAS IN PROGRESS FOR | | VERIFYING ITS OPERABILITY. THE CURRENT HEAT SINK IS THE MAIN CONDENSER AND | | THERE WAS NO ECCS ACTUATION. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+