U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/17/94 - 05/18/94 ** EVENT NUMBERS ** 27108 27211 27222 27262 27263 27264 27265 27266 27267 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27108 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 04/17/94 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 12:28 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/17/94 | +------------------------------------------------+EVENT TIME: 12:00[EDT]| |NRC NOTIFIED BY: JOE VARGA |LAST UPDATE DATE: 05/17/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM LAZARUS 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N Y 65 POWER OPERATION | 65 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 DECLARED THE STEAM DRIVEN AUX FEED PUMP INOPERABLE DUE TO A | | MISWIRING OF THE ROOM COOLING DAMPERS WHICH PLACES THE UNIT OUTSIDE ITS | | DESIGN BASIS. | | | | "A REVIEW OF THE AUXILIARY FEED PUMP ROOM COOLER CIRCUIT HAS DISCOVERED A | | CONTACT WIRED INCORRECTLY. THIS MISWIRING RESULTED IN THE ROOM COOLER BEING | | INOPERABLE UNDER NORMAL CONDITIONS AND, UNDER STEAM BREAK CONDITIONS IN THE | | "23" AUX FEED PUMP ROOM, WOULD DUMP STEAM TO THE LOCAL AREAS INSTEAD OF THE | | PENETRATION AREA. ADMINISTRATIVELY AN INOPERABLE ROOM COOLER REQUIRES THE | | APPLICABLE PUMP TO BE DECLARED INOPERABLE. THIS MEANS THE "23" AUX FEED | | PUMP HAS TECHNICALLY BEEN INOPERABLE FOR AN INDETERMINATE PERIOD OF TIME, | | BUT DEFINITELY GREATER THAN THE TIME ALLOWANCE OF 72 HOURS PER TECH SPEC | | 3.7.1.2.D ACTION A. THIS PLACES THE PLANT IN A CONDITION OUTSIDE THE DESIGN | | BASIS." | | | | THIS CONDITION WAS DISCOVERED AT APPROXIMATELY 1500EDT ON 4/16/94 WHILE | | PERFORMING A SURVEILLANCE ON ANOTHER ROOM COOLER. DURING THIS SURVEILLANCE | | DISCREPANCIES WERE FOUND WHICH UPON FURTHER INVESTIGATION IDENTIFIED THE | | MISWIRING. NORMAL SURVEILLANCES WOULD NOT DETECT THIS CONDITION. THE | | MISWIRING CAUSES IMPROPER DAMPER REPOSITIONING DURING A POSTULATED STEAM | | LINE BREAK, i.e., PREVENTS STEAM FROM EXHAUSTING TO OUTSIDE. THE LICENSEE | | IS INVESTIGATING WHETHER UNIT 1 IS AFFECTED (SCHEMATICS SHOW SIGNIFICANT | | DIFFERENCES BETWEEN UNITS). AUX FEED PUMP "23" WAS DECLARED INOPERABLE AT | | 0350EDT ON 4/17. THE LICENSEE ESTIMATES THAT THE MISWIRING WILL BE | | CORRECTED TODAY. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1707EDT 4/17/94 FROM VARGA TO SANDIN * * * | | REVIEW OF UNIT 1 DETERMINED THAT THE ROOM COOLER FOR AUX FEED PUMP "13" HAS | | ALSO BEEN MISWIRED. NO TECH SPEC A/S IS APPLICABLE DUE TO THE CURRENT MODE | | OF THE PLANT. THE LICENSEE WILL CORRECT THIS PROBLEM PRIOR TO STARTUP. THE | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. NOTIFIED R1DO(LAZARUS) | | | | * * * UPDATE 1248EDT 5/17/94 FROM KAFANTARIS TO WEAVER * * * | | THE LICENSEE HAS RETRACTED THIS EVENT. THE LICENSEE ENGINEERING STAFF | | REVIEWED THE VARIOUS FAILURE MECHANISMS IN DETAIL. THE FOLLOWING | | CONCLUSIONS WERE DRAWN. 1) WITH D/P PD-8608 WIRED INCORRECTLY, THE TURBINE | | DRIVEN AUX FEED PUMP WOULD STILL HAVE OPERATED UNDER BOTH NORMAL AND | | ACCIDENT CONDITIONS. 2) A STEAM LINE BREAK WOULD NOT HAVE AFFECTED THE | | ADJACENT MOTOR DRIVEN AUX FEED PUMPS. ENGINEERING WORK BOOK PACKAGE | | ECA-1EE-0054 CHANGED THE THE WIRING TO ALLOW THE DAMPERS LOGIC TO FUNCTION | | AS WAS ORIGINALLY INTENDED. THE WORK PACKAGE WAS COMPLETED ON 4/17/94. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27211 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 05/05/94 | |UNIT: [2] [3] [ ] STATE: PA |NOTIFICATION TIME: 17:31 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 05/05/94 | +------------------------------------------------+EVENT TIME: 16:30[EDT]| |NRC NOTIFIED BY: CHRIS SCHWARZ |LAST UPDATE DATE: 05/17/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |P. K. EAPEN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL ROOM VENTILATION RADIATION MONITORS MAY NOT HAVE MET DESIGN | | REQUIREMENTS. | | | | THE TRAIN "A" PROGRAM OF THE CONTROL ROOM VENTILATION RADIATION MONITORING | | SYSTEM WAS CHANGED FROM STATISTICAL AVERAGING TO 10 MINUTE AVERAGING. THE | | LICENSEE DID NOT KNOW IF THE 10 MINUTE AVERAGING PROGRAM WOULD HAVE MET | | DESIGN CRITERIA SINCE THE DESIGN HAD NOT BEEN REVIEWED. THE TIME PERIOD OF | | CONCERN IS FROM AN UNSPECIFIED TIME THIS MORNING UNTIL 1645 TODAY. THE | | PROBLEM WAS DISCOVERED AT 1630 TODAY WHEN WORKERS WERE CONDUCTING A ROUTINE | | DEBRIEF OF THE JOB. THE STATISTICAL AVERAGING PROGRAM WAS REINSTALLED IN | | TRAIN "A" AT 1645. TRAIN "B" WAS INOPERABLE DURING THIS ENTIRE TIME. | | | | A MODIFICATION WAS UNDERWAY TO REPLACE ELECTRONIC COMPONENTS IN BOTH TRAINS | | "A" AND "B" OF THE CONTROL ROOM RADIATION MONITORING SYSTEM. THE TRAIN "A" | | MODIFICATION WAS SUCCESSFULLY COMPLETED LAST WEEK. THE TRAIN "B" | | MODIFICATION COMMENCED THIS MORNING. SIGNAL SPIKES ENCOUNTERED DURING THE | | MODIFICATION INSTALLATION ON TRAIN "B" WERE FIXED BY USING THE 10 MINUTE | | AVERAGING PROGRAM. THIS CHANGE WAS NOT INCLUDED IN THE MODIFICATION. THIS | | PROGRAM CHANGE WAS THEN APPLIED TO TRAIN "A". TRAIN "B" WAS STILL | | INOPERABLE AT THE TIME OF THIS NOTIFICATION. THE TECHNICAL SPECIFICATION | | ACTION STATEMENT FOR THIS SYSTEM WAS ENTERED ON 4/30/94 FOR WORK ON | | TRAIN "B". THE LCO EXPIRES ON 5/7/94. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2124 ON 5/5/94 BY SCHWARZ TAKEN BY WEAVER * * * | | A SPIKE ON CHANNEL "C" OF THE MAIN CONTROL ROOM VENTILATION RADIATION | | MONITORING SYSTEM FAILED TO AUTO INITIATE CONTROL ROOM EMERGENCY | | VENTILATION. OPERATORS SUBSEQUENTLY MANUALLY INITIATED EMERGENCY | | VENTILATION. CHANNELS "A" & "C" ARE IN TRAIN "A" AND CHANNELS "B" & "D" | | ARE IN TRAIN "B". THE LOGIC IS NORMALLY ONE OUT OF TWO TAKEN TWICE. TRAIN | | "B" WAS INOPERABLE AT THE TIME OF THIS EVENT DUE TO THE MODIFICATION | | DESCRIBED ABOVE. BECAUSE OF THE WORK ON TRAIN "B" THE LOGIC WAS ALTERED TO | | ALLOW EITHER CHANNEL "A" OR "C" ALONE TO INITIATE EMERGENCY VENTILATION. | | | | THE LICENSEE BELIEVES THE FAILURE OF CHANNEL "C" TO INITIATE EMERGENCY | | VENTILATION WAS CAUSED BY AN INCORRECT INSTALLATION OF THE MODIFICATION | | PREVIOUSLY DESCRIBED. FURTHER, THE LICENSEE BELIEVES OUT OF DATE PRINTS | | WERE USED TO INSTALL THE MODIFICATION. THE USE OF THE OLD PRINTS CAUSED | | CHANNEL "C" TO BE INADVERTENTLY JUMPERED OUT. BASED ON THEIR REVIEW TO | | THIS POINT THE LICENSEE HAS CONCLUDED THAT A TRIP OF CHANNEL "A" WOULD HAVE | | INITIATED EMERGENCY VENTILATION. | | | | THE LICENSEE INTENDS TO EVALUATE THE CHANGES PERFORMED AND RESTORE TRAIN | | "A" TO ITS ORIGINALLY INTENDED CONDITION I.E., EITHER CHANNEL WILL INITIATE | | EMERGENCY VENTILATION. CONTROL ROOM VENTILATION WILL THEN BE RETURNED TO | | ITS NORMAL LINEUP. A ROOT CAUSE INVESTIGATION WILL BE PERFORMED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1316 ON 5/17/94 FROM FOSS TO WEAVER * * * | | THE LICENSEE HAS RETRACTED THIS EVENT BASED ON TWO FACTORS. | | | | 1) FURTHER ENGINEERING REVIEW OF THE 10 MINUTE AVERAGING PROGRAM FOUND THE | | PROGRAM TO BE ACCEPTABLE IN THAT IT MEETS DESIGN CRITERIA. | | | | 2) THE BAD TEMPORARY CHANGE PROCEDURE ONLY AFFECTED CHANNEL C. CHANNEL A | | REMAINED OPERABLE THROUGHOUT THE TIME PERIOD IN QUESTION. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27222 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 05/08/94 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 17:28 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 05/08/94 | +------------------------------------------------+EVENT TIME: 14:45[CDT]| |NRC NOTIFIED BY: RUSSEL GILBERT |LAST UPDATE DATE: 05/17/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER RDO | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RCIC SYSTEM DISCOVERED TO BE INOPERABLE. | | | | AT 1445 CDT THE LICENSEE DISCOVERED THAT THE FLOW CONTROLLER FOR RCIC WAS | | READING MINUS 52 GALLONS PER MINUTE. THE INTEGRATED COMPUTER SYSTEM WAS | | ALSO READING MINUS 52 GPM. SINCE THIS FAILURE COULD HAVE PREVENTED RCIC | | FROM PERFORMING ITS SAFETY FUNCTION, RCIC WAS DECLARED INOPERABLE. THIS IS | | A 7 DAY LCO. THE CAUSE OF THE FAILURE IS NOT YET KNOWN. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1124EDT ON 5/17/94 FROM MORROW BY S.SANDIN * * * | | AN ENGINEERING REVIEW COMPLETED ON 5/12/94 CONCLUDED THAT THE RCIC FLOW | | CONTROLLER INDICATION WAS NOT AN ADVERSE CONDITION AND THAT THE FLOW | | CONTROLLER WAS IN TOLERANCE OF THE FLOW INPUT THROUGHOUT THE FULL RANGE. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOLTIFIED R2DO(McALPINE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27262 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 05/17/94 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 03:37 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 05/17/94 | +------------------------------------------------+EVENT TIME: 02:29[EDT]| |NRC NOTIFIED BY: STEVE PETERMAN |LAST UPDATE DATE: 05/17/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COMBINED LEAKAGE OF ALL FOUR MAIN STEAM LINES EXCEEDED TS ALLOWED LIMIT. | | | | "THE RESULTS OF THE LOCAL LEAK RATE TEST (LLRT) OF THE COMBINED LEAKAGE OF | | ALL FOUR MAIN STEAM LINES WAS 137.3 SCFH. FERMI-2 TECH SPEC SECTION | | 3.6.1.2.C STATES "PRIMARY CONTAINMENT LEAKAGE RATES SHALL BE LIMITED TO | | LESS THAN OR EQUAL TO 100 SCFH FOR ALL FOUR MAIN STEAM LINES". INDIVIDUAL | | MAIN STEAM LINE ISOLATION VALVES WILL BE LEAKRATE TESTED TO DETERMINE THE | | NECESSARY REPAIRS. A FULL REPORT WILL BE PROVIDED PER 10CFR50.73." | | | | THE LICENSEE WILL INFORM THE NRC REGION3(MONTE PHILLIPS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27263 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 05/17/94 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 04:46 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 05/17/94 | +------------------------------------------------+EVENT TIME: 02:00[CDT]| |NRC NOTIFIED BY: RANDY DUS |LAST UPDATE DATE: 05/17/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER RDO | |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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 EXPERIENCED A 22 MINUTE LOSS OF SHUTDOWN COOLING DUE TO A PROCEDURAL | | DEFICIENCY IDENTIFIED DURING EDG TESTING. | | | | "WHILE PERFORMING LTS-800-105 "1A D/G 24 HR RUN SURVEILLANCE", AN ISOLATION | | SIGNAL TO THE RHR INBOARD ISOLATION VALVE "1E12-F009" WAS RECEIVED. THIS | | RESULTED IN A TEMPORARY LOSS OF SHUTDOWN COOLING. SHUTDOWN COOLING WAS | | RESTARTED 22 MINUTES LATER (AFTER VERIFYING FILL AND VENT). THE ISOLATION | | SIGNAL IS BELIEVED TO HAVE COME FROM THE LOSS OF, AND SUBSEQUENT RETURN OF | | POWER (FROM THE "1A D/G") TO LEAK DETECTION LOGIC." | | | | THE DIESEL TEST REQUIRED THAT BUS "142Y" BE ENERGIZED FROM THE DIVISION 2 | | EDG "1A". THE DIV 1 TRAIN "A" RHR WAS IN SERVICE AT THE TIME. THE PROCEDURE | | DID NOT ACCOUNT FOR THE LEAK DETECTION LOGIC RECEIVING POWER FROM BOTH DIV | | 1 AND DIV 2. ALL SYSTEMS FUNCTIONED AS REQUIRED. THE DIESEL TEST WAS | | COMPLETED SATISFACTORILY. RCS TEMPERATURE PRIOR TO AND FOLLOWING THE LOSS | | OF SHUTDOWN COOLING REMAINED 82F. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27264 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 05/17/94 | |UNIT: [2] [3] [ ] STATE: PA |NOTIFICATION TIME: 10:06 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 05/17/94 | +------------------------------------------------+EVENT TIME: 05:58[EDT]| |NRC NOTIFIED BY: DISHONG |LAST UPDATE DATE: 05/17/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER 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 N 0 REFUELING | 0 REFUELING | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ACTUATION OF THE CONTROL VENTILATION SYSTEM IN THE EMERGENCY MODE DUE TO | | HIGH RAD LEVEL INDICATION FOR REASON UNKNOWN. | | | | "DURING NORMAL OPERATIONS WITH UNIT 2 IN REFUEL MODE AND UNIT 3 AT 100% | | POWER, CONTROL ROOM VENTILATION RADIATION LEVELS AS SENSED BY RIS-0760 A | | THRU D INCREASED TO THE TRIP SETPOINT AND CONTROL ROOM EMERGENCY | | VENTILATION INITIATED. CHANNELS A AND C INDICATED SLIGHTLY HIGHER THAN | | NORMAL RAD LEVELS OF 100 CPM (BELOW TRIP). CHANNELS B AND D INDICATED | | APPROXIMATELY 700 CPM FOR 10 MINUTES (TRIP AT 350 CPM) THEN RETURNED TO | | NORMAL. CONTROL ROOM VENTILATION RETURNED TO NORMAL AT 0623." | | | | THE LICENSEE IS INVESTIGATING WHETHER THE HIGH LEVEL INDICATION IS | | ATTRIBUTED TO THE MOVEMENT OF RAD MATERIAL. NO GRAB SAMPLES WERE TAKEN TO | | VERIFY THE ABSENCE OF AN AIRBORNE CONDITION AND THE RAD MONITOR IS | | CONSIDERED OPERABLE AT THIS TIME. THE LICENSEE WILL INFORM THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 27265 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COMMONWEALTH EDISON |NOTIFICATION DATE: 05/17/94 | | CITY: DOWNERS GROVE REGION: 3 |NOTIFICATION TIME: 14:05 [ET]| | COUNTY: STATE: IL |EVENT DATE: 03/22/94 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[CDT]| | DOCKET: |LAST UPDATE DATE: 05/17/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JOHN SCHRAGE | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PART 21 NOTIFICATION ON TECHNO CORPORATION DAMPERS | | | | COMMONWEALTH EDISON MADE THIS NOTIFICATION BECAUSE A SECONDARY CONTAINMENT | | ISOLATION DAMPER SUPPLIED BY TECHNO CORPORATION FAILED A SURVEILLANCE AT | | THE LASALLE NUCLEAR POWER PLANT. THE DAMPER CONTAINED AN AIR CYLINDER | | MANUFACTURED BY PARKER HANNIFIN. THE AIR CYLINDER CONTAINED AN EXCESSIVE | | AMOUNT OF RUST INHIBITOR WHICH CAUSED THE INTERNAL COMPONENTS TO STICK OVER | | TIME AND AT HIGH AIR FLOW TEMPERATURES. | | | | ALL LASALLE UNIT 1 & 2 TECHNO DAMPERS EQUIPPED WITH PARKER CYLINDERS WERE | | REPLACED BETWEEN FEBRUARY 1 AND MAY 1 1994. NO OTHER COMMONWEALTH EDISON | | PLANT USES THE PARKER CYLINDERS. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27266 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 05/17/94 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 17:14 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/17/94 | +------------------------------------------------+EVENT TIME: 13:36[CDT]| |NRC NOTIFIED BY: GLENN KAEGI |LAST UPDATE DATE: 05/17/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER RDO | |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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL ISOLATION OF THE REACTOR WATER CLEANUP SYSTEM (RWCU) | | | | THE RWCU SYSTEM WAS MANUALLY ISOLATED WHEN THE BRAVO RWCU PUMP TRIPPED. THE | | OPERATORS ISOLATED THE SYSTEM BECAUSE THEY THOUGHT THE PUMP TRIP MAY HAVE | | BEEN CAUSED BY A SYSTEM ISOLATION SIGNAL. LATER, THE CAUSE OF THE PUMP | | TRIP WAS DETERMINED TO BE A GROUND FAULT ON AN OFF SITE 161KV LINE. THE | | FAULT HAD LOWERED SUPPLY VOLTAGE LONG ENOUGH TO TRIP THE PUMP. THE FAULT | | WAS CLEARED BY PROTECTIVE BREAKERS OPENING OFF SITE. | | | | THE A RWCU PUMP IS CURRENTLY RUNNING WITH THE B PUMP AVAILABLE. THE | | LICENSEE WILL INFORM THE DRP SECTION CHIEF IN LIEU OF THE RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27267 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 05/17/94 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 20:39 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 05/17/94 | +------------------------------------------------+EVENT TIME: 14:30[PDT]| |NRC NOTIFIED BY: CLYDE MACKAMAN |LAST UPDATE DATE: 05/17/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR 50 APPENDIX R COMPLIANCE ISSUES THAT COULD AFFECT THE PLANT'S SAFE | | SHUTDOWN CAPABILITY. | | | | FOUR ISSUES HAVE BEEN IDENTIFIED. | | | | 1) IN THE EVENT OF A MAIN CONTROL ROOM FIRE, THE TIME BETWEEN A SCRAM AND | | OPERATOR CONTROL OF SAFE SHUTDOWN SYSTEMS AT THE REMOTE AND ALTERNATE | | REMOTE SHUTDOWN PANELS AND OTHER REMOTE LOCATIONS IS SIGNIFICANT. EXISTING | | APP R ANALYSIS MAY NOT ADEQUATELY ADDRESS EQUIPMENT, SYSTEM FAILURE MODES, | | AND PLANT RESPONSES THAT COULD IMPACT OPERATOR RESPONSE TIMES. | | | | 2) IN THE EVENT OF A MAIN CONTROL ROOM FIRE, THE HIGH PRESSURE CORE SPRAY | | SYSTEM COULD BE ACTUATED BY A FIRE INDUCED SPURIOUS SIGNAL TO INJECT INTO | | THE REACTOR VESSEL. EXISTING APP R ANALYSIS AND PROCEDURES MAY NOT | | ADEQUATELY ADDRESS METHODOLOGY AND TIMING REQUIREMENTS FOR MITIGATION OF | | SPURIOUS HPCS ACTUATION TO ASSURE SAFE SHUTDOWN. | | | | 3) FIRES IN CERTAIN AREAS MAY RESULT IN AN INADVERTENT FIRE INDUCED | | ACTUATION OF THE REACTOR CORE ISOLATION COOLING SYSTEM AND INJECTION INTO | | THE REACTOR VESSEL. SINCE RCIC IS NOT CREDITED FOR SAFE SHUTDOWN, SYSTEM | | CONTROLS ARE NOT PROTECTED FROM THE EFFECTS OF FIRE. EXISTING APP R | | ANALYSIS AND PROCEDURES MAY NOT ADEQUATELY ADDRESS METHODOLOGY AND TIMING | | REQUIREMENTS FOR MITIGATION OF A SPURIOUS RCIC ACTUATION TO ASSURE SAFE | | SHUTDOWN. | | | | 4) SYSTEMS REQUIRED FOR SAFE SHUTDOWN IN THE EVENT OF A FIRE HAVE BEEN | | EVALUATED TO ASSURE THAT AT LEAST ONE SHUTDOWN PATH IS ALWAYS AVAILABLE. | | HOWEVER, MANY FIRE AREAS CONTAIN AFFECTED EQUIPMENT INVOLVING THE POTENTIAL | | FAILURE OF MANY COMPONENTS AND SYSTEMS NOT DIRECTLY RELATED TO THE SAFE | | SHUTDOWN PATH. EXISTING APP R ANALYSIS HAS NOT EVALUATED THE FIRE INDUCED | | FAILURE OF THIS NON-SAFE SHUTDOWN RELATED EQUIPMENT ON AN INDIVIDUAL BASIS | | TO ADDRESS THE EFFECTS ON SAFE SHUTDOWN. | | | | NO IMMEDIATE CORRECTIVE ACTIONS WERE REQUIRED AS WNP-2 IS CURRENTLY | | SHUTDOWN FOR THEIR ANNUAL MAINTENANCE AND REFUELING OUTAGE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+