U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/14/97 - 04/15/97 ** EVENT NUMBERS ** 31950 32143 32145 32146 32147 32148 32149 32150 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31950 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 03/14/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 07:48 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 03/14/97 | +------------------------------------------------+EVENT TIME: 07:30[EST]| |NRC NOTIFIED BY: DOUG LACUYER |LAST UPDATE DATE: 04/14/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN 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 +------------------------------------------------------------------------------+ | IDENTIFICATION OF CRACKS IN VERTICAL SHROUD WELD HEAT AFFECTED ZONES | | | | AS A RESULT OF AUGMENTED IN-SERVICE INSPECTION OF THE REACTOR CORE SHROUD | | IN ACCORDANCE WITH THE BOILING WATER REACTOR VESSEL INTERNAL PROJECT | | (BWRVIP07) GUIDELINES, WELD INDICATIONS (CRACKS) WERE FOUND IN THE HEAT | | AFFECTED ZONES ON THE OUTSIDE DIAMETER ONLY. A SIGNIFICANT PORTION OF THE | | EQUIVALENT LENGTH OF WELDS V9 AND V10 EXHIBITED INDICATIONS. INSPECTION IS | | CONTINUING, AND OTHER VERTICAL WELDS MAY BE CRACKED. THIS EXCEEDS THE | | INITIAL FLAW EVALUATION ACCEPTANCE CRITERIA OF A MINIMUM REQUIRED UNCRACKED | | LENGTH OF 27 INCHES. EXPANDED SAMPLE INSPECTIONS ARE UNDER WAY TO | | DETERMINE THE EXTENT OF CRACKING OF OTHER SHROUD VERTICAL WELDS IN | | ACCORDANCE WITH THE BWRVIP07 CRITERIA, WHICH WAS RECENTLY REVIEWED AND | | ACCEPTED BY THE NRC STAFF FOR UNIT 1. AS A RESULT OF THE EXPANDED | | EXAMINATIONS, ENGINEERING PLANS TO ASSESS THE ACCEPTABILITY OF THE CRACKING | | AND OVERALL SAFETY IMPLICATIONS. ALL OF THE REACTOR FUEL IS IN THE SPENT | | FUEL POOL AT THIS TIME. BASED UPON THIS DETAILED ANALYSIS, THIS | | NOTIFICATION MAY BE RESCINDED. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * * * RETRACTION ON 04/14/97 @ 0835EDT BY LeCuyer TAKEN BY MACKINNON * * * | | | | AFTER EXTENSIVE NONDESTRUCTIVE EXAMINATION, EVALUATION, AND ANALYSIS THE | | LICENSEE IS RESCINDING THIS EVENT NOTIFICATION FOR THE VERTICAL WELD | | CRACKING FOR THE NINE MILE POINT UNIT 1 SHROUD. A DETAILED EVALUATION | | REPORT WAS DEVELOPED AND SUBMITTED TO THE NRC ON APRIL 10, 1997. THE REPORT | | INDICATED THAT THE UNIT 1 SHROUD WOULD HAVE PERFORMED ITS DESIGN FUNCTION. | | THE REPORT ALSO INDICATED THAT SAFE OPERATION DURING THE LAST CYCLE WAS NOT | | JEOPARDIZED. THE ROOT CAUSE FOR THE CRACKING IS INTERGRANULAR STRESS | | CORROSION CRACKING WHICH HAS BEEN EXHIBITED IN OTHER BWR's AS WELL. THE | | CRACKING WAS ANALYZED IN ACCORDANCE WITH NRC APPROVED BWRVIP METHODS AND | | ASME CODES. R1DO (NOGGLE) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32143 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 04/13/97 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 15:28 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/13/97 | +------------------------------------------------+EVENT TIME: 14:45[EDT]| |NRC NOTIFIED BY: JAMES R. BARNES |LAST UPDATE DATE: 04/14/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNEXPECTED LOSS OF 120/240VAC VITAL BUS DURING TESTING OF "2A" EMERGENCY | | DIESEL GENERATOR (EDG). | | | | "AT APPROXIMATELY 1350EDT DURING THE PERFORMANCE OF 42SV-R43-008-OS (DIESEL | | GENERATOR LOCA/LOSP LOGIC SYSTEM FUNCTIONAL TEST) THE VITAL AC BUS WAS | | DEENERGIZED WHEN ITS ALTERNATE SUPPLY BREAKER WAS RACKED TO THE TEST | | POSITION. THIS RESULTED IN AN ESF WHEN THE FISSION PRODUCT SAMPLE VALVE | | 2D11-F050 CLOSED. VITAL AC SYS WAS RESTORED VIA THE NORMAL SUPPLY AND ALL | | CONDITIONS RESET. | | | | AFTER REVIEW OF THE ABOVE EVENT AT 1445EDT IT WAS DISCOVERED THAT THE | | EMERGENCY RESPONSE DATA SYSTEM WAS ALSO LOST AS A RESULT OF THE | | DEENERGIZATION OF THE VITAL AC SYS. THIS SYSTEM WAS ALSO RESET AND IS NOW | | FUNCTIONAL." | | | | PRIOR TO THE TEST, THE STATIC TRANSFER SWITCH WAS ALIGNED TO THE ALTERNATE | | POWER SUPPLY WHICH IS THE 600VAC BUS "2C". THE NORMAL POWER SUPPLY IS FROM | | THE 120/240VAC STATIC INVERTER ASSOCIATED WITH THE 125VDC BATTERY FLOATED | | BY A 125VDC BATTERY CHARGER CONNECTED TO THE 600VAC BUS "2D". WHEN THE | | ALTERNATE SUPPLY BREAKER WAS OPENED PER THE TEST PROCEDURE FOR THE "2A" | | EDG, THE 120/240 V VITAL AC DISTRIBUTION CABINET "2A" WAS DEENERGIZED | | RESULTING IN THE LOSS OF THOSE LOADS IDENTIFIED ABOVE. THE LICENSEE | | ATTRIBUTES THE CAUSE TO AN INADEQUATE PROCEDURE WHICH DID NOT HAVE AS A | | PREREQUISITE VERIFICATION THAT THE STATIC TRANSFER SWITCH WAS ALIGNED TO | | THE NORMAL POWER SUPPLY. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE AT 1528 ON 4/14/97 BY BARNES TO GOULD*** THE LICENSEE IS | | RETRACTING THE ESF ACTUATION PART OF THIS REPORT. SINCE NO ESF ACTUATION | | OCCURRED DUE TO THE "2D11-F050" VALVE ALREADY BEING CLOSED PRIOR TO THE | | EVENT, THE ESF PART OF THE REPORT SHOULD NOT HAVE BEEN MADE. THE RESIDENT | | INSPECTOR WILL BE INFORMED. REG 2 RDO(SKINNER) WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32145 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 04/14/97 | |UNIT: [ ] [ ] [3] STATE: AL |NOTIFICATION TIME: 15:05 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 04/14/97 | +------------------------------------------------+EVENT TIME: 11:42[CDT]| |NRC NOTIFIED BY: MORROW |LAST UPDATE DATE: 04/14/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 REPORTED THAT AN INADVERTENT MANUAL START OF THE "3D" DIESEL | | GENERATOR OCCURRED. | | | | THIS TOOK PLACE WHILE REDUNDANT START TESTING OF DIESEL GENERATOR "3C" WAS | | IN PROGRESS. AT THE POINT WHEN THE CONTROL ROOM OPERATOR WAS REQUESTED TO | | GIVE A MANUAL START SIGNAL TO DIESEL "3C" FROM PANEL "3-9-23C", IN ERROR HE | | GAVE DIESEL GENERATOR "3D" A START SIGNAL AT PANEL "3-9-23D". DIESEL "3D" | | WAS IN STANDBY, AND THUS FAST STARTED AND RAN NORMALLY WITH ITS OUTPUT | | BREAKER OPEN. DIESEL GENERATOR "3D" WAS MANUALLY SHUTDOWN AND RETURNED TO | | STANDBY AT 1153. DIESEL GENERATOR "3C" WAS THE ONLY SAFETY RELATED | | EQUIPMENT OUT OF SERVICE DURING THIS EVENT. THE RESIDENT INSPECTOR WAS | | NOTIFIED.. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32146 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 04/14/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 15:48 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/14/97 | +------------------------------------------------+EVENT TIME: 14:55[EDT]| |NRC NOTIFIED BY: MAY |LAST UPDATE DATE: 04/14/97 | |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 +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED A CABLE SEPARATION CONDITION WHICH DOES NOT MEET THE | | DIVISION 1 AND DIVISION 2 SEPARATION CRITERIA. | | | | THIS CONDITION EXIST BETWEEN THE FEEDER CABLES FOR DIVISION 2 LPCI | | INJECTION VALVES, THE RECIRC VALVES IN THE RECIRC LOOP, AND DIV 1 HPCI | | INJECTION VALVE, TORUS SUCTION VALVES AND RECIRC TEST VALVE. THIS LACK OF | | SEPARATION OCCURS IN A PULL BOX BETWEEN THE SWITCHGEAR ROOM AND THEIR | | REACTOR BUILDING. THEIR OPERABILITY ASSESSMENT HAS DETERMINED THAT DURING | | AN ACCIDENT CONDITION WITH A LO-LO LEVEL, THE FEEDER BREAKER FOR THE LPCI | | VALVES WILL DE-ENERGIZE, BUT THE VALVES WILL BE SUPPLIED POWER FROM THE | | BATTERY BANK. DIVISION 1 HPCI WOULD START AND BE SUPPLIED POWER BY THE | | CABLE WHICH GOES THROUGH THE PULL BOX. THEREFORE, THE DIVISION 1 CABLE WILL | | BE THE ONLY ENERGIZED CABLE IN THE PULL BOX DURING THAT ACCIDENT CONDITION. | | THE RESIDENT WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32147 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 04/14/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 17:40 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/14/97 | +------------------------------------------------+EVENT TIME: 14:45[CDT]| |NRC NOTIFIED BY: MIELKE |LAST UPDATE DATE: 04/14/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT THEY HAVE DISCOVERED SIX PREVIOUSLY UNREPORTED | | CONDITIONS RELATED TO APPENDIX "R" SCENARIOS THAT SHOULD HAVE BEEN | | REPORTED. | | | | THESE SIX CONDITIONS HAD BEEN IDENTIFIED IN CONDITION REPORTS(CRs): | | | | "96-553" - REVIEW OF THE APPENDIX R SAFE SHUTDOWN ANALYSIS INDICATED THAT A | | MANUAL OPERATION OF BREAKERS MAY BE REQUIRED DURING A POSTULATED FIRE IN | | THE CABLE SPREADING ROOM, REQUIRING ENTRY INTO THE AREA. | | | | "96-136" - REVIEW OF APPENDIX R SAFE SHUTDOWN ANALYSIS INDICATED THE | | POTENTIAL TO LOSE DC POWER TO ESSENTIAL INSTRUMENTATION DURING A POSTULATED | | FIRE IN THE NORTH ZONE OF THE AUXILIARY FEEDWATER(AFW) PUMP ROOM. | | | | "94-328" - REVIEW OF THE APPENDIX R SAFE SHUTDOWN ANALYSIS INDICATED THE | | POTENTIAL TO LOSE AN EMERGENCY DIESEL GENERATOR(EDG) IF THE DIESEL IS | | LOADED IN ACCORDANCE WITH ABNORMAL OPERATING PROCEDURE(AOP-10A) DURING THE | | WORST-CASE POSTULATED FIRE THAT AFFECTS THE CONTROL ROOM. | | | | "92-372" - REVIEW OF THE APPENDIX R SAFE SHUTDOWN ANALYSIS INDICATED THE | | APPENDIX R ESSENTIAL EQUIPMENT LIST DID NOT INCLUDE VENTILATION EQUIPMENT | | AS EQUIPMENT NECESSARY TO ACHIEVE HOT SHUTDOWN. | | | | "96-889" - REVIEW OF THE APPENDIX R SAFE SHUTDOWN ANALYSIS FOLLOWING THE | | DIESEL GENERATOR ADDITION PROJECT INDICATED A POTENTIAL TO LOSE ALL POWER | | FROM EMERGENCY DIESEL GENERATORS(EDGs) FOR A POSTULATED FIRE IN THE NORTH | | ZONE OF THE AUXILIARY FEEDWATER PUMP ROOM. | | | | "96-959" - REVIEW OF THE APPENDIX R SAFE SHUTDOWN ANALYSIS INDICATED THE | | POTENTIAL FOR A SPURIOUS BREAKER OPERATION TO PREVENT PROPER BREAKER | | STRIPPING DURING A POSTULATED FIRE. | | | | COMPENSATORY ACTIONS HAD BEEN IMPLEMENTED AS NECESSARY PER THE ORIGINAL | | CRs, AND WILL CONTINUE. REVISED OPERABILITY DETERMINATIONS WILL BE | | PERFORMED FOR EACH OF THE ORIGINAL CRs. | | | | THE RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32148 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/14/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 19:14 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/14/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 10:50[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/14/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |BRUCE BURGESS RDO | | DOCKET: 0707001 |JOHN GREEVES EO | +------------------------------------------------+RICHARD BARRETT 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 +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THAT A BRANCH SECTION OF PIPING ON A SPRINKLER | | SYSTEM WAS NOT CONNECTED TO THE SUPPLY HEADER. | | | | DURING A WALKDOWN OF THE HIGH PRESSURE FIREWATER SYSTEM IN "C-337" IT WAS | | DISCOVERED THAT A BRANCH SECTION OF PIPING ON SPRINKLER SYSTEM "A-5", WAS | | NOT CONNECTED TO THE FIRE WATER SUPPLY HEADER. THE SPRINKLER SYSTEM IN | | QUESTION IS DESIGNED TO SUPPLY FIRE PROTECTION TO BUILDING EXHAUST FANS | | "SE-32" AND "SE-32A". THE SYSTEM WAS DECLARED INOPERABLE AND AN HOURLY | | FIRE PATROL; WAS INITIATED FOR THE AFFECTED AREA AS REQUIRED BY TSR | | 2.4.4.5. THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32149 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 04/14/97 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 21:21 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 04/14/97 | +------------------------------------------------+EVENT TIME: 14:45[CDT]| |NRC NOTIFIED BY: TURNER |LAST UPDATE DATE: 04/14/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL JONES RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 HAS DECLARED ERDS INOPERABLE. | | | | THE CAUSE FOR ERDS BEING INOPERABLE IS DUE TO THE COMPUTER BEING DOWN. | | TECHNICIANS ARE CURRENTLY TROUBLESHOOTING. THE RESIDENT INSPECTOR WAS | | NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32150 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 04/15/97 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 02:12 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/15/97 | +------------------------------------------------+EVENT TIME: 00:37[CDT]| |NRC NOTIFIED BY: COTTON |LAST UPDATE DATE: 04/15/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JONES 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 +------------------------------------------------------------------------------+ | TURBINE-DRIVEN AUXILIARY FEEDWATER PUMP STARTED DUE TO VALVE FAILURE | | | | TURBINE-DRIVEN AUX FEEDWATER STEAM SUPPLY VALVE (2-HV-2452-2) FAILED OPEN, | | STARTING TDAFWP 2-01. THE PUMP INJECTED WATER TO ALL FOUR STEAM GENERATORS | | FOR APPROXIMATELY 30-40 SECONDS, UNTIL AFW FLOW CONTROL VALVES WERE | | MANUALLY CLOSED. THE MAIN FEEDWATER LEVEL CONTROL SYSTEM COMPENSATED FOR | | THE AFW FLOW, AND STEAM GENERATOR LEVELS REMAINED ESSENTIALLY UNCHANGED. | | THE LICENSEE'S INITIAL INVESTIGATION INDICATES THAT THE VALVE FAILURE WAS | | DUE TO A RUPTURED DIAPHRAGM. OPERATORS SECURED THE PUMP BY CLOSING MANUAL | | ISOLATION VALVES IN LINE WITH THE FAILED STEAM SUPPLY VALVE. THE NRC | | RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+