U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/28/97 - 01/29/97 ** EVENT NUMBERS ** 31486 31669 31672 31673 31674 31675 31676 31677 31678 31679 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31486 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 12/19/96 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 17:45 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 12/19/96 | +------------------------------------------------+EVENT TIME: 17:00[EST]| |NRC NOTIFIED BY: JERALD KAHN |LAST UPDATE DATE: 01/28/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD BELLAMY RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | |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 | 99 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECH SPEC REQUIRED SHUTDOWN BECAUSE THE LICENSEE NEGLECTED TO PERFORM AN | | INSPECTION OF THE "SHOOT OUT STEEL" UNDER THE REACTOR VESSEL. | | | | THE LICENSEE STARTED A TECH SPEC REQUIRED SHUTDOWN PER TECH SPEC 3.1.3.8 | | DUE TO FAILURE TO PERFORM THE REQUIRED GAP INSPECTION FOR THE SHOOT OUT | | STEEL STRUCTURAL BARRIERS UNDER THE REACTOR VESSEL. THE LICENSEE PERFORMED | | A VISUAL INSPECTION DURING THEIR LAST REFUELING OUTAGE, BUT THE GAP WAS NOT | | MEASURED. FAILURE TO PERFORM THE REQUIRED INSPECTION PLACES THE UNIT IN A | | POTENTIALLY UNANALYZED CONDITION. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | | | | * * * UPDATE AT 1359 ON 01/28/97 BY STEVE FREGEAU ENTERED BY JOLLIFFE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. | | | | THE GAPS ON ALL 185 CONTROL ROD DRIVES WERE INSPECTED WHILE THE PLANT WAS | | SHUTDOWN. APPROXIMATELY 10% OF THE AS-FOUND GAPS WERE SLIGHTLY OUTSIDE THE | | ORIGINAL INSPECTION CRITERIA. THE LICENSEE (AND GENERAL ELECTRIC) HAS | | EVALUATED THE AS-FOUND DIMENSIONS, AND CONCLUDED THAT THE STRUCTURE WAS, IN | | FACT, OPERABLE. THEREFORE, THE REACTOR SHUTDOWN HAD NOT BEEN REQUIRED BY | | PLANT TECHNICAL SPECIFICATIONS. THE ENGINEERING EVALUATION ALSO CONCLUDED | | THAT THE APPLICABLE DESIGN BASIS HAD NOT BEEN COMPROMISED AND THAT THE | | REACTOR HAD NOT BEEN OPERATED IN AN UNANALYZED CONDITION. THUS, THE | | LICENSEE IS RETRACTING THIS EVENT. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. THE HOO NOTIFIED R1DO (GENE KELLY). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31669 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 01/27/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 15:12 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 01/27/97 | +------------------------------------------------+EVENT TIME: 12:35[CST]| |NRC NOTIFIED BY: RAY VENCI |LAST UPDATE DATE: 01/28/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP 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 +------------------------------------------------------------------------------+ | - HPCI SYSTEM STOP VALVE OPENED TOO FAST DURING A TS SURVEILLANCE TEST - | | | | WHILE REVIEWING TEST DATA FROM A TECH SPEC SURVEILLANCE TEST PERFORMED ON | | 01/22/97, THE LICENSEE DETERMINED THAT A HPCI SYSTEM STOP VALVE OPENED | | FASTER THAN THE TEST ACCEPTANCE CRITERIA ALLOWED. THE LICENSEE DECLARED | | THE HPCI SYSTEM INOPERABLE. | | | | TECH SPEC LCO A/S 3.5.A.3 REQUIRES THE LICENSEE TO RESTORE THE HPCI SYSTEM | | TO OPERABLE STATUS WITHIN 14 DAYS OR TO PLACE UNIT 2 IN AT LEAST A HOT | | SHUTDOWN CONDITION WITHIN THE FOLLOWING 12 HOURS. | | | | THE LICENSEE PLANS TO RETEST THE VALVE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1427 ON 01/28/97 BY RAY VENCI ENTERED BY JOLLIFFE * * * | | | | FURTHER INVESTIGATION BY THE LICENSEE REVEALED THAT THE CAUSE OF THE ABOVE | | EVENT WAS INCORRECT TIMING OF THE STOP VALVE. ADDITIONAL TESTING INDICATED | | THAT THE VALVE STROKE TIME WAS WITHIN THE ACCEPTABLE RANGE WITH NO | | SIGNIFICANT CHANGE FROM PREVIOUS DATA. AT NO TIME WAS THE HPCI SYSTEM | | INOPERABLE AND IT WOULD HAVE PERFORMED ITS INTENDED FUNCTION AT ALL TIMES. | | THE LICENSEE EXITED TECH SPEC LCO A/S 3.5.A.3 AT 1830 (CST) ON 01/27/97. | | THUS, THE LICENSEE DESIRES TO RETRACT THIS EVENT. THE LICENSEE INFORMED | | THE NRC RESIDENT INSPECTOR. | | | | THE HOO NOTIFIED R3DO JIM CREED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31672 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/28/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 11:34 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/28/97 | +------------------------------------------------+EVENT TIME: 11:20[EST]| |NRC NOTIFIED BY: CLEARY |LAST UPDATE DATE: 01/28/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KELLY 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 +------------------------------------------------------------------------------+ | CONTAINMENT ISOLATION VALVE MAY NOT CLOSE QUICKLY ENOUGH TO MITIGATE | | RADIOACTIVITY RELEASE | | | | THE LICENSEE HAS DETERMINED THAT CONTAINMENT ISOLATION VALVE 1-RC-206 MAY | | NOT CLOSE QUICKLY ENOUGH FOLLOWING A DESIGN BASIS ACCIDENT, ASSUMING A | | FAILURE OF THE REDUNDANT ISOLATION VALVE TO CLOSE. THIS VALVE, LOCATED ON | | THE RBCCW SYSTEM, IS AN AC OPERATED VALVE, SUPPLIED BY THE GAS TURBINE. THE | | REDUNDANT VALVE (1-RC-207) IS A DC OPERATED VALVE. ASSUMING A LOCA, LOOP, | | AND THE FAILURE OF VALVE 1-RC-207 TO CLOSE, VALVE 1-RC-206 WOULD BE | | REQUIRED TO CLOSE WITHIN 60 SECONDS TO ISOLATE THE CONTAINMENT. AC POWER | | FROM THE GAS TURBINE WOULD NOT BE AVAILABLE FOR 48 SECONDS, AND THE TYPICAL | | STROKE TIME FOR THE VALVE IS 20 SECONDS (UP TO 35 SECONDS ALLOWABLE). THUS, | | THE STROKE TIME FOR THIS VALVE WOULD EXCEED THE MAXIMUM ALLOWABLE ISOLATION | | TIME. | | | | THE LICENSEE PLANS TO REALIGN THE POWER SUPPLY FOR THIS VALVE FROM THE GAS | | TURBINE TO THE EMERGENCY DIESEL GENERATOR, WHICH PROVIDES AC POWER WITHIN | | 13 SECONDS OF STARTUP. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31673 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 01/28/97 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 12:02 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 01/28/97 | +------------------------------------------------+EVENT TIME: 10:38[EST]| |NRC NOTIFIED BY: STEVE DAVIS |LAST UPDATE DATE: 01/28/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE KELLY RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - FREON-22 GAS LEAK INTO THE ATMOSPHERE REPORTED TO THE NY STATE DEC - | | | | THE LICENSEE REPORTED TO THE NEW YORK STATE DEPARTMENT OF ENVIRONMENTAL | | CONSERVATION (DEC) THAT 11 POUNDS OF FREON-22 GAS HAD LEAKED INTO THE | | ATMOSPHERE FROM CONTROL ROOM AIR CONDITIONER #32B ON 01/27/97. | | | | THE FREON GAS DISPERSED INTO THE ATMOSPHERE AND DOES NOT REPRESENT A HAZARD | | TO PUBLIC HEALTH AND SAFETY OR REQUIRE CLEANUP. NO PLANT PERSONNEL WERE | | ADVERSELY AFFECTED BY THE LEAK. | | | | THE LICENSEE WILL REPAIR THE LEAK AND RECHARGE THE AIR CONDITIONER. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31674 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 01/28/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 14:42 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 01/28/97 | +------------------------------------------------+EVENT TIME: 11:08[CST]| |NRC NOTIFIED BY: RICH CHEAR |LAST UPDATE DATE: 01/28/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - FULL SCRAM SIGNAL WITH Rx SHUTDOWN IN REFUELING OUTAGE - | | | | THE PLANT IS IN OPERATIONAL CONDITION 5 (REFUELING) IN A REFUELING OUTAGE | | WITH ALL CONTROL RODS COMPLETELY INSERTED INTO THE CORE. | | | | THE CABLE TO DIVISION 2 INTERMEDIATE RANGE MONITOR (IRM) CHANNEL 'F' HAD | | BEEN DISCONNECTED AND SAFETY TAGGED FOR SCHEDULED MAINTENANCE ACTIVITIES. | | DISCONNECTING THE IRM CABLE INPUT AN IRM TRIP SIGNAL (HALF SCRAM SIGNAL) TO | | THE REACTOR PROTECTION SYSTEM (RPS). | | | | AT 1108 (CST) ON 01/28/97, I&C TECHNICIANS DISCONNECTED THE CABLE TO | | DIVISION 1 IRM CHANNEL 'E' IN PREPARATION TO SAFETY TAG THE CHANNEL FOR | | MAINTENANCE ACTIVITIES. DISCONNECTING THE IRM CABLE INPUT A SECOND IRM | | TRIP SIGNAL (SECOND HALF SCRAM SIGNAL) TO THE RPS WHICH RESULTED IN A FULL | | REACTOR SCRAM SIGNAL. | | | | SINCE ALL CONTROL RODS WERE COMPLETELY INSERTED INTO THE CORE, THERE WAS | | NO CONTROL ROD MOVEMENT DUE TO THE REACTOR SCRAM SIGNAL. CONTROL ROOM | | OPERATORS RESET THE REACTOR SCRAM SIGNAL TO NORMAL AT 1125 (CST) ON | | 01/28/97. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31675 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 01/28/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 15:23 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/28/97 | +------------------------------------------------+EVENT TIME: 15:00[EST]| |NRC NOTIFIED BY: BOB VASEY |LAST UPDATE DATE: 01/28/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED 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 | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SEVERAL SYSTEMS OUTSIDE THEIR DESIGN BASIS PER NRC GENERIC LETTER 96-06 - | | | | AS A RESULT OF AN ENGINEERING EVALUATION OF NRC GENERIC LETTER 96-06, THE | | LICENSEE HAS DETERMINED THAT PORTIONS OF THE REACTOR COOLANT PUMP SEAL | | WATER RETURN LINE, THE REACTOR COOLANT SYSTEM SAMPLE LINES, AND THE | | ACCUMULATOR SAMPLE LINES ARE OUTSIDE THEIR DESIGN BASIS. | | | | SPECIFICALLY, FOLLOWING A DESIGN BASIS ACCIDENT, WHEN THE ABOVE SYSTEMS | | ARE ISOLATED, THE PIPING PORTIONS WHICH PENETRATE THE CONTAINMENT COULD BE | | THERMALLY OVERPRESSURIZED, RESULTING IN PIPE STRESSES IN EXCESS OF UFSAR | | ALLOWABLE STRESSES. | | | | INITIAL LICENSEE CALCULATIONS INDICATE THAT WHILE UFSAR ALLOWABLE STRESSES | | WOULD BE EXCEEDED FOR THE ABOVE SYSTEMS AND CONDITIONS, ASME B&PV CODE, | | SECTION III, APPENDIX 'F', LEVEL 'D' SERVICE LIMITS WOULD NOT BE EXCEEDED. | | | | THEREFORE, THESE SYSTEMS ARE DETERMINED TO BE OPERABLE AND ABLE TO PERFORM | | THEIR CONTAINMENT ISOLATION FUNCTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31676 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 01/28/97 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 16:31 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 01/28/97 | +------------------------------------------------+EVENT TIME: 14:52[CST]| |NRC NOTIFIED BY: BRETT WELLER |LAST UPDATE DATE: 01/28/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED 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 +------------------------------------------------------------------------------+ | - SEVERAL SYSTEMS EXCEED UFSAR ALLOWABLE STRESSES PER NRC GL 96-06 - | | | | AS A RESULT OF AN ENGINEERING EVALUATION OF NRC GENERIC LETTER 96-06, | | THE LICENSEE HAS DETERMINED THAT, WHEN ISOLATED, PORTIONS OF THE DRYWELL | | FLOOR DRAIN SUMP SYSTEM, RESIDUAL HEAT REMOVAL SHUTDOWN COOLING SYSTEM, | | AND RESIDUAL HEAT REMOVAL HEAD SPRAY SYSTEM WOULD EXCEED UFSAR ALLOWABLE | | STRESSES DURING CERTAIN DESIGN BASIS ACCIDENTS. | | | | THE LICENSEE'S PIPING ANALYSIS INDICATES THAT THESE PORTIONS OF THE ABOVE | | SYSTEMS ARE OPERABLE (i.e., THEY WOULD NOT RUPTURE AND THE CONTAINMENT | | INTEGRITY WOULD BE INTACT IN ALL DESIGN BASIS ACCIDENTS PER NRC GENERIC | | LETTER 91-18 GUIDANCE). | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31677 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 01/28/97 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 19:04 [ET]| |RX TYPE: [1] GE-1 |EVENT DATE: 01/28/97 | +------------------------------------------------+EVENT TIME: 18:50[EST]| |NRC NOTIFIED BY: MIKE BOURASSA |LAST UPDATE DATE: 01/28/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - DEMIN WATER LINE SUSCEPTIBLE TO OVERPRESSURIZATION PER NRC GL 96-06 - | | | | DURING A LICENSEE ENGINEERING EVALUATION OF NRC GENERIC LETTER 96-06, | | THE LICENSEE HAS DETERMINED THAT THE FUNCTIONALLY NON-SAFETY RELATED | | DEMINERALIZED WATER LINE IS SUSCEPTIBLE TO OVERPRESSURIZATION DURING A | | POSTULATED DESIGN BASIS ACCIDENT. | | | | A PRELIMINARY OVERPRESSURIZATION STRESS ANALYSIS INDICATED THAT | | DEMINERALIZED WATER PIPE HOOP STRESSES WOULD EXCEED THEIR ULTIMATE VALUE | | ASSUMING THE CONSEQUENCES OF A 0.63 SQUARE FEET MAIN STEAM LINE BREAK, | | SOLID PIPE, AND ZERO LEAKAGE OF THE VALVES IN THE LINE. | | | | IN ORDER FOR WATER TO BECOME TRAPPED IN THE LINE, SEVERAL VALVES MUST | | CLOSE. DURING A LOCA WITH A LOOP, THE DEMINERALIZED WATER SUPPLY VALVE | | (#CV-4105) WILL AUTOMATICALLY CLOSE. IN ADDITION, THE DEMINERALIZED WATER | | SUPPLY VALVE TO THE EMERGENCY CONDENSER (#CV-4028), WHICH IS NORMALLY | | CLOSED, WILL AUTOMATICALLY CLOSE, IF OPEN. DEMINERALIZED WATER WILL THEN BE | | TRAPPED IN A PIPE SEGMENT BETWEEN CV-4105 AND VCU-300, AND ANOTHER SEGMENT | | OF DEMINERALIZED WATER WILL BE TRAPPED BETWEEN CV-4028 AND ITS ASSOCIATED | | CHECK VALVE, VEC-300. | | | | THE ABOVE VALVES ARE NOT CONTAINMENT ISOLATION VALVES AND CLOSE UPON A | | LOOP. | | | | THE LICENSEE IS PERFORMING AN OPERABILITY DETERMINATION AND WILL COMPLETE | | IT PRIOR TO PLANT RESTART SCHEDULED FOR 01/31/97. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31678 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 01/29/97 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 00:47 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 01/28/97 | +------------------------------------------------+EVENT TIME: 23:23[CST]| |NRC NOTIFIED BY: MARK COVEY |LAST UPDATE DATE: 01/29/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DISCOVERY OF LOSS OF SECURITY EQUIPMENT. COMPENSATORY MEASURES ARE BEING | | TAKEN. | | | | SEE HOO LOG FOR FURTHER DETAILS | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31679 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 01/29/97 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 05:05 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 01/29/97 | +------------------------------------------------+EVENT TIME: 03:40[CST]| |NRC NOTIFIED BY: McDONALD |LAST UPDATE DATE: 01/29/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY PARAMETER DISPLAY SYSTEM (SPDS) IS OUT OF SERVICE. | | | | THE SPDS IS OUT OF SERVICE DUE TO A COMPUTER PROBLEM. ALL PLANT INDICATIONS | | INCLUDING THE PLANT DISPLAY SYSTEM ARE FULLY OPERABLE. LICENSEE HAS CALLED | | IN THEIR COMPUTER TECHNICIANS TO REPAIR THE SPDS COMPUTER. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE OF THIS EVENT. | | | | ***UPDATE @ 0549 ET ON 01/29/97 BY McDONALD TAKEN BY MACKINNON*** | | | | THE SPDS MONITOR IS BURNED OUT. LICENSEE WILL REPLACE THE MONITOR. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+