U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/19/96 - 03/20/96 ** EVENT NUMBERS ** 29996 30105 30130 30131 30132 30133 30134 30135 30136 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29996 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 02/19/96 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 16:42 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 02/19/96 | +------------------------------------------------+EVENT TIME: 15:00[CST]| |NRC NOTIFIED BY: PAUL BREWER |LAST UPDATE DATE: 03/20/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHUCK CAIN 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 +------------------------------------------------------------------------------+ | CONTROL ROOM HVAC COOLING COILS REQUIRED FOR POST LOSS OF COOLANT ACCIDENTS | | HEAT REMOVAL WERE FOUND INCAPABLE OF REMOVING THEIR REQUIRED HEAT LOAD. | | | | AS PART OF TECHNICAL SPECIFICATION IMPROVEMENT PROGRAM, A SURVEILLANCE TEST | | WAS DEVELOPED TO DETERMINE THE HEAT REMOVAL CAPABILITY OF THE CONTROL ROOM | | HVAC UNITS. PERFORMANCE DATA OBTAINED INDICATES THE CONTROL ROOM HVAC UNITS | | MAY NOT HAVE THE CAPABILITY OF REMOVING THE MAXIMUM DESIGN BASED HEAT LOADS | | WITH A SINGLE UNIT OF 658,300 BTU/HR. ENGINEERING EVALUATED THE DATA AND | | DETERMINED THE POST LOCA HEAT REMOVAL CAPABILITY OF THE "A" CONTROL ROOM | | HVAC UNIT COIL TO BE 356,301 BTU/HR AT THE EVALUATED CONDITION, AND THE | | POST LOCA HEAT REMOVAL CAPABILITY OF THE "B" CONTROL ROOM HVAC UNIT COIL TO | | BE 431,725 BTU/HR AT THE EVALUATED CONDITION. THE REQUIRED POST LOCA HEAT | | REMOVAL CAPABILITY FOR EACH OF THE COILS IS 658,300 BTU/HR. LICENSEE SAID | | THAT THIS PROBLEM WAS CORRECTED TWO OR THREE WEEKS AGO AND HE DID NOT KNOW | | WHAT WAS DONE TO CORRECT THE PROBLEM. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | | | | * * * UPDATE AT 0013 ON 03/20/96 BY RUFFIN ENTERED BY HOO JOLLIFFE * * * | | | | LICENSEE DETERMINED THAT THE CONTROL ROOM HVAC UNITS, IN THEIR AS-FOUND | | CONDITION AT THE TIME OF THIS EVENT, WOULD HAVE PERFORMED ADEQUATELY TO | | REMOVE HEAT TO MAINTAIN CONTROL ROOM TEMPERATURE BELOW 120øF, THE DESIGN | | BASIS TEMPERATURE. THUS, LICENSEE DESIRES TO RETRACT THIS EVENT. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. HOO NOTIFIED R4DO LINDA | | HOWELL. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30105 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 03/13/96 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 14:20 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/13/96 | +------------------------------------------------+EVENT TIME: 11:20[CST]| |NRC NOTIFIED BY: R PEARSON |LAST UPDATE DATE: 03/19/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STEAM GENERATOR #12 WELDED SLEEVE JOINT WAS FOUND NOT TO MEET THE DESIGN | | BASIS REQUIREMENTS FOR LEAK TIGHTNESS AND MINIMUM AVERAGE WELD HEIGHT. | | | | DURING INSPECTION OF #12 STEAM GENERATOR TUBES IN FEBRUARY, 1996, A STEAM | | GENERATOR TUBE WELDED SLEEVE WAS REMOVED FROM ROW 7 COLUMN 63 FOR | | METALLURGICAL EXAMINATION DUE TO POTENTIAL LEAKAGE AND EDDY CURRENT | | INDICATIONS. THE METALLURGICAL EXAMINATION OF THE TUBE-TO-SLEEVE UPPER | | JOINT FOUND THAT THE WELDED SLEEVE JOINT DID NOT MEET THE DESIGN BASIS | | REQUIREMENTS FOR LEAK TIGHTNESS AND MINIMUM AVERAGE WELD HEIGHT. THE WELDED | | JOINT IS DEGRADED IN THAT A LACK OF WELD FUSION RESULTED IN A LEAK PATH | | FROM THE PRIMARY TO SECONDARY SIDE. THIS SLEEVE WAS IN SERVICE FROM | | JANUARY, 1993 UNTIL JANUARY, 1996. PRELIMINARY EVALUATION INDICATED THAT | | TUBE #R7C63 WOULD HAVE MET THE STRUCTURAL AND LEAKAGE REQUIREMENTS OF DRAFT | | REGULATORY GUIDE 1.121, "BASES FOR PLUGGING DEGRADED PRESSURIZED WATER | | REACTOR STEAM GENERATOR TUBES". THE OTHER UNIT 1 STEAM GENERATOR DOES NOT | | HAVE ANY SLEEVES IN IT. THE UNIT 2 STEAM GENERATORS DO NOT HAVE ANY SLEEVES | | IN THEM. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1146 ON 3/19/96 FROM PEARSON TAKEN BY KARSCH * * * | | | | DEGRADED CONDITIONS WERE FOUND IN THREE ADDITIONAL SLEEVED TUBES. TUBES IN | | ROW 5 COLUMN 48, ROW 7 COLUMN 52, AND ROW 9 COLUMN 57 DID NOT MEET MINIMUM | | DESIGN REQUIREMENTS. IN ALL CASES, THE DEFECTIVE JOINTS ARE INSTALLATION | | RELATED AND NOT SERVICE RELATED. LEAK PATHS EXISTED AND MINIMUM WELD | | HEIGHTS WERE NOT MET. THE SLEVES WERE IN SERVICE SINCE 1/93. PRELIMINARY | | EVALUATION SHOWS THAT ALL JOINTS WOULD HAVE MET STRUCTURAL AND LEAKAGE | | REQUIREMENTS OF REG GUIDE 1.121 AND TECH SPECS (WHICH ALLOW SOME LEAKAGE). | | THE LICENSEE'S ADMINISTRATIVE REQUIREMENT IS FOR THE SLEEVE TO BE LEAK | | TIGHT AND THE DESIGN BASIS IS FOR A LEAK TIGHT SLEEVE. THE SLEEVING | | PROCEDURES WILL BE UPGRADED. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. THE HOO NOTIFIED R3DO JACOBSON. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30130 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 03/19/96 | |UNIT: [ ] [2] [ ] STATE: MN |NOTIFICATION TIME: 02:47 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/19/96 | +------------------------------------------------+EVENT TIME: 00:11[CST]| |NRC NOTIFIED BY: BRUCE ANDERSON |LAST UPDATE DATE: 03/19/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON 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 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTO REACTOR TRIP FROM 100% POWER ON LOW LOW STEAM GENERATOR WATER LEVEL. | | | | THE LICENSEE SUSPECTS THAT SEPARATION OF THE DISK AND STEM ON A FEEDWATER | | REGULATING VALVE CAUSED THE LOSS OF FEEDWATER FLOW TO THE "21" STEAM | | GENERATOR. THE RESULTING LOSS OF WATER LEVEL IN THE STEAM GENERATOR CAUSED | | A REACTOR TRIP. ALL CONTROL RODS INSERTED FULLY INTO THE REACTOR CORE | | FOLLOWING THE TRIP. AUXILIARY FEEDWATER PUMPS "21" AND "22" WERE ACTUATED | | AND SUPPLIED FEEDWATER TO THE STEAM GENERATORS. BYPASS VALVES AND THE MAIN | | CONDENSER ARE AVAILABLE FOR THE REMOVAL OF DECAY HEAT. LETDOWN ISOLATION | | OCCURRED FOLLOWING THE REACTOR TRIP BECAUSE PRESSURIZER LEVEL FELL BELOW | | 14% FOR A SHORT PERIOD OF TIME. NO SAFETY VALVES LIFTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30131 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 03/19/96 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 05:32 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 03/19/96 | +------------------------------------------------+EVENT TIME: 03:27[CST]| |NRC NOTIFIED BY: KEN PIOTEREK |LAST UPDATE DATE: 03/19/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON 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 +------------------------------------------------------------------------------+ | HIGH PRESSURE SAFETY INJECTION (HPSI) SYSTEM DECLARED INOPERABLE AND A 14 | | DAY TECH SPEC LCO ENTERED. | | | | THE LICENSEE STARTED THE HPSI SYSTEM TO PERFORM QCOP0010-09, "SAMPLING HPSI | | TURBINE RESERVOIR OIL". SEVEN MINUTES INTO THE PROCEDURE ALARM B9 ON THE | | 9023 PANEL, "HPSI MOTOR OVERLOAD", WAS RECEIVED FOR THE HPSI AUXILIARY OIL | | PUMP. HPSI WAS DECLARED INOPERABLE AND A 14 DAY LIMITING CONDITION FOR | | OPERATION WAS ENTERED IN ACCORDANCE WITH TECH SPEC 3.5.C. THE LICENSEE IS | | INVESTIGATING THE CAUSE OF THE MOTOR OVERLOAD. THE LICENSEE INFORMED THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30132 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 03/19/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 06:49 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/19/96 | +------------------------------------------------+EVENT TIME: 04:30[EST]| |NRC NOTIFIED BY: JESSE PIKE |LAST UPDATE DATE: 03/19/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON 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 1 STARTUP | 1 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RCIC ISOLATED WHILE THE SYSTEM WAS BEING PREPARED FOR SERVICE. | | | | AFTER DRAINING THE RCIC STEAM SUPPLY LINES, THE BYPASS VALVE WAS OPENED TO | | WARM THE STEAM LINE. THE SYSTEM IMMEDIATELY ISOLATED DUE TO A HIGH STEAM | | FLOW SIGNAL. NO LINE BREAK WAS FOUND. THE ISOLATION WAS RESET AND THE | | RCIC WAS SUCCESSFULLY PLACED INTO SERVICE. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR AND LOWER ALLOWAYS CREEK TOWNSHIP. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 30133 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WILLIAM BEAUMONT HOSPITAL |NOTIFICATION DATE: 03/19/96 | | CITY: ROYAL OAK REGION: 3 |NOTIFICATION TIME: 17:40 [ET]| | COUNTY: STATE: MI |EVENT DATE: 03/19/96 | |LICENSE#: 2101333-01 AGREEMENT: N |EVENT TIME: 10:30[EST]| | DOCKET: |LAST UPDATE DATE: 03/19/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN JACOBSON RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: SCHULTZ | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE WILLIAM BEAUMONT HOSPITAL REPORTED A POSSIBLE THERAPEUTIC MEDICAL | | MISADMINISTRATION. | | | | THE LICENSEE WAS TREATING A PATIENT FOR CANCER. THE TREATMENT PLAN | | SPECIFIED 7 SOURCE OR DWELL POSITIONS WITHIN THE TREATMENT SITE. PRIOR TO | | THE BEGINNING OF THE FIRST TREATMENT, ALL BUT ONE OF THE CORRECT TREATMENT | | PARAMETERS WERE ENTERED. THE TREATMENT PLAN CALLED FOR A STEP LENGTH OF 2.5 | | MILLIMETERS, INSTEAD, A STEP LENGTH WAS ENTERED AT 5.0 MILLIMETERS. SO WHEN | | THE STEP LENGTH WAS ALTERED TO THE LONGER LENGTH, THE LENGTH OF THE | | TREATMENT VOLUME WAS ALSO LONGER. THEREFORE, THE DOSE THAT WAS DELIVERED | | WAS LESS THAN THE PRESCRIBED DOSE. THE FIRST DWELL POSITION WAS ACTUALLY | | LOCATED OUTSIDE THE TREATMENT SITE WHILE BEING IN THE CYLINDER. HOWEVER, IT | | WAS LOCATED 1" FROM THE PATIENT'S PERINEUM WHICH MAY HAVE RESULTED IN THE | | PATIENT POSSIBLY RECEIVING A MAXIMUM DOSE TO THE SKIN AT THE THIGHS OF | | APPROX 500 RADS. THE LICENSEE DOES NOT EXPECT ANY ADVERSE AFFECTS TO THE | | PATIENT. THE LICENSEE RE-RAN THE TREATMENT PLAN @ 12:00 FOR THAT FRACTION | | AND RETREATED THE PATIENT WITH THE PRESCRIBED DOSE OF 500 RADS +/- 5%. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30134 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 03/19/96 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 20:15 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 03/19/96 | +------------------------------------------------+EVENT TIME: 19:30[EST]| |NRC NOTIFIED BY: BURCHFIELD |LAST UPDATE DATE: 03/19/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |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 | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE ENTERED A 4 HOUR LCO ACTION STATEMENT DUE TO THE "2HP-3" | | CONTAINMENT ISOLATION VALVE BEING DECLARED INOPERABLE. | | | | AS A RESULT OF EVALUATING DATA, AN ENGINEERING ANALYSIS HAS DETERMINED THAT | | VALVE "2HP-3" (CONTAINMENT ISOLATION VALVE FOR THE LETDOWN COOLER OUTLET) | | MAY NOT BE ABLE TO CLOSE AGAINST FULL DIFFERENTIAL PRESSURE UNDER CERTAIN | | ACCIDENTS SCENARIOS. ASSUMING A SINGLE FAILURE OF THE SECOND CONTAINMENT | | ISOLATION VALVE FOR THE SAME PENETRATION, IT COULD POTENTIALLY RESULT IN | | THE FAILURE TO ISOLATE A CONTAINMENT PENETRATION FOLLOWING AN ACCIDENT. | | THE IMMEDIATE TECH SPEC ACTION STATEMENT ACTION IS TO CLOSE THE SUSPECT | | VALVE AND OPEN ITS BREAKER. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | NOTE: SEE EVENT #30135 FOR A RELATED EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30135 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 03/19/96 | |UNIT: [ ] [ ] [3] STATE: SC |NOTIFICATION TIME: 20:15 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 03/19/96 | +------------------------------------------------+EVENT TIME: 19:30[EST]| |NRC NOTIFIED BY: BURCHFIELD |LAST UPDATE DATE: 03/19/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK 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 +------------------------------------------------------------------------------+ | THE LICENSEE DECLARED "3HP-3" CONTAINMENT ISOLATION VALVE INOPERABLE. | | | | AS A RESULT OF EVALUATING DATA, AN ENGINEERING ANALYSIS HAS DETERMINED THAT | | VALVE "3HP-3" (CONTAINMENT ISOLATION VALVE FOR THE LETDOWN COOLER OUTLET) | | MAY NOT BE ABLE TO CLOSE AGAINST FULL DIFFERENTIAL PRESSURE UNDER CERTAIN | | ACCIDENT SCENARIOS. ASSUMING A SINGLE FAILURE OF THE SECOND CONTAINMENT | | ISOLATION VALVE FOR THE SAME PENETRATION, IT COULD POTENTIALLY RESULT IN | | THE FAILURE TO ISOLATE A CONTAINMENT PENETRATION FOLLOWING AN ACCIDENT. | | THE LICENSEE TAGGED THE VALVE INOPERABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | NOTE: SEE EVENT #30134 FOR A RELATED EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30136 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/19/96 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 20:35 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/19/96 | +------------------------------------------------+EVENT TIME: 20:00[EST]| |NRC NOTIFIED BY: NELSON |LAST UPDATE DATE: 03/19/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO VITAL 480 VAC MCC ENCLOSURE DOORS FOUND IN DEGRADED CONDITION. | | | | LICENSEE DISCOVERED THE GASKET MATERIAL ON TWO VITAL 480 VAC MOTOR CONTROL | | CENTER (MCC) ENCLOSURE DOORS WAS DEGRADED. THIS CONDITION, THEY BELIEVE, | | COULD ALLOW STEAM FROM A HIGH ENERGY STEAM BREAK TO ENTER THE MCC | | ENCLOSURES. THE LICENSEE WILL REPLACE THE GASKETS. | | | | THE LICENSEE NOTIFIED STATE OFFICIALS AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+