U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/26/96 - 09/27/96 ** EVENT NUMBERS ** 30949 30952 31061 31062 31063 31064 31065 31066 31067 +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 30949 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: BICRON |NOTIFICATION DATE: 09/02/96 | | CITY: NEWBURY REGION: 3 |NOTIFICATION TIME: 14:22 [ET]| | COUNTY: STATE: OH |EVENT DATE: 08/02/96 | |LICENSE#: 34-06558-05 AGREEMENT: N |EVENT TIME: 10:15[EDT]| | DOCKET: |LAST UPDATE DATE: 09/26/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN JACOBSON RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JEFF KENNEDY | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BICRON OF NEWBURY, OHIO, REPORTED A LOST 0.012-MICROCURIE AMERICIUM-241 | | SOURCE. | | | | BICRON UTILIZES AMERICIUM-241 SOURCES TO MANUFACTURE SODIUM IODIDE | | DETECTORS WITH A PULSAR UNIT INSIDE TO GIVE A STEADY COUNT RATE. DURING | | THE PERFORMANCE OF THIS PROCESS AT APPROXIMATELY 1015 ON AUGUST 2, 1996, A | | 0.012-MICROCURIE AMERICIUM-241 CAPSULE POPPED OUT OF THE HANDS OF AN | | OPERATOR AND DISAPPEARED. (THE REPORTING LIMIT IS 0.01 MICROCURIES.) IN | | AN EFFORT TO SEARCH FOR THE MISSING CAPSULE, THE LICENSEE COMPLETELY | | DISMANTLED THE SMALL ROOM THAT THE OPERATOR WAS WORKING IN, BUT THE | | 3/8-INCH DIAMETER BY 3/8-INCH LONG SOURCE (DETECTOR UNIT) WAS NOT FOUND. | | THE LICENSEE CURRENTLY BELIEVES THAT THE SOURCE MAY HAVE GOTTEN CAUGHT IN | | THE CUFF OF THE OPERATOR'S LAB COAT WHEN IT FELL FROM THE OPERATOR'S HANDS | | AND THAT IT MAY HAVE SUBSEQUENTLY BEEN LOST FROM THERE. THE LICENSEE DOES | | NOT BELIEVE THAT THERE IS AN EXTERIOR EXPOSURE RISK ASSOCIATED WITH THIS | | EVENT. | | | | THE LICENSEE NOTIFIED NRC REGION 3 (MICHAEL FONZER) LAST WEEK AND PLANS TO | | FOLLOWUP WITH A WRITTEN NOTICE. (REFER TO THE HOO LOG FOR A LICENSEE | | CONTACT ADDRESS AND TELEPHONE NUMBERS.) | | | | * * * UPDATE 1340 9/25/96 FROM KENNEDY TAKEN BY STRANSKY * * * | | | | THE LICENSEE HAS RECOVERED THE LOST SOURCE. THE NRC REGION 3 OFFICE HAS | | BEEN CONTACTED BY THE LICENSEE REGARDING THIS EVENT. HOO NOTIFIED R3DO | | (WRIGHT). | | | | * * * UPDATE 0852 9/26/96 FROM JEFF KENNEDY TAKEN BY MACKINNON * * * | | | | THE LICENSEE SAID THAT THE SOURCE WAS LOST ON 07/31/96 NOT ON 08/02/96. | | HOO NOTIFIED (WRIGHT). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30952 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 09/03/96 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 17:12 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/03/96 | +------------------------------------------------+EVENT TIME: 14:45[EDT]| |NRC NOTIFIED BY: JOHN KONOVALCHICK |LAST UPDATE DATE: 09/26/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID SILK 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE TO LIST SEVERAL MANUAL TURBINE DRAIN VALVES IN THE EMERGENCY | | OPERATING PROCEDURE FOR COPING ACTIONS FOLLOWING A HYPOTHETICAL STEAM | | GENERATOR TUBE RUPTURE IN CONJUNCTION WITH THE FAILURE OF THE MAIN STEAM | | ISOLATION VALVE ASSOCIATED WITH THE RUPTURED STEAM GENERATOR | | | | DURING A DISCUSSION OF A RECENT DESIGN CHANGE ON THE NEW STEAM TRAPS, THE | | LICENSED OPERATORS IN TRAINING DISCOVERED A PROBLEM WITH AN EMERGENCY | | OPERATING PROCEDURE. THE SPECIFIC PROBLEM INVOLVED A SCENARIO WHERE A | | HYPOTHETICAL STEAM GENERATOR TUBE RUPTURE OCCURS IN CONJUNCTION WITH THE | | FAILURE OF THE MAIN STEAM ISOLATION VALVE ASSOCIATED WITH THE RUPTURED | | STEAM GENERATOR. THE EMERGENCY OPERATING PROCEDURE COPING ACTIONS REQUIRE | | CLOSURE OF THE OTHER MAIN STEAM ISOLATION VALVES AND CLOSURE OF SEVERAL | | MANUAL ISOLATION VALVES TO CONTROL THE SPREAD OF RADIOACTIVE MATERIAL AND | | TO PREVENT AN UNCONTROLLED COOLDOWN OF THE REACTOR COOLANT SYSTEM. SEVERAL | | MANUAL TURBINE DRAIN VALVES WERE FOUND TO BE MISSING FROM THE EMERGENCY | | OPERATING PROCEDURE AND COULD HAVE CAUSED THE RUPTURED STEAM GENERATOR'S | | CONTENTS TO FLOW TO THE MAIN CONDENSER AND SUBSEQUENTLY TO THE PLANT VENT | | STACK. THERE WERE OTHER EMERGENCY PROCEDURES IN PLACE TO DEAL WITH THE | | CONTINUED DEPRESSURIZATION OF THE RUPTURED STEAM GENERATOR. | | | | CURRENTLY, BOTH SALEM UNITS ARE DEFUELED, AND THE EMERGENCY OPERATING | | PROCEDURES ARE NOT REQUIRED TO BE UTILIZED TO MITIGATE DESIGN BASIS | | ACCIDENTS. THE LICENSEE BELIEVES THAT THERE IS NO SIGNIFICANT IMPACT ON | | THE HEALTH AND SAFETY OF THE PUBLIC DUE TO THIS PROBLEM. | | | | THE LICENSEE NOTIFIED THE LOWER ALLOWAYS CREEK TOWNSHIP AND PLANS TO NOTIFY | | THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1815 ON 09/26/96 BY FRED PRIESTLY ENTERED BY JOLLIFFE * * * | | | | UPON FURTHER EVALUATION OF THE CONDITIONS DESCRIBED ABOVE, THE LICENSEE | | DETERMINED THAT THE RELEASE OF RADIOACTIVE MATERIAL THROUGH THE MAIN | | TURBINE MANUAL DRAIN VALVES WAS BOUNDED BY THE DOSE CALCULATION THAT WAS | | DEVELOPED TO SUPPORT THE CONTROL ROOM VENTILATION DESIGN MODIFICATION. | | | | BASED UPON THIS DETERMINATION, THE LICENSEE DESIRES TO RETRACT THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE HOO NOTIFIED R1DO CLIFF ANDERSON. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31061 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 09/26/96 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 04:16 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 09/26/96 | +------------------------------------------------+EVENT TIME: 01:55[CDT]| |NRC NOTIFIED BY: MATTSON |LAST UPDATE DATE: 09/26/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEOFFREY WRIGHT 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 +------------------------------------------------------------------------------+ | THE PLANT ENTERED A 7 DAY LCO ACTION STATEMENT WHEN HPCI WAS DECLARED | | INOPERABLE. | | | | HPCI WAS DECLARED INOPERABLE WHEN THE HPCI PUMP DISCHARGE TEMPERATURE | | EXCEEDED 150øF. THE CAUSE OF THIS INCREASE IS BEING INVESTIGATED. ALL OTHER | | ECCS EQUIPMENT WAS OPERABLE. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31062 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 09/26/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 14:39 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 09/26/96 | +------------------------------------------------+EVENT TIME: 14:34[EDT]| |NRC NOTIFIED BY: TIM KULTERMAN |LAST UPDATE DATE: 09/26/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWENTY ONE SAFETY RELATED AIR OPERATED VALVES (AOV) ARE CONTROLLED BY | | SOLENOID OPERATED PILOT VALVES (SOV) WHICH DO NOT RECEIVE CLASS 1E POWER. | | LOSS OF POWER COULD CAUSE THE AOVs TO OPEN DIVERTING SAFETY INJECTION FLOW | | AND POSSIBLY CAUSING PUMP RUN-OUT. | | | | THE LICENSEE DETERMINED THAT THE FOLLOWING AOVs: 3SIL*AV8889B, 8889D, | | 8878A, 8878B, 8878C, 8878D, 8877A, 8877B, 8877C, 8877D, 8879A, 8879B, | | 8879C, 8879D, 8872A, 8872B, 8872C, 8872D; 3SIH*AV8882, 8889A, AND 8889C | | ARE CONTROLLED BY SOVs WHICH RECEIVE POWER FROM A NON-SAFETY POWER SUPPLY. | | LOSS OF THIS POWER SUPPLY COULD CAUSE THE AOVs TO FAIL INTO THE OPEN | | POSITION. THESE AOVs ARE BOUNDARY ISOLATION VALVES. FAILURE OF ONE OR | | MORE OF THESE AOVs IN THE OPEN POSITION COULD DEGRADE THE SAFETY INJECTION | | SYSTEM. | | | | THESE AOVs ARE LOCATED IN THE ACCUMULATOR FILL LINES AND COULD RESULT IN | | DRAINING THE ACCUMULATORS, OR THEY ARE LOCATED IN CHECK VALVE LEAKAGE | | MONITORING LINES AND COULD LEAD TO SI PUMP RUN-OUT IF A VALVE FAILED OPEN | | AND A CHECK VALVE OR NON-SAFETY RELATED PIPING WERE DEGRADED. THE LICENSEE | | HAS NOT YET DETERMINED THEIR CORRECTIVE ACTIONS. THE LICENSEE INFORMED THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31063 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/26/96 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 15:08 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/26/96 | +------------------------------------------------+EVENT TIME: 13:20[EDT]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 09/26/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEOFFREY WRIGHT 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP SIGNAL GENERATED DUE TO A PROCEDURAL ERROR. | | | | A REACTOR TRIP SIGNAL WAS RECEIVED WHEN THE HIGH VOLTAGE POWER FUSES FOR | | ONE OF TWO INTERMEDIATE RANGE NUCLEAR INSTRUMENTATION CHANNELS (N-35) WERE | | PULLED IN CONJUNCTION WITH A CHANNEL CALIBRATION PROCEDURE. THE PROCEDURE | | DID NOT ADDRESS BLOCKING THE SIGNAL AND THE RESULTANT TRIP SIGNAL WAS NOT | | EXPECTED BY THE CONTROL ROOM OPERATORS. | | | | NO EQUIPMENT CHANGED POSITION AND NO SAFETY SYSTEMS ACTUATED. THE CONTROL | | RODS WERE ALREADY FULLY INSERTED AND THE REACTOR TRIP BREAKERS WERE TAGGED | | OPEN AND THE CONTROL ROD DRIVE MOTOR-GENERATOR SETS WERE REMOVED FROM | | SERVICE. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31064 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 09/26/96 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 15:34 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/26/96 | +------------------------------------------------+EVENT TIME: 14:30[EDT]| |NRC NOTIFIED BY: MIKE EMPEY |LAST UPDATE DATE: 09/26/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THREE VALVES FAILED THE 10CFR50 APPENDIX J "AS FOUND" COMBINED LEAK RATE | | TEST. | | | | ONE CONTAINMENT PENETRATION VALVE FAILED THE TYPE C LOCAL LEAK RATE TEST | | AND TWO ADDITIONAL VALVES CAUSED THE B AND C MAXIMUM PATH WAY LEAKAGE RATE | | TO EXCEED THE TECH SPEC ACCEPTANCE CRITERIA. THIS LEAK RATE IS THE "AS | | FOUND" CONDITION OF THESE VALVES AFTER SHUTDOWN. THE ACTUAL " AS-FOUND" | | LEAKAGE COULD NOT BE DETERMINED BECAUSE THE LEAK RATE EXCEEDED THE CAPACITY | | OF THE TEST RIG. IF THE PLANT WERE OPERATING THIS DEGRADATION WOULD HAVE | | EXCEEDED THE AUTHORIZED CONTAINMENT LEAKAGE LIMITS. THE LICENSEE INFORMED | | THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31065 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 09/26/96 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 19:56 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 09/26/96 | +------------------------------------------------+EVENT TIME: 17:45[EDT]| |NRC NOTIFIED BY: MIKE BECKER |LAST UPDATE DATE: 09/26/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CCW SYSTEM SURGE TANK NOT SEISMICALLY QUALIFIED WHEN ABOVE 75% LEVEL - | | | | A LICENSEE ENGINEERING EVALUATION DETERMINED THAT THE COMPONENT COOLING | | WATER (CCW) SYSTEM SURGE TANK, COMMON TO BOTH UNITS, IS NOT SEISMICALLY | | QUALIFIED WHEN THE TANK WATER LEVEL IS ABOVE 75%. CURRENTLY, THE WATER | | LEVEL IS 48%. THE LICENSEE HAS PLACED ADMINISTRATIVE CONTROLS IN EFFECT | | TO PREVENT THE TANK WATER LEVEL FROM BEING INCREASED ABOVE 75%. IF THE | | WATER LEVEL IN THE TANK IS INCREASED ABOVE 75%, PLANT OPERATORS ARE THEN | | REQUIRED TO INITIATE A PLANT SHUTDOWN PER TECH SPEC LCO A/S 3.0.3. | | | | COMPONENT COOLING IS USED FOR RHR COOLING DURING PLANT SHUTDOWN AND REACTOR | | COOLING PUMP COOLING DURING NORMAL PLANT OPERATIONS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31066 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 09/26/96 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 22:43 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/26/96 | +------------------------------------------------+EVENT TIME: 20:00[EDT]| |NRC NOTIFIED BY: JOHN KONOALCHICK |LAST UPDATE DATE: 09/26/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - INTERMEDIATE HEAD SAFETY INJECTION PUMP OPERATED ABOVE ITS MAXIMUM | | ANALYZED RANGE - | | | | WITH BOTH UNITS DEFUELED, THE LICENSEE WAS EVALUATING THE HIGH PRESSURE | | OUTPUT FROM THE UNIT 2 #22 SAFETY INJECTION PUMP. THE LICENSEE DISCOVERED | | THAT THE #22 PUMP OPERATES ABOVE THE MAXIMUM ANALYZED RANGE (PUMP HEAD | | CURVE) AS DETERMINED BY WESTINGHOUSE IN THE SALEM DESIGN BASIS (REF: LCR | | #91-03). | | | | THIS PUMP HAD PREVIOUSLY BEEN INSTALLED IN UNIT 1 AS THE #12 SAFETY | | INJECTION PUMP. WHILE INSTALLED IN UNIT 1, THE #12 SAFETY INJECTION PUMP | | HAD OPERATED ABOVE THE ANALYZED RANGE OF THE WESTINGHOUSE ACCIDENT | | ANALYSIS. | | | | THIS EVENT IS BEING REPORTED AS AN EVENT FOUND WHILE THE REACTOR WAS | | SHUTDOWN. HAD THIS EVENT BEEN DISCOVERED WHILE THE PLANT WAS OPERATING, | | IT WOULD HAVE RESULTED IN THE PLANT, INCLUDING ITS SAFETY BARRIERS, BEING | | IN AN UNANALYZED CONDITION THAT SIGNIFICANTLY COMPROMISED PLANT SAFETY. | | | | LICENSEE SYSTEM ENGINEERING PERSONNEL ARE EVALUATING THE PERFORMANCE OF | | THE #22 SAFETY INJECTION PUMP TO DETERMINE APPROPRIATE CORRECTIVE ACTIONS. | | | | THE LICENSEE NOTIFIED LOCAL OFFICIALS AND WILL INFORM THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31067 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 09/27/96 | |UNIT: [ ] [2] [ ] STATE: VA |NOTIFICATION TIME: 00:08 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 09/26/96 | +------------------------------------------------+EVENT TIME: 21:35[EDT]| |NRC NOTIFIED BY: BECKER |LAST UPDATE DATE: 09/27/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK 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 | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A CONTAINMENT PURGE SYSTEM ISOLATION SIGNAL DUE TO A | | HIGH-HIGH RADIATION SIGNAL FROM THE MANIPULATOR CRANE RAD MONITOR. | | | | THIS OCCURRED DURING THE REACTOR VESSEL HEAD SET EVOLUTION, WHEN THE VESSEL | | HEAD CAME CLOSE TO THE CRANE AND THE HIGH-HIGH SETPOINT (45MR/HR) WAS | | SENSED FOR APPROX. 20 SECONDS BY THE MANIPULATOR CRANE RAD MONITOR. THIS | | GENERATED THE CONTAINMENT PURGE ISOLATION SIGNAL. THE CONTAINMENT PURGE WAS | | RE-ESTABLISHED AT 21:51 WHEN THE REACTOR HEAD WAS BEING LOWERED ONTO THE | | GUIDE STUDS AND THE MANIPULATOR CRANE RAD MONITOR RETURNED TO 5MR/HR. THE | | RI WILL BE INFORMED. | +------------------------------------------------------------------------------+