U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/18/96 - 03/19/96 ** EVENT NUMBERS ** 30109 30125 30126 30127 30128 30129 30130 30131 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30109 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 03/14/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 10:57 [ET]| |RX TYPE: [1] CE |EVENT DATE: 03/14/96 | +------------------------------------------------+EVENT TIME: 08:58[CST]| |NRC NOTIFIED BY: JAMES COOK |LAST UPDATE DATE: 03/18/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |AL CHAFFEE EO | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | TECH SPEC REQUIRED SHUTDOWN | | | | "AT 0843 CST, 480 VAC MOTOR CONTROL CENTER MCC-4A2 WAS REMOVED FROM SERVICE | | FOR MAINTENANCE ACTIVITIES, AND AN EIGHT HOUR LCO WAS ENTERED IAW TECH SPEC | | 2.7(2)g. | | | | "AT 0858 CST, I&C WAS INVESTIGATING NOISE ON INSTRUMENT LOOP 340, | | CONTAINMENT SPRAY TEMPERATURE, WHEN A TECHNICIAN ACCIDENTALLY SHORTED AN AC | | LEAD. THIS CAUSED INSTRUMENT BUS AI-40B TO REVERSE TRANSFER TO THE BYPASS | | TRANSFORMER. THIS SUPPLIES THE INSTRUMENT BUS FROM 480 VAC MCC-4B1 INSTEAD | | OF STATIC INVERTER EE-8J AND RENDERS THE INSTRUMENT BUS INOPERABLE SINCE IT | | IS NOT SUPPLIED FROM ITS NORMAL POWER SOURCE. | | | | "THE LOSS OF THE INSTRUMENT BUS WOULD HAVE BEEN AN EIGHT HOUR LCO IAW TECH | | SPEC 2.7(2)H, HOWEVER THE MODIFICATION OF MINIMUM REQUIREMENTS FOR TECH | | SPEC 2.7 ONLY ALLOWS ONE CONDITION TO EXIST AT A TIME. IF MORE THAN ONE | | EXISTS, THE REACTOR MUST BE PLACED IN HOT SHUTDOWN WITHIN THE FOLLOWING 12 | | HOURS. | | | | "IAW EPIP-OSC-1, A TECH SPEC REQUIRED SHUTDOWN MEETS THE CONDITIONS FOR | | DECLARING AN UNUSUAL EVENT, BUT INSTRUMENT BUS AI-40B WAS RETURNED TO ITS | | NORMAL POWER SUPPLY (EE-8J) AT 0905 CST. THIS NOTIFICATION IS BEING MADE | | AS INFORMATION THAT CONDITIONS EXISTED FOR DECLARATION OF AN UNUSUAL EVENT, | | BUT ONE WAS NOT DECLARED SINCE THE CONDITION WAS CORRECTED IN AN EXPEDIENT | | TIME FRAME." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AS WELL AS THE STATES OF | | NEBRASKA AND IOWA. | | | | ***UPDATE ON 3/18/96 @ 16:29 BY MATZKE TO GOULD*** THE LICENSEE IS | | RETRACTING THIS EVENT SINCE IT HAS BEEN DETERMINED THAT THE DECISION TO | | ENTER TS 2.7(2)g FOR THE REMOVAL OF A SINGLE MCC(MCC-4A2) WAS AN OVERLY | | CONSERVATIVE DECISION. THE LICENSEE DID NOT NEED TO ENTER T.S. 2.7(2) | | UNTIL INSTRUMENT BUS AI-40B WAS TRANSFERRED TO THE BYPASS TRANSFORMER. A | | TS SHUTDOWN WAS NEVER REQUIRED, MAKING THIS EVENT NOT REPORTABLE. | | THE RI WILL BE NOTIFIED AND REG 4 (HOWELL) WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30125 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 03/17/96 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 19:32 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/17/96 | +------------------------------------------------+EVENT TIME: 18:34[EST]| |NRC NOTIFIED BY: WILLIAMS |LAST UPDATE DATE: 03/18/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |PEEBLES RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ZWOLINSKI EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |AUSTIN FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 60 POWER OPERATION | 60 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH UNITS BEING SHUT DOWN AFTER ALL SERVICE WATER PUMPS DECLARED | | INOPERABLE | | | | AT 1834 ON 3/17/96, THE LICENSEE COMMENCED A SHUTDOWN OF UNIT 2 AFTER | | ADMINISTRATIVELY DECLARING ALL SERVICE WATER PUMPS INOPERABLE. THIS ACTION | | WAS TAKEN DUE TO THE DISCOVERY OF GALVANIC CORROSION ON A PUMP IMPELLER | | RETAINING RING BOLT FOLLOWING THE FAILURE OF THE '2A' NUCLEAR SERVICE WATER | | PUMP. SIMILAR CORROSION WAS ALSO FOUND ON THE '1B' CONVENTIONAL SERVICE | | WATER AND '1B' NUCLEAR SERVICE WATER PUMPS. THE LICENSEE WILL COMMENCE A | | SHUTDOWN OF UNIT 1 AT 2130 THIS EVENING. BOTH UNITS WILL BE TAKEN TO COLD | | SHUTDOWN. AT THIS TIME, ALL OPERATING SERVICE WATER PUMPS ARE FUNCTIONING | | WITHIN NOMINAL PARAMETERS. | | | | AT 1920 ON 3/17/96, AN UNUSUAL EVENT WAS DECLARED AS A DISCRETIONARY ACTION | | IN RESPONSE TO THIS EVENT. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY | | THE LICENSEE. | | | | ***UPDATE ON 3/18/96 @ 21:42 BY TOMPSON TO GOULD*** THE NOUE WAS TERMINATED | | AT 21:30. BOTHE UNITS IN COLD S/D. THE RI WILL BE INFORMED. THE REG | | 2(PEEBLES), EO(MARSH) & FEMA(AUSTIN) WERE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30126 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 03/18/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 04:24 [ET]| |RX TYPE: [1] CE |EVENT DATE: 03/18/96 | +------------------------------------------------+EVENT TIME: 01:15[CST]| |NRC NOTIFIED BY: SCOTT LINDQUIST |LAST UPDATE DATE: 03/18/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON 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 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A CONTAINMENT PURGE HAD RECENTLY BEEN STARTED WHEN A VENTILATION ACTUATION | | ISOLATION ON HIGH STACK RADIATION OCCURRED. | | | | THE PURGE WAS STOPPED WHEN RAD MONITOR RMO 52 READ 20,315 COUNTS PER | | MINUTE. THE SET POINT IS 20,300 CPM. RMO 62 ALSO SHOWED AN INCREASED | | COUNT RATE. THE PURGE ISOLATION SET POINT IS AT 15% BELOW THE 10CFR20 | | INSTANTANEOUS RELEASE LIMIT, THEREFORE, NO PART 20 LIMITS AT THE SITE | | BOUNDARY WERE EXCEEDED. CONTAINMENT AREA AND PROCESS MONITORS REMAINED | | CONSTANT THROUGHOUT THE EVENT. THE LICENSEE WILL TAKE CONTAINMENT AIR | | SAMPLES AND WILL INVESTIGATE THE CAUSE OF THE INCREASED COUNT RATE. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30127 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 03/18/96 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 17:32 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/18/96 | +------------------------------------------------+EVENT TIME: 17:26[EST]| |NRC NOTIFIED BY: WOOKEY |LAST UPDATE DATE: 03/18/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON 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 THE POTENTIAL FOR THE BLOCK WALLS, USED TO SUPPORT | | CERTAIN BANKS OF THE MAIN STATION BATTERIES, BEING OUTSIDE THE DESIGN | | BASIS. | | | | ON 3/13/96 AN EVENT REPORT WHICH ADDRESSED A POTENTIAL PROBLEM WITH THE | | BLOCK WALLS WHICH PROVIDE SUPPORT FOR CERTAIN BANKS OF THE MAIN STATION | | BATTERIES WAS SUBMITTED. AN AP0156.01 FORM WAS COMPLETED AND THE ISSUE WAS | | DETERMINED NOT TO BE REPORTABLE AT THAT TIME. FURTHER EVALUATION HAS BEEN | | COMPLETED WHICH CONCLUDES THAT THE AFFECTED BLOCK WALLS ARE IN A | | CONFIGURATION WHICH IS OUTSIDE THE CURRENT DESIGN BASIS. THIS CONCLUSION | | IS BASED ON THE FOLLOWING: | | | | 1) FURTHER INVESTIGATION HAS DETERMINED THAT THE LICENSEE HAS A NRC | | SAFETY EVALUATION REPORT WHICH DOCKETS USE OF A PARTICULAR | | CALCULATION METHODOLOGY TO CALCULATE WALL LOADS DURING A SEISMIC | | EVENT. | | | | 2) UTILIZING THIS DOCKETED CALCULATION METHODOLOGY, THE LOADS WHICH | | WOULD BE CREATED IN THE WALLS, AS THEY EXIST TODAY, WOULD EXCEED | | THEIR DESIGN BASIS. | | | | IT IS THEREFORE CONCLUDED THAT THESE WALLS DO NOT MEET THEIR DESIGN BASIS | | AND THE EVENT IS REPORTABLE. THE WALLS ARE STILL CONSIDERED OPERABLE, | | HOWEVER, AND THE CONCERN IS RELATED TO INFORMATION RESULTING FROM DOCKETED | | CALCULATION METHODOLOGY. ADDITIONAL EVALUATIONS PERFORMED BY THE LICENSEE | | ENGINEERS AND A CONSULTANT HAVE DETERMINED THAT THE WALLS WOULD REMAIN | | STANDING DURING A DESIGN BASIS SEISMIC EVENT. | | THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30128 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 03/18/96 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 18:10 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/18/96 | +------------------------------------------------+EVENT TIME: 17:42[EST]| |NRC NOTIFIED BY: HAMILTON |LAST UPDATE DATE: 03/18/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |TAD MARSH EO | |KSNM 70.52(a) LOSS OF SNM/CRIT |AUSTIN FEMA | | |CHARLEY HAUGHNEY EO | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THEY CANNOT ACCOUNT FOR ELEVEN INCORE FLUX DETECTORS. | | | | DURING A SELF-ASSESSMENT OF THEIR SPECIAL NUCLEAR MATERIAL CONTROL PROGRAM, | | THE LICENSEE IDENTIFIED THAT ELEVEN INCORE FLUX DETECTORS COULD NOT BE | | ACCOUNTED FOR. EACH DETECTOR CONTAINED 4 MILLIGRAMS OF ENRICHED U-235. | | BASED ON THE BEST INFORMATION AVAILABLE, IT IS BELIEVED THAT THE DETECTORS | | WERE SHIPPED TO THE BARNWELL S.C. BURIAL FACILITY IN AUGUST 1981. | | AUTHORITIES AT BARNWELL HAVE BEEN CONTACTED AND ARE REVIEWING SHIPPING | | MANIFEST FROM THIS TIME FRAME TO CONFIRM SHIPMENT. | | | | IT IS BELIEVED THAT MATERIAL CONTROLS IN 1981 TIME FRAME WERE CONSISTENT | | WITH INDUSTRY PRACTICES REGARDING LESS THAN ONE-GRAM QUANTITIES OF SPECIAL | | NUCLEAR MATERIALS. NRC CALLED THESE INDUSTRY PRACTICES INTO QUESTION IN | | INFORMATION NOTICE 88-34. | | | | THIS INFORMATION WAS KNOWN BY THE LICENSEE AT THE TIME OF SHIPMENT AND | | SHOULD HAVE BEEN REPORTED AT THAT TIME. AN EXACT COUNT AND SHIPPING RECORDS | | ARE NOT AVAILABLE TO CONFIRM THE EXACT NUMBER SHIPPED TO BARNWELL. THEY ARE | | STILL INVESTIGATING. THE RI WILL BE NOTIFIED. THE STATES OF NJ & DE WERE | | NOTIFIED ALONG WITH LOWER ALLOWAYS CREEK TOWNSHIP AND OTHER GOVT. AGENCIES. | | A PRESS RELEASE WAS ALSO MADE. | | | | ***UPDATE ON 3/18/96 @ 18:41 FROM HAMILTON TO GOULD*** THE NOUE WAS | | TERMINATED AT 18:20 DUE TO THE FULL CLOSURE OF THE LOSS OF THE SPECIAL | | NUCLEAR MATERIAL EVENT. THE LICENSEE BELIEVES THAT THE SPECIAL NUCLEAR | | MATERIAL WAS BURIED AT BARNWELL. THEY ARE DOING FURTHER INVESTIGATIONS. THE | | RI WILL BE NOTIFIED ALONG WITH STATE AND LOCAL AGENCIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30129 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 03/18/96 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 20:38 [ET]| |RX TYPE: [1] B&W-R-LP |EVENT DATE: 03/18/96 | +------------------------------------------------+EVENT TIME: 17:00[EST]| |NRC NOTIFIED BY: IMLAY |LAST UPDATE DATE: 03/18/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON 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 Y 95 POWER OPERATION | 95 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED A SCAFFOLD ERECTED IN THE PLANT WAS BLOCKING 3 OF | | THE 6 BLOWOUT PANELS FOR THE #4 MECHANICAL PENETRATION ROOM. | | | | THE SCAFFOLD WAS APPROXIMATELY 12" FROM THE BLOWOUT PANELS. PRELIMINARY | | EVALUATION OF THE CONDITION REVEALED THE MAXIMUM PRESSURE REACHED IN THE | | AUXILIARY BUILDING NEGATIVE PRESSURE AREAS AND CONTAINMENT ANNULUS WOULD | | EXCEED THE ASME CODE LIMIT FOR CONTAINMENT EXTERNAL PRESSURE, HOWEVER, THE | | PRESSURE REACHED WOULD BE LESS THAN THE FAILURE POINT OF UPDATED SAFETY | | ANALYSIS REPORT SECTION 3.6. FURTHERMORE, THE MAXIMUM PRESSURE REACHED IS | | LESS THAN THE STRUCTURAL LIMIT OF ROOM 314(# 4 MECHANICAL PENETRATION | | ROOM). THE LICENSEE IS MAKING PLANS TO REMOVE THE SCAFFOLD. THE RI WILL BE | | INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |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 +------------------------------------------------------------------------------+ | REACTOR TRIP ON LOW LOW STEAM GENERATOR LEVEL, CAUSE NOT YET DETERMINED. | | | | THE LICENSEE SUSPECTS THAT SEPARATION OF THE DISK AND STEM ON A FEED WATER | | REGULATING VALVE CAUSED THE LOSS OF FEED WATER 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 FEED WATER 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. | +------------------------------------------------------------------------------+