U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/17/94 - 10/18/94 ** EVENT NUMBERS ** 27870 27910 27911 27912 27913 27914 27915 +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 27870 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ITT FLUID TECHNOLOGY CORPORATION |NOTIFICATION DATE: 10/06/94 | | CITY: INDUSTRY REGION: 4 |NOTIFICATION TIME: 07:12 [ET]| | COUNTY: STATE: CA |EVENT DATE: 08/03/94 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:01[PDT]| | DOCKET: |LAST UPDATE DATE: 10/17/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: FACSIMILE | | |HQ OPS OFFICER: WILLIAM HUFFMAN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PART 21 REPORT CONCERNING RELAYS USED IN INDICATING SWITCHES MANUFACTURED | | BY ITT BARTON OF INDUSTRY, CALIFORNIA. | | | | ITT BARTON IS A SUPPLIER OF BASIC COMPONENTS TO THE NUCLEAR POWER INDUSTRY. | | RELAYS USED IN THE ITT BARTON MODEL 288 INDICATING SWITCH HAVE BEEN | | DETERMINED TO BE NOT THE SAME AS THOSE QUALIFIED FOR SEISMIC APPLICATION. | | RELAYS THAT WERE SUPPLIED IN JANUARY OF 1994 WERE INTERCHANGEABLE IN FIT, | | MATERIAL, AND FUNCTION, BUT DIFFERENT IN FORM THAN THE ORIGINALLY QUALIFIED | | SEISMIC RELAYS. INVESTIGATION HAS REVEALED THAT OTHER UNQUALIFIED RELAYS | | MAY HAVE BEEN SUPPLIED BETWEEN 1975 AND 1984. | | | | THE UNQUALIFIED RELAYS ARE GOING TO BE PLACED THROUGH A SEISMIC TESTING | | EVALUATION PROGRAM TO ASSESS THE POTENTIAL FOR FAILURE UNDER SEISMIC | | CONDITIONS. FINAL ACTIONS AND NOTIFICATIONS WILL BE MADE DEPENDING ON THE | | RESULTS OF THE SEISMIC TESTING. | | | | *** UPDATE FROM LICENSEE ON 10/17/94 AT 15:30 EDT VIA FACSIMILE *** | | THE ABOVE DESCRIBED RELAYS HAVE BEEN TESTED AND QUALIFIED FOR REPLACEMENT | | OF THE ORIGINAL CIRCA 1972 RELAYS. ITT BARTON CONSIDERS THAT NO FURTHER | | REPORTING ACTION VIA PART 21 IS REQUIRED. DOCUMENTATION OF THE TEST PROGRAM | | IS EXPECTED TO BE AVAILABLE BY DECEMBER 1,1994. | | | | COPIES OF THE FACSIMILE HAVE BEEN SENT TO NRR(HAASS) AND NMSS(RAMSEY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27910 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 10/17/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 05:07 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 10/17/94 | +------------------------------------------------+EVENT TIME: 04:14[EDT]| |NRC NOTIFIED BY: DUBAY |LAST UPDATE DATE: 10/17/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CONTAINMENT PURGE ISOLATION VALVE DRIFTED OPEN AND WOULD NOT CLOSE - | | | | WITH UNIT 2 IN A REFUELING OUTAGE AND CORE ALTERATIONS (UNCOUPLING CONTROL | | RODS) IN PROGRESS, THE AIR OPERATED OUTER CONTAINMENT PURGE ISOLATION VALVE | | (#2-AC-7) DRIFTED OPEN. CONTROL ROOM OPERATORS IMMEDIATELY ATTEMPTED TO | | CLOSE THE VALVE FROM THE CONTROL ROOM WITH THE HAND SWITCH, BUT IT DID NOT | | CLOSE. LICENSEE SUSPENDED ALL CORE ALTERATIONS. CONTROL ROOM OPERATORS | | THEN ATTEMPTED TO CLOSE THE VALVE WITH A TEST HIGH RADIATION SIGNAL AND | | IT DID NOT CLOSE. | | | | APPROXIMATELY 15 MINUTES LATER, CONTROL ROOM OPERATORS CLOSED THE VALVE BY | | BOTH A HAND SWITCH SIGNAL AND A TEST HIGH RADIATION SIGNAL AND THEN FAILED | | THE VALVE CLOSED BY ISOLATING ITS AIR SUPPLY. | | | | THE INNER CONTAINMENT PURGE ISOLATION VALVE (#2-AC-6) IN SERIES WITH THIS | | VALVE FAILED ITS LOCAL LEAK RATE TEST ON 10/13/94 AND HAS BEEN CLOSED SINCE | | THAT TIME. ALSO 2 NON-SAFETY RELATED VALVES DOWNSTREAM OF 2-AC-7 HAVE BEEN | | MAINTAINED CLOSED. | | | | LICENSEE IS INVESTIGATING THE CAUSE. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27911 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 10/17/94 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 11:27 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 10/17/94 | +------------------------------------------------+EVENT TIME: 09:12[CDT]| |NRC NOTIFIED BY: COX |LAST UPDATE DATE: 10/17/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - RHR SYSTEM SUCTION VALVES CLOSED BY FALSE SYSTEM HIGH PRESSURE SIGNAL - | | | | WITH THE PLANT IN CONDITION 4 (COLD SHUTDOWN) IN A REFUELING OUTAGE WITH | | MINIMAL DECAY HEAT PRESENT LICENSEE REMOVED THE RHR SYSTEM FROM SHUTDOWN | | COOLING BY STOPPING THE RHR PUMPS. | | | | AT THE SAME TIME, WHILE I & C TECHNICIANS WERE PERFORMING AN EXCESS FLOW | | CHECK VALVE TEST, A FALSE HIGH PRESSURE SIGNAL TO THE RHR SYSTEM WAS | | GENERATED WHICH CAUSED THE RHR SYSTEM SUCTION VALVES TO CLOSE. | | | | THE NEXT STEP IN REMOVING THE RHR SYSTEM FROM SHUTDOWN COOLING WAS TO | | CLOSE THESE VALVES. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27912 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 10/17/94 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 13:34 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 10/17/94 | +------------------------------------------------+EVENT TIME: 13:00[EDT]| |NRC NOTIFIED BY: RICH DONOVAN |LAST UPDATE DATE: 10/17/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES 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 +------------------------------------------------------------------------------+ | OPERABILITY STATUS OF EMERGENCY GAS TURBINE GENERATOR UNDER EVALUATION. | | | | AN INADVERTENT ACTUATION OF THE ECCS SYSTEM INCLUDING THE EMERGENCY GAS | | TURBINE AND THE DIESEL GENERATOR OCCURRED DURING THE 1994 REFUELING OUTAGE | | (SEE EVENT #27058 DATED 4/8/94). A RECENT ASSESSMENT OF THIS EVENT HAS | | DETERMINED THAT DURING THE ACTUATION, THE INITIATION SIGNAL TO THE GAS | | TURBINE WAS REMOVED PRIOR TO THE GAS TURBINE COMPLETING ITS START CYCLE. | | THE GAS TURBINE SUBSEQUENTLY TRIPPED ON HIGH EXHAUST GAS TEMPERATURE. | | | | IT APPEARS THAT THE GAS TURBINE START SEQUENCE TRANSFERRED FROM AN | | EMERGENCY MODE TO NORMAL. THIS CAUSED FUEL TO BE CUT BACK QUICKLY AND | | RESULTED IN A "FLAME OUT" CONDITION. THE FLAME OUT LED TO THE HIGH EXHAUST | | GAS TEMPERATURE CONDITION AND THE TRIP SIGNAL. | | | | THE EMERGENCY START LOGIC FOR THE GAS TURBINE SHOULD HAVE GONE TO | | COMPLETION WITHOUT THE TRIP AND THE START SIGNAL SHOULD NOT HAVE BEEN | | REMOVED WITHOUT DELIBERATE OPERATOR ACTION. THIS IS IN VIOLATION OF | | IEEE-279 FOR SAFETY RELATED EQUIPMENT. AN OPERABILITY DETERMINATION IS | | UNDERWAY FOR THE GAS TURBINE AT THIS TIME. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27913 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 10/17/94 | |UNIT: [ ] [2] [ ] STATE: AZ |NOTIFICATION TIME: 15:40 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 10/17/94 | +------------------------------------------------+EVENT TIME: 12:00[MST]| |NRC NOTIFIED BY: RAY ROBERTS |LAST UPDATE DATE: 10/17/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH |AL CHAFFEE EO | | | | | |E. McPEEK IAT | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 2 STARTUP | 2 STARTUP | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL TAMPERING OF SAFETY RELATED EQUIPMENT DISCOVERED. | | | | THE NRC RESIDENT INSPECTOR FOUND SEVERAL INDICATING LIGHT LENSES FOR | | VARIOUS VALVES ON A REMOTE SHUTDOWN PANEL WERE SHOWING THE WRONG | | INDICATIONS. FURTHER INVESTIGATION DETERMINED THAT APPROXIMATELY | | 20 RED AND GREEN VALVE POSITION INDICATING LENSES ON THE "A" AND "B" | | REMOTE SHUTDOWN PANELS WERE SWAPPED. | | | | PLANT SECURITY WAS IMMEDIATELY NOTIFIED. INVESTIGATION IS IN PROGRESS | | TO DETERMINE IF ANY MAINTENANCE HAS BEEN PERFORMED ON THE SHUTDOWN PANELS | | RECENTLY. THE SHUTDOWN PANELS ARE IN A VITAL AREA WHICH REQUIRES A KEY | | CARD FOR ENTRY. THEREFORE, A RECORD OF ALL PERSONNEL WHO HAVE BEEN IN | | THE VICINITY OF THE PANELS IS AVAILABLE. CHECKS OF OTHER EQUIPMENT | | PANELS HAVE NOT DISCOVERED ANY SIMILAR CONDITION. | | | | THERE IS NOT YET A BASELINE DATE OF WHEN THE LENSES WERE LAST CONFIRMED | | TO BE CORRECT. THIS IS CONSIDERED ONLY A PRECAUTIONARY REPORT AT THIS TIME | | AND HAS NOT YET BEEN CLASSIFIED AS A TAMPERING EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27914 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 10/17/94 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 15:30 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 10/17/94 | +------------------------------------------------+EVENT TIME: 11:30[PDT]| |NRC NOTIFIED BY: C.L. PERINO |LAST UPDATE DATE: 10/17/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | TEMPORARY LOSS OF A COUNTY EMERGENCY COMMUNICATIONS PHONE LINE. | | | | THE LICENSEE DISCOVER AT 11:30 PDT THAT THE "CRASH PHONE" COMMUNICATIONS TO | | BENTON FRANKLIN COUNTY HAD BEEN LOST. THIS IS A DEDICATED LINE USED TO MAKE | | THE IMMEDIATE NOTIFICATION TO THE COUNTY EOC IN THE EVENT OF AN EMERGENCY. | | THE LINE WAS DOWN FROM 9:30 PDT TO 10:15 PDT TODAY. COMMERCIAL AND RADIO | | COMMUNICATIONS REMAINED AVAILABLE DURING THE PHONE SYSTEM OUTAGE. THE CRASH | | PHONE LINE HAS BEEN RESTORED TO FULL OPERABILITY. | | | | THE NRC RESIDENT INSPECTOR AND LOCAL AUTHORITIES WERE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27915 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 10/17/94 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 23:14 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/17/94 | +------------------------------------------------+EVENT TIME: 20:12[CDT]| |NRC NOTIFIED BY: MIKE DAVIS |LAST UPDATE DATE: 10/17/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 4160 VOLT EMERGENCY BUS DEGRADED VOLTAGE RELAYS OUT OF CALIBRATION. | | | | THE LICENSEE HAS DETERMINED THAT THE METHODOLOGY FOR CALIBRATING THE 4160 | | VOLT EMERGENCY BUS DEGRADED VOLTAGE RELAYS HAS RESULTED IN THE RELAYS BEING | | OUT OF CALIBRATION. THE DEGRADED VOLTAGE CONDITION ON THE EMERGENCY BUSES | | IS MONITORED VIA A STEP DOWN TRANSFORMER WHICH HAS A TECH SPEC ACTUATION | | SETPOINT SPECIFIED AT BETWEEN 108 VOLTS TO 111 VOLTS. THE LICENSEE HAD | | NOTICED DRIFT AND CHANGE IN THE SETPOINTS FROM THE PREVIOUS CALIBRATION TO | | THE PRESENT. | | | | AN ENGINEERING EVALUATION DETERMINED THAT THE CHANGE WAS DUE | | INCONSISTENCIES IN THE POWER SUPPLY GENERATING THE CALIBRATION SIGNAL | | VOLTAGE. A SIGNAL CONDITIONER WAS PLACED ON THE POWER SUPPLY AND THE | | CALIBRATION OF THE RELAYS WAS CHECKED. THE SETPOINTS WERE FOUND TO BE IN | | THE 104 TO 105 VOLT RANGE AND OUTSIDE OF TECH SPEC REQUIREMENTS. | | | | THE "A" TRAIN DEGRADED VOLTAGE RELAYS HAVE BEEN RECALIBRATED AND THE "A" | | 4160 VOLT EMERGENCY BUS IS CONSIDERED OPERABLE. THE "B" TRAIN BUS RELAYS | | ARE BEING CALIBRATED AT THIS TIME. THE LICENSEE CONSIDERS THE "B" TRAIN BUS | | INOPERABLE UNTIL THE RELAYS ARE RECALIBRATED. THE LCO TIME CLOCK FOR | | COMPLETING THE CALIBRATION IS 12 HOURS OR BE IN HOT SHUTDOWN. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED. | +------------------------------------------------------------------------------+