U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/12/96 - 06/13/96 ** EVENT NUMBERS ** 30621 30622 30623 30624 30625 30626 30627 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30621 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 06/12/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 13:40 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/12/96 | +------------------------------------------------+EVENT TIME: 11:30[EDT]| |NRC NOTIFIED BY: VICTOR WALZ |LAST UPDATE DATE: 06/12/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KENNETH JENISON 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - HPCI SYSTEM FAILED ITS QUARTERLY ASME SECTION XI INSERVICE TEST - | | | | DURING SCHEDULED QUARTERLY ASME SECTION XI INSERVICE TESTING OF THE | | HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM, THE HPCI BOOSTER PUMP | | DIFFERENTIAL PRESSURE MEASURED 236.3 PSID. THIS VALUE EXCEEDS THE REQUIRED | | ACTION RANGE UPPER LIMIT VALUE OF 235.6 PSID. | | | | FAILURE TO MEET THIS TEST ACCEPTANCE CRITERIA RESULTED IN THE HPCI SYSTEM | | BEING DECLARED INOPERABLE PER TECHNICAL SPECIFICATION 3.5.C.1 (7 DAY LCO). | | THE HPCI SYSTEM REMAINS IN ITS NORMAL STANDBY LINEUP AND IS AVAILABLE FOR | | MANUAL OR AUTOMATIC INJECTION, IF NEEDED. | | | | PLANT ENGINEERING PERSONNEL ARE REVIEWING THE TEST DATA AND TEST | | INSTRUMENTATION. PREVIOUS TESTING HAS MET ALL TEST ACCEPTANCE CRITERIA | | WITH NO PERFORMANCE DETERIORATION DETECTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30622 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 06/12/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 14:16 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 06/12/96 | +------------------------------------------------+EVENT TIME: 14:00[EDT]| |NRC NOTIFIED BY: LOU PALONE |LAST UPDATE DATE: 06/12/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KENNETH JENISON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COMPONENT COOLING WATER SYSTEM WOULD EXCEED ITS DESIGN TEMPERATURE LIMIT IF | | THE RHR FLOW CONTROL VALVE FAILED OPEN DURING A PLANT COOLDOWN | | | | DURING A SYSTEM REVIEW, THE LICENSEE DETERMINED THAT IF THE RHR FLOW | | CONTROL VALVE FAILS OPEN WHILE COOLING THE PLANT DOWN IN MODE 3 OR 4, THE | | COMPONENT COOLING PRIMARY SYSTEM WILL EXCEED ITS DESIGN TEMPERATURE LIMIT. | | | | THE LICENSEE IS DETERMINING CORRECTIVE ACTIONS AND WILL CORRECT THIS | | CONDITION PRIOR TO PLANT RESTART. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30623 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 06/12/96 | |UNIT: [ ] [3] [ ] STATE: PA |NOTIFICATION TIME: 14:24 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 06/12/96 | +------------------------------------------------+EVENT TIME: 11:00[EDT]| |NRC NOTIFIED BY: DOUG CREMER |LAST UPDATE DATE: 06/12/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KENNETH JENISON RDO | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - REFUEL FLOOR ACCESS DOOR PROPPED OPEN VIOLATING SECONDARY CONTAINMENT - | | | | THE LICENSEE DISCOVERED THAT THE REFUEL FLOOR ROOF ACCESS DOOR HAD BEEN | | PROPPED OPEN FROM 1000 UNTIL 1100 BY PERSONNEL PERFORMING TESTING IN THE | | AREA. | | | | WITH THIS DOOR OPEN, IT WOULD NOT BE EXPECTED THAT SECONDARY CONTAINMENT | | COULD FULFILL ITS DESIGN FUNCTION. | | | | PLANT OPERATION WAS UNAFFECTED BY THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 30624 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: TEKTRONIX, INC., BEAVERTON, OR |NOTIFICATION DATE: 06/12/96 | | CITY: BEAVERTON REGION: 4 |NOTIFICATION TIME: 14:37 [ET]| | COUNTY: STATE: OR |EVENT DATE: 06/12/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 12:00[PDT]| | DOCKET: |LAST UPDATE DATE: 06/12/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN PELLET RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: STEPHEN G. BROWN | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - LICENSEE LOST THREE RADIOACTIVE AIR IONIZERS WITH POLONIUM-210 SOURCES - | | | | THE LICENSEE CONDUCTED A SEARCH AND COULD NOT LOCATE THE FOLLOWING THREE | | LOST RADIOACTIVE AIR IONIZERS: | | | | 1 - AIR IONIZER LEASED FROM AMERSHAM CORPORATION LOCATED IN ARLINGTON | | HEIGHTS, IL. ORIGINALLY CONTAINED 10 MILLICURIES OF POLONIUM-210. | | IT WAS SHIPPED TO TEKTRONIX ON 09/22/92. MODEL NUMBER: PDM1002H4, | | SERIAL NUMBER: P2JA1162, DETERMINED LOST ON 05/15/96. | | | | 2 - AN IN-LINE AIR IONIZER FROM NRD, INC LOCATED AT GRAND ISLAND, NEW YORK. | | ORIGINALLY CONTAINED 20 MILLICURIES OF POLONIUM-210. IT WAS SHIPPED TO | | TEKTRONIX ON 10/19/90. MODEL NUMBER: P-2013, SERIAL NUMBER: 36930, | | DETERMINED LOST ON 06/07/96. | | | | 3 - AN IN-LINE AIR IONIZER FROM NRD, INC LOCATED AT GRAND ISLAND, NEW YORK. | | ORIGINALLY CONTAINED 20 MILLICURIES OF POLONIUM-210. IT WAS SHIPPED TO | | TEKTRONIX ON 10/19/90. MODEL NUMBER: P-2031, SERIAL NUMBER: 36929, | | DETERMINED LOST ON 06/07/96. | | | | THE LICENSEE HAS CONDUCTED AN INVENTORY CHECK AND IS PREPARING A LONG TERM | | MANAGEMENT PLAN TO PREVENT ANY FUTURE LOSSES. | | | | THE LICENSEE HAS RECEIVED A NOTICE OF VIOLATION FROM REGION IV AS A RESULT | | OF THE LOSS OF ITEM #1 ABOVE. (REGION IV - JEFF CRUZ) | | | | SEE THE HOO LOG FOR CALLER'S TELEPHONE NUMBER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30625 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 06/12/96 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 16:55 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/12/96 | +------------------------------------------------+EVENT TIME: 14:40[EDT]| |NRC NOTIFIED BY: WILLIAMS |LAST UPDATE DATE: 06/12/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN 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 STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A LETDOWN ISOLATION AS THE RESULT OF A DECREASE IN | | PRESSURIZER LEVEL. | | | | WITH THE UNIT STABLE IN MODE 3 AT NORMAL OPERATING PRESSURE AND TEMPERATURE | | (557F, 2235 PSIG) AND THE SHUTDOWN BANKS WITHDRAWN, STEAM DUMP "1PV-507B" | | FAILED OPEN. THE RESULTING TRANSIENT CAUSED A COOL-DOWN IN THE RCS OF | | APPROXIMATELY 5F AND AN ASSOCIATED DECREASE IN PRESSURIZER LEVEL. THE DROP | | IN PZR LEVEL CAUSED A LETDOWN ISOLATION. THE MSIV'S WERE SHUT TO STOP THE | | STEAM FLOW AND TERMINATE THE TRANSIENT. THE STEAM DUMP WAS MANUALLY | | ISOLATED AND THE MSIV'S HAVE BEEN RE-OPENED. THE PLANT IS STABLE. THE | | CAUSE OF THE STEAM DUMP FAILING OPEN WAS A POSITIONER BEING OUT OF | | CALIBRATION. THEY ARE CURRENTLY MAKING REPAIRS. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30626 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 06/12/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 18:11 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 06/12/96 | +------------------------------------------------+EVENT TIME: 15:41[EDT]| |NRC NOTIFIED BY: SIDELINGER |LAST UPDATE DATE: 06/12/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KENNETH JENISON RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R N 0 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE REACTOR WAS MANUALLY TRIPPED AFTER A PROBLEM WITH 2 RODS DURING ROD | | INSERTION. | | | | THIS OCCURRED WHILE REACTOR STARTUP WAS IN PROGRESS AND 2 RODS IN CONTROL | | BANK "D" FAILED TO STEP OUT WHEN REQUIRED. ROD INSERTION WAS MANUALLY | | INITIATED TO RETURN TO MODE 3. WHILE PERFORMING THIS EVOLUTION, 2 RODS IN | | CONTROL BANK "B" BEGAN TO INSERT OUT OF SEQUENCE. THE REACTOR WAS MANUALLY | | TRIPPED, MODE 3 WAS ENTERED, AND SHUTDOWN MARGIN WAS VERIFIED. ALL RODS | | FULLY INSERTED WHEN THE REACTOR TRIP BREAKERS OPENED. THERE WAS NO ECCS | | INJECTION AND NO RELIEF VALVES LIFTED. THE CAUSE OF THE ROD CONTROL | | PROBLEMS IS UNKNOWN, BUT I&C ROD CONTROL MAINTENANCE EFFORTS ARE IN | | PROGRESS. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30627 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 06/13/96 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 02:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/13/96 | +------------------------------------------------+EVENT TIME: 00:50[EDT]| |NRC NOTIFIED BY: JACK BRISSON |LAST UPDATE DATE: 06/13/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R N 0 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP DUE TO LOSS OF POWER TO VITAL INVERTER SUPPLYING INTERMEDIATE | | RANGE NUCLEAR INSTRUMENTATION. | | | | THE UNIT WAS SHUTTING DOWN FOR A REFUELING, PREPARING TO CONDUCT ROD DROP | | TESTS WHEN A CIRCUIT BREAKER FROM THE VITAL DISTRIBUTION CENTER VITAL | | INVERTER TRIPPED (CAUSE UNKNOWN). THIS LOSS OF POWER CAUSED NUMEROUS | | ERRONEOUS INSTRUMENTATION INDICATIONS, INCLUDING A SPURIOUS HIGH READING ON | | ONE CHANNEL OF INTERMEDIATE RANGE NUCLEAR INSTRUMENTATION, WHICH TRIPPED | | THE REACTOR. ALL CONTROL RODS FULLY INSERTED FOLLOWING THE TRIP. TWO ESF | | ACTUATIONS OCCURRED. FEED WATER ISOLATED DUE TO LOW REACTOR COOLANT | | TEMPERATURE FOLLOWING THE REACTOR TRIP, AND AUXILIARY FEED WATER WAS | | MANUALLY INITIATED. VITAL POWER TO CHANNEL "A" HAS BEEN RESTORED, FED FROM | | A REGULATED NON-SAFETY SOURCE. THE UNIT IS STABLE IN MODE 3. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+