U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/16/94 - 09/19/94 ** EVENT NUMBERS ** 27780 27788 27789 27790 27791 27792 27793 27794 27795 27796 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27780 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 09/13/94 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 19:15 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 09/13/94 | +------------------------------------------------+EVENT TIME: 17:25[CDT]| |NRC NOTIFIED BY: BOOHER |LAST UPDATE DATE: 09/16/94 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWYER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 89 POWER OPERATION | 89 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RHR HEAT EXCHANGERS MAY NOT TRANSFER SUFFICIENT HEAT DURING PERIODS OF HIGH | | RIVER WATER TEMPERATURES DUE TO INSUFFICIENT RHR SERVICE WATER FLOW. | | | | THE LICENSEE REPORTED THAT FLOW THROUGH THE RHR HEAT EXCHANGERS MAY NOT BE | | SUFFICIENT TO TRANSFER ACCIDENT HEAT LOADS DURING PERIODS OF OPERATION AT | | THE MAXIMUM DESIGN HEAT EXCHANGER INLET TEMPERATURE OF 95øF. DURING A | | DESIGN REVIEW, THE LICENSEE DETERMINED THAT, DUE TO INSTRUMENT | | INACCURACIES, MEASURED FLOW THROUGH THE A AND C RHR HEAT EXCHANGERS MAY NOT | | MEET THE REQUIRED FLOW OF 7940 GPM. (THIS REQUIREMENT WAS CALCULATED FROM | | THE FSAR REQUIREMENT THAT ACCIDENT HEAT LOADS BE ADEQUATELY TRANSFERRED UP | | TO A RIVER TEMPERATURE OF 95øF.) DURING A FLOW TEST, CONTROL ROOM | | INSTRUMENTS INDICATED A COMBINED FLOW OF 8300 GPM THROUGH THE A AND C HEAT | | EXCHANGERS, WITH A COMBINED INSTRUMENT UNCERTAINTY OF +/- 400 GPM. ASSUMING | | WORST-CASE INSTRUMENT UNCERTAINTY, THE LICENSEE HAS CONCLUDED THAT THE | | ACTUAL FLOW COULD FALL SHORT OF THE REQUIRED FLOW. THE RIVER TEMPERATURE | | IS CURRENTLY 81.4øF. | | | | THE LICENSEE IS ATTEMPTING TO QUANTIFY THE ACTUAL INSTRUMENT INACCURACIES, | | AND MAY RETRACT THIS EVENT. THE RI WILL BE INFORMED. | | | | * * * UPDATE AT 1509 ON 09/16/94 BY KNIGHT ENTERED BY HOO JOLLIFFE * * * | | | | LICENSEE DESIRES TO RETRACT THIS EVENT SINCE THE CALCULATED LOOP FLOW | | ACCURACY SHOULD BE 283 GPM IN ACCORDANCE WITH THE METHOD SPECIFIED IN | | REG GUIDE 1.105 AND ISA STANDARD 67.04 AND NOT 400 GPM AS STATED ABOVE. | | | | THUS, THE ABOVE CONDITION IS NOT OUTSIDE THE DESIGN BASIS OF THE PLANT AND | | THE RHR HEAT EXCHANGERS ARE CONSIDERED ADEQUATE TO MEET THE DESIGN BASES | | FOR CONTAINMENT COOLING/DECAY HEAT REMOVAL FOR THE DESIGN MAXIMUM RIVER | | TEMPERATURE OF 95 DEGREES F. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTIFIED R2DO LAWYER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27788 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 09/15/94 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 21:44 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 09/15/94 | +------------------------------------------------+EVENT TIME: 14:45[PDT]| |NRC NOTIFIED BY: SWANK |LAST UPDATE DATE: 09/16/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CONTAINMENT ISOLATION VALVES COULD FAIL DUE TO A SINGLE RELAY FAILURE - | | | | DURING A DESIGN REVIEW, LICENSEE DETERMINED THAT THE CONTAINMENT ISOLATION | | LOGIC FOR THE HYDRAULIC LINES ASSOCIATED WITH THE RECIRCULATION FLOW | | CONTROL VALVES DID NOT MEET THE REQUIREMENTS OF GDC 56 IN THAT A SINGLE | | RELAY FAILURE COULD RESULT IN A LINE PENETRATING CONTAINMENT NOT ISOLATING | | UPON DEMAND. | | | | THIS CONDITION IMPACTS 8 HYDRAULIC LINES & 16 CONTAINMENT ISOLATION VALVES. | | | | LICENSEE IMMEDIATELY NOTIFIED REGION 4 (KEN PERKINS AND BILL BEACH), | | NRR (JIM CLIFFORD AND ELINOR ADENSAM) AND THE NRC RESIDENT INSPECTOR. | | | | AT 2100 (EDT), NRR GRANTED THE LICENSEE A VERBAL NOTICE OF ENFORCEMENT | | DISCRETION TO ALLOW CONTINUED PLANT OPERATION FOR 14 DAYS WHILE AN | | EMERGENCY TECHNICAL SPECIFICATION AMENDMENT IS PROCESSED. | | | | HOO NOTE (KARSCH): PER CLARIFICATION AT 0600 ON 09/16/94 FROM NRR ADENSAM - | | | | THE LICENSEE'S TECH SPEC AMENDMENT WILL REQUEST A WAIVER OF COMPLIANCE | | UNTIL THEIR FIRST FORCED SHUTDOWN OR UNTIL THE SPRING 95 OUTAGE, | | WHICHEVER COMES FIRST, SO THEY DON'T HAVE TO ATTEMPT TO CORRECT THIS | | DEFICIENCY WHILE THE PLANT IS AT POWER. | | | | * * * UPDATE AT 1925 ON 09/16/94 BY SWANK ENTERED BY HOO JOLLIFFE * * * | | | | THE FOLLOWING IS A CORRECTION TO THE ABOVE EVENT REPORT: | | | | CONTRARY TO THE ABOVE EVENT REPORT, THE CONTAINMENT ISOLATION LOGIC NOT | | MEETING THE SINGLE FAILURE CRITERIA IS A VIOLATION OF THE REQUIREMENTS OF | | PLANT TECH SPECS INSTEAD OF A VIOLATION OF THE REQUIREMENTS OF GDC 56, | | PRIMARY CONTAINMENT ISOLATION. | | | | HOO NOTIFIED R4DO STETKA. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27789 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 09/16/94 | |UNIT: [1] [ ] [ ] STATE: VA |NOTIFICATION TIME: 02:05 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 09/15/94 | +------------------------------------------------+EVENT TIME: 22:45[EDT]| |NRC NOTIFIED BY: FRANK GLENN |LAST UPDATE DATE: 09/16/94 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE LAWYER RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PERSONNEL AIR LOCK OPENED DURING CORE ALTERATIONS. | | | | DURING CONTROL ROD UNLATCH VERIFICATION TESTING THE LICENSEE DETERMINED | | THAT THE CONTAINMENT OUTER DOOR ESCAPE HATCH FOR THE PERSONNEL AIR LOCK | | HAD BEEN OPENED WITH THE INNER DOOR OPEN. THE TESTING WAS STOPPED IN | | ACCORDANCE WITH TECH SPECS FOR CONTAINMENT INTEGRITY DURING CORE | | ALTERATIONS, AND THE INCIDENT WAS INVESTIGATED. | | | | PROPER ADMINISTRATIVE CONTROLS (A BLUE TAG AND LARGE RED PLAQUE) WERE IN | | PLACE TO PREVENT DOOR OPERATION, BUT WERE VIOLATED BY A CONTRACT HEAVY | | EQUIPMENT OPERATOR. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27790 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 09/16/94 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 11:23 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 09/16/94 | +------------------------------------------------+EVENT TIME: 10:25[EDT]| |NRC NOTIFIED BY: GORDON MADER |LAST UPDATE DATE: 09/16/94 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |BBBB 20.403 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - PACKAGE RECEIVED AT THE PLANT HAD HIGH RADIATION LEVELS - | | | | A PACKAGE CONTAINING SUPER COMPACTED DRY WASTE WAS RETURNED TO THE PLANT | | FROM SCIENTIFIC ECOLOGY CORPORATION IN TENN. | | | | DURING RECEIPT INSPECTION OF THE PACKAGE AT THE PLANT, A RADIATION SURVEY | | INDICATED THAT RADIATION LEVELS OF THE PACKAGE EXCEEDED THE DOSE RATE | | LIMITS OF 10CFR71.47 (200 MR/HR). THE INITIAL READING ON THE BOTTOM OF | | THE PACKAGE WAS 300 MR/HR. THE READING ON THE SHIELDED TRAILER BED WAS | | BELOW 200 MR/HR. NO PERSONNEL WERE OVEREXPOSED. | | | | THE CARRIER IS HITTMAN TRANSPORT COMPANY. SEE THE HOO LOG FOR THE CARRIER | | FAX NUMBER. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | LICENSEE NOTIFIED REGION 3 JIM McCORMICK-BARGER IN ACCORDANCE WITH THE | | REQUIREMENTS OF 10CFR20.1906(d)(2). | | | | SEE EVENT #27771 FOR A SIMILAR EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27791 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 09/16/94 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 13:56 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 09/16/94 | +------------------------------------------------+EVENT TIME: 10:20[EDT]| |NRC NOTIFIED BY: BANKE |LAST UPDATE DATE: 09/16/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 98 POWER OPERATION | 98 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -VITAL BUSES TRIPPED & EDG STARTED DUE TO MAINTENANCE PROCEDURE DEFICIENCY- | | | | WHILE PERFORMING A POST MAINTENANCE TEST OF CIRCUIT BREAKER #12AX, | | ELECTRICIANS GENERATED A VALID TRIP SIGNAL TO CIRCUIT BREAKER #12BX DUE TO | | A DEFICIENCY IN THE MAINTENANCE PROCEDURE. THE TRIP SIGNAL CAUSED AN | | UNDERVOLTAGE TRIP OF VITAL BUSES #16 AND #17. EDG 'B' STARTED AND | | ENERGIZED BUSES #16 AND #17. CONTROL ROOM OPERATORS STABILIZED THE PLANT | | AND VERIFIED PROPER OPERATION OF EDG 'B' AND RESTORED ALL SYSTEMS TO NORMAL | | BY 1142. | | | | LICENSEE IS REVIEWING ALL APPROPRIATE TEST PROCEDURES AND RELATED DRAWINGS | | AND WILL MAKE REVISIONS AS NECESSARY. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27792 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 09/16/94 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 16:56 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 09/16/94 | +------------------------------------------------+EVENT TIME: 14:10[CDT]| |NRC NOTIFIED BY: BOB BROWN |LAST UPDATE DATE: 09/16/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A LICENSEE MAINTENANCE SUPERVISOR TESTED POSITIVE FOR THE PRESENCE OF | | DRUGS. THE EMPLOYEE'S ACCESS AUTHORIZATION TO THE PLANT WAS WITHDRAWN | | AND THE EMPLOYEE WAS REFERRED TO THE EMPLOYEE ASSISTANCE PROGRAM. | | | | LICENSEE IS INVESTIGATING THE EMPLOYEE'S RECENT PAST WORK PERFORMANCE. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | LICENSEE NOTIFIED R3 JIM BELANGER. | | | | SEE HOO LOG FOR DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27793 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 09/16/94 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 18:53 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/16/94 | +------------------------------------------------+EVENT TIME: 18:15[EDT]| |NRC NOTIFIED BY: COLOMB |LAST UPDATE DATE: 09/16/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 75 POWER OPERATION | 75 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TWO DESIGN ASSUMPTIONS IN TURBINE BUILDING HELB ANALYSIS ARE INCORRECT - | | | | DURING A REVIEW OF THE PLANT EQUIPMENT QUALIFICATION PROGRAM AS PART | | OF THE RESPONSE TO INFORMATION NOTICE 92-052, LICENSEE DISCOVERED | | THAT TWO DESIGN ASSUMPTIONS IN THE ANALYSIS OF THE EFFECT OF A | | HIGH ENERGY LINE BREAK (HELB) IN THE TURBINE BUILDING ARE INCORRECT. | | | | THE FIRST ASSUMPTION IS THAT TWO ELECTRIC SWITCHGEAR ROOMS IN THE | | TURBINE BUILDING THAT CONTAIN SAFETY RELATED EQUIPMENT ARE SEALED. | | HOWEVER, BOTH SWITCHGEAR ROOMS CONTAIN OPEN VENTILATION DAMPERS. | | LICENSEE SHUT THE DAMPERS TO ISOLATE THE ELECTRIC SWITCHGEAR ROOMS. | | THESE ROOMS CONTAIN INTERNAL VENTILATION EQUIPMENT. | | | | THE SECOND ASSUMPTION IS THAT NO REQUIRED SAFETY RELATED EQUIPMENT | | IS INSTALLED IN THE TURBINE BUILDING EXCEPT IN THE SWITCHGEAR ROOMS. | | HOWEVER, ONE SAFETY RELATED VENTILATION CONTROL PANEL WHICH PROVIDES | | A SUPPORT FUNCTION TO EQUIPMENT REQUIRED TO MITIGATE THE CONSEQUENCES | | OF THE ANALYZED ACCIDENT IS INSTALLED IN THE TURBINE BUILDING OUTSIDE | | THE SWITCHGEAR ROOMS. LICENSEE DECLARED THE CONTROL PANEL AND ITS | | ASSOCIATED EQUIPMENT INOPERABLE. THIS ACTION PLACES THE LICENSEE IN | | A 7 DAY SHUTDOWN LCO ON THE 'B' EMERGENCY SERVICE WATER SYSTEM. | | | | LICENSEE INTENDS TO INSTALL AN ELECTRICAL JUMPER IN THE CONTROL PANEL | | TO ISOLATE THE VENTILATION CONTROL CIRCUITS. THIS ACTION WILL ENABLE | | THE LICENSEE TO EXIT THE LCO. | | | | LICENSEE IS DEVELOPING A CORRECTIVE ACTION PLAN TO DETERMINE THE LONG | | TERM RESOLUTION AND TO ENSURE THAT NO OTHER EQUIPMENT IS AFFECTED. | | | | LICENSEE INTENDS TO SUBMIT AN LER ON THIS EVENT. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27794 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 09/17/94 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 07:30 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 09/17/94 | +------------------------------------------------+EVENT TIME: 06:25[EDT]| |NRC NOTIFIED BY: JACOBS |LAST UPDATE DATE: 09/17/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 +------------------------------------------------------------------------------+ | THE PLANT RECEIVED A LPCI INITIATION SIGNAL ALONG WITH AUTO START OF THE | | "A" D/G. | | | | THIS OCCURRED WHEN I&C TECHS WERE REPLACING A POWER SUPPLY FOR THE ECCS | | ANALOG TRIP SYSTEM(THE CAUSE IS BEING INVESTIGATED). WHEN LPCI INITIATION | | SIGNAL OCCURRED THEY RECEIVED AN "A" D/G START AND D/G LOAD SHED ON THE "B" | | LOOP (WHICH WAS TAGGED OUT). LPCI LOOP SELECTION WAS THE "B" LOOP SO THE | | RUNNING "A" LOOP PUMP, WHICH WAS IN SHUTDOWN COOLING MODE, WAS ISOLATED | | WHEN THE INJECTION VALVES IN THE "A" LOOP WERE CLOSED. AT THIS POINT | | SHUTDOWN COOLING WAS LOST FOR 20 MINS BEFORE IT WAS RESTORED. COOLANT | | TEMPERATURE INCREASE WAS APPROXIMATELY 2 DEGREES. THE LOGIC WAS RESET, THE | | D/G WAS SECURED AND ALL SYSTEMS WERE RETURNED TO NORMAL WITHIN 20 MINS. | | THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27795 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 09/17/94 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 09:56 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 09/17/94 | +------------------------------------------------+EVENT TIME: 06:18[CDT]| |NRC NOTIFIED BY: WALGREN |LAST UPDATE DATE: 09/17/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE PLANT REPORTED THAT THEY HAD CLOSURE OF THE FEEDWATER ISOLATION VALVES. | | | | THIS OCCURRED WHILE THEY WERE IN MODE 4 COOLING DOWN ON RHR IN PREPARATION | | FOR REFUELING. THE SOURCE RANGE CHANNEL SEN-31 HAD BEEN DECLARED INOPERABLE | | AT 18:12CT ON 9/16/94 DUE TO INDICATED COUNTS INCREASING WITH NO INCREASE | | IN INPUT COUNTS. SOURCE RANGE CHANNEL SEN-32 EXHIBITED THE SAME BEHAVIOR | | AND IT TOO WAS DECLARED INOPERABLE AT 05:55CT ON 9/17/94. WITH BOTH | | CHANNELS INOP, THEY ENTERED TS 3.3.1 WHICH REQUIRES THAT REACTOR TRIP | | BREAKERS BE OPENED, SUSPENSION OF ALL OPERATIONS INVOLVING POSITIVE | | REACTIVITY BE INITIATED AND VERIFICATION OF THE SHUTDOWN MARGIN. WHEN THE | | REACTOR TRIP BREAKERS WERE OPENED, THE ESF ACTUATION SIGNAL FOR FEEDWATER | | ISOLATION WAS ACTUATED AND THE FEEDWATER ISOLATION VALVES CLOSED. THIS WAS | | AN EXPECTED OCCURRENCE, BUT THE ISOLATION VALVES WERE NOT CLOSED PRIOR TO | | THE SIGNAL BEING ACTIVATED. THEY ARE WORKING TO RESTORE THE SOURCE RANGE | | INSTRUMENTATION. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27796 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 09/17/94 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 15:44 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 09/17/94 | +------------------------------------------------+EVENT TIME: 12:24[EDT]| |NRC NOTIFIED BY: BANKE |LAST UPDATE DATE: 09/17/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 98 POWER OPERATION | 98 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MCB SAFEGUARDS DC FAILURE ANNUNCIATOR ALARMED DUE TO A BLOWN FUSE - | | | | A REACTOR OPERATOR DISCOVERED A NORMALLY LIT RED SAFEGUARDS DC FAILURE | | LIGHT ON THE RELAY ROOM SI RACK 'B' PANEL EXTINGUISHED. | | | | WHILE CHANGING THE LIGHT BULB, THE REACTOR OPERATOR OBSERVED A FLASH AND | | THE WHITE SI UNBLOCK LIGHT ALSO EXTINGUISHED. | | | | AT 1224, THE MAIN CONTROL BOARD (MCB) SAFEGUARDS DC FAILURE ANNUNCIATOR | | #L-31 ALARMED. | | | | AT 1346, I & C TECHNICIANS LOCATED AND REPLACED BLOWN FUSE #FUSIB1/SIBF1-P | | WHICH CLEARED THE #L-31 ANNUNCIATOR ALARM. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+