U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/03/94 - 11/04/94 ** EVENT NUMBERS ** 27979 27980 27981 27982 27983 27984 27985 27986 27987 27988 27989 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27979 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 11/03/94 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 09:41 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 11/03/94 | +------------------------------------------------+EVENT TIME: 08:46[EST]| |NRC NOTIFIED BY: DAVE CROOK |LAST UPDATE DATE: 11/03/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | FALSIFICATION OF PRE-EMPLOYMENT SCREENING RECORDS. | | | | A CONTRACT PAINTER WAS DETERMINED TO HAVE PROVIDED FALSE INFORMATION | | CONCERNING PREVIOUS DRUG HISTORY. THE INDIVIDUAL'S SITE ACCESS HAS BEEN | | PERMANENTLY DENIED. THE NRC RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27980 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 11/03/94 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 13:24 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 11/03/94 | +------------------------------------------------+EVENT TIME: 12:40[EST]| |NRC NOTIFIED BY: SINGER |LAST UPDATE DATE: 11/03/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH HIGH HEAD SAFETY INJECTION PUMPS (HHSI) INOPERABLE DUE TO OPERATOR | | ERROR | | | | BOTH UNIT 3 HIGH HEAD SAFETY INJECTION PUMPS WERE PLACED IN THE PULL TO | | LOCK (PTL) POSITION, RENDERING THEM INOPERABLE. THIS PLACED UNIT 3 OUTSIDE | | ITS DESIGN BASIS. | | | | WHILE PERFORMING INTEGRATED SAFEGUARDS TESTING ON UNIT 4 WITH THE 4A HHSI | | PUMP OUT OF SERVICE DUE TO THE TESTING, BOTH UNIT 3 HHSI PUMPS WERE | | INADVERTENTLY PLACED IN PTL. THE CONDITION WAS DISCOVERED DURING CONTINUED | | TESTING. THE UNIT 3 PUMPS WERE IMMEDIATELY PLACED IN THEIR NORMAL AUTO | | START CONDITION. THE LICENSEE ESTIMATES THE AMOUNT OF TIME SPENT IN THIS | | CONDITION AS ONE TO TWO HOURS. THE HHSI SYSTEM IS A SHARED SYSTEM BETWEEN | | UNITS 3 & 4 AT TURKEY POINT. THERE ARE TWO PUMPS PER UNIT IN THE SYSTEM. | | | | THE INVESTIGATION CONTINUES INTO THIS EVENT. IT APPEARS THERE WAS A STEP | | IN THE PROCEDURE WHICH REQUIRED THE UNIT 3 HHSI PUMPS TO BE RUN AND THEN | | SECURED. THE LICENSEE BELIEVES THE PUMPS WERE PLACED IN PTL AT THIS POINT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27981 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 11/03/94 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 14:42 [ET]| |RX TYPE: [1] CE |EVENT DATE: 11/03/94 | +------------------------------------------------+EVENT TIME: 11:15[EST]| |NRC NOTIFIED BY: TIM KILLE |LAST UPDATE DATE: 11/03/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |AL CHAFFEE EO | | |JOHN DAVIDSON IAT | | |NANCY ERVIN IAT | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | BOMB THREAT | | | | THE LICENSEE DOES NOT BELIEVE THE THREAT IS CREDIBLE. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. THERE HAS NOT BEEN ANY MEDIA | | INTEREST. THE FBI HAS BEEN NOTIFIED. | | | | SEE HOO LOG FOR DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27982 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 11/03/94 | |UNIT: [3] [4] [ ] STATE: FL |NOTIFICATION TIME: 16:09 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 11/03/94 | +------------------------------------------------+EVENT TIME: 15:15[EST]| |NRC NOTIFIED BY: PREVAT |LAST UPDATE DATE: 11/03/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 4 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A PROGRAMMABLE LOGIC CONTROLLER (PLC) IN "TEST" MODE WAS DISCOVERED TO | | IMPEDE THE ACTUATION OF ENGINEERED SAFETY FEATURES (ESF) EQUIPMENT. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "DURING INTEGRATED SAFEGUARDS TESTING ON TURKEY POINT UNIT 4 SAFEGUARDS | | TRAIN "A", THE TURKEY POINT UNIT 3 "A" HIGH HEAD SAFETY INJECTION PUMP | | FAILED TO START. PLANT STAFF INVESTIGATED THE FAILURE OF THE PUMP TO | | START. PRELIMINARY INFORMATION, BASED IN PART ON TESTING CONDUCTED ON THE | | TURKEY POINT PLANT SIMULATOR, INDICATES THAT THE PROGRAMMED LOGIC | | CONTROLLER (PLC), WHICH IS NORMALLY IN AN AUTO-TEST MODE, MAY NOT MEET ITS | | DESIGN BASIS. A VALID SAFEGUARDS SIGNAL MAY NOT START ITS ASSOCIATED | | SAFEGUARDS EQUIPMENT. IT APPEARS THAT THIS INABILITY TO ACTUATE SAFEGUARDS | | EQUIPMENT OCCURS DURING A PORTION OF THE TEST CYCLE. | | | | FPL BELIEVES, THAT WHEN THE PLC IS NOT IN TEST, SAFEGUARDS ACTUATION WOULD | | OCCUR AS DESIGNED. AS A RESULT, THE FOUR PLC's (TWO PER UNIT) ARE BEING | | TAKEN OUT OF TEST. | | | | FPL IS CONTINUING A DESIGN EVALUATION." END OF TEXT. | | | | AFTER DISCOVERING THAT A VALID ENGINEERED SAFETY FEATURES (ESF) ACTUATION | | SIGNAL MAY NOT START ITS ASSOCIATED ESF EQUIPMENT WITH THE PROGRAMMABLE | | LOGIC CONTROLLER (PLC) IN "TEST" MODE, THE LICENSEE PERFORMED A SIMULATION | | OF THE CONDITION. THIS SIMULATION DETERMINED THAT THE PLC, WHILE ACTIVE IN | | ITS TEST CYCLE, MAY IMPEDE THE ACTUATION OF ASSOCIATED ESF EQUIPMENT. THE | | LICENSEE PROCEEDED TO TAKE THE PLC OUT OF "TEST" MODE AND CONFIRMED THE | | FUNCTIONALITY OF THE ESF LOGIC. | | | | THE PLC IS A DIAGNOSTIC DEVICE WHICH (WHILE IN "TEST" MODE) TESTS THE ESF | | LOGIC ON AN HOURLY BASIS TO DETECT ANY FAULTS IN THE LOGIC. THE PLCs WERE | | INSTALLED IN THE SEQUENCERS FOR BOTH UNITS IN 1991. THE PLC HAS NO SAFETY | | FUNCTION AND DOES NOT AFFECT THE FUNCTIONALITY OF THE ESF ACTUATION SYSTEM | | WHEN DISABLED. | | | | AN INVESTIGATION IS BEING CONDUCTED AND LONG-TERM CORRECTIVE ACTIONS WILL | | BE DETERMINED. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27983 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 11/03/94 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 15:59 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 11/03/94 | +------------------------------------------------+EVENT TIME: 15:49[EST]| |NRC NOTIFIED BY: JOHN STANFORD |LAST UPDATE DATE: 11/03/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE DISCOVERED A POTENTIAL FOR THE LOSS OF RHR DURING A LOCA IF THE | | LOCA OCCURRED DURING A MONTHLY SURVEILLANCE | | | | THE LICENSEE DISCOVERED THIS POTENTIAL PROBLEM DURING MOV TESTING AND | | REVIEW. DURING MONTHLY ESF PUMP TESTING A COMMON RHR SUCTION SUPPLY MOV | | FROM THE RWST (REFUELING WATER STORAGE TANK) IS OPENED TO PROVIDE NPSH TO | | THE RHR PUMPS. IT HAS BEEN DETERMINED THAT IF A LOCA WERE TO OCCUR DURING | | THIS TESTING & THE MOV WAS LEFT OPEN, RHR SUCTION FROM THE CONTAINMENT | | WOULD BE LOST. THIS COULD OCCUR WHEN CONTAINMENT PRESSURE LOWERED SUCH | | THAT THE RWST WOULD BE SUPPLYING THE RHR SUCTION. WHEN THE RWST WENT DRY, | | SUCTION WOULD BE LOST TO THE RHR PUMPS, AND CORE COOLING WOULD BE LOST. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AS WELL AS APPROPRIATE | | STATE AND LOCAL GOVERNMENT OFFICIALS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27984 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 11/03/94 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 17:28 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/02/94 | +------------------------------------------------+EVENT TIME: 16:53[CST]| |NRC NOTIFIED BY: MARK COUGHLIN |LAST UPDATE DATE: 11/03/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |NLTR LICENSEE 24 HR REPORT | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADEQUATE CONTROL ROOM ENVELOPE SURVEILLANCE PROCEDURE | | | | TEXT OF A LICENSEE FACSIMILIE: | | "AT 1653 HOURS ON NOVEMBER 2, 1994, IT WAS DISCOVERED THAT AN AREA OF THE | | CONTROL ROOM ENVELOPE OF UNIT 1 WOULD NOT MAINTAIN A POSITIVE PRESSURE WITH | | RESPECT TO ADJACENT AREAS AS REQUIRED BY TECH SPEC 4.7.7.E.3. IN ADDITION, | | THE TECH SPEC SURVEILLANCE WAS DETERMINED TO BE INADEQUATE DUE TO NOT FULLY | | TESTING ALL THE NECESSARY LOCATIONS WITHIN THE CONTROL ROOM ENVELOPE TO | | ENSURE COMPLIANCE WITH THE SURVEILLANCE REQUIREMENTS OF TECH SPEC | | 4.7.7.E.3. AT THAT TIME, UNIT 1 AND UNIT 2 ENTERED TECH SPEC 3.0.3. AFTER | | AIR FLOW ADJUSTMENTS AND RETESTING PROVED COMPLIANCE WITH TECH SPEC | | 4.7.7.E.3, UNIT 1 EXITED TECH SPEC 3.0.3 AT 1916 HOURS ON 11/2/94. | | | | UNIT 2 INVOKED TECH SPEC 4.0.3 TO COLLECT DATA FOR THE ADDITIONAL LOCATIONS | | THAT NEEDED TO BE TESTED. IT WAS DETERMINED DURING THE TESTING THAT PARTY | | OF THE DATA COLLECTED FOR UNIT 2 WAS UNACCEPTABLE, SO AT 0544 HOURS ON | | 11/3/94 UNIT 2 WENT BACK INTO 3.0.3 UNTIL POSITIVE PRESSURE COULD BE | | RE-ESTABLISHED. AT 0819 HOURS, 3.0.3 WAS EXITED BACK TO 4.0.3 TO FINISH | | DATA COLLECTION WHEN THE REQUIRED POSITIVE PRESSURE WAS OBTAINED. DATA | | COLLECTION CONTINUED AND AT 1009 HOURS 4.0.3 WAS EXITED AFTER TESTING | | PROVED COMPLIANCE WITH TECH SPEC 4.7.7.E.3. | | | | THIS IS BEING REPORTED AS A VIOLATION OF PLANT OPERATING LICENSE SECTION | | 2.G.2.C(2) (24 HOUR REPORT)." | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27985 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 11/03/94 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 17:59 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/03/94 | +------------------------------------------------+EVENT TIME: 16:30[CST]| |NRC NOTIFIED BY: KEN STRUBLE |LAST UPDATE DATE: 11/03/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF AN OIL SPILL | | | | AT 1600 ON 11/3/94, THE LICENSEE DISCOVERED THAT ONE PINT OF OIL HAD BEEN | | SPILLED IN THE RESERVOIR MAKEUP PUMPING FACILITY FOREBAY. THE LICENSEE | | INFORMED THE TEXAS GENERAL LAND OFFICE AT 1630. EFFORTS ARE UNDERWAY TO | | INSTALL BOOMS ON THE RIVER SIDE OF THE STRUCTURE. THE OIL IS BEING KEPT IN | | THE FOREBAY NOW BECAUSE THE MAKE UP PUMPS ARE RUNNING. THE OIL SPILLED | | DURING MAINTENANCE ON A SCREEN WASHING PUMP. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 27986 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COPES-VULCAN INCORPORATED |NOTIFICATION DATE: 11/03/94 | | CITY: LAKE CITY REGION: 1 |NOTIFICATION TIME: 13:39 [ET]| | COUNTY: STATE: PA |EVENT DATE: 11/03/94 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EST]| | DOCKET: |LAST UPDATE DATE: 11/03/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: SCARPELLI | | |HQ OPS OFFICER: GREG SCARFO | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DEFECTIVE COPES-VULCAN YOKES WERE DELIVERED TO SEVERAL UTILITIES. | | | | THE FOLLOWING IS A TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "COPES-VULCAN, LAKE CITY, PENNSYLVANIA, HAS BEEN INFORMED BY TENNESSEE | | VALLEY AUTHORITY, SEQUOYAH, THAT NINE (9) YOKES, P/N 342849, SUPPLIED TO | | THEM AS PART OF AN UPGRADE PROGRAM, HAVE DISCREPANT 1/2-13UNC TAPED HOLES | | WHICH COULD IMPACT THE ABILITY TO OPERATE IF INSTALLED. | | | | COPES-VULCAN HAS TRACED THE PROBLEM TO A MANUFACTURING OPERATION WHICH | | DRILLS THE HOLES OVERSIZE AND THEN USES A ROLL TAP TO RE-FORM THE THREADS. | | IF A ROLL TAP IS NOT USED, THE THREAD MINOR DIAMETER IS OVERSIZE TO THE | | POINT OF WEAKENING THE THREAD. THIS IS WHAT HAPPENED IN THIS INSTANCE. | | | | AN INVESTIGATION INTO THE AFFECTED YOKES HAS LIMITED THE USAGE TO NINE (9) | | YOKES AT TVA, ONE (1) YOKE AT THE WISCONSIN POWER AND ONE (1) YOKE AT | | FARLEY SOUTHERN COMPANY. THE TVA YOKES HAVE NOT BEEN INSTALLED AT THIS | | TIME AND THE WISCONSIN POWER, POINT BEACH, ACTUATOR WHICH MAY CONTAIN A | | DEFECTIVE YOKE, WOULD PERFORM ITS FAIL SAFE MODE AS DELIVERED WAS WOULD THE | | VALVE AT FARLEY. | | | | THE AFFECTED UTILITIES HAVE BEEN NOTIFIED AS OF NOVEMBER 3, 1994." END OF | | TEXT. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27987 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 11/03/94 | |UNIT: [1] [ ] [ ] STATE: CA |NOTIFICATION TIME: 19:07 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/03/94 | +------------------------------------------------+EVENT TIME: 16:00[PST]| |NRC NOTIFIED BY: BOB MAGRUDER |LAST UPDATE DATE: 11/03/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STEAM GENERATOR INSPECTION RESULTS WERE MISCLASSIFIED | | | | TECH SPEC 4.4.5.2 REQUIRES RESULTS OF S/G TUBE INSPECTIONS BE CLASSIFIED AS | | CATEGORY C-III IF MORE THAN 10% OF TOTAL TUBES INSPECTED ARE DEGRADED TUBES | | OR MORE THAN 1% OF THE INSPECTED TUBES ARE DEFECTIVE. SINCE 36 TUBES WERE | | FOUND TO BE DEFECTIVE (GREATER THAN 1% OF THOSE INSPECTED), THE S/G RESULTS | | SHOULD HAVE BEEN CLASSIFIED AS CATEGORY C-III. THE LICENSEE DID NOT | | CLASSIFY THE RESULTS AS C-III BECAUSE THEY INTERPRETED THE ABOVE ON A PER | | UNIT BASIS AND NOT PER STEAM GENERATOR BASIS. | | | | THESE INSPECTIONS WERE DONE DURING THE MOST RECENT REFUELING OUTAGE IN THE | | SPRING OF THIS YEAR. THE LICENSEE BECAME AWARE OF THEIR MISTAKEN | | UNDERSTANDING OF THE REQUIREMENT WHEN S/G INSPECTIONS WERE PERFORMED DURING | | A UNIT 2 REFUELING OUTAGE THAT HAS JUST BEEN COMPLETED. ALL OF THE TUBES | | IN QUESTION WERE PLUGGED DURING THE SPRING REFUELING OUTAGE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27988 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 11/03/94 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 21:56 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/03/94 | +------------------------------------------------+EVENT TIME: 20:48[EST]| |NRC NOTIFIED BY: KAFANTARIS |LAST UPDATE DATE: 11/03/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LETDOWN HEAT EXCHANGER (HX) ROOM DAMPER INSTALLED BACKWARDS | | | | THE #2 LETDOWN HX ROOM BACKDRAFT DAMPER WAS DISCOVERED TO BE INSTALLED | | BACKWARDS. THIS DAMPER IS DESIGNED TO PREVENT BREAK INDUCED STEAM FLOW | | FROM REACHING VITAL EQUIPMENT ON THE 84' ELEVATION OF THE AUXILIARY | | BUILDING. THE LICENSEE HAS NOT DETERMINED THE POTENTIAL EFFECT ON VITAL | | EQUIPMENT IN THE AREA. THIS REPORT IS BEING MADE IAW GENERIC LETTER 91-18 | | BECAUSE THE CONDITION IS "INDETERMINATE". | | | | DETAILED ENGINEERING EVALUATION IS UNDERWAY TO ASSESS THIS CONDITION & | | POTENTIAL EFFECT. THE EQUIVALENT DAMPER AT SALEM UNIT 1 HAS BEEN FOUND TO | | BE INSTALLED CORRECTLY. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27989 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 11/04/94 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 02:53 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 11/04/94 | +------------------------------------------------+EVENT TIME: 02:43[EST]| |NRC NOTIFIED BY: BOOTH |LAST UPDATE DATE: 11/04/94 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ANDERSON RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 99 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT ENTERED SHUTDOWN LCO DUE TO LOSS OF CONTROL ROD POSITION INDICATION. | | | | AT 0104 ON 11/4/94, THE FULL CORE POSITION DISPLAY BECAME INOPERABLE FOR | | UNKNOWN REASONS. THIS INCLUDED A LOSS OF CONTROL ROD POSITION INDICATION | | IN THE CONTROL ROOM, EXCEPT FOR FOUR CONTROL RODS. CONTROL ROD POSITION | | INPUTS TO THE PROCESS COMPUTER ARE ALSO INOPERABLE. TECHNICAL | | SPECIFICATIONS REQUIRE THAT CONTROL ROD POSITION INDICATION BE RESTORED | | WITHIN ONE HOUR, OR THAT THE PLANT BE PLACED INTO HOT SHUTDOWN WITHIN THE | | FOLLOWING 12 HOURS. CONTROL ROD POSITION INDICATION HAS NOT BEEN RESTORED | | AT THIS TIME. | | | | AT 0243, THE LICENSEE COMMENCED A REACTOR SHUTDOWN AND REDUCED POWER | | SLIGHTLY BY ADJUSTING REACTOR RECIRCULATION FLOW. THE LICENSEE STATED | | THAT, SINCE CONTROL ROD POSITION INDICATION IS UNAVAILABLE, CONTROL ROD | | MOVEMENT IS INADVISABLE AT THIS TIME. THEREFORE, THE LICENSEE INTENDS TO | | MAINTAIN REACTOR POWER NEAR 100% TO MINIMIZE XENON TRANSIENTS WHICH WOULD | | REQUIRE THAT OPERATORS MOVE INDIVIDUAL CONTROL RODS TO KEEP THE REACTOR | | CORE WITHIN ESTABLISHED THERMAL LIMITS. AS A CONTINGENCY, THE LICENSEE IS | | MONITORING PARAMETERS WHICH WOULD INDICATE REACTIVITY CHANGES ASSOCIATED | | WITH CONTROL ROD DRIFT OR MOVEMENT. THE LICENSEE PLANS TO CONTINUE | | TROUBLESHOOTING THE CONTROL ROD POSITION INDICATION FOR SEVERAL MORE HOURS, | | AT WHICH TIME THEY INTEND TO REDUCE POWER AND MANUALLY SCRAM THE REACTOR TO | | COMPLY WITH TECHNICAL SPECIFICATIONS IF ROD POSITION INDICATION HAS NOT | | BEEN RESTORED. THE RI HAS BEEN INFORMED. | | | | *** UPDATE AT 0541 11/4/94 BY RESTUCCIO TAKEN BY STRANSKY *** | | | | THE UNIT EXITED THE TECHNICAL SPECIFICATION SHUTDOWN LCO WHEN CONTROL ROD | | POSITION INDICATION WAS RESTORED TO THE CONTROL ROOM. I&C TECHNICIANS | | DISCOVERED A FAULTY PROBE DATA PROCESSING CARD IN THE ROD POSITION | | INDICATION SYSTEM. THE FAULTY CARD HAS BEEN REPLACED AND THE ROD POSITION | | INDICATION SYSTEM IS NOW FUNCTIONING PROPERLY. THE RI WILL BE INFORMED. | +------------------------------------------------------------------------------+