U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/13/97 - 06/16/97 ** EVENT NUMBERS ** 32476 32477 32478 32479 32480 32481 32482 32483 32484 32485 32486 32487 32488 32489 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32476 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 06/13/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 07:55 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 06/13/97 | +------------------------------------------------+EVENT TIME: 05:23[EDT]| |NRC NOTIFIED BY: PAUL FREEMAN |LAST UPDATE DATE: 06/13/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A LOW-LOW STEAM GENERATOR WATER LEVEL ENGINEERED SAFETY FEATURE (ESF) | | SIGNAL OCCURRED DUE TO UNINTENTIONAL DRAINING OF THE 'C' STEAM GENERATOR. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AT 0523 EDT ON 06/13/97, [A] STEAM GENERATOR 'C' LOW-LOW LEVEL ESF SIGNAL | | WAS RECEIVED. THE SIGNAL WAS DUE TO LEVEL IN [STEAM GENERATOR] 'C' | | DECREASING TO LESS THAN 14% NARROW RANGE LEVEL. THE LEVEL DECREASE WAS DUE | | TO STROKING OF [VALVE] FW-V48, [STEAM GENERATOR] 'C' [FEEDWATER ISOLATION | | VALVE], AND WATER FLOWING INTO THE DRAINED HEADER. [THE EMERGENCY | | FEEDWATER (EFW)] PUMPS DID NOT START. THE EFW PUMPS WERE REMOVED FROM | | SERVICE. [THE] REACTOR TRIP BREAKERS WERE OPEN PRIOR TO THE EVENT." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32477 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 06/13/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 12:23 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 06/13/97 | +------------------------------------------------+EVENT TIME: 12:00[EDT]| |NRC NOTIFIED BY: RANDALL SEIFRIED |LAST UPDATE DATE: 06/13/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |CHRIS GRIMES/NRR EO | |NLCO TECH SPEC LCO A/S |RICHARD BARRETT/AEOD IRD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO THE INABILITY TO MONITOR | | UNIDENTIFIED LEAKAGE IN THE DRYWELL | | | | UNIT 1 ENTERED THE PREREQUISITES FOR THE PLANT SHUTDOWN PROCEDURE AT 1200 | | AS REQUIRED BY TECHNICAL SPECIFICATION 3.2.5, REACTOR COOLANT SYSTEM | | LEAKAGE. TECHNICAL SPECIFICATION 3.2.5(b) REQUIRES A MINIMUM OF ONE | | OPERABLE LEAKAGE MEASUREMENT CHANNEL FOR EACH DRYWELL FLOOR DRAIN AND | | EQUIPMENT DRAIN SUMP. OTHERWISE, THE PLANT MUST BE PLACED IN COLD SHUTDOWN | | WITHIN 24 HOURS. | | | | AT 0755 ON JUNE 13, 1997, FLOOR DRAIN SUMP LEAKAGE MONITORING ABILITY WAS | | LOST DUE TO THE FAILURE OF A DRYWELL FLOOR DRAIN SUMP ISOLATION VALVE | | DURING A SCHEDULED SURVEILLANCE TEST AND DUE TO THE SUBSEQUENT CLOSURE OF | | THE SECOND ISOLATION VALVE BY OPERATIONS PERSONNEL. CLOSURE OF BOTH OF | | THESE ISOLATION VALVES RESULTED IN THE INABILITY TO PUMP WATER OUT OF THE | | SUMP. THIS IN TURN RESULTED IN A HIGH LEVEL IN THE FLOOR DRAIN SUMP AND | | THE LOSS OF LEAKAGE RATE MEASUREMENT CAPABILITY WHEN THE LEVEL WENT ABOVE | | THE LEVEL OF THE MONITORING SYSTEM. THEREFORE, THE LICENSEE LOST THE | | CAPABILITY TO MONITOR UNIDENTIFIED DRYWELL LEAKAGE. (THE LICENSEE STILL | | HAS THE ABILITY TO MONITOR IDENTIFIED LEAKAGE.) AT THE TIME OF THIS EVENT, | | THERE WAS NO ABNORMAL REACTOR COOLANT SYSTEM LEAKAGE. | | | | THE LICENSEE IS CURRENTLY WORKING ON THE CONTROL CIRCUITS OUTSIDE THE | | DRYWELL. THE LICENSEE ALSO PLANS TO PLACE THE UNIT IN COLD SHUTDOWN AND | | PERFORM A DRYWELL ENTRY TO INSPECT THE VALVE AND LIMIT SWITCHES ASSOCIATED | | WITH THE VALVE. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32478 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 06/13/97 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 15:20 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 06/13/97 | +------------------------------------------------+EVENT TIME: 11:55[CDT]| |NRC NOTIFIED BY: BRIAN GRANT AND TOM KIMES |LAST UPDATE DATE: 06/13/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED 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 | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNAUTHORIZED ENTRY INTO THE PROTECTED AREA | | | | AT 1155 CDT, AN UNAUTHORIZED ENTRY WAS MADE INTO THE PROTECTED AREA FOR | | APPROXIMATELY 3 TO 5 MINUTES. IMMEDIATE CORRECTIVE ACTIONS WERE TAKEN UPON | | DISCOVERY. THE LICENSEE DOES NOT BELIEVE THAT THERE WAS ANY MALEVOLENT | | INTENT ASSOCIATED WITH THIS EVENT, AND THE CAUSE OF THE EVENT IS CURRENTLY | | UNDER INVESTIGATION. THIS EVENT WAS DETERMINED TO BE REPORTABLE AT 1325 | | CDT. (REFER TO THE HOO LOG FOR ADDITIONAL DETAILS AND FOR A SITE CONTACT | | TELEPHONE NUMBER.) | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 32479 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ST. MICHAEL'S HOSPITAL |NOTIFICATION DATE: 06/13/97 | | CITY: NEWARK REGION: 1 |NOTIFICATION TIME: 16:18 [ET]| | COUNTY: ESSEX STATE: NJ |EVENT DATE: 06/13/97 | |LICENSE#: 29-06759-01 AGREEMENT: N |EVENT TIME: 13:00[EDT]| | DOCKET: |LAST UPDATE DATE: 06/13/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |RICHARD KEIMIG RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: DR. CONTE | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ST. MICHAEL'S HOSPITAL LOCATED IN NEWARK, NEW JERSEY, REPORTED A MEDICAL | | MISADMINISTRATION DUE TO PATIENT INTERVENTION. | | | | AN IODINE-131 THERAPY CAPSULE WAS RECENTLY IDENTIFIED AT A MEDICAL WASTE | | DUMP SITE (LOCATION UNKNOWN). THE CAPSULE APPARENTLY CAME FROM MEDICAL | | WASTE RECEIVED AT THE WASTE DUMP FROM ST. ELIZABETH'S HOSPITAL LOCATED IN | | ELIZABETH, NEW JERSEY. FURTHER INVESTIGATION REVEALED THAT THE CAPSULE WAS | | USED AT ST. MICHAEL'S HOSPITAL TO TREAT A PATIENT FOR HYPOTHYROIDISM ON | | APRIL 18, 1997. THIS TREATMENT INVOLVED THE SWALLOWING OF AN IODINE-131 | | THERAPY CAPSULE WITH AN ACTIVITY OF APPROXIMATELY 19.8 MILLICURIES. A | | PHYSICIAN AT ST. ELIZABETH'S HOSPITAL DETERMINED THAT THERE IS CURRENTLY NO | | RESIDUAL RADIOACTIVITY IN THE PATIENT'S THYROID GLAND INDICATING THAT THE | | TREATMENT WAS NOT RECEIVED. THE LICENSEE STATED THAT THE PATIENT WAS GIVEN | | THE CAPSULE TO SWALLOW WITH WATER ON APRIL 18, 1997. HOWEVER, IT IS | | CURRENTLY BELIEVED THAT THE PATIENT DID NOT SWALLOW THE CAPSULE DURING THIS | | TREATMENT AND THAT THE PATIENT (WHO VOLUNTEERED AT ST. ELIZABETH'S | | HOSPITAL) DISCARDED THE CAPSULE IN THE TRASH AT ST. ELIZABETH'S HOSPITAL. | | | | THIS TREATMENT WAS THE FOURTH TREATMENT OF THIS KIND FOR THIS PATIENT OVER | | APPROXIMATELY A ONE-YEAR PERIOD. THE CURRENT ACTIVITY OF THE IODINE-131 | | CAPSULE IS 900 MICROCURIES. THE LICENSEE'S INVESTIGATION IS CURRENTLY ON | | GOING. | | | | THE LICENSEE NOTIFIED THE NRC REGION 1 OFFICE (DR. SHANBAKY). (REFER TO | | THE HOO LOG FOR A SITE ADDRESS AND TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32480 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 06/13/97 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 16:25 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 06/13/97 | +------------------------------------------------+EVENT TIME: 15:58[EDT]| |NRC NOTIFIED BY: RICHARD BONNER |LAST UPDATE DATE: 06/13/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT A REACTOR PROTECTION TRIP SETPOINT MAY BE NON-CONSERVATIVE | | | | THE INSTRUMENT UNCERTAINTIES ASSOCIATED WITH CERTAIN REACTOR PROTECTION | | SYSTEM FUNCTIONS MAY NOT HAVE BEEN FACTORED INTO A REACTOR TRIP SETPOINT. | | SPECIFICALLY, THE UNCERTAINTIES ASSOCIATED WITH THE REACTOR PROTECTION | | SYSTEM CORE PROTECTION CALCULATORS MAY NOT HAVE BEEN FACTORED INTO THE | | THERMAL MARGIN/LOW PRESSURIZER PRESSURE REACTOR TRIP SETPOINT. THE | | LICENSEE PLANS TO COMPLETE CORRECTIVE ACTIONS PRIOR TO RESTART OF THE UNIT | | FROM THE CURRENT PLANT SHUTDOWN. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE APPLICABLE STATE | | AND LOCAL AGENCIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32481 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/13/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 17:03 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/13/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:55[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/13/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JAMES CREED RDO | | DOCKET: 0707002 |JOHN AUSTIN/NMSS EO | +------------------------------------------------+RICHARD BARRETT/AEOD IRD | |NRC NOTIFIED BY: STEVE MAY | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |PAAA 95.57(b) LOSS OF CLASSIFIED INFO | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COMPROMISE OF CONFIDENTIAL RESTRICTED DATA (ONE-HOUR REPORT) | | | | AT 1555, THE NRC RESIDENT INSPECTOR IDENTIFIED A COMPROMISE OF CONFIDENTIAL | | RESTRICTED DATA IN THE X-330 PROCESS BUILDING. IMMEDIATE CORRECTIVE | | ACTIONS WERE TAKEN UPON DISCOVERY. (REFER TO THE HOO LOG FOR ADDITIONAL | | INFORMATION.) | | | | THE PORTSMOUTH REPORTING PROCEDURES REQUIRE THAT INITIAL NOTIFICATIONS BE | | MADE TO NRC REGION 3 AND THE NRC DIVISION OF SECURITY BETWEEN THE HOURS OF | | 0800 AND 1745. PORTSMOUTH NOTIFIED THE THE NRC REGION 3 OFFICE (CREED) AT | | 1647. THE NRC RESIDENT INSPECTOR WAS ALSO INFORMED OF THIS EVENT | | NOTIFICATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32482 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 06/13/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 17:24 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/13/97 | +------------------------------------------------+EVENT TIME: 17:15[EDT]| |NRC NOTIFIED BY: M. F. EMPEY |LAST UPDATE DATE: 06/13/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG 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 +------------------------------------------------------------------------------+ | DISCOVERY THAT THE ORIGINAL PRIMARY CONTAINMENT PAINT WAS NOT DESIGN BASIS | | ACCIDENT QUALIFIED OR TESTED IN ACCORDANCE WITH THE FINAL SAFETY ANALYSIS | | REPORT (FSAR) AND THAT IT COULD EXPERIENCE PREMATURE BLISTERING | | | | DURING A REVIEW OF AN INDUSTRY EVENT REGARDING CONTAINMENT MATERIALS | | (SPECIFICALLY COATINGS), IT WAS DETERMINED THE VERMONT YANKEE'S ORIGINAL | | PRIMARY CONTAINMENT PAINT WAS NOT DESIGN BASIS ACCIDENT QUALIFIED AT THE | | TIME OF LICENSING. FURTHERMORE, WHAT TESTING HAS BEEN COMPLETED ON THE | | EXISTING PAINT DOES NOT MEET THE REQUIREMENTS OF FSAR SECTION 14.9.1.6. | | THIS SECTION OF THE FSAR REGARDS RADIATION RESISTANCE. | | | | THE LICENSEE BELIEVES THAT THIS ISSUE IS ALREADY BOUNDED WITHIN AN INDUSTRY | | NOTICE (NRC BULLETIN 96-03), AND THE LICENSEE DOES NOT BELIEVE THAT THIS IS | | AN OPERABILITY ISSUE. THE UNIT IS NOT CURRENTLY IN ANY TECHNICAL | | SPECIFICATION LIMITING CONDITIONS FOR OPERATION AS A RESULT OF THIS ISSUE. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR TOMORROW MORNING. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32483 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 06/13/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 17:34 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 06/13/97 | +------------------------------------------------+EVENT TIME: 15:27[EDT]| |NRC NOTIFIED BY: LARRY NARON |LAST UPDATE DATE: 06/13/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 95 POWER OPERATION | 95 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ISOLATION OF THE REACTOR WATER CLEANUP SYSTEM DUE TO HIGH DIFFERENTIAL FLOW | | | | AT 1527, THE REACTOR WATER CLEANUP SYSTEM ISOLATED ON HIGH DIFFERENTIAL | | FLOW. OPERATORS WERE IN THE PROCESS OF CONDUCTING FILTER DEMINERALIZER | | EVOLUTIONS WHEN THE ISOLATION OCCURRED. BOTH DIVISIONS OF THE DIFFERENTIAL | | FLOW LOGIC ACTUATED AND ISOLATED THE INBOARD AND OUTBOARD CONTAINMENT | | ISOLATION VALVES. THE ISOLATION SYSTEM FUNCTIONED AS EXPECTED AND AS | | DESIGNED. | | | | DURING THE EVENT, FIRE ALARMS ACTUATED IN THE 'A' REACTOR WATER CLEANUP | | PUMP ROOM. FOLLOWUP INVESTIGATIONS IDENTIFIED A PARTIAL SEAL FAILURE ON | | THE 'A' REACTOR WATER CLEANUP PUMP. | | | | THE CAUSE OF THE HIGH DIFFERENTIAL FLOW IS UNDER INVESTIGATION. THE 'A' | | REACTOR WATER CLEANUP PUMP WAS ISOLATED BY THE REACTOR WATER CLEANUP SYSTEM | | ISOLATION LOGIC. | | | | AT THIS TIME, THE UNIT IS IN A TECHNICAL SPECIFICATION LIMITING CONDITION | | FOR OPERATION FOR MONITORING REACTOR COOLANT CONDUCTIVITY BECAUSE | | CONTINUOUS MONITORING CAPABILITY WAS LOST. CHEMISTRY PERSONNEL ARE | | REQUIRED TO ESTABLISH AN ALTERNATE SAMPLE PATH AND TO TAKE SAMPLES EVERY | | FOUR HOURS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32484 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 06/13/97 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 17:49 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 06/13/97 | +------------------------------------------------+EVENT TIME: 17:15[EDT]| |NRC NOTIFIED BY: RICHARD SWEENEY |LAST UPDATE DATE: 06/13/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DISCOVERY OF A MORE DIRECT PATH FOR POST LOSS OF COOLANT ACCIDENT COATING | | DEBRIS TO REACH THE REACTOR BUILDING SUMP THAN WAS ORIGINALLY ACCOUNTED FOR | | IN THE EXISTING TRANSPORT ANALYSIS | | | | IT WAS DISCOVERED THAT THE EXISTING TRANSPORT ANALYSIS OF THE REACTOR | | BUILDING COATING DEBRIS FROM INSIDE THE 'D' RING WALLS DID NOT ACCOUNT FOR | | THE EXISTENCE OF THE SCUPPERS IN THE SOUTH 'D' RING WALL. (SCUPPERS ARE | | SMALL HOLES WITHIN APPROXIMATELY SIX INCHES OF THE FLOOR THAT WOULD ALLOW | | FLUID TO EXIT ONE AREA AND GO TO ANOTHER AREA.) THE PATH COULD ALLOW | | CHIPS, FLAKES, AND/OR LOOSE DEBRIS TO SETTLE ON THE REACTOR BUILDING SUMP | | SCREEN POSSIBLY CAUSING THE REACTOR BUILDING SUMP TO BECOME INOPERABLE. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32485 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 06/13/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 23:47 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/13/97 | +------------------------------------------------+EVENT TIME: 21:56[EDT]| |NRC NOTIFIED BY: H. HANSON, JR. |LAST UPDATE DATE: 06/13/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 97 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING CONTROL ROD TESTING, CONTROL ROD 26-27 (CLOSE TO CENTER OF THE CORE) | | SCRAMMED AND WENT FROM THE 48 POSITION TO THE 00 POSITION (FULLY INSERTED). | | | | THE LICENSEE WAS PERFORMING A TECHNICAL SPECIFICATION WEEKLY REACTOR | | PROTECTION SYSTEM (RPS) MANUAL HALF SCRAM SURVEILLANCE TEST (WHERE THE | | LICENSEE PLACES A MANUAL HALF SCRAM ON EACH ONE OF THE FOUR RPS CHANNELS | | INDIVIDUALLY) WHEN A SINGLE CONTROL ROD SCRAMMED. CONTROL ROD 26-27 | | SCRAMMED FROM A FULL-OUT POSITION TO A FULL-IN POSITION WHEN THE 'B1' RPS | | CHANNEL WAS TESTED. ALL OTHER CONTROL RODS WERE VERIFIED TO BE IN THEIR | | PRE-TRIP CONDITION. REACTOR CORE POWER DECREASED APPROXIMATELY 3% AS A | | RESULT OF THE ROD INSERTION. | | | | INITIAL TROUBLESHOOTING EFFORTS INDICATED THAT THE CAUSE OF THE SINGLE ROD | | SCRAM WAS A BLOWN 'A' RPS FUSE WHICH SUPPLIED POWER TO THE 'A' SIDE SCRAM | | SOLENOID FOR CONTROL ROD 26-27. REPLACEMENT EFFORTS FOR THIS FUSE ARE | | CURRENTLY IN-PROGRESS. THERE WERE NO OTHER ACTIVITIES IN PROGRESS AT THE | | TIME OF THE EVENT THAT COULD HAVE RESULTED IN THIS FAILURE. REACTOR | | COOLANT SAMPLES INDICATED THAT THERE WAS NO FUEL DAMAGE. THE LICENSEE ALSO | | STATED THAT THE FUEL BUNDLES SURROUNDING THE CONTROL ROD THAT FULLY | | INSERTED INTO THE CORE WERE NOT EXCEEDING THEIR THERMAL LIMITS. HOPE CREEK | | PLANS TO CONTINUE TO OPERATE AT A 97% POWER LEVEL UNTIL CONTROL ROD 26-27 | | IS PROPERLY REPOSITIONED. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32486 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 06/14/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 12:32 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/14/97 | +------------------------------------------------+EVENT TIME: 09:18[CDT]| |NRC NOTIFIED BY: BOB WITZAK |LAST UPDATE DATE: 06/14/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA 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 18 POWER OPERATION | 18 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNPLANNED OPENING OF A DRYWELL-TO-TORUS VACUUM BREAKER (UNPLANNED ACTUATION | | OF AN ENGINEERED SAFETY FEATURE) | | | | DURING THE PERFORMANCE OF PROCEDURE 2.2.60, PRIMARY CONTAINMENT COOLING AND | | NITROGEN INERTING SYSTEM, 1 OF THE 12 DRYWELL-TO-TORUS VACUUM BREAKERS | | (PC-AOV-NRV25) OPENED AT 0918 CDT WHEN DIFFERENTIAL PRESSURE REACHED | | APPROXIMATELY 0.3 PSID. INERTING OF THE PRIMARY CONTAINMENT WAS IN | | PROGRESS WITH THE TORUS BEING INERTED FIRST. THE PROCEDURE REQUIRES THAT | | THE 24-INCH PURGE AND VENT INLET BE USED FOR PURGING AND THAT THE 2-INCH | | BYPASS AROUND THE OUTBOARD 24-INCH VENT VALVE BE USED FOR VENTING. THE | | TORUS WAS PRESSURIZED WITH RESPECT TO THE DRYWELL DUE TO THE DIFFERENCE IN | | FLOW PATHS, AND THE VALVE OPENED IN ORDER TO RELIEVE THE DIFFERENTIAL | | PRESSURE. THE OPERATOR LOWERED NITROGEN FLOW RATE, AND THE VALVE CLOSED AT | | 0925 CDT WHEN THE DIFFERENTIAL PRESSURE BEGAN TO EQUALIZE BETWEEN THE | | DRYWELL AND TORUS. THE OPENING OF THIS DRYWELL-TO-TORUS VACUUM BREAKER | | CONSTITUTES AN UNPLANNED ENGINEERED SAFETY FEATURE ACTUATION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32487 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 06/14/97 | |UNIT: [ ] [ ] [3] STATE: SC |NOTIFICATION TIME: 13:46 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 06/14/97 | +------------------------------------------------+EVENT TIME: 10:00[EDT]| |NRC NOTIFIED BY: MIKE HILL |LAST UPDATE DATE: 06/14/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT SHIFTING OF THE 3B REACTOR BUILDING COOLING UNIT (RBCU) FROM | | HIGH SPEED TO LOW SPEED (ACTUATION OF AN ENGINEERED SAFETY FEATURE) DUE TO | | PERSONNEL ERROR DURING EMERGENCY SAFEGUARDS TESTING | | | | DURING EMERGENCY SAFEGUARDS TESTING OF EMERGENCY SAFEGUARDS DIGITAL | | CHANNELS 5 AND 6, THE 3B RBCU WAS INADVERTENTLY SHIFTED FROM HIGH SPEED TO | | LOW SPEED (THE EMERGENCY SAFEGUARDS POSITION). THIS OCCURRED WHEN I&E | | TECHNICIANS FAILED TO LIFT THE PROPER LINKS WHILE TESTING EMERGENCY | | SAFEGUARDS DIGITAL CHANNEL 6. A LINK HAD BEEN LIFTED FOR THE TESTING OF | | THE 3B RBCU ON EMERGENCY SAFEGUARDS DIGITAL CHANNEL 5, AND IT WAS ASSUMED | | THAT THIS WAS THE SAME LINK REQUIRED FOR THE TESTING OF THE 3B RBCU ON | | EMERGENCY SAFEGUARDS DIGITAL CHANNEL 6. THE 3B RBCU WAS STOPPED BY CONTROL | | ROOM PERSONNEL AT 1001, AND THE RESPONSIBLE MECHANICAL SYSTEMS ENGINEER WAS | | CONTACTED. THE 3B RBCU WAS RESTARTED AT 1035, AND IT WAS DECLARED OPERABLE | | AT 1053 AFTER TEMPERATURE STABILIZED. | | | | DURING THE TIME THAT THE 3B RBCU WAS INOPERABLE, THE UNIT WAS IN A 7-DAY | | TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION. UNIT 3 REMAINED | | AT 100% POWER, AND THERE WAS NO AFFECT ON UNIT OPERATION. THE LICENSEE | | BELIEVES THAT THIS NOTIFICATION WAS CONSERVATIVE DUE TO DIFFICULTY IN THE | | INTERPRETATION OF NUREG-1022. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32488 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/14/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:55 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/14/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/14/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JAMES CREED RDO | | DOCKET: 0707002 |JOHN AUSTIN/NMSS EO | +------------------------------------------------+RICHARD BARRETT/AEOD IRD | |NRC NOTIFIED BY: KEITH WILLIAMSON | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |HHHH OFFSITE NOTIFICATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF A PYRANOL LEAK FROM A HIGH VOLTAGE CAPACITOR BANK | | IN THE X-333 PROCESS BUILDING (4-HOUR REPORT) | | | | THIS 4-HOUR EVENT NOTIFICATION WAS MADE IN ACCORDANCE WITH PROCEDURE | | UE2-MC-RE1030, REVISION 2, APPENDIX D, SECTION P, FOR ANY EVENT OR | | SITUATION RELATED TO THE PROTECTION OF THE ENVIRONMENT FOR WHICH | | NOTIFICATION OF OTHER GOVERNMENT AGENCIES HAS BEEN MADE. | | | | APPROXIMATELY 1 PINT OF PYRANOL LEAKED FROM HIGH VOLTAGE CAPACITOR BANK | | #3367B IN THE X-333 PROCESS BUILDING. (PYRANOL IS A TYPE OF OIL WITH A | | HIGH CONCENTRATION OF POLYCHLORINATED BIPHENYLS.) THE LEAK WAS CONTAINED | | WITHIN THE BUILDING IN THE AFFECTED AREA. THE AREA WAS IMMEDIATELY | | CORDONED OFF. CLEANUP ACTIVITIES HAVE BEEN INITIATED AND WILL CONTINUE | | UNTIL SAMPLE RESULTS MEET ENVIRONMENTAL PROTECTION AGENCY CLEANUP | | STANDARDS. ENVIRONMENTAL COMPLIANCE ENGINEERING PERSONNEL ARE CURRENTLY | | DEVELOPING A CORRECTIVE ACTION PLAN TO REPAIR THE PYRANOL LEAK. | | | | ALTHOUGH THERE WAS NO ENVIRONMENTAL INSULT OR AFFECT TO THE HEALTH AND | | SAFETY OF PERSONNEL, PORTSMOUTH NOTIFIED THE OHIO ENVIRONMENTAL PROTECTION | | AGENCY OF THIS EVENT. THE NRC RESIDENT INSPECTOR WAS ALSO INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32489 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/15/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 16:40 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/15/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 10:45[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/15/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |JAMES CREED RDO | | DOCKET: 0707001 | | +------------------------------------------------+ | |NRC NOTIFIED BY: MATT C. MAURER | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INOPERABLE NORMETEX PUMP UF6 RELEASE DETECTION SYSTEM DUE TO PERSONNEL | | ERROR DURING THE PERFORMANCE OF A SURVEILLANCE TEST ON THE REDUNDANT PUMP | | (24-HOUR REPORT) | | | | AT 1045 CDT ON JUNE 15, 1997, A SYSTEM ENGINEER DETERMINED THAT THE C-310 | | WEST NORMETEX PUMP UF6 RELEASE DETECTION SYSTEM WAS INADVERTENTLY RENDERED | | INOPERABLE DURING THE PERFORMANCE OF TECHNICAL SAFETY REQUIREMENT | | SURVEILLANCE SR-2.3.4.3-1 ON THE C-310 EAST NORMETEX PUMP ON JUNE 13, 1997. | | AS DESCRIBED IN SECTION 3.4.2 OF THE SAFETY ANALYSIS REPORT, THE UF6 | | RELEASE DETECTION SYSTEM IS DESIGNED TO ALARM WHEN ANY PROCESS GAS DETECTOR | | HEAD ACTUATES AND TO SHUT THE PUMP DOWN AND CLOSE THE INLET AND OUTLET | | BLOCK VALVES WHEN ANY TWO ADJACENT PROCESS GAS DETECTOR HEADS ARE ACTUATED. | | | | DURING THE PLANNED PERFORMANCE OF THE EAST NORMETEX PUMP SURVEILLANCE ON | | JUNE 13, 1997, THE MAINTENANCE MECHANIC IS REQUIRED TO LIFT AND LAND | | PROGRAMMABLE CONTROLLER OUTPUT LEADS ASSOCIATED WITH THE EAST NORMETEX | | PUMP. THE INDIVIDUAL ALSO INCORRECTLY LIFTED AND LANDED THE OUTPUT LEADS | | ASSOCIATED WITH THE WEST NORMETEX PUMP. THE LIFTING AND LANDING OF LEADS | | ON THE WEST NORMETEX PUMP EFFECTIVELY CAUSED THE WEST NORMETEX PUMP UF6 | | DETECTION SYSTEM TO BE INOPERABLE. THIS SYSTEM IS REQUIRED TO BE OPERABLE | | WHEN THE PUMP IS IN MODE 2 (WITHDRAWAL). THE WEST NORMETEX PUMP WAS IN | | MODE 2 FROM 0935 CDT UNTIL 1510 CDT ON JUNE 13, 1997, WHILE THE PLANNED | | SURVEILLANCE WAS BEING PERFORMED ON THE EAST NORMETEX PUMP. | | | | ANOMALIES WITH THE WEST NORMETEX PUMP UF6 DETECTION SYSTEM WERE FIRST | | DISCOVERED DURING THE PERFORMANCE OF A ROUTINE 'SMOKE TEST' ON THE | | OFF-STREAM WEST NORMETEX PUMP IN COMPLIANCE WITH OPERATIONS LONG-TERM ORDER | | 310-96-013 AT 1355 CDT ON JUNE 14, 1997. TROUBLESHOOTING AND EMPLOYEE | | INTERVIEWS RESULTED IN THE DISCOVERY THAT THE UF6 DETECTION SYSTEM WAS | | INOPERABLE ON THE WEST NORMETEX WHEN IT WAS ON MODE 2 ON JUNE 13, 1997. | | THIS EVENT IS REPORTABLE UNDER CRITERIA J.1 OF PROCEDURE UE2-RA-RE1030 | | (10 CFR 76.120.c AND d). | | | | PADUCAH NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+