U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/15/97 - 10/16/97 ** EVENT NUMBERS ** 32540 33087 33088 33089 33090 33091 33092 33093 33094 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32540 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 06/25/97 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 20:48 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 06/25/97 | +------------------------------------------------+EVENT TIME: 20:30[EDT]| |NRC NOTIFIED BY: OWENS |LAST UPDATE DATE: 10/15/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N Y 100 POWER OPERATION | 70 POWER OPERATION | | 3 | N Y 15 STARTUP | 15 STARTUP | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED THAT BLANKETED INSULATION WITH QUESTIONABLE | | QUALIFICATIONS MAY HAVE BEEN INSTALLED IN ALL THREE UNITS. | | | | ON 6/24/97, AN INSPECTION OF THE UNIT 1 REACTOR BUILDING IDENTIFIED TWO | | SECTIONS OF RCS PIPING WHICH HAD BLANKETED INSULATION. ENGINEERING | | QUESTIONED THE QUALIFICATION OF THE INSULATION, AND EFFORTS WERE INITIATED | | TO DETERMINE IF SIMILAR BLANKETED INSULATION MAY BE INSTALLED IN UNITS 2 & | | 3. LATER ON 6/24/97, WITH UNIT 3 AT 15% POWER, A TOUR OF THE UNIT 3 REACTOR | | BUILDING IDENTIFIED TWO SMALL PIECES OF BLANKET INSULATION ON THE RCS HOT | | LEGS. THE BLANKET INSULATION WAS REMOVED FROM UNITS 1 & 3 TO FURTHER | | DETERMINE ITS QUALIFICATIONS. | | | | ON 6/25/97, AN INSPECTION OF THE SUBJECT INSULATION CONCLUDED THAT THE | | INSULATION MAY NOT MEET DESIGN QUALIFICATIONS. UNCERTAINTY EXISTS | | REGARDING THE TRANSPORTABILITY OF THIS INSULATION TO THE CONTAINMENT SUMP | | AND THE POTENTIAL FOR THE CLOGGING OF THE SUMP DURING THE RECIRCULATION | | PHASE OF A LOCA. ENGINEERING IMMEDIATELY BEGAN AN EVALUATION OF THE IMPACT | | OF THE SUSPECT INSULATION ON SUMP OPERABILITY. AT 2015 ON 6/25/97, | | ENGINEERING CONCLUDED THAT OPERABILITY OF THE SUMP MAY NOT BE JUSTIFIED | | BASED UPON INFORMATION AVAILABLE AT THIS TIME. | | | | AS A RESULT OF THESE FINDINGS, UNIT 2 CONSERVATIVELY ENTERED T.S. 3.0 AT | | 2030, WHICH REQUIRED THAT THE UNIT BE PLACED IN HOT S/D WITHIN 24 HOURS. | | UNIT 2 HAD BEEN OPERATING AT 100% PRIOR TO ENTRY INTO T.S. 3.0. THE | | LICENSEE IS CONSERVATIVELY REPORTING THIS ON UNITS 2 & 3 AS A CONDITION | | THAT MAY BE OUTSIDE THE DESIGN BASIS OF THE PLANT, IN THAT THE UNQUALIFIED | | INSULATION COULD POTENTIALLY RESULT IN THE INOPERABILITY OF THE LPI, HPI | | AND RBS SYSTEMS DURING THE RECIRCULATION PHASE OF A LOCA. THIS EVENT IS | | ALSO REPORTABLE FOR UNIT 2 AS A T.S. REQUIRED SHUTDOWN. SINCE UNIT 1 IS | | ALREADY IN COLD S/D, THE EVENT IS REPORTED AS A CONDITION THAT ALONE COULD | | HAVE PREVENTED THE FULFILLMENT OF THE SAFETY FUNCTION OF THE LPI, HPI, AND | | RBS SYSTEMS NEEDED TO MITIGATE THE CONSEQUENCES OF AN ACCIDENT. ADDITIONAL | | TESTING AND ANALYSIS MAY CONCLUDE THAT THE INSULATION IS ACCEPTABLE FOR | | APPLICATION IN CONTAINMENT. | | | | SINCE THE SUBJECT INSULATION HAS BEEN REMOVED FROM UNITS 1 & 3, NO CURRENT | | OPERABILITY CONCERNS EXIST FOR THESE UNITS. EFFORTS ARE UNDERWAY TO INSPECT | | AND REMOVE ANY SUSPECT INSULATION FROM UNIT 2 ONCE REACTOR POWER HAS BEEN | | REDUCED. | | | | THE RESIDENT INSPECTOR WILL BE INFORMED. | | | | * * * UPDATE AT 0107 ON 06/26/97 FROM OWENS TAKEN BY STRANSKY * * * | | | | THE UNIT 2 REACTOR BUILDING INSPECTION HAS BEEN COMPLETED, WITH ONE PIECE | | OF QUESTIONABLE INSULATION FOUND AND REMOVED. THE TECHNICAL SPECIFICATION | | REQUIRED SHUTDOWN WAS EXITED AT 0030 EDT. REACTOR POWER HAD BEEN REDUCED TO | | 20%, AND WILL BE RETURNED TO 100%. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | THE HOO NOTIFIED R2DO (MILT SHYMLOCK). | | | | ***UPDATE ON 10/15/93 @ 1343 BY NIX TO GOULD*** THE LICENSEE IS RETRACTING | | THIS EVENT AFTER REVIEWING THE RESULTS OF THE DESTRUCTIVE EXAMINATION AND | | LABORATORY ANALYSES ON THE SUBJECT INSULATION. BASED ON THESE EXAMINATIONS | | AND ANALYSES, ENGINEERING OBTAINED THE INSULATION TRANSPORTABILITY | | INFORMATION TO ENABLE COMPLETION OF A MORE DETAILED EVALUATION OF ECCS | | OPERABILITY DURING THE REACTOR BUILDING SUMP RECIRCULATION MODE OF A LOCA. | | THIS INSULATION WAS DETERMINED TO BE MUCH LESS BUOYANT THAN ASSUMED IN THE | | ORIGINAL OPERABILITY EVALUATION. AS A RESULT, THE MORE DETAILED EVALUATION | | OF ECCS OPERABILITY CONCLUDED THAT REACTOR BUILDING SUMP BLOCKAGE WOULD NOT | | OCCUR, AND THAT ECCS WOULD PERFORM ITS INTENDED SAFETY FUNCTION DURING A | | LOCA. | | | | THE RESIDENT INSPECTOR WAS INFORMED AND REG 2 RDO(PEEBLES) WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 33087 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: TUOMEY REGIONAL MEDICAL CENTER |NOTIFICATION DATE: 10/15/97 | | CITY: SUMTER REGION: 2 |NOTIFICATION TIME: 08:31 [ET]| | COUNTY: STATE: SC |EVENT DATE: 09/23/97 | |LICENSE#: 10-0010 AGREEMENT: Y |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 10/15/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |THOMAS PEEBLES RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: WOODRUFF (REGION 2) | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT | | | | NRC REGION 2 WAS NOTIFED BY THE STATE OF SOUTH CAROLINA REGARDING A MEDICAL | | MISADMINISTRATION BY A STATE LICENSEE. ON 9/23/97, A RADIATION TREATMENT | | FOR PROSTATE CANCER USING A Pd-103 SOURCE WAS PERFORMED ON THE WRONG | | PATIENT. THE ACTUAL PATIENT HAD THE SAME NAME AS THE INTENDED PATIENT. NO | | FURTHER INFORMATION WAS AVAILABLE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 33088 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: DUBOSE NATIONAL ENERGY SERVICES INC |NOTIFICATION DATE: 10/15/97 | | CITY: CLINTON REGION: 2 |NOTIFICATION TIME: 15:06 [ET]| | COUNTY: STATE: NC |EVENT DATE: 10/15/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 10/15/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |THOMAS PEEBLES RDO | | | | +------------------------------------------------+VERN HODGE NRR | |NRC NOTIFIED BY: DAILEY(FAX) | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DUBOSE NATIONAL ENERGY SERVICES INC SUBMITTED A POTENTIAL PART 21 REPORT. | | | | THE "DEFECT" IN QUESTION IS SOME 3/4" SCHEDULE 40 PIPING WHICH MAY HAVE | | WALL THICKNESS AS LOW AS .087" WHEN THE MINIMUM ALLOWED BY SA 312 | | SPECIFICATIONS IS .099". THIS PIPING WAS SHIPPED TO CAROLINA POWER & LIGHT | | AND VIRGINIA POWER AND THE NORTH ANNA SITE DISCOVERED THIS CONDITION. THEY | | HAVE RETURNED A SAMPLE OF MATERIAL TO THE PRODUCER, SANDVIK STEEL, FOR | | EVALUATION. BOTH SHIPMENTS OF PIPING TO THE TWO CUSTOMERS HAD THE SAME | | HEAT #46989. THE CUSTOMERS HAVE BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33089 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 10/15/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 17:08 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/14/97 | +------------------------------------------------+EVENT TIME: 19:30[EDT]| |NRC NOTIFIED BY: MLACHAK |LAST UPDATE DATE: 10/15/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | FAILURE TO MEET REQUIRED ACCUMULATOR PRESSURE FOR WITHDRAWAL OF CONTROL | | ROD. | | | | AT 0852 ON 10/14/97, AN ACCUMULATOR FAULT WAS RECEIVED ON HCU 18-39 AND THE | | ACCUMULATOR WAS REMOVED FROM SERVICE FOR NITROGEN PRE-CHARGING AT 1321. | | | | AT 1930, ANTICIPATORY ROD STROKING WAS PERFORMED ON ROD 18-39. I&C | | REPORTED THAT ACCUMULATOR 18-39 WAS READING APPROXIMATELY 500 PSIG AT | | 2120. | | | | AT 2200, IT WAS DISCOVERED THAT THE INSTRUMENT BLOCK VALVE (EP-111) WAS | | CLOSED ON HCU 18-39. THE HCU WAS WALKED DOWN, AND ONLY THE EP-111 WAS | | FOUND TO BE OUT OF POSITION. THREE MINUTES LATER, DIRECTION WAS GIVEN TO | | SLOWLY OPEN THE EP-111 AND ACCUMULATOR PRESSURE WAS OBSERVED TO BE 1,340 | | PSIG (THE REQUIREMENT FOR ACCUMULATOR PRESSURE TO WITHDRAW A CONTROL ROD IS | | 1,520 PSIG). THIS CONDITION RESULTED IN A TECH SPEC VIOLATION. | | | | SOMETIME BETWEEN 1321 AND 1900, EP-111 WAS CLOSED DUE TO A NITROGEN LEAK ON | | THE INSTRUMENT BLOCK FOR HCU 18-39. A REVIEW OF THE PLANT NARRATIVE LOG | | INDICATED THAT HCU 18-39 WAS NEVER LOGGED AS RETURNED TO SERVICE. ALSO | | THEY FOUND NO ENTRY REGARDING THE CLOSING OF EP-111 ON HCU 18-39. IN | | ADDITION, AN INCOMPLETE VERIFICATION CHECKLIST FOR HCU 18-39 WAS FOUND IN | | THE FOREMAN'S AREA. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33090 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 10/15/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 17:08 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/15/97 | +------------------------------------------------+EVENT TIME: 07:45[EDT]| |NRC NOTIFIED BY: MLACHAK |LAST UPDATE DATE: 10/15/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 DISCOVERED THE "B" EMERGENCY SERVICE WATER (ESW) PUMP FAILED TO | | START IN THE REQUIRED TIME FOLLOWING 2 LOOP/LOCA TESTING. | | | | A SURVEILLANCE PERFORMED ON 10/12/97 DETERMINED THAT THE "B" ESW PUMP | | FAILED TO START IN ITS SEQUENCE TIME REQUIREMENT. THE TEST IS USED TO | | VERIFY THAT SEQUENCE TIME IS WITHIN ñ10% OF DESIGN FOR EACH LOAD SEQUENCE | | TIMER ASSOCIATED WITH THE DIVISION I AND II DIESEL GENERATORS. THE ESW "B" | | PUMP SEQUENCE TIME WAS FOUND TO BE OUTSIDE OF THE 10% TOLERANCE BAND | | (REQUIREMENT IS <22 SECONDS, THE ACTUAL WAS 24.5 SECONDS). HOWEVER, IT WAS | | NOT RECOGNIZED AT THIS TIME THAT THE DGs WERE INOPERABLE. WHENEVER LESS | | THAN THREE DIESEL GENERATORS ARE OPERABLE, REQUIRED ACTIONS ARE TO BE TAKEN | | DURING MODES 1, 2, AND 3. | | | | IT WAS ALSO DISCOVERED, BASED ON THIS RECENT ISSUE, THAT A PREVIOUS | | SURVEILLANCE PERFORMED DURING REFUELING OUTAGE 5 IN 1996 ALSO RECORDED ESW | | "B" PUMP SEQUENCE TIME OUTSIDE THE ñ10% TS REQUIREMENT. THERE IS FIRM | | EVIDENCE TO BELIEVE THAT, AT A MINIMUM, THE PLANT WAS NOT OPERATED IN | | ACCORDANCE WITH TS 3.8.1, "AC SOURCES OPERATING," DURING THE LAST FUEL | | CYCLE. SPECIFICALLY, TS 3.8.1 CONDITION B, "ONE REQUIRED DG INOPERABLE," | | REQUIRED ACTIONS WERE NOT PERFORMED IN RESPONSE TO THE UNDISCOVERED | | CONDITION. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33091 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/15/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 17:12 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/15/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:35[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/15/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JIM MCCORMICKBARGER RDO | | DOCKET: 0707002 |LARRY CAMPER EO | +------------------------------------------------+ | |NRC NOTIFIED BY: MAY | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PORTSMOUTH GASEOUS DIFFUSION PLANT NOTIFIED THE OHIO EPA THAT THEY HAD | | EXCEEDED THE NPDES LIMIT FOR EFFLUENT pH. | | | | "ON 10/15/97 AT 1355 HOURS, THE X-700 BIODENITRIFICATION PROCESS EXCEEDED | | THE pH EFFLUENT LIMIT ESTABLISHED BY THE NATIONAL POLLUTANT DISCHARGE | | ELIMINATION SYSTEM (NPDES). | | | | THE EFFLUENT pH LIMIT FOR THE PROCESS IS 9.0 AND THE NPDES SAMPLE RESULT | | WAS 9.1. THE SYSTEM WAS IMMEDIATELY SHUTDOWN AND AN "AS-FOUND" INSPECTION | | WILL BE CONDUCTED. | | | | AN OFFSITE NOTIFICATION TO THE OHIO ENVIRONMENTAL PROTECTION AGENCY (OEPA) | | WAS MADE PER AGREEMENT AND WAS REPORTED THAT THERE WAS NO OFFSITE IMPACT." | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33092 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 10/15/97 | |UNIT: [1] [2] [ ] STATE: SC |NOTIFICATION TIME: 17:37 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/15/97 | +------------------------------------------------+EVENT TIME: 15:30[EDT]| |NRC NOTIFIED BY: JENKINS |LAST UPDATE DATE: 10/15/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE SOUTH CAROLINA DEPARTMENT OF HEALTH AND | | ENVIRONMENTAL CONTROLS AND THE NATIONAL RESPONSE CENTER OF AN OIL SHEEN ON | | LAKE WYLIE. | | | | THE SOURCE OF THE OIL SHEEN WAS FROM PERFORMING PREVENTIVE MAINTENANCE (PM) | | ON A MAIN FIRE PUMP EARLIER TODAY. DURING THE PM, OIL OVERFLOWED FROM THE | | BEARING RESERVOIR TO AN AREA AROUND THE PUMP MOTOR. WHEN THE MAIN FIRE PUMP | | WAS STARTED FOR A PERFORMANCE TEST, THE OIL WAS WASHED INTO THE LAKE | | IMMEDIATELY BELOW THE PUMP INTAKE STRUCTURE. ALL OF THE OIL WAS CONTAINED | | WITHIN THE PRIMARY BOOM BENEATH THE PUMP STRUCTURE. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33093 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 10/15/97 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 18:33 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/15/97 | +------------------------------------------------+EVENT TIME: 15:30[EDT]| |NRC NOTIFIED BY: RUPPERT |LAST UPDATE DATE: 10/15/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |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 +------------------------------------------------------------------------------+ | PLANT ENGINEERING STAFF IDENTIFIED THAT AN AS-BUILT DISCREPANCY EXISTED FOR | | THE "OA" RHR SERVICE WATER SYSTEM RADIATION MONITOR. | | | | THIS DISCREPANCY IS FOR THE "OA" RESIDUAL HEAT REMOVAL SERVICE WATER SYSTEM | | (RHRSW) RADIATION MONITOR TO DETECT EMERGENCY SERVICE WATER (ESW) EFFLUENT | | ACTIVITY. THE ASSOCIATION OF THIS RAD MONITOR WITH THE ESW SYSTEM HAS NO | | AUTOMATIC ACTION (ALARM FUNCTION ONLY). THIS RAD MONITOR ALSO HAS SHARED | | DUTY WITH THE RETURN PATH FROM THE RHRSW SYSTEM WHICH WOULD AUTOMATICALLY | | TRIP THE RHRSW PUMP IN THE EVENT OF DETECTION OF A HIGH RADIATION CONDITION | | (THIS AUTOMATIC ACTION IS STILL FUNCTIONAL). THE RAD MONITOR WAS THEREFORE | | DECLARED INOPERABLE PUTTING THEM IN A LCO ACTION STATEMENT. TO SATISFY | | THIS ACTION, SAMPLING WAS STARTED AT SIX HOUR INTERVALS AS REQUIRED BY | | PLANT PROCEDURES. THE RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33094 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 10/15/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 21:30 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 10/15/97 | +------------------------------------------------+EVENT TIME: 19:15[CDT]| |NRC NOTIFIED BY: CRAVENS |LAST UPDATE DATE: 10/15/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT DECLARED THE REFRIGERATION CONTROL UNIT (RCU) FOR THE CONTROL | | ROOM HVAC INOPERABLE AND THEY ENTERED A 30 DAY LCO ON UNIT 1. | | | | WHILE PERFORMING THE QUARTERLY TESTING OF THE CONTROL ROOM HVAC SYSTEM | | VALVES, IT WAS DETERMINED THAT INADEQUATE FLOW TO THE RCU WAS MEASURED. THE | | SURVEILLANCE TESTS THE OPEN FUNCTION OF A CHECK VALVE IN THE RHRSW SUPPLY | | LINE AS REQUIRED BY THE INSERVICE TEST PROGRAM. A DESIGN FLOW RATE OF 120 | | GPM TO THE RCU IS REQUIRED, BUT ONLY 115 GPM WAS MEASURED. THE RCU WAS | | DECLARED INOPERABLE AND THEY ENTERED A 30 DAY LCO. | | | | THE RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+