U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/20/98 - 03/23/98 ** EVENT NUMBERS ** 33575 33892 33925 33926 33927 33928 33929 33930 33931 33932 33933 33934 33935 33936 33937 33938 33939 33940 33941 33942 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33575 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 01/22/98 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 12:51 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 01/22/98 | +------------------------------------------------+EVENT TIME: 12:15[EST]| |NRC NOTIFIED BY: MIKE DAVID |LAST UPDATE DATE: 03/20/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN CARUSO 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 +------------------------------------------------------------------------------+ | DISCOVERY OF THE POTENTIAL INABILITY TO SATISFY MAXIMUM FLOW REQUIREMENTS | | WHEN THE TEST ISOLATION VALVE FOR THE SAFETY INJECTION COLD LEG CHECK | | VALVES IS OPEN. | | | | DURING THE EARLIER PART OF THIS OPERATING CYCLE (OL05), THE TEST ISOLATION | | VALVE FOR THE SAFETY INJECTION COLD LEG CHECK VALVES (#SI-V131) REMAINED | | OPEN FOR EXTENDED PERIODS OF TIME TO SUPPORT A CHECK VALVE BACK-LEAKAGE | | SURVEILLANCE PROCEDURE. THIS VALVE PROVIDES AN ALTERNATE PARALLEL FLOW | | PATH FOR EMERGENCY CORE COOLING SYSTEM (ECCS) COLD LEG INJECTION. THE | | PERIOD OF OPERATION WHEN THE VALVE WAS OPEN COULD HAVE RESULTED IN THE | | INABILITY TO SATISFY THE TECHNICAL SPECIFICATION [4.5.2.h.2(b)] MAXIMUM | | FLOW REQUIREMENT OF 669 GPM, ASSUMING STANDARD FAILURE CRITERIA. THE | | POTENTIAL ACCIDENT SCENARIO WOULD INVOLVE VALVE #SI-V131 BEING OPEN | | CONCURRENT WITH A B-TRAIN SOLID STATE PROTECTION SYSTEM (SSPS) FAILURE. THE | | B-TRAIN SSPS FAILURE WOULD PREVENT OPERATION OF THE B-TRAIN ECCS PUMPS AND | | WOULD ALSO PREVENT THE AUTOMATIC CLOSURE OF VALVE #SI-V131. POST-ECCS | | OPERATION WOULD RESULT IN THE A-TRAIN SAFETY INJECTION PUMP EXCEEDING THE | | VALUE STATED IN TECHNICAL SPECIFICATIONS FOR PUMP RUNOUT CONDITIONS. | | | | THE LICENSEE BELIEVES THAT THIS CONDITION IS REPORTABLE, AS A 4-HOUR | | NON-EMERGENCY REPORT, PURSUANT TO 10CFR50.72(b)(2)(iii)(D) AS A CONDITION | | THAT ALONE COULD HAVE PREVENTED THE FULFILLMENT OF THE SAFETY FUNCTION OF | | STRUCTURES OR SYSTEMS THAT ARE NEEDED TO MITIGATE THE CONSEQUENCES OF AN | | ACCIDENT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE ON 3/20/98 @ 1149 BY MORRISSEY TO GOULD*** THE LICENSEE IS | | RETRACTING THIS EVENT. THE LICENSEE HAS DETERMINED THAT THE POSTULATED | | ACCIDENT SCENARIO DESCRIBED IN THE EVENT WAS NOT CREDIBLE. THE INITIAL | | DETERMINATION WAS BASED ON THE PREMISE THAT THE NNS PIPING DOWNSTREAM OF | | "SI-V131" WAS ASSUMED TO BREAK AS A RESULT OF A SEISMIC EVENT. THE | | LICENSEE HAS DETERMINED THAT THE SUBJECT PIPING, WHICH IS INSTALLED PER | | ANSI B31.1, ACTUALLY MEETS THE ASME SECTION III CLASS 2 STRESS LIMITS SUCH | | THAT A POSTULATED PIPE BREAK IS NOT CREDIBLE COINCIDENT WITH OTHER LOADING | | COMBINATIONS. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED. REG 1 RDO(BARKLEY) WAS NOTIFIED. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33892 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/13/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 09:20 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/12/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:31[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/20/98 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |GARY SHEAR RDO | | DOCKET: 0707001 |JOSEPHINE PICCONE EO | +------------------------------------------------+ | |NRC NOTIFIED BY: W. F. CAGE | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MOMENTARY LOSS OF POWER TO THE C-360 CRITICALITY ACCIDENT ALARM SYSTEM | | BEACONS AND FACILITY PROCESS GAS LEAK DETECTION SYSTEM (24-HOUR REPORT) | | | | AT 1131 CST ON 03/12/98, 480-VOLT AC POWER WAS LOST TO THE C-360 BUILDING | | WHEN A CRANE SHOE (A SLIDING ELECTRICAL CONTACT) HUNG AND PULLED AN | | ELECTRICAL CABLE CAUSING A SHORT CIRCUIT. THIS POWER LOSS WAS CAUSED BY | | THE TRIPPING OF BREAKER FS12T AS A RESULT OF A FAULT ON THE C-360 BUILDING | | EAST CRANE. POWER TO THE C-360 CRITICALITY ACCIDENT ALARM SYSTEM (CAAS) | | BEACONS AND THE FACILITY PROCESS GAS LEAK DETECTION (PGLD) SYSTEM WAS | | MOMENTARILY LOST. POWER WAS IMMEDIATELY RESTORED TO THE FACILITY BY | | RECLOSING BREAKER FS12T. | | | | AUTOCLAVE #1 WAS IN A MODE WHERE THE PGLD SAFETY SYSTEM WAS REQUIRED BY | | TECHNICAL SAFETY REQUIREMENT (TSR) 2.1.4.2 TO BE AVAILABLE AND OPERABLE. | | THE C-360 BUILDING CAAS WAS REQUIRED TO BE OPERABLE PER TSR 2.1.4.5. DUE | | TO THE MOMENTARY POWER LOSS TO THE C-360 CAAS BEACONS AND PGLD SYSTEM, THIS | | INCIDENT IS REPORTABLE AS A 24-HOUR EVENT REPORT PER 10 CFR 76.120(c)(2). | | | | PADUCAH NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE ON 3/20/98 @ 1540 BY MAURER TO GOULD*** THE LICENSEE IS | | RETRACTING THIS EVENT. SUBSEQUENT TESTING OF THE "C-360 ELECTRICAL SYSTEM | | AND A REVIEW OF THE BUILDING ELECTRICAL DRAWINGS HAVE REVEALED THAT POWER | | TO LIGHTING PANEL "LP-T", SUPPLYING THE CAAS AND THE PGLD, AUTOMATICALLY | | TRANSFERRED TO AN ALTERNATE BUS AS DESIGNED. DUE TO THIS AUTOMATIC POWER | | TRANSFER, THE ABILITY FOR THE CAAS AND PGLD SYSTEMS TO PERFORM THEIR | | INTENDED SAFETY FUNCTION WAS NOT DISABLED. BASED ON THIS ANALYSIS, THE | | SUBJECT NOTIFICATION IS BEING RETRACTED. | | | | THE RESIDENT HAS BEEN NOTIFIED. THE REG 3 RDO(LEACH) WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33925 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/20/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 00:01 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/19/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:15[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/20/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |MELVYN LEACH RDO | | DOCKET: 0707002 |DON COOL, NMSS EO | +------------------------------------------------+JOSEPH GIITTER IRD | |NRC NOTIFIED BY: ERIC SPAETH | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - NRC BULLETIN 91-01, 24 HOUR REPORT - LOSS OF MODERATION SAFETY CONTROL - | | | | AT 1115 ON 03/19/98, PLANT PERSONNEL DISCOVERED THAT A NUCLEAR CRITICALITY | | SAFETY APPROVAL (NCSA) REQUIREMENT WAS NOT BEING MAINTAINED IN A BOUNDARY | | CONTROL STATION OF THE X-330 PROCESS BUILDING. NCSA PLANT 01B.A01, PART B, | | REQUIREMENT #4, STATES THAT DRY ACTIVE WASTE BAGS SHALL HAVE HOLES IN THE | | BOTTOM OF EACH BAG TO ALLOW FOR SOLUTION DRAINAGE. | | | | AT A BOUNDARY CONTROL STATION, PLANT PERSONNEL DISCOVERED DRY ACTIVE | | WASTE IN A WATER SOLUBLE LAUNDRY BAG THAT DID NOT HAVE HOLES IN ITS BOTTOM. | | AN ACCUMULATION OF DRY ACTIVE WASTE IN A BAG COULD HAVE A MASS GREATER | | THAN A SAFE MASS OF U-235; THE ACCUMULATION OF LIQUID INSIDE THE BAG COULD | | MODERATE THIS MASS. AT 1230, PLANT PERSONNEL CORRECTED THIS DEFICIENCY BY | | REMOVING THE DRY ACTIVE WASTE FROM THE BAG AND PROPERLY DISPOSING OF IT. | | | | THIS CONDITION CONSTITUTES A LOSS OF CONTROL 'B' (MODERATION) ON THE DOUBLE | | CONTINGENCY MATRIX FOR CONTINGENCY EVENT #B.7.1. CONTROL 'A' (MASS) WAS | | MAINTAINED THROUGHOUT THIS EVENT. | | | | THE LOSS OF ONE OF TWO NUCLEAR CRITICALITY SAFETY CONTROLS IS REPORTABLE TO | | THE NRC PER THE REQUIREMENTS OF NRC BULLETIN 91-01, 24 HOUR REPORT. | | | | THERE WAS NO LOSS OF HAZARDOUS OR RADIOACTIVE MATERIAL, AND THERE WERE NO | | RADIOACTIVE OR RADIOLOGICAL CONTAMINATION EXPOSURES AS A RESULT OF THIS | | EVENT. | | | | PLANT PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR AND THE SITE DOE | | REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33926 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 03/20/98 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 04:40 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 03/20/98 | +------------------------------------------------+EVENT TIME: 03:11[EST]| |NRC NOTIFIED BY: GEORGE VOISHNIS |LAST UPDATE DATE: 03/20/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD BARKLEY 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 | M/R Y 71 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -MANUAL REACTOR SCRAM FROM 71% POWER DUE TO SJAE LOW STEAM PRESSURE ALARM- | | | | AT 0305, THE CONTROL ROOM RECEIVED A STEAM JET AIR EJECTOR (SJAE) LOW | | STEAM PRESSURE ALARM FOR UNKNOWN REASONS. AT 0311, CONTROL ROOM OPERATORS | | MANUALLY SCRAMMED THE REACTOR FROM 71% POWER DUE TO DECREASING MAIN | | CONDENSER VACUUM. TWO CONTROL RODS RESTED AT THE "02" POSITION AND CONTROL | | ROOM OPERATORS MANUALLY DROVE THE CONTROL RODS TO THE "00" POSITION. | | FOLLOWING THE REACTOR SCRAM, THE PLANT RECEIVED AN AUTOMATIC REACTOR SCRAM | | SIGNAL DUE TO LOW REACTOR VESSEL WATER LEVEL (136 INCHES). REACTOR VESSEL | | WATER LEVEL WAS RESTORED TO NORMAL LEVEL (155 TO 165 INCHES) BY THE MAIN | | FEEDWATER SYSTEM. CONTROL ROOM OPERATORS MANUALLY STARTED THE MECHANICAL | | MAIN CONDENSER VACUUM PUMP TO RESTORE MAIN CONDENSER VACUUM. STEAM IS | | BEING DUMPED TO THE MAIN CONDENSER. NO SAFETY/RELIEF VALVES LIFTED | | FOLLOWING THE SCRAM. | | | | THE PLANT IS STABLE IN CONDITION 3 (HOT SHUTDOWN). | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE SJAE LOW STEAM PRESSURE | | ALARM. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33927 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/20/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 11:35 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/19/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:05[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/20/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |MELVYN LEACH RDO | | DOCKET: 0707002 |DON COOL/NMSS EO | +------------------------------------------------+JOSEPH GIITTER/AEOD IRD | |NRC NOTIFIED BY: CURT SISLER | | |HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NRC BULLETIN 91-01, 24 HOUR REPORT, LOSS OF SINGLE NCSA CONTROL | | | | OPERATIONS PERSONNEL DISCOVERED A NUCLEAR CRITICALITY SAFETY APPROVAL | | (NCSA) REQUIREMENT WAS NOT BEING MAINTAINED IN THE X-705 DECONTAMINATION | | BUILDING. 2 B-25 BOXES OF CUT CONTAMINATED SCRAP METAL WERE FOUND TO BE IN | | VIOLATION OF THE 5 FOOT EDGE-TO-EDGE SPACING REQUIREMENT AS SPECIFIED IN | | PROCEDURE. THE SECOND NCSA OR CONTROL "B" (MASS/MODERATION) WAS MAINTAINED | | THROUGHOUT THIS EVENT. THE DEFICIENCY, SPACING, WAS IMMEDIATELY CORRECTED | | BY OPERATIONS PERSONNEL. | | | | THERE WAS NO LOSS OF HAZARDOUS OR RADIOACTIVE MATERIAL AND THERE WAS NO | | RADIOACTIVE OR RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS | | EVENT. | | | | PLANT PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR AND ONSITE DOE | | REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33928 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 03/20/98 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 11:56 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/20/98 | +------------------------------------------------+EVENT TIME: 09:32[EST]| |NRC NOTIFIED BY: MEYER |LAST UPDATE DATE: 03/20/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS JOHNSON RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFF SITE NOTIFICATION WAS MADE BY THE LICENSEE TO THE BURKE COUNTY SHERIFF | | AND THE CORONER'S DEPARTMENT. | | | | AT 0827 THE CONTROL ROOM RECEIVED A REPORT THAT A CONTRACT EMPLOYEE WAS | | INJURED AND ONSITE MEDICAL PERSONNEL RESPONDED. THE EMPLOYEE WAS FOUND ON | | THE LOWEST LEVEL OF THE TURBINE BUILDING. OFF SITE AMBULANCE SUPPORT WAS | | DISPATCHED AND THE EMPLOYEE WAS TRANSPORTED TO BURKE COUNTY HOSPITAL WHERE | | HE WAS PRONOUNCED DEAD AT 0932. | | | | THE RESIDENT INSPECTOR AND LOCAL AGENCIES WERE NOTIFIED. OTHER GOVERNMENT | | AGENCIES WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33929 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/20/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 12:23 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/19/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:20[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/20/98 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |MELVYN LEACH RDO | | DOCKET: 0707001 |COOL EO | +------------------------------------------------+JOSEPH GIITTER IRD | |NRC NOTIFIED BY: MAURER | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THAT STEAM BLOWDOWN TESTING OF THE NEWLY INSTALLED | | #1 BOILER AT THE "C-600" STEAM PLANT WAS CREATING AUDIBLE SOUNDS THAT WOULD | | PRECLUDE A LARGE SECTION OF THE OUTDOOR 12 RAD AREA NEAR THE "C-400" AND | | "C-409" CHEMICAL BUILDINGS FROM HAVING AN AUDIBLE CRITICALITY ACCIDENT | | ALARM SYSTEM(CAAS). THE DETECTABILITY OF THE "C-400" AND "C-409" CAAS WAS | | UNAFFECTED BY THE BOILER TESTING. UPON DISCOVERY OF THIS AUDIBILITY ISSUE, | | THE BLOWDOWN TESTING OF THE "C-600" #1 BOILER WAS CEASED. | | | | THE RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33930 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 03/20/98 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 13:29 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 03/20/98 | +------------------------------------------------+EVENT TIME: 13:00[EST]| |NRC NOTIFIED BY: PROPER |LAST UPDATE DATE: 03/20/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS JOHNSON RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE HAS IDENTIFIED AN ISSUE CONCERNING THE ABILITY TO ISOLATE | | EMERGENCY FEEDWATER(EFW) TO A FAULTED STEAM GENERATOR FOR A SECONDARY | | SYSTEM PIPE BREAK OUTSIDE CONTAINMENT. | | | | DURING A DESIGN REVIEW OF THE EFW SYSTEM, A POSTULATED ACCIDENT SCENARIO | | INVOLVING A SECONDARY SYSTEM PIPE BREAK OUTSIDE CONTAINMENT COINCIDENT WITH | | LOSS OF OFFSITE POWER AND A LOSS OF "A" TRAIN DC POWER FROM BUS "1HA" WAS | | REVIEWED. THIS SPECIFIC CONDITION AND RESULTANT EFFECT ON EQUIPMENT | | QUALIFICATION HAS NOT BEEN PREVIOUSLY ANALYZED. THIS SEQUENCE PREVENTS | | START OF THE "A" TRAIN DIESEL GENERATOR, RESULTS IN A LOSS OF CONTROL OF | | THE TURBINE DRIVEN EFW(TDEFW) PUMP FLOW(OTHER THAN PUMP SPEED CONTROL) TO | | STEAM GENERATORS, AND PREVENTS TRIPPING THE TDEFW FROM THE MAIN CONTROL | | ROOM. | | | | THE RESULTING MASS AND ENERGY RELEASE OUTSIDE THE REACTOR BUILDING MAY | | IMPACT LONG TERM ENVIRONMENTAL EQUIPMENT QUALIFICATION(EQ) FOR EQUIPMENT IN | | THE AREA. THIS ACCIDENT SEQUENCE WAS NOT SPECIFICALLY ANALYZED FOR MASS | | AND ENERGY EFFECTS. | | | | OPERATOR GUIDANCE CURRENTLY DIRECTS THE OPERATOR TO ISOLATE THE FAULTED | | STEAM GENERATOR FLOW WITHIN 10 MINUTES FROM THE MAIN CONTROL BOARD OR | | LOCALLY AT THE EQUIPMENT. HOWEVER THE GUIDANCE FOR ISOLATION FROM THE | | REMOTE CONTROL ROOM IS NOT SPECIFICALLY PROVIDED. ISOLATION FROM THE | | REMOTE CONTROL ROOM IS EXPECTED TO BE ACCOMPLISHED WITHIN ANALYSIS | | ASSUMPTION. | | | | THE INTERIM ACTIONS TAKEN TO ADDRESS PROCEDURAL GUIDANCE FOR THE OPERATORS | | INCLUDES: | | | | 1. A PROCEDURE REVISION TO THE EOP USERS GUIDE TO DESCRIBE OPERATOR ACTIONS | | IN THIS SPECIFIC EVENT. | | | | 2. TRAINING WILL BE PROVIDED TO OPERATIONS PERSONNEL PRIOR TO STARTING | | THEIR NEXT SHIFT. | | | | 3. AN OPERATOR WILL BE STATIONED IN THE REMOTE CONTROL ROOM TO PERFORM | | TDEFW PUMP ISOLATION FOR THIS EVENT. | | | | LONG TERM ACTION INCLUDES CONTINUED ENGINEERING EVALUATION OF THE EVENT. | | ALSO ACTUAL MASS AND ENERGY RELEASE FOR THIS EVENT AND A REVIEW FOR EFFECT | | ON EQUIPMENT QUALIFICATION WILL BE ASSESSED. | | | | THE PROBABILITY OF THIS SEQUENCE OF EVENTS HAS BEEN ESTIMATED AT 3E-12/YEAR | | WHICH IS BELOW THE TYPICAL ANALYSIS THRESHOLD OF CONCERN OF 1E-06/YEAR | | DESCRIBED IN ANSI/ANS 51.1-1983. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33931 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 03/20/98 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 13:40 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/20/98 | +------------------------------------------------+EVENT TIME: 11:00[CST]| |NRC NOTIFIED BY: DENNIS HIGINBOTHAN |LAST UPDATE DATE: 03/20/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MELVYN LEACH 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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION MADE FOR DISCOVERY OF DIESEL FUEL IN SOIL EXCAVATION. | | | | DURING EXCAVATION FOR AN ADDITION TO THE SERVICE BUILDING, PERSONNEL | | IDENTIFIED THE PRESENCE OF DIESEL OIL IN THE SOIL. COMPANY ENVIRONMENTAL | | SERVICES PERSONNEL AND SITE PERSONNEL HAVE NOT BEEN ABLE TO QUANTIFY THE | | AMOUNT OR IDENTIFY THE SOURCE. INVESTIGATION WILL CONTINUE TO TRY TO | | IDENTIFY THE SOURCE AND QUANTIFY THE AMOUNT OF DIESEL OIL. THE LICENSEE | | NOTIFIED THE NATIONAL RESPONSE CENTER AND THE ILLINOIS EMERGENCY MANAGEMENT | | ASSOCIATION OF THIS DISCOVERY. NEITHER UNIT IS AFFECTED BY THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33932 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 03/20/98 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 15:51 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/20/98 | +------------------------------------------------+EVENT TIME: 15:00[EST]| |NRC NOTIFIED BY: RUPPERT |LAST UPDATE DATE: 03/20/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD BARKLEY 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 +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED DUCTWORK CONNECTING TWO UNIT 1 SAFE SHUTDOWN AREAS | | WHICH DID NOT HAVE THE REQUIRED FIRE DAMPER INSTALLED TO MAINTAIN | | SEPARATION OF SAFE SHUTDOWN EQUIPMENT. | | | | PRELIMINARY REVIEW INDICATES THAT, IN THE EVENT OF A FIRE IN ONE OF THE | | AFFECTED SAFE SHUTDOWN AREAS, THE FIRE COULD PROPAGATE AND EFFECT THE | | SECOND AREA. UNDER THIS CONDITION SUFFICIENT EQUIPMENT WOULD NOT BE | | AVAILABLE TO RESPOND TO AN APPENDIX R FIRE. THIS CONDITION IS BELIEVED TO | | HAVE EXISTED SINCE INITIAL CONSTRUCTION. AN HOURLY FIRE WATCH AND OPERABLE | | FIRE DETECTION HAVE BEEN IN PLACE IN ACCORDANCE WITH TECH REQUIREMENTS | | MANUAL SECT. 3.7.7. | | | | AN ADDITIONAL PENETRATION ON UNIT 1 WAS ALSO VERIFIED TO BE MISSING A | | DAMPER, HOWEVER IN THIS CASE IT DOES NOT HAVE THE SAME IMPACT ON SAFE | | SHUTDOWN. UNIT 2 IS ALSO BEING INSPECTED TO VERIFY IF THE SAME CONDITION | | EXISTS ON THAT UNIT. A PRELIMINARY ASSESSMENT OF THE IMPACT ON UNIT 2 | | INDICATES THAT THE ABSENCE OF THESE DAMPERS WOULD NOT RENDER SUFFICIENT | | SAFE SHUTDOWN EQUIPMENT INOPERABLE TO PREVENT SAFE SHUTDOWN ON UNIT 2 IN | | THE EVENT OF AN APPENDIX R FIRE. | | | | THE RESIDENT INSPECTOR WILL BE INFORMED. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33933 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 03/20/98 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 17:57 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/20/98 | +------------------------------------------------+EVENT TIME: 17:00[EST]| |NRC NOTIFIED BY: GORLEY |LAST UPDATE DATE: 03/20/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS JOHNSON RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | A CONTRACT EMPLOYEE TESTED POSITIVE ON A RANDOM DRUG TEST TAKEN ON 3/11/98. | | TEST RESULTS WERE REPORTED ON 3/20/98. THE EMPLOYEE'S ACCESS HAS BEEN | | TERMINATED AND A REVIEW OF HIS WORK IS IN PROGRESS. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33934 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/20/98 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 18:48 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/20/98 | +------------------------------------------------+EVENT TIME: 18:30[EST]| |NRC NOTIFIED BY: SANTINI |LAST UPDATE DATE: 03/20/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD BARKLEY 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DISCOVERED A POSSIBLE CONDITION WHICH COULD RESULT IN THE | | OVERPRESSURE PROTECTION SYSTEM BEING DECLARED INOPERABLE. | | | | DURING THE PERFORMANCE OF THE LICENSEE'S INVESTIGATIONS OF THE 125VDC PANEL | | CIRCUITS, BOTH POWER OPERATED RELIEF VALVES(PORV), PCV-455C AND PCV-456, | | SOLENOIDS AND CONTROL CIRCUITS WERE FOUND TO HAVE A COMMON 125VDC POWER | | SOURCE. THIS CONDITION COULD HAVE RENDERED THE OVERPRESSURE PROTECTION | | SYSTEM INOPERABLE UPON A SINGLE FAILURE OR LOSS OF THE 125VDC SUPPLY | | RESULTING IN THE PLANT BEING OUTSIDE IT'S DESIGN BASIS. THIS INFORMATION | | IS PRELIMINARY AND WILL BE SUPPLEMENTED OR MODIFIED AS NECESSARY WHEN THEY | | HAVE COMPLETED THEIR INVESTIGATION. THE PLANT IS IN COLD SHUTDOWN, BUT THE | | LINEUP CONFIGURATION THE PLANT IS IN DOES NOT REQUIRE THE OVERPRESSURE | | PROTECTION SYSTEM TO BE OPERABLE. CORRECTIVE MEASURES WILL BE IMPLEMENTED | | PRIOR TO RESTART. | | | | THE RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33935 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 03/21/98 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 02:10 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 03/21/98 | +------------------------------------------------+EVENT TIME: 01:40[EST]| |NRC NOTIFIED BY: M THOMAS |LAST UPDATE DATE: 03/21/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM JOHNSON RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SEVERE THUNDERSTORMS CAUSED ALL THE EMERGENCY SIRENS IN LEE COUNTY TO | | BECOME INOPERABLE. | | | | THE MAIN CONTROL ROOM WAS NOTIFIED BY THE SYSTEM DISPATCHER THAT ALL SIRENS | | FOR LEE COUNTY HAD BEEN LOST. DURING THE EVENING, SEVERE THUNDER STORMS | | OCCURRED AND POSSIBLY LED TO THE SIREN LOSS. THE PLANT REMAINS AT 100% | | POWER WITH ALL SAFETY SYSTEMS FUNCTIONING NORMALLY AND OPERABLE. THE SYSTEM | | SERVICE CREW IS IN PROCESS OF REPAIRING THE SIRENS IN LEE COUNTY. ESTIMATED | | RESTORATION TIME IS NOT CURRENTLY AVAILABLE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | ***UPDATE ON 03/21/98 @ 0417 BY JOE DAVIS TAKEN BY MACKINNON*** | | | | ALL EMERGENCY SIRENS IN LEE COUNTY WERE RESTORED TO SERVICE AT 0345. | | R2DO (TOM JOHNSON) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS UPDATE BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33936 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 03/21/98 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 02:13 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 03/21/98 | +------------------------------------------------+EVENT TIME: 01:38[EST]| |NRC NOTIFIED BY: CROSSMAN |LAST UPDATE DATE: 03/21/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM JOHNSON 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 89 POWER OPERATION | 89 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION TO THE SURROUNDING COUNTY GOVERNMENT AGENCIES OF HIGH | | LAKE LEVEL. | | | | HIGH LAKE LEVEL (250.9') REQUIRED NOTIFICATION OF LOCAL GOVERNMENT AGENCIES | | AND RESIDENTS. THIS IS REQUIRED FOR DOWNSTREAM FLOODING CONCERNS AS LAKE | | ANNA DAM RADIAL GATES ARE OPENED TO CONTROL THE LEVEL OF THE LAKE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33937 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/21/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 12:36 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/20/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:30[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/21/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |MELVYN LEACH RDO | | DOCKET: 0707002 |SUSAN SHANKMAN EO | +------------------------------------------------+ | |NRC NOTIFIED BY: MAY | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24 HOUR - 91-01 BULLETIN RESPONSE | | | | OPERATIONS PERSONNEL DISCOVERED THAT NUCLEAR CRITICALITY SAFETY | | APPROVAL(NCSA) REQUIREMENTS WERE NOT BEING MAINTAINED IN THE "X-333" | | PROCESS BUILDING. A WASTE ACCUMULATION AREA HAD A FIVE GALLON CAN | | CONTAINING URANIUM BEARING WASTE OIL SPACED LESS THAN THE TWO FOOT | | EDGE-TO-EDGE SPACING AS SPECIFIED IN REQUIREMENT #5 OF NCSA-PLANT045.A02 | | AND REQUIREMENT #4 OF NCSA-PLANT070.A00. THIS LOSS OF SPACING CONSTITUTES | | A LOSS OF ONE CONTROL(INTERACTION). CONTROL "A" IN THE DOUBLE CONTINGENCY | | EVENTS FOR CONTINGENCY EVENTS A/B 7.1 OF NCSA PLANT045.A02 AND A/B 7.1 OF | | NCSA PLANT070.A00. CONTROL "B"(VOLUME) WAS MAINTAINED THROUGH THIS EVENT. | | THE DEFICIENCY(LOSS OF CONTROL "A") WAS IMMEDIATELY CORRECTED UNDER | | DIRECTION OF FACILITY NUCLEAR CRITICALITY SAFETY PERSONNEL. | | | | THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR | | RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. DOE SITE REPRESENTATIVE WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33938 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 03/21/98 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 13:16 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 03/21/98 | +------------------------------------------------+EVENT TIME: 12:30[EST]| |NRC NOTIFIED BY: PERRY |LAST UPDATE DATE: 03/21/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD BARKLEY 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 +------------------------------------------------------------------------------+ | TEMPERATURE IN THE "A" DIESEL GENERATOR ROOM DECREASED BELOW ITS MINIMUM | | REQUIRED FSAR TEMPERATURE. | | | | THE LICENSEE REPORTED THAT THE TEMPERATURE IN THE "A" DIESEL GENERATOR ROOM | | DROPPED BELOW THE MINIMUM ROOM TEMPERATURE(60øF) REQUIRED BY THE FSAR. THE | | TEMPERATURE IN THE ROOM DECREASED TO 58øF DUE TO HIGH WINDS BLOWING BACK | | THROUGH THE AIR DAMPERS. THE "A" DIESEL IS STILL CONSIDERED OPERABLE AND | | WILL REMAIN SO IF THE ROOM TEMPERATURE REMAINS ABOVE 50øF. THEY WILL | | MONITOR THE TEMPERATURE HOURLY AND TAKE MEASURES TO PREVENT IT FROM GETTING | | ANY LOWER THEN IT IS. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 33939 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: CROW-BUTTE RESOURCES |NOTIFICATION DATE: 03/21/98 | | CITY: CRAWFORD REGION: 4 |NOTIFICATION TIME: 15:41 [ET]| | COUNTY: STATE: NE |EVENT DATE: 03/21/98 | |LICENSE#: SUA-1534 AGREEMENT: Y |EVENT TIME: 09:15[CST]| | DOCKET: |LAST UPDATE DATE: 03/21/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BILL JONES RDO | | |SUSAN SHANKMAN EO | +------------------------------------------------+JOSEPH GIITTER IRD | |NRC NOTIFIED BY: HUFFMAN |JOE HOLONICH NMSS | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THEY EXCEEDED THE UPPER CONTROL LIMITS ON ONE OF | | THEIR SHALLOW MONITOR WELLS(#SM6-26). | | | | THE CONFIRMING ANALYSIS GAVE THE FOLLOWING RESULTS: | | | | THE SODIUM UPPER CONTROL LIMIT FOR THE MULTIPLE PARAMETER IS 32 MG/L | | THE SODIUM ANALYSIS WAS 33 MG/L | | | | THE SULFATE UPPER CONTROL LIMIT FOR THE MULTIPLE PARAMETER IS 18 MG/L | | THE SULFATE ANALYSIS WAS 19 MG/L | | | | THE CHLORIDE UPPER CONTROL LIMIT FOR THE SINGLE PARAMETER IS 9 MG/L | | THE CHLORIDE ANALYSIS WAS 9.7 MG/L | | | | THIS IS THE FIRST TIME THIS WELL HAS BEEN SAMPLED SINCE IT WAS BASELINED | | AND THE MINE UNIT 6 WAS JUST TURNED ON AND THEY BELIEVE THIS IS NOT A TRUE | | EXCURSION, BUT INSTEAD A FALSE EXCURSION. THE NEAREST LIXIVIANT INJECTION | | IS NEARLY 2000 FT AWAY FROM THE AREA. THEY HAVE DRILLED SOME ADDITIONAL | | WELLS NEAR THE SHALLOW MONITOR AND THEY THINK THE INCREASED READINGS WERE | | CAUSED BY DRILLING MUD WHICH CONTAMINATED THE SAMPLE. HOWEVER, THEY DID | | PUT IT ON EXCURSION STATUS SO THEY WILL SAMPLE ONCE A WEEK UNTIL THEY GET | | IT CLEANED UP. | | | | THERE WAS NO OFF SITE SPILL AND NOTHING REACHED ANY DRAINAGE AREAS, STREAMS | | OR RIVERS. | | | | THE STATE REPRESENTATIVE HAS BEEN NOTIFIED BY THE LICENSEE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33940 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 03/22/98 | |UNIT: [1] [2] [ ] STATE: MN |NOTIFICATION TIME: 01:10 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/21/98 | +------------------------------------------------+EVENT TIME: 20:19[CST]| |NRC NOTIFIED BY: L HENRY |LAST UPDATE DATE: 03/22/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MELVYN LEACH 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 +------------------------------------------------------------------------------+ | OFF SITE NOTIFICATION | | | | FAILURE OF MAKEUP SYSTEM TO #12 DIESEL DRIVEN COOLING WATER PUMP RESULTED | | IN THE SYSTEM OVERFLOWING TO THE MISSISSIPPI RIVER. APPROXIMATELY 130 | | GALLONS OF 660ppm NITRITES WAS SPILLED TO THE ENVIRONMENT. THE LICENSEE | | REPORTED THIS EVENT TO THE MINNESOTA POLLUTION CONTROL AGENCY AND TO THE | | GOODHEU COUNTY SHERIFF. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | A FACSIMILE OF THIS EVENT WAS SENT TO THE FOLLOWING FEDERAL GOVERNMENT | | AGENCIES: FEDERAL EMERGENCY MANAGEMENT AGENCY, DEPARTMENT OF ENERGY, | | DEPARTMENT OF AGRICULTURE, DEPARTMENT OF HEALTH AND HUMAN SERVICES, | | ENVIRONMENTAL PROTECTION AGENCY, AND THE DEPARTMENT OF TRANSPORTATION | | (NATIONAL RESPONSE CENTER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33941 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 03/22/98 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 03:37 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/22/98 | +------------------------------------------------+EVENT TIME: 00:17[EST]| |NRC NOTIFIED BY: CARL RICH |LAST UPDATE DATE: 03/22/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICH BARKLEY 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 94 POWER OPERATION | 85 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOAD CENTER CIRCUIT BREAKER TRIPPED WHICH EVENTUALLY CAUSED REACTOR WATER | | CLEANUP (RWCU) SYSTEM OUTBOARD ISOLATION VALVE TO CLOSE ON A HIGH | | DIFFERENTIAL TEMPERATURE SIGNAL. | | | | AT 0003 HOURS ON 03/22/98 THE 480V BREAKER SUPPLYING 124B LOAD CENTER | | TRIPPED. THIS TRIP CAUSED THE REACTOR ENCLOSURE HVAC (WHICH SERVES RWCU | | PUMP ROOMS) AND THE RWCU SYSTEMS TO TRIP. DIFFERENTIAL TEMPERATURES IN THE | | RWCU PUMP ROOMS INCREASED FROM 19 DEGREES TO THE TRIP SETPOINT OF 32 | | DEGREES AT 0015 CAUSING THE OUTBOARD ISOLATION VALVE, HV-044-1F004 TO | | ISOLATE. AT 0018 THE REACTOR ENCLOSURE HVAC WAS RESTORED AND TEMPERATURES | | IN THE RWCU PUMP ROOMS IMMEDIATELY STARTED TO DECREASE. THE INBOARD | | ISOLATION LOGIC NEVER REACHED THE DIFFERENTIAL TEMPERATURE ISOLATION | | SETPOINT AND THEREFORE DID NOT ISOLATE. HOWEVER, THE INBOARD ISOLATION | | VALVE, HV-044-1F001, WAS MANUALLY CLOSED (PART OF SECURING THE SYSTEM). | | | | AT 0039 WITH BOTH THE INBOARD AND OUTBOARD ISOLATION VALVES CLOSED THE RWCU | | SYSTEM RECEIVED A HIGH DIFFERENTIAL FLOW ISOLATION SIGNAL WHICH WAS | | GENERATED DUE TO THE SYSTEM BEING TAKEN OUT OF SERVICE. | | | | THE LOSS OF THE 480V 124B LOAD CENTER CAUSED A LOSS OF COOLING TO THE | | RECIRCULATION PUMP MOTOR COOLERS. THE REACTOR OPERATOR REDUCED REACTOR | | POWER LEVEL FROM 94% TO 85% TO REDUCE THE HEAT LOADS ON THE RECIRCULATION | | PUMP MOTORS. | | | | THE BREAKER THAT TRIPPED HAD BEEN INSTALLED ON 03/18/98 AND IT TRIPPED | | ABOUT FIVE MINUTES AFTER A FAN WAS STARTED. THE LICENSEE HAS HAD THE | | BREAKER REMOVED AND THEY WILL CHECK THE BREAKER TRIP SETPOINTS. THE OLD | | BREAKER THAT HAD BEEN REMOVED FROM THE 124B LOAD CENTER ON 03/18/98 WILL BE | | REINSTALLED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33942 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/23/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 00:47 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/22/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 08:15[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/23/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |MIKE JORDAN RDO | | DOCKET: 0707002 |SUSAN SHANKMAN, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: ERIC SPAETH | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF MODERATION CONTROL - A DRY ACTIVE WASTE BAG FOUND NOT TO HAVE HOLES | | IN THE BOTTOM OF IT. | | | | NRC BULLETIN 91-01 24 HOUR NOTIFICATION | | | | ON 03/22/98 @ 0815 HOURS IT WAS DISCOVERED THAT A NUCLEAR CRITICALLY SAFETY | | APPROVAL (NCSA) REQUIREMENT WAS NOT BEING MAINTAINED IN A BOUNDARY CONTROL | | STATION (BCS) OF THE X-330 BUILDING (CASCADE PROCESS BLDG). NCSA PLANT | | 018.A01, PART "B", REQUIREMENT #4 STATES THAT DRY ACTIVE WASTE (DAW) BAGS | | SHALL HAVE HOLES IN THE BOTTOM OF EACH BAG TO ALLOW FOR SOLUTION | | DRAINAGE.AT A BOUNDARY CONTROL STATION (BCS), DAW WAS DISCOVERED IN A | | SANITARY TRASH BAG WITHOUT HOLES IN THE BOTTOM. THIS CONSTITUTES A LOSS OF | | CONTROL "B" (MODERATION) IN THE DOUBLE CONTINGENCY MATRIX FOR CONTINGENCY | | EVENT B.1.1. CONTROL "A" (MASS) WAS MAINTAINED THROUGHOUT THIS EVENT. THE | | DEFICIENCY WAS IMMEDIATELY CORRECTED BY REMOVING THE DAW. THERE WAS NO LOSS | | OF HAZARDOUS/RADIOACTIVE MATERIAL OR RADIOACTIVE/RADIOLOGICAL CONTAMINATION | | EXPOSURE AS A RESULT OF THIS EVENT. | | | | SAFETY SIGNIFICANCE OF EVENTS: | | | | DAW WAS PLACED IN A BAG THAT DID NOT HAVE HOLES IN THE BOTTOM. THE BAG WAS | | A SANITARY BAG. | | | | POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW | | CRITICALITY COULD OCCUR): | | | | IN THE EVENT THAT AN ACCUMULATION OF DAW IN A BAG COULD HAVE GREATER THAN | | SAFE MASS OF U-235, THE ACCUMULATION OF LIQUID COULD MODERATE THIS MASS. | | | | CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): | | | | MODERATION (LOST) | | | | MASS (CONTROLLED) | | | | ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS | | LIMIT AND % WORST CASE OF CRITICAL MASS): | | | | LESS THAN 10% U-235 | | | | NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION | | OF THE FAILURES OR DEFICIENCIES: | | | | DRY ACTIVE WASTE (DAW) WAS FOUND IN A SANITARY TRASH BAG WITHOUT HOLES. THE | | NCSA REQUIRES HOLES IN DAW BAGS TO PREVENT THE ACCUMULATION OF MODERATORS | | IN THE BAG. | | | | CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: | | | | THE DAW WAS REMOVED AND PROPERLY DISPOSED OF. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED. DOE SITE REPRESENTATIVE WAS | | INFORMED. | +------------------------------------------------------------------------------+