U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/30/98 - 02/02/98 ** EVENT NUMBERS ** 33484 33628 33629 33630 33631 33632 33633 33634 33635 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33484 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/02/98 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 13:29 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/02/98 | +------------------------------------------------+EVENT TIME: 13:05[EST]| |NRC NOTIFIED BY: RAY MARTIN |LAST UPDATE DATE: 01/31/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FRANK COSTELLO RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH IMPEDANCE FAULTS THAT COULD IMPAIR ABILITY TO MAINTAIN UNIT IN MODE 3 | | DURING A POSTULATED CONTROL ROOM FIRE IDENTIFIED DURING APPENDIX R REVIEW. | | | | "MILLSTONE UNIT 3 IS MAKING A 4 HOUR NOTIFICATION IAW 50.72(b)(2)(iii) OF | | AN EVENT OR CONDITION THAT ALONE COULD HAVE PREVENTED THE FULFILLMENT OF | | THE SAFETY FUNCTION OF STRUCTURES OR SYSTEMS THAT ARE NEEDED TO SHUTDOWN | | THE REACTOR AND MAINTAIN IT IN A SAFE SHUTDOWN CONDITION. | | | | "DURING A REVIEW OF THE MP3 APPENDIX R ANALYSIS, IT WAS DETERMINED THAT | | DURING A CONTROL ROOM FIRE, INSTRUMENTATION REQUIRED TO MAINTAIN THE PLANT | | IN A STABLE MODE 3 CONDITION MAY NOT HAVE BEEN AVAILABLE AT THE ALTERNATE | | SHUTDOWN STATION. DUE TO THE CONSEQUENCES OF MULTIPLE HIGH IMPEDANCE | | FAULTS ON VARIOUS 120VAC AND 125VDC POWER PANELS, BOTH POWER SUPPLIES TO | | THE FIRE TRANSFER SWITCH PANEL AND THE 'A' AUXILIARY SHUTDOWN PANEL | | INSTRUMENTATION MAY HAVE BEEN LOST. THE MULTIPLE HIGH IMPEDANCE FAULT | | ANALYSIS ASSUMED THAT THESE FAULTED CONDITIONS COULD BE MITIGATED BY | | OPERATION OF CIRCUIT BREAKERS TO CLEAR THE HIGH IMPEDANCE FAULTS. UPON | | REVIEW, IT WAS FOUND THAT SOME ACTIONS REQUIRED REPLACEMENT OF FUSES TO | | VIAC 1 (VITAL INSTRUMENTATION). FUSE REPLACEMENT IS NOT CREDITED TO | | ACHIEVE STABLE MODE 3 CONDITIONS FOR ALTERNATE SHUTDOWN REQUIREMENTS. | | FURTHERMORE, THE ALTERNATE POWER SUPPLY DID NOT HAVE ADEQUATE ISOLATION TO | | PROTECT IT DURING A CONTROL ROOM FIRE. UNDER THE ABOVE CONDITIONS, THE | | ABILITY TO SHUTDOWN AND MAINTAIN THE REACTOR IN A SAFE SHUTDOWN CONDITION | | COULD NOT BE DEMONSTRATED." | | | | THE LICENSEE INFORMED STATE AND LOCAL AGENCIES AND THE NRC RESIDENT | | INSPECTOR. | | | | * * * UPDATE AT 1510 ON 01/31/98 BY JOE RUTTAR TO FANGIE JONES * * * | | | | SUBSEQUENT ANALYSIS BY INTERNAL DESIGN ENGINEERING INDICATES THAT MULTIPLE | | HIGH IMPEDANCE FAULTS ARE UNLIKELY TO OCCUR IN THE PANELS, AND IF THEY WERE | | TO OCCUR, THE UPSTREAM FUSES WOULD NOT BLOW CAUSING A LOSS OF POWER TO THE | | VITAL AND NONVITAL PANELS. BECAUSE POWER WOULD CONTINUE TO BE SUPPLIED TO | | THE FIRE TRANSFER SWITCH AND "A" TRAIN AUXILIARY SHUTDOWN PANELS VIA THE | | VITAL/NONVITAL PANELS, IN THE EVENT OF A CONTROL ROOM FIRE RESULTING IN | | MULTIPLE HIGH IMPEDANCE FAULTS, THE PLANT HAD NOT OPERATED IN A CONDITION | | THAT ALONE COULD HAVE PREVENTED THE FULFILLMENT OF A SAFETY FUNCTION OF | | STRUCTURES OR SYSTEMS THAT ARE NEEDED TO SHUTDOWN THE REACTOR AND MAINTAIN | | IT IN A SHUTDOWN CONDITION, 10CFR50.72(b)(2)(iii). THEREFORE, THIS | | CONDITION IS NOT REPORTABLE AND THIS NOTIFICATION IS RETRACTED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR AS WELL AS STATE AND | | LOCAL GOVERNMENT AGENCIES. THE HEADQUARTERS OPERATION OFFICER NOTIFIED THE | | R1DO (DAVID SILK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33628 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 01/30/98 | |UNIT: [ ] [2] [3] STATE: SC |NOTIFICATION TIME: 12:56 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 01/30/98 | +------------------------------------------------+EVENT TIME: 12:45[EST]| |NRC NOTIFIED BY: MIKE HILL |LAST UPDATE DATE: 01/30/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SURVEILLANCES NOT PERFORMED IN LITERAL COMPLIANCE TO SPECIFIED FREQUENCIES. | | | | THE LICENSEE HAS DETERMINED, AFTER DISCUSSION WITH THE NRC, THAT SEVERAL | | SURVEILLANCES REQUIRED BY TECHNICAL SPECIFICATIONS (TS) HAVE NOT BEEN | | PERFORMED IN ACCORDANCE WITH THE LITERAL INTERPRETATION OF THE SPECIFIED | | FREQUENCIES. CONTRARY TO PHRASES SUCH AS "DURING EACH REFUELING OUTAGE," | | SURVEILLANCES HAVE BEEN PERFORMED ON A "REFUELING OUTAGE" FREQUENCY | | INTERPRETED AT 18 MONTHS WITH A MAXIMUM INTERVAL OF 22 MONTHS AND 15 DAYS. | | DURING CONVERSATIONS WITH THE NRC, IT HAS BEEN REVEALED THAT, BY LITERAL | | INTERPRETATION, APPLICABLE SURVEILLANCES PERFORMED DURING POWER OPERATION | | OR COLD SHUTDOWN DO NOT COUNT AS MEETING THESE REQUIREMENTS. THEREFORE, | | OCONEE IS TECHNICALLY IN NONCOMPLIANCE AND HAS "MISSED" REQUIRED | | SURVEILLANCES RELATED TO THE OPERABILITY OF UNITS 2 & 3 BORATED WATER | | STORAGE TANKS AND THE LOW PRESSURE INJECTION SYSTEMS. THESE COMPONENTS ARE | | REQUIRED FOR EMERGENCY CORE COOLING SYSTEM OPERABILITY. IT IS ANTICIPATED | | THAT FURTHER REVIEW WILL IDENTIFY ADDITIONAL SYSTEMS AFFECTED BY THIS | | ISSUE. | | | | THIS IS A "LITERAL COMPLIANCE" ISSUE, AS ALL AFFECTED SURVEILLANCES HAVE | | BEEN PERFORMED WITHIN THE LAST 22 MONTHS AND 15 DAYS. | | | | OCONEE HAS ENTERED TS 3.0 ON BOTH UNITS 2 & 3 AND IS INITIATING REQUESTS | | FOR DISCRETIONARY ENFORCEMENT PENDING A TS CHANGE TO REDEFINE THE | | "REFUELING OUTAGE" FREQUENCY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1648 ON 01/30/98 BY MIKE HALL TO FANGIE JONES * * * | | | | AT 1530, THE NRC GRANTED ENFORCEMENT DISCRETION PENDING A TS CHANGE TO | | REDEFINE "REFUELING OUTAGE" FREQUENCY. THEREFORE, OCONEE UNITS 2 & 3 | | HAVE EXITED TS 3.0 AND ARE CONTINUING NORMAL OPERATION. OCONEE WILL BE | | SUBMITTING A REQUEST FOR A CHANGE IN TS TO RESOLVE THE LITERAL | | INTERPRETATION ISSUE. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE HEADQUARTERS OPERATIONS OFFICER INFORMED THE R2DO (CHRIS CHRISTENSEN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33629 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 01/30/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 23:20 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 01/30/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:05[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/30/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |BRUCE JORGENSEN RDO | | DOCKET: 0707002 |MARGARET FEDERLINE EO | +------------------------------------------------+RICHARD BARRETT IRD | |NRC NOTIFIED BY: GREG BARCH | | |HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC BULLETIN 91-01 EVENT. | | | | THE LICENSEE DISCOVERED AN EMPTY MOP BUCKET ON ITS SIDE IN A POSTED | | CONTAMINATION AREA OF BUILDING X-710. THE MOP BUCKET DID NOT HAVE THE | | PASSIVE DESIGN FEATURE OF AT LEAST 2 SLOTS CUT INTO PARALLEL SIDES SO THAT | | THE SLOTS WOULD BE NO MORE THAN 1.5 INCHES FROM THE BOTTOM OF THE INTERIOR | | SURFACE OF THE MOP BUCKET. THIS DESIGN FEATURE ASSURES THE LEVEL | | (1.5 INCHES FOR 100% U-235 IN THIS INSTANCE) IS NOT EXCEEDED. THIS | | DISCOVERY CONSTITUTES A VIOLATION OF NUCLEAR CRITICALITY SAFETY APPROVAL | | (NCSA) PLANT 066.A02, CONTINGENCY EVENT B.2.1, CONTROL A, REQUIREMENT #2. | | CONTROL B WAS MAINTAINED THROUGH OUT THE EVENT. THE MOP BUCKET WAS | | RELOCATED TO AN AUTHORIZED LOCATION. FURTHER INVESTIGATION WILL TAKE PLACE | | TO DETERMINE THE CAUSE OF THIS EVENT. | | | | POTENTIAL CRITICALITY PATHWAYS INVOLVED [BRIEF SCENARIO(S) OF HOW | | CRITICALITY COULD OCCUR]: | | EXCEED FILL LIMIT (UNSAFE GEOMETRY) OF THE BUCKET. | | | | CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): | | GEOMETRY, ENRICHMENT. | | | | ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS | | LIMIT AND % WORST CASE OF CRITICAL MASS): | | N/A - MOP BUCKET WAS EMPTY. | | | | NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION | | OF THE FAILURES OR DEFICIENCIES: | | BUCKET WITHOUT PROPER PASSIVE CONTROLS IN UNAUTHORIZED AREA. | | | | CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: | | MOP BUCKET WAS RELOCATED TO AN AREA WHERE STANDARD MOP BUCKETS ARE | | PERMITTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND THE ONSITE DOE | | REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33630 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 01/30/98 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 23:54 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 01/30/98 | +------------------------------------------------+EVENT TIME: 21:55[EST]| |NRC NOTIFIED BY: JEFF KLENK |LAST UPDATE DATE: 01/30/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID SILK RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |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 | 60 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TS REQUIRED SHUTDOWN TO REPAIR HPCI TURBINE EXHAUST ISOLATION VALVE. | | | | "AT 0919 HOURS ON JANUARY 28, 1998, THE LIMERICK GENERATING STATION (LGS) | | UNIT 1 HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM TURBINE EXHAUST LINE | | ISOLATION VALVE, HV-055-1F072, WAS DECLARED INOPERABLE DUE TO THE FAILURE | | OF THE VALVE TO STROKE FULL CLOSED DURING SURVEILLANCE TESTING. THE | | APPLICABLE TECHNICAL SPECIFICATIONS (TS) LIMITING CONDITION FOR OPERATION | | (LCO) ACTION FOR THIS PRIMARY CONTAINMENT ISOLATION VALVE REQUIRED THE | | AFFECTED PENETRATION TO BE ISOLATED WHICH RENDERED THE HPCI SYSTEM | | INOPERABLE. THE HPCI SYSTEM LCO PROVIDES 14 DAYS TO RESTORE HPCI TO | | OPERABLE STATUS OR BE IN HOT SHUTDOWN. HOWEVER, UNIT 1 MUST BE SHUT DOWN | | IN ORDER TO PERFORM REPAIRS ON THIS VALVE. SENIOR PLANT MANAGEMENT ELECTED | | TO SHUT DOWN UNIT 1 AND REPAIR THE VALVE PRIOR TO THE END OF THE 14-DAY | | LCO. AT 2155 HOURS ON JANUARY 30, 1998, THE SHUTDOWN OF LGS UNIT 1 WAS | | INITIATED. ACCORDINGLY, THIS 1-HOUR NOTIFICATION IS BEING MADE PURSUANT TO | | THE REQUIREMENTS OF 10CFR50.72(b)(1)(i)(A) AS THE INITIATION OF A PLANT | | SHUTDOWN REQUIRED BY TS." | | | | THE LICENSEE ESTIMATES COMPLETION OF REPAIRS AND RESTART BY FEBRUARY 4, | | 1998. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33631 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 01/31/98 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 09:58 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 01/31/98 | +------------------------------------------------+EVENT TIME: 03:15[EST]| |NRC NOTIFIED BY: JERE FREEMAN |LAST UPDATE DATE: 01/31/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID SILK RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | PLANT SECURITY EVENT - | | | | SAFEGUARDS SYSTEM DEGRADATION RELATED TO SITE AREA BOUNDARY. IMMEDIATE | | COMPENSATORY MEASURES WERE TAKEN UPON DISCOVERY. | | | | REFER TO HOO LOG BOOK FOR FURTHER DETAILS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33632 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 01/31/98 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 17:53 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 01/31/98 | +------------------------------------------------+EVENT TIME: 16:00[CST]| |NRC NOTIFIED BY: RICH CHEAR |LAST UPDATE DATE: 01/31/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DIVISION 1 EDG DECLARED INOPERABLE DUE TO PROBLEM ASSOCIATED WITH ENGINE | | SYSTEM REPORT #10CFR21-0077 ON DEFECTIVE ENGINE START SOLENOID. | | | | WHILE REVIEWING REPORT #10CFR21-0077 ISSUED BY ENGINE SYSTEMS, INC ON | | AIR START SOLENOID VALVES WITH A DEFECT, THE LICENSEE DETERMINED THAT THE | | DC CALCULATION FOR DIVISION (DIV) 1 DC SYSTEM HAD UTILIZED AN INCORRECT | | CIRCUIT LENGTH IN ESTABLISHING THE VOLTAGE DROP FROM THE DIV 1 DC MCC TO | | THE DIV 1 EMERGENCY DIESEL GENERATOR (EDG) CONTROL PANEL. THE ACTUAL | | VOLTAGE DROP VALUE IS ABOUT 15 VOLTS VERSUS THE CALCULATED 2.67 VOLTS | | AND CAUSES THE VOLTAGE TO BE LOWER THAN THE MINIMUM REQUIRED TO ASSURE | | OPERATION OF ALL EQUIPMENT FED FROM THE DIV 1 EDG CONTROL PANEL. | | | | BASED ON THE ABOVE INFORMATION, THE DIV 1 EDG CONTROL PANEL HAS BEEN | | SUBJECTED TO INSUFFICIENT VOLTAGE TO ENSURE OPERATION OF DIV 1 EDG CONTROL | | CIRCUITRY AND RENDER THE DIV 1 EDG INOPERATIVE. THE PLANT WILL NOT BE | | RESTARTED UNTIL NEW ANALYSIS OR CORRECTION OF THE PROBLEM HAS ENSURED THAT | | THE DIV 1 EDG IS OPERABLE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33633 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 01/31/98 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 18:58 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/31/98 | +------------------------------------------------+EVENT TIME: 18:04[EST]| |NRC NOTIFIED BY: GEORGE STOROLIS |LAST UPDATE DATE: 01/31/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID SILK RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |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 | 70 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH TRAINS OF COMPONENT COOLING WATER AND REACTOR PLANT RIVER WATER | | SYSTEMS DECLARED INOPERABLE PROMPTING UNIT 1 SHUTDOWN. | | | | THE LICENSEE HAS ENTERED TECHNICAL SPECIFICATION (TS) 3.0.3 REQUIRING | | UNIT 1 SHUTDOWN. IT HAS DETERMINED THAT THE SURVEILLANCE REQUIREMENTS OF | | TS 4.7.3.1.b & c AND 4.7.4.1.b & c, VERIFICATION OF VALVE POSITION AND | | STROKE TESTING OF THE COMPONENT COOLING WATER SYSTEM AND REACTOR PLANT | | RIVER WATER SYSTEM MANUAL AND POWER OPERATED VALVES, COULD NOT BE | | COMPLETED. THE UNIT 1 SHUTDOWN AND COOLDOWN WILL CONTINUE TO MODE 5 | | TO ALLOW ACCESS TO THE CONTAINMENT, ENABLING THE COMPLETION OF THE | | SURVEILLANCE. IT IS EXPECTED TO TAKE ABOUT 3 DAYS TO COMPLETE THE | | SHUTDOWN AND SURVEILLANCES IN ORDER TO RESTART UNIT 1. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33634 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 02/01/98 | |UNIT: [ ] [2] [ ] STATE: MN |NOTIFICATION TIME: 10:53 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 02/01/98 | +------------------------------------------------+EVENT TIME: 08:50[CST]| |NRC NOTIFIED BY: PAT RYAN |LAST UPDATE DATE: 02/01/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - DEFECT IN PRIMARY SYSTEM PRESSURE BOUNDARY DISCOVERED WHILE IN MODE 5 - | | | | UNIT 2 IS IN MODE 5 (COLD SHUTDOWN) IN A MAINTENANCE OUTAGE. | | | | DURING WELDING REPAIRS TO THE PART LENGTH INTERMEDIATE CANOPY SEAL WELD, | | THE LICENSEE OBSERVED A DEFECT ON THE MOTOR TUBE BASE OF THIS SAME PART | | LENGTH HOUSING. THE DEFECT IS ABOVE AND REMOTE TO THE WELDING AREA AND | | WAS DISCOVERED WHILE VISUALLY INSPECTING THE WELDING AREA. FURTHER | | CHARACTERIZATION OF THIS DEFECT IN THE PRIMARY SYSTEM PRESSURE BOUNDARY | | IS IN PROGRESS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33635 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 02/01/98 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 12:30 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 02/01/98 | +------------------------------------------------+EVENT TIME: 09:18[EST]| |NRC NOTIFIED BY: GROFF |LAST UPDATE DATE: 02/01/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |ELINOR ADENSAM EO | |AESF 50.72(b)(2)(ii) ESF ACTUATION |RICHARD BARRETT IRD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | A/R Y 96 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTO REACTOR SCRAM FROM 96% POWER DUE TO A MAIN TURBINE TRIP. | | | | AN AUTO REACTOR SCRAM OCCURRED FROM 96% POWER DUE TO A MAIN TURBINE TRIP | | SIGNAL (MAIN TURBINE CONTROL VALVE FAST CLOSURE) CAUSED BY A DISTURBANCE | | ON THE 345 KV MAIN AUX TRANSFORMER (MAT) FOR UNKNOWN REASONS. ON THE 345 | | KV MAT, MAIN GENERATOR OUTPUT BREAKERS "CM", "CF", AND "CT" OPENED. THE | | 345 KV BUSES, HOWEVER, REMAINED ENERGIZED THROUGH THE "DM" AND "DF" | | BREAKERS, THE REDUNDANT OFFSITE POWER FEED. | | | | ALL CONTROL RODS FULLY INSERTED, NO INITIATION OF ECCS OCCURRED, AND NO | | SAFETY/RELIEF VALVES LIFTED. REACTOR VESSEL WATER LEVEL IS STABLE AND | | BEING CONTROLLED IN THE NORMAL OPERATING BAND USING THE MAIN FEEDWATER | | SYSTEM. REACTOR PRESSURE IS BEING CONTROLLED VIA THE MAIN TURBINE BYPASS | | VALVES TO THE MAIN CONDENSER. ALL EMERGENCY DIESEL GENERATORS ARE OPERABLE | | AND AVAILABLE. | | | | FOLLOWING THE SCRAM, REACTOR VESSEL WATER LEVEL INITIALLY DROPPED | | 120 INCHES, CAUSING LEVEL 3 ISOLATIONS. THE FOLLOWING ISOLATIONS OCCURRED: | | GROUP 4 - RHR SHUTDOWN COOLING AND HEAD SPRAY, GROUP 13 - DRYWELL SUMPS AND | | GROUP 15 - TRAVERSING INCORE PROBE SYSTEM. ALL VALVES IN GROUPS 4 AND 15 | | WERE CLOSED PRIOR TO THE ISOLATION SIGNAL, AND GROUP 13 VALVES CLOSED, AS | | DESIGNED. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE 345 KV MAT DISTURBANCE AND | | PLANS TO ISSUE A PRESS RELEASE. AT THE TIME OF THE SCRAM, AN OPERATOR WAS | | PERFORMING THE RELAY HOUSE ALARM TESTS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+