U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/02/97 - 10/03/97 ** EVENT NUMBERS ** 32318 32924 32932 32978 33019 33020 33021 33022 33023 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32318 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 05/12/97 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 18:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/12/97 | +------------------------------------------------+EVENT TIME: 16:30[EDT]| |NRC NOTIFIED BY: JOSEPH HACKNEY |LAST UPDATE DATE: 10/02/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN 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 N 0 HOT STANDBY | 0 HOT STANDBY | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR FAILURE OF BOTH TRAINS OF AUXILIARY FEEDWATER DUE TO | | VORTEXING IN THE AUXILIARY FEEDWATER CONDENSATE STORAGE TANK IF THE TANK IS | | NOT ISOLATED BEFORE REACHING THE 17-INCH LEVEL. | | | | MCGUIRE CALCULATION MCC-1223.42-00-0037 INDICATES THE POTENTIAL FOR | | VORTEXING IN THE AUXILIARY FEEDWATER CONDENSATE STORAGE TANK IF THE TANK IS | | NOT ISOLATED PRIOR TO REACHING THE 17-INCH LEVEL. THE VORTEXING COULD | | INTRODUCE AIR INTO THE AUXILIARY FEEDWATER PUMP SUCTION RESULTING IN A | | FAILURE OF BOTH TRAINS OF AUXILIARY FEEDWATER TO PERFORM THEIR SAFETY | | RELATED FUNCTION. | | | | THE LICENSEE HAS IMPLEMENTED COMPENSATORY ACTIONS TO ENSURE SWAPOVER OF | | AUXILIARY FEEDWATER TO AN ASSURED RAW WATER SYSTEM PRIOR TO REACHING THE | | 17-INCH TANK LEVEL. THE LICENSEE PLANS TO KEEP THIS COMPENSATORY ACTION IN | | PLACE UNTIL AN ENGINEERING EVALUATION DETERMINES THAT VORTEXING DOES NOT | | COMPROMISE AUXILIARY FEEDWATER OPERABILITY OR UNTIL IMPLEMENTATION OF A | | SYSTEM MODIFICATION. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE ON 06/09/97 AT 1634 FROM WASHAM TO GOULD * * * | | | | THE LICENSEE REPORTED THAT THE POTENTIAL VORTEXING INVOLVING THE AUXILIARY | | FEEDWATER CONDENSATE STORAGE TANK HAS BEEN RESOLVED BY CALCULATIONS. THE | | RESULTS OF THIS ANALYSIS INDICATE THAT A VORTEX IN THE AUXILIARY FEEDWATER | | CONDENSATE STORAGE TANK WILL NOT IMPACT OPERABILITY OF THE AUXILIARY | | FEEDWATER PUMPS. COMPENSATORY ACTIONS ARE NO LONGER NEEDED TO MITIGATE | | THIS ISSUE. ADDITIONAL CALCULATIONS ARE BEING PERFORMED TO EVALUATE OTHER | | MECHANISMS THAT MAY AFFECT AUXILIARY FEEDWATER OPERABILITY. THE | | COMPENSATORY ACTIONS FOR SWAPOVER WILL REMAIN IN PLACE UNTIL OTHER | | MECHANISMS THAT AFFECT PAST OPERABILITY ARE EVALUATED BY ENGINEERING | | ANALYSIS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE OPERATIONS OFFICER | | NOTIFIED THE R2DO (PAUL FREDRICKSON). | | | | * * * UPDATE ON 10/02/97 AT 1538 FROM JOHN WASHAM TO TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | SITE ENGINEERING PERSONNEL HAVE COMPLETED THE ANALYSES AND CONCLUDED THAT A | | POTENTIAL AIR VOID IN THE [AUXILIARY FEEDWATER] SUCTION HEADER CANNOT | | AFFECT [AUXILIARY FEEDWATER] PUMP OPERABILITY. [THE LICENSEE DETERMINED | | THAT] THE [AUXILIARY FEEDWATER] SYSTEM WAS PAST OPERABLE AND WAS CAPABLE OF | | PERFORMING ITS [INTENDED] SAFETY FUNCTION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R2DO (MCALPINE). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32924 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 09/14/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 10:49 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/14/97 | +------------------------------------------------+EVENT TIME: 07:11[EDT]| |NRC NOTIFIED BY: DEVIN PRICE |LAST UPDATE DATE: 10/02/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC START OF SACS PUMP DUE TO IMPROPERLY PERFORMED PROCEDURE | | | | THE 'A' SAFETY AUXILIARIES COOLING SYSTEM (SACS) PUMP AUTOMATICALLY STARTED | | DUE TO AN INTERLOCK WITH ITS ASSOCIATED TECHNICAL SUPPORT CENTER (TSC) | | CHILLED WATER CIRCULATING PUMP. THE LICENSEE WAS IN THE PROCESS OF SWAPPING | | OVER TO THE 'C' SACS PUMP AT THE TIME OF THE EVENT. THE INTERLOCK IS | | DESIGNED TO PROVIDE SACS COOLING WATER TO THE TSC CHILLER IF IT IS RUNNING. | | THE LICENSEE REPORTED THAT THE EVENT WAS CAUSED BY AN IMPROPERLY PERFORMED | | PUMP SWAP. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | * * * 1251 OCTOBER 2, 1997, UPDATE FROM FAULKNER RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. BASED UPON FURTHER | | REVIEW, THE LICENSEE DETERMINED THAT THE SIGNAL PROVIDED BY THE TSC CHILLED | | WATER CIRCULATING PUMP TO THE SACS PUMP WAS NOT AN ENGINEERED SAFETY | | FEATURE (ESF) SIGNAL. THEREFORE, THE LICENSEE BELIEVES THAT THE 'A' SACS | | PUMP START WAS NOT CAUSED BY AN ESF SIGNAL AND THAT THIS EVENT IS NOT | | REPORTABLE IN ACCORDANCE WITH 10 CFR 50.72(b)(2)(ii). | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE R1DO (KELLY) | | WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32932 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 09/16/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 01:20 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/15/97 | +------------------------------------------------+EVENT TIME: 23:11[EDT]| |NRC NOTIFIED BY: FAULKNER |LAST UPDATE DATE: 10/02/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STATION SERVICE WATER (SSW) PUMP AUTOMATICALLY STARTED DURING TESTING. | | | | THE FOLLOWING IS TEXT FROM A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "THE 'D' SSW PUMP AUTO STARTED FROM A SUSPECTED LOW FLOW SIGNAL WHILE | | RESTORING THE PUMPS CONTROL LOGIC FROM THE 'EMERGENCY TAKEOVER' MODE OF | | OPERATION TO THE 'NORMAL' MODE. THE REMOTE SHUTDOWN SYSTEM SURVEILLANCE | | TEST WAS IN PROGRESS. THIS WAS AN UNEXPECTED RESPONSE. SERVICE WATER PUMP | | LOW FLOW AUTO START IS AN ESF SIGNAL LISTED IN THE HOPE CREEK UFSAR TABLE | | 7.3.15. THE PUMP WAS SHUT DOWN BY OPERATORS IN THE CONTROL ROOM. | | TROUBLESHOOTING IS IN PROGRESS TO DETERMINE THE CAUSE." | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | * * * 1251 OCTOBER 2, 1997, UPDATE FROM FAULKNER RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. BASED UPON FURTHER | | REVIEW, THE LICENSEE DETERMINED THAT THE SERVICE WATER PUMP LOW FLOW | | AUTOMATIC START WAS NOT AN ENGINEERED SAFETY FEATURE (ESF) SIGNAL. | | THEREFORE, THE LICENSEE BELIEVES THAT THE 'D' SERVICE WATER PUMP START WAS | | NOT CAUSED BY AN ESF SIGNAL AND THAT THE EVENT IS NOT REPORTABLE IN | | ACCORDANCE WITH 10 CFR 57.70(b)(2)(ii). | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE R1DO (KELLY) | | WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32978 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 09/22/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 21:15 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 09/22/97 | +------------------------------------------------+EVENT TIME: 18:25[EDT]| |NRC NOTIFIED BY: BRIAN STETSON |LAST UPDATE DATE: 10/02/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EMERGENCY DIESEL GENERATOR (EDG) DIVISION 2 RECEIVED AN INVALID START | | SIGNAL DURING TESTING. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "THE DIVISION 2 DIESEL GENERATOR WAS BEING RUN TO SUPPORT TESTING. DUE TO | | THE NATURE OF THE TESTS, A JUMPER HAD BEEN INSTALLED TO OVERRIDE THE | | NON-EMERGENCY TRIPS. | | | | THE DIESEL GENERATOR CONTROL SWITCH WAS TAKEN TO STOP TO SHUT DOWN THE | | DIESEL, AND DECREASING RPMs WERE OBSERVED. THE DIESEL GENERATOR CONTROL | | SWITCH WAS RETURNED TO AUTO, AND THE DIESEL RETURNED TO RATED SPEED. | | | | THE AIR JUMPER WHICH HAD BEEN INSTALLED TO SUPPORT TESTING ACTED AS A [LOSS | | OF COOLANT ACCIDENT] SIGNAL. THIS IS AN INVALID SIGNAL, BUT [IT] DID CAUSE | | THE DIESEL TO RETURN TO RATED SPEED." | | | | THE LICENSEE IS CONTINUING AN INVESTIGATION TO DETERMINE ROOT CAUSE AND | | NOTED THAT THIS INVALID START SIGNAL HAD OCCURRED IN THE PAST DURING | | TESTING. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * 1512 OCTOBER 2, 1997, UPDATE FROM MLACHAK RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. THE LICENSEE HAS | | DETERMINED THAT THIS WAS NOT AN ENGINEERED SAFETY FEATURE ACTUATION AND | | THAT THIS EVENT WAS NOT REPORTABLE DUE TO THE CONDITIONS FOR THE TEST, THE | | LACK OF A VALID INITIATION SIGNAL, AND ISOLATION FROM EMERGENCY CORE | | COOLING SYSTEM EQUIPMENT. | | | | THE EDG RESTARTED BECAUSE IT DID NOT COAST TO A LOW ENOUGH RPM FOR | | COMBUSTION TO STOP. THE LICENSEE STATED THAT THIS SHOULD HAVE BEEN | | IDENTIFIED IN THE PROCEDURE. AFTER THE EDG WAS OPERATING NORMALLY, THE EDG | | CONTROL SWITCH WAS HELD IN THE 'STOP' POSITION UNTIL THE EDG REACHED ZERO | | RPM. THE EDG SHUTDOWN AS EXPECTED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R3DO (JACOBSON). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33019 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 10/02/97 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 09:55 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/02/97 | +------------------------------------------------+EVENT TIME: 07:14[EDT]| |NRC NOTIFIED BY: FRANK SOENS |LAST UPDATE DATE: 10/02/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE KELLY RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 MANUALLY TRIPPED THE REACTOR FROM 100% POWER FOLLOWING THE LOSS OF | | BOTH OPERATING STEAM GENERATOR FEED PUMPS. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AN UNDETERMINED PROBLEM CAUSED BOTH STEAM GENERATOR FEED PUMPS TO TRIP DUE | | TO LOW SUCTION PRESSURE. OPERATORS MANUALLY TRIPPED THE REACTOR FROM 100%. | | AN AFW AUTOSTART SIGNAL WAS AUTOMATICALLY GENERATED FROM THE SGFW PUMPS | | TRIP. INITIALLY, STEAM DUMPS TO CONDENSER WORKED AS DESIGNED. WHEN THE | | PLANT COOLED TO < 543øF, THE STEAM DUMPS BLOCKED AND FAILED TO UNBLOCK WHEN | | TEMPERATURE WAS IMMEDIATELY RESTORED. OPERATORS MANUALLY CONTROLLED | | TEMPERATURE USING THE MS-10's (ATMOSPHERIC S/G RELIEFS). THE '22' S/G | | STEAM FLOW CHANNEL II BISTABLE ILLUMINATED AND LATER CLEARED. THE '22' AND | | '24MS167' (MAIN STEAMLINE ISOLATION VALVES) INDICATED NOT FULL OPEN; | | OPERATORS INITIATED AN OPEN SIGNAL AND LOCALLY VERIFIED THE VALVES WERE | | 100% OPEN. POST TRIP COOLDOWN WAS ACCEPTABLE AND THE MSIV's REMAIN OPEN. | | '2R46A-E (MAIN STEAM LINE RAD MONITORS) WERE INOPERABLE PRIOR TO THE TRIP | | DUE TO SCHEDULED MAINTENANCE. ALL OTHER IMPORTANT AND SAFETY-RELATED | | EQUIPMENT OPERATED AS DESIGNED." | | | | ALL CONTROL RODS FULLY INSERTED FOLLOWING THE MANUAL TRIP. NONE OF THE | | PRIMARY OR SECONDARY SAFETIES LIFTED DURING THE TRANSIENT. IN ADDITION, | | THERE WAS NO MAINTENANCE WORK IN PROGRESS PRIOR TO THE LOSS OF BOTH STEAM | | GENERATOR FEED PUMPS. AFTER THE STEAM DUMPS BLOCKED, RCS TEMPERATURE | | RETURNED TO 548øF WHICH SHOULD HAVE RESULTED IN UNBLOCKING OF THE STEAM | | DUMPS AT 547øF (NO LOAD Tave). THE '22' STEAM FLOW CHANNEL II WAS DECLARED | | INOPERABLE AFTER INDICATING BETWEEN 20-30% STEAM FLOW FOLLOWING THE TRIP | | (OTHER CHANNELS INDICATED APPROXIMATELY 5%). UNIT 2 IS CURRENTLY STABLE | | WITH BOTH AUXILIARY MOTOR-DRIVEN FEEDWATER PUMPS IN SERVICE REJECTING DECAY | | HEAT VIA THE ATMOSPHERIC DUMPS. (THERE IS NO INDICATION OF STEAM GENERATOR | | TUBE LEAKAGE.) | | | | THE LICENSEE PLANS TO INFORM THE LOWER ALLOWAYS CREEK TOWNSHIP AND HAS | | INFORMED THE NRC RESIDENT INSPECTOR. A PRESS RELEASE IS ALSO PLANNED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33020 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 10/02/97 | |UNIT: [1] [ ] [ ] STATE: FL |NOTIFICATION TIME: 14:13 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 10/02/97 | +------------------------------------------------+EVENT TIME: 12:50[EDT]| |NRC NOTIFIED BY: HURCHALLA |LAST UPDATE DATE: 10/02/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION REGARDING THE DISCOVERY OF CONTAMINATED MATERIAL | | DELIVERED TO THE SITE FOR AN UPCOMING OUTAGE | | | | AN EQUIPMENT TRAILER FROM POWER CUTTING, INC., USED FOR NORMAL | | NON-RADIOACTIVE MATERIALS TRANSPORTATION CONTAINED A WELDING LEAD WITH | | 30,000 DISINTEGRATIONS PER MINUTE (DPM) FIXED CONTAMINATION. OTHER ITEMS | | HAVE BEEN FOUND DURING THESE SURVEYS INCLUDING A TOOL FROM MAMMOET WHICH | | HAD APPROXIMATELY 1,000 DPM SMEARABLE (LOOSE) CONTAMINATION. THE TRAILER, | | TOOLS, AND OTHER MATERIALS HAVE BEEN MOVED TO A RADIOACTIVE MATERIALS | | STORAGE AREA, AND THE VENDORS HAVE BEEN NOTIFIED. | | | | AT 1250 ON OCTOBER 2, 1997, THE LICENSEE NOTIFIED THE STATE OF FLORIDA, | | DEPARTMENT OF HEALTH, BUREAU OF RADIATION CONTROL. THE LICENSEE ALSO | | NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33021 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GENERAL ELECTRIC CO. |NOTIFICATION DATE: 10/02/97 | | RXTYPE: ADVANCED FUEL R&D AND PILOT PLANTS |NOTIFICATION TIME: 15:44 [ET]| |COMMENTS: HOT CELL R&D |EVENT DATE: 10/01/97 | | |EVENT TIME: 14:00[PDT]| | |LAST UPDATE DATE: 10/02/97 | | CITY: PLEASANTON REGION: 4 +-----------------------------+ | COUNTY: ALAMEDA STATE: CA |PERSON ORGANIZATION| |LICENSE#: SNM-960 AGREEMENT: Y |BILL JONES RDO | | DOCKET: 07000754 |MIKE BELL, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: BENTON MURRAY | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |KBBE 70.50(b)(2)(i) ACCID MIT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INSTRUMENT FAILURE AT THE GENERAL ELECTRIC VALLECITOS NUCLEAR CENTER (A HOT | | CELL/MATERIALS HANDLING FACILITY) (24-HOUR REPORT) | | | | DURING THE PERFORMANCE OF A MONTHLY SOURCE CHECK ON THE RADIOACTIVE | | MATERIALS LAB CRITICALITY DETECTOR SYSTEM, THE ALARM FAILED TO SOUND WHEN | | THE SOURCE WAS PLACED NEXT TO THE DETECTOR (WHICH WAS LOCATED IN THE POOL | | OPERATING AREA). AS A RESULT, THE DETECTOR WAS REPLACED, AND THE REMOVED | | DETECTOR RESPONDED PROPERLY DURING SUBSEQUENT SHOP TESTING ON ANOTHER | | METER. IT WAS THEN NOTICED THAT THE REMOTE METER WAS STICKING. THIS 0 TO | | 10 æA METER WAS LOCATED IN A CLEAN OPERATING AREA NEAR THE OFFICES. IT HAS | | A MECHANICAL TRIP SETPOINT AT 3.1 æA AND NORMALLY READS 4.5 æA WITH THE | | CHECK SOURCE AT THE DETECTOR. THE LICENSEE STATED THAT THE METER HAS TO | | FUNCTION PROPERLY FOR THE APPROPRIATE ALARM TO COME IN. AS A RESULT, THE | | METER HAS BEEN CHANGED OUT AND TAKEN TO THE SHOP FOR INSPECTION. THE | | LICENSEE HAS SUSPENDED ALL FUEL MOVEMENT UNTIL IT CAN BE DETERMINED THAT | | THE NEW METER IS FUNCTIONING PROPERLY. | | | | THERE ARE VERY LOW QUANTITIES (APPROXIMATELY 1,760 GRAMS) OF FISSILE | | MATERIAL (PRIMARILY IRRADIATED UO2) LOCATED IN THE BUILDING. DURING THE | | MONTH IN QUESTION, THERE WERE APPROXIMATELY 12 FUEL MOVEMENTS, AND THE | | LARGEST AT ANY ONE TIME WAS ABOUT 162 GRAMS. IN ADDITION TO THE | | CRITICALITY DETECTOR, THERE ARE AREA RADIATION MONITORS THROUGHOUT THE | | AREA. DURING THIS TIME FRAME, NONE OF THE MONITORS ALARMED, AND THERE WERE | | NO UNUSUAL PERSONNEL RADIATION EXPOSURES DETECTED ON WORKERS' SELF READING | | DOSIMETERS. THIS INDICATED THAT THERE WERE NO UNDETECTED ACCIDENTAL | | PROBLEMS. | | | | THE LICENSEE NOTIFIED THE NRC REGION 4 FIELD OFFICE (CHUCK HOOKER). (REFER | | TO THE HOO LOG FOR A SITE CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33022 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 10/02/97 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 17:43 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/02/97 | +------------------------------------------------+EVENT TIME: 16:00[CDT]| |NRC NOTIFIED BY: GREGORY BRYAN |LAST UPDATE DATE: 10/02/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL JONES 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT THE MINIMUM GAP IN THE CENTRIFUGAL CHARGING PUMP (CCP) COLD | | LEG INJECTION THROTTLE VALVES FOR BOTH UNITS IS LESS THAN THE FINE MESH | | SIZE IN THE CONTAINMENT RECIRCULATION SUMP SCREENS | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "IN EVALUATING ONE-ERR-97-000719, IT WAS DISCOVERED THAT THE MINIMUM GAP IN | | THE CCP COLD LEG INJECTION THROTTLE VALVES FOR BOTH UNITS ([VALVES] | | 1/2SI-8810A/B/C/D) IS LESS THAN THE FINE MESH SIZE IN THE CONTAINMENT | | [RECIRCULATION] EMERGENCY SUMP SCREEN[S] (i.e., 0.115 INCH[ES]). THIS IS | | CONTRARY TO THE REQUIREMENTS OF [REGULATORY GUIDE] 1.82, AS COMMITTED IN | | THE [FINAL SAFETY ANALYSIS REPORT], THAT THE MINIMUM RESTRICTIONS IN THE | | SYSTEM SERVED BY THE SUMP BE THE BASIS FOR THE SIZE OF THE MESH. | | ONE-ERR-96-000166 (USING ATTACHED WPT-15748) ESTIMATED THE PERCENT OPEN | | POSITION OF THE THROTTLE VALVES BASED ON THE UNIT 1 PIPING LAYOUT AND | | RELATIVE BRANCH POSITIONS ALONG WITH THE RECORDED VALVE POSITIONS FROM THE | | PRE-OP[ERATIONAL] TESTING AND CONCLUDED THAT ONLY 8810D HAD A MINIMUM GAP | | POTENTIALLY SLIGHTLY LESS THAN 0.115 INCHES. IT ESTIMATED THAT 14% OPEN | | (1.4 TURNS) WOULD EQUATE TO [A] 0.115-INCH GAP. DATA TAKEN ON VALVE | | POSITION VERSUS MINIMUM GAP SHOWS THAT THE MINIMUM GAP FOR THIS TYPE OF | | VALVE IS SMALLER THAN PREVIOUSLY EVALUATED. THE MINIMUM GAP FOR BOTH | | VALVES 8810C AND 8810D COULD BE LESS THAN 0.0625 INCHES. AFTER DISCUSSIONS | | WITH REGULATORY AFFAIRS, IT WAS CONSERVATIVELY DETERMINED THAT THIS | | CONDITION IS OUTSIDE THE DESIGN BASIS AND [IS, THEREFORE,] REPORTABLE UNDER | | 10 CFR 50.72(b)(1)(ii)(B)." | | | | "EMERGENCY CORE COOLING OPERABILITY IS NOT AFFECTED. DEBRIS MOST LIKELY TO | | PASS THROUGH THE EMERGENCY SUMP SCREEN THAT COULD BE LARGER THAN THE | | THROTTLE VALVE OPENINGS WOULD LIKELY BE FRAGMENTED BY THE [RESIDUAL HEAT | | REMOVAL (RHR)] AND CCP PUMPS. HIGH DIFFERENTIAL PRESSURE AT THE THROTTLE | | VALVE WOULD BE EXPECTED TO FORCE THE DEBRIS THROUGH THE VALVE. THEREFORE, | | CLOGGING WOULD NOT BE EXPECTED TO OCCUR. IN ADDITION, FOR [A] LARGE BREAK | | [LOSS OF COOLANT ACCIDENT (LOCA)], MOST OF THE LONG-TERM RECIRCULATION FLOW | | IS PROVIDED BY THE RHR SYSTEM INJECTION LINES AND DOES NOT PASS THROUGH ANY | | THROTTLE VALVES. RHR FLOW ITSELF SHOULD BE ADEQUATE FOR LONG-TERM CORE | | COOLING. FOR [A] SMALL BREAK LOCA, AUXILIARY FEEDWATER WOULD ALSO BE | | INDEPENDENTLY AVAILABLE FOR CORE COOLING. THEREFORE, THE EMERGENCY CORE | | COOLING FUNCTION CAN BE EXPECTED TO PERFORM ITS SAFETY FUNCTION." | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33023 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 10/02/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 22:11 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/02/97 | +------------------------------------------------+EVENT TIME: 19:20[EDT]| |NRC NOTIFIED BY: AL W. HARTNER |LAST UPDATE DATE: 10/02/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE KELLY RDO | |NINF INFORMATION ONLY | | |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 | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR COOLANT SYSTEM (RCS) PRESSURIZER POWER OPERATED RELIEF VALVE OPENED | | FOR UNKNOWN REASONS. | | | | AT 1920, RCS PRESSURIZER POWER OPERATED RELIEF VALVE 2RCS-PCV455C OPENED | | FOR UNKNOWN REASONS. THE REACTOR OPERATOR VERIFIED THAT NO VALID HIGH | | PRESSURE CONDITION EXISTED AND THEN MANUALLY CLOSED THE VALVE. RCS | | PRESSURE REDUCED FROM A NOMINAL VALUE OF 2,235 PSIG TO APPROXIMATELY 2,180 | | PSIG BEFORE THE VALVE WAS CLOSED. RCS PRESSURE RECOVERED TO 2,235 PSIG | | WITHIN 5 MINUTES. | | | | RCS PRESSURE DID NOT REDUCE TO ANY ACTUATION SETPOINTS. TECHNICAL | | SPECIFICATION 3.2.5, "DEPARTURE FROM NUCLEATE BOILING PARAMETERS," WAS | | ENTERED FOR 4 MINUTES WHILE RCS PRESSURE WAS LESS THAN 2,220 PSIA. POWER | | OPERATED RELIEF VALVE MOTOR-OPERATED BLOCK VALVE 2RCS-MOV535 WAS CLOSED AT | | 2018. | | | | THE LICENSEE STATED THAT THERE WERE NO MAINTENANCE OR SURVEILLANCE | | ACTIVITIES ONGOING AT THE TIME OF THIS EVENT. THE LICENSEE'S INVESTIGATION | | INTO THE CAUSE OF THE VALVE OPERATION CONTINUES. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+