U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/17/97 - 10/20/97 ** EVENT NUMBERS ** 32950 32988 33047 33099 33100 33101 33102 33103 33104 33105 33106 33107 33108 33109 33110 33111 33112 33113 33114 33115 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32950 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 09/17/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 16:55 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 09/17/97 | +------------------------------------------------+EVENT TIME: 14:55[CDT]| |NRC NOTIFIED BY: HALVERSON |LAST UPDATE DATE: 10/17/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ 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 +------------------------------------------------------------------------------+ | THE LICENSEE IS NOT SURE IF INSTRUMENT INACCURACIES WERE INCLUDED IN THE | | CALCULATED TECHNICAL SPECIFICATION VALUE FOR HPCS, LPCS, AND LPCI PUMP | | DIFFERENTIAL PRESSURE. | | | | WHILE IN THE PROCESS OF EVALUATING ECCS ACCEPTANCE CRITERIA IN THE CLINTON | | POWER STATION IMPROVED TECHNICAL SPECIFICATIONS, SURVEILLANCE REQUIREMENTS | | 3.5.1.4 AND 3.5.2.5, IT WAS DETERMINED THAT THE PUMP DIFFERENTIAL PRESSURES | | STATED FOR THE LPCS, LPCI, AND HPCS PUMPS MAY NOT BE CONSERVATIVE FOR THE | | STATED PUMP FLOWS. IT IS CURRENTLY BEING DETERMINED WHETHER THE VALUES | | STATED IN THE TECHNICAL SPECIFICATIONS HAVE BEEN CALCULATED CORRECTLY. | | UNTIL IT CAN BE CLEARLY DETERMINED THAT THE VALUES STATED IN THE TECHNICAL | | SPECIFICATIONS ARE CORRECT, THE LPCS, LPCI, AND HPCS SYSTEMS WILL BE | | CONSIDERED INOPERABLE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE AT 2048 ON 10/17/97 BY FUNKHOUSER, TAKEN BY WEAVER * * * | | | | AN ENGINEERING REVIEW HAS DETERMINED THAT SUFFICIENT MARGIN TO PUMP | | DIFFERENTIAL PRESSURE EXISTS TO SUPPORT THE OPERABILITY OF THE HPCS, LPCI, | | AND LPCS SYSTEMS. BASED ON THE ENGINEERING REVIEW, THIS CONDITION IS NOT A | | REPORTABLE EVENT. THEREFORE, THE LICENSEE IS RETRACTING THIS EVENT. THE | | LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED THE R3DO | | (MCCORMICKBARGER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32988 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/25/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 10:11 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/25/97 | +------------------------------------------------+EVENT TIME: 08:45[EDT]| |NRC NOTIFIED BY: AMY OLVERA |LAST UPDATE DATE: 10/17/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS 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 | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NON-SAFETY RELATED AIR HEADERS LACK OVERPRESSURE PROTECTION. | | | | DURING AN ARCHITECTURAL ENGINEERING INSPECTION, A QUESTION WAS RAISED | | REGARDING THE LACK OF OVERPRESSURE PROTECTION ON THE 20, 50, AND 85-PSIG | | CONTROL AIR HEADERS. THE SPECIFIC CONCERN IS THE POTENTIAL FOR COMMON MODE | | FAILURE OF BOTH TRAINS OF SAFETY-RELATED EQUIPMENT SERVED BY THE AIR | | HEADERS. THE OVERPRESSURE CONDITION IS POSTULATED TO BE CAUSED BY | | REGULATOR FAILURE. | | | | ALTHOUGH SYSTEM REVIEWS HAVE FOUND NO COMPONENT FAILURE MODE WHICH WOULD | | RESULT IN THE DEVICES BEING INCAPABLE OF GOING TO THEIR FAIL-SAFE POSITION, | | A DESIGN CHANGE PACKAGE HAS BEEN PREPARED TO PROVIDE OVERPRESSURE | | PROTECTION ON THE 20, 50 AND 85 PSIG HEADERS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * 1532 OCTOBER 3, 1997, UPDATE FROM OLVERA RECEIVED BY TROCINE * * * | | | | THE LICENSEE PROVIDED THE FOLLOWING EVENT NOTIFICATION UPDATE: | | | | THE ORIGINAL REPORT IDENTIFIED THAT THERE WAS A LACK OF OVERPRESSURE | | PROTECTION ON THE 20, 50, AND 85-PSIG CONTROL AIR HEADERS. UPON FURTHER | | INVESTIGATION OF THIS MATTER, THE LICENSEE HAS IDENTIFIED 22 VALVES ON AIR | | HEADERS WHICH SUPPLY AIR AT A PRESSURE EXCEEDING THE PRESSURE RATINGS OF | | THE VALVE ACTUATORS. TWENTY OF THESE VALVES HAVE ACTUATORS THAT ARE RATED | | FOR 45 PSIG AND ARE ON AIR HEADERS SUPPLYING AIR AT 50 PSIG. TWO VALVES | | HAVE ACTUATORS RATED FOR 55 PSIG AND ARE ON HEADERS SUPPLYING AIR AT 85 | | PSIG. | | | | THE 20 VALVES ON THE 50-PSIG HEADERS ARE ALL FROM THE SAME MANUFACTURER | | WHICH HAS TESTED THIS TYPE OF VALVE TO 60 PSIG. THESE VALVES WILL REMAIN | | ON THEIR CURRENT HEADERS. THE 2 VALVES ON THE 85-PSIG HEADERS WILL EITHER | | BE PLACED ON 50-PSIG HEADERS OR A REGULATOR WILL BE INSTALLED PRIOR TO UNIT | | STARTUP. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R3DO (JACOBSON). | | | | * * * UPDATE AT 1413 ON 10/17/97 BY OLVERA, TAKEN BY WEAVER * * * | | | | THIS UPDATE APPLIES TO THE FIRST UPDATE ONLY AND NOT THE ORIGINAL REPORT. | | VENDOR INFORMATION SHOWS THAT THE 20 VALVES RATED FOR 45 PSIG BUT PLACED ON | | 50 PSIG HEADERS WERE ACTUALLY TESTED BY THE VENDOR AT 60 PSIG. | | | | THE MAINTENANCE AND TESTING RECORDS FOR THE REMAINING 2 VALVES, WHICH ARE | | RATED FOR 55 PSIG AND PLACED ON 85 PSIG HEADERS, WERE REVIEWED. THESE | | VALVES ARE 1-CCR-441 AND 1-ZRV-11. | | | | 1-CCR-441 SUPPLIES COOLING WATER TO 2 CONTAINMENT PENETRATIONS AND IS | | REQUIRED TO CLOSE FOR CONTAINMENT ISOLATION. THE MAINTENANCE RECORDS | | SHOWED THAT THIS VALVE HAS EXPERIENCED DIAPHRAGM FAILURE. EACH FAILURE | | RESULTED IN THE VALVE GOING TO ITS CLOSED (SAFE) POSITION. | | | | 1-ZRV-11 IS A 3-WAY VALVE THAT, WHEN OPEN ALLOWS FIRE PROTECTION WATER TO | | FLOW TO THE SPRINKLER HEADS FOR CHARCOAL FILTERS IN A VENTILATION UNIT. | | WHEN CLOSED, THE VALVE BLOCKS WATER FLOW AND ALLOWS THE SPRINKLER SYSTEM TO | | DRAIN. THE VALVE IS A NORMALLY CLOSED, AIR-TO-OPEN COMPONENT DESIGNED TO | | FAIL CLOSED. 1-ZRV-11 DOES NOT SEE THE 85 PSIG AIR PRESSURE ON A | | CONTINUOUS BASIS. AN UPSTREAM SOLENOID VALVE 1-ZRV-11 ONLY ALLOWS AIR | | PRESSURE TO THE DIAPHRAGM ON INDICATION OF HIGH TEMPERATURE IN THE CHARCOAL | | BED. THIS VALVE HAS NO HISTORY OF PROBLEMS DURING ITS SCHEDULED TESTS | | AND HAS HAD NO HISTORY OF FAILURE. BOTH OF THESE VALVES WILL BE PLACED | | ON 50 PSIG HEADERS PRIOR TO RESTART. | | | | THE LICENSEE HAS CONCLUDED THAT THE VALVES WITH AIR PRESSURE EXCEEDING THE | | VALVE ACTUATOR'S RATING DO NOT CONSTITUTE UNANALYZED CONDITIONS WHICH | | SIGNIFICANTLY IMPACT PLANT SAFETY. THEREFORE, THE FIRST EVENT UPDATE IS | | RETRACTED. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE HOO | | INFORMED THE R3DO (MCCORMICKBARGER). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33047 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 10/08/97 | |UNIT: [ ] [ ] [3] STATE: AZ |NOTIFICATION TIME: 18:34 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 10/07/97 | +------------------------------------------------+EVENT TIME: 18:02[MST]| |NRC NOTIFIED BY: DAN MARKS |LAST UPDATE DATE: 10/17/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE 24-HOUR REPORT DUE TO EXCEEDING LICENSED THERMAL POWER LIMIT | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "AT APPROXIMATELY 1802 MST ON OCTOBER 7, 1997, PALO VERDE UNIT 3 | | EXPERIENCED A BRIEF NONRECURRING POWER INCREASE ASSOCIATED WITH AN | | EQUIPMENT FAILURE, PEAKING AT 102.1% RATED THERMAL POWER. UNIT 3 WAS | | OPERATING AT APPROXIMATELY 100% POWER PRIOR TO THE TRANSIENT. THE TIME | | ABOVE 100% WAS APPROXIMATELY 109 SECONDS. THE TIME ABOVE 102% WAS LESS THAN | | 7 SECONDS. THE SHIFTLY AVERAGE POWER LEVEL DID NOT EXCEED 100%. THE | | TRANSIENT VIOLATED THE UNIT 3 FACILITY OPERATING LICENSE, NPF-74, CONDITION | | 2.C(1) WHICH AUTHORIZES OPERATION TO 100% POWER (3876 MEGAWATTS THERMAL). | | LICENSE CONDITION 2.G REQUIRES REPORTING OF ANY VIOLATION OF THE | | REQUIREMENTS CONTAINED IN SECTION 2.C OF THE LICENSE. | | | | THE MINIMUM REACTOR COOLANT COLD LEG TEMPERATURE DURING THE TRANSIENT WAS | | APPROXIMATELY 551.7øF, REMAINING ABOVE THE TECHNICAL SPECIFICATION (TS) | | LIMIT FOR OPERATION (TS 3.2.6) AND THE MINIMUM TEMPERATURE FOR CRITICALITY | | (TS 3.1.1.4). MINIMUM PRESSURIZER PRESSURE DURING THE TRANSIENT WAS | | APPROXIMATELY 2224 PSIA, REMAINING WITHIN THE NORMAL OPERATING RANGE (TS | | 3.2.8). PRESSURIZER LEVEL REMAINED WITHIN TS LIMITS THROUGHOUT THE | | TRANSIENT (TS 3.4.3.1). SINCE REGULATING GROUP 5 CEAs WERE BELOW THE POWER | | DEPENDENT INSERTION LIMITS (PDIL, <108 INCHES WITHDRAWN) FROM 1821 TO 1830 | | MST, SHUTDOWN MARGIN WAS VERIFIED ADEQUATE TO COMPLY WITH SURVEILLANCE | | REQUIREMENT 4.1.1.2.1.b. | | | | THE CAUSE OF THE TRANSIENT WAS A FAILED BELLOWS IN 3JMTNPSL0513, A PRESSURE | | SWITCH THAT MONITORS PRESSURE IN CROSSAROUND PIPING FROM THE MOISTURE | | SEPARATOR REHEATER TO LOW PRESSURE TURBINE 'A'. THE SWITCH FAILURE CAUSED | | THE 2ND STAGE REHEATER DRAIN TANK HIGH LEVEL CONTROL VALVES TO OPEN. THE | | HIGH LEVEL CONTROL VALVES OPENING RESULTED IN STEAM DUMPING DIRECTLY TO THE | | CONDENSER, AN EXCESS STEAM DEMAND TRANSIENT. THE OPERATING CREW REDUCED | | TURBINE LOAD TO COMPENSATE FOR THE STEAM DEMAND, RETURNING REACTOR POWER | | BELOW 100% AND ISOLATED 2ND STAGE REHEAT. | | | | THIS EVENT IS CATEGORIZED AS AN EXCESS STEAM DEMAND EVENT. THIS IS AN | | ANTICIPATED OPERATIONAL OCCURRENCE (AOO), OR MODERATE FREQUENCY EVENT, AND | | IS BOUNDED BY THE ANALYSIS PRESENTED IN UFSAR 15.1.4, CASE 1 (INADVERTENT | | OPENING OF AN ATMOSPHERIC DUMP VALVE WITH NO SINGLE FAILURE). AN | | EXAMINATION OF THE DATA SHOWED THAT THE POWER EXCURSION, RCS PRESSURE AND | | TEMPERATURE TRENDS WERE NOT OF SUFFICIENT MAGNITUDE TO CHALLENGE THE DNBR | | OR LHR LIMITS, AND THAT NO OTHER SAFETY LIMITS (PRIMARY/SECONDARY PRESSURE | | LIMITS, SHUTDOWN MARGIN) APPEAR TO HAVE BEEN CHALLENGED. | | | | NO ESF OR REACTOR PROTECTION SYSTEM ACTUATIONS OCCURRED, AND NONE WERE | | REQUIRED. | | | | THE EVENT DID NOT RESULT IN ANY CHALLENGES TO THE FISSION PRODUCT BARRIER | | OR RESULT IN ANY RELEASES OF RADIOACTIVE MATERIALS. THERE WERE NO ADVERSE | | SAFETY CONSEQUENCES OR IMPLICATIONS AS A RESULT OF THIS EVENT. THE EVENT | | DID NOT ADVERSELY AFFECT THE SAFE OPERATION OF THE PLANT OR HEALTH AND | | SAFETY OF THE PUBLIC." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1650 ON 10/17/97 BY DAN MARKS, TAKEN BY WEAVER * * * | | | | PALO VERDE ENGINEERING PERSONNEL HAVE EVALUATED THE TRANSIENT AND | | DETERMINED THAT THE PEAK POWER DID NOT EXCEED 101.9%. UNIT 3 WAS OPERATING | | AT APPROXIMATELY 100% POWER PRIOR TO THE TRANSIENT. THE TIME ABOVE 100% | | WAS APPROXIMATELY 109 SECONDS. THE SHIFTLY AVERAGE POWER LEVEL DID NOT | | EXCEED 100%. GUIDANCE PROVIDED IN NRC INSPECTION PROCEDURE 61706, | | PARAGRAPH 03.02d, STATES THAT IT IS PERMISSIBLE TO EXCEED THE FULL STEADY | | STATE LICENSED POWER LEVEL BY AS MUCH AS 2% FOR AS LONG AS 15 MINUTES. | | THEREFORE, THE TRANSIENT DID NOT VIOLATE THE UNIT 3 FACILITY OPERATING | | LICENSE, NPF-74, CONDITION 2.C(1) WHICH AUTHORIZES OPERATION TO 100% POWER | | (3876 MEGAWATTS THERMAL). | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED OF THE RETRACTION. THE HOO | | NOTIFIED THE R4DO (STETKA). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33099 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 10/17/97 | |UNIT: [ ] [2] [ ] STATE: TN |NOTIFICATION TIME: 10:59 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/17/97 | +------------------------------------------------+EVENT TIME: 10:00[EDT]| |NRC NOTIFIED BY: HAYS |LAST UPDATE DATE: 10/17/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | |CASTO IAT | | |McPEEK IAT | | |DAVIDSON IAT | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANT SECURITY EVENT. | | | | POTENTIAL EQUIPMENT TAMPERING. REFER TO THE HOO LOG FOR ADDITIONAL DETAILS. | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33100 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 10/17/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 12:46 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/17/97 | +------------------------------------------------+EVENT TIME: 11:45[EDT]| |NRC NOTIFIED BY: CHRISTOPHER HYNES |LAST UPDATE DATE: 10/17/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SOME CHEMICAL AND VOLUME CONTROL SYSTEM PIPE SUPPORTS WERE FOUND THAT DO | | NOT MEET CODE LIMITS. | | | | EVALUATIONS TO DOCUMENT ORIGINAL STONE & WEBSTER ENGINEERING CORPORATION | | PIPE SUPPORT DESIGN DEFICIENCIES ON SMALL BORE PIPING, FOUND THREE (3) | | SUPPORTS ON THE CHEMICAL AND VOLUME CONTROL SYSTEM (CVCS) BEYOND THE | | AMERICAN INSTITUTE OF STEEL CONSTRUCTION (AISC) CODE LIMITS AND THE | | OPERABILITY ALLOWANCE OF GENERIC LETTER (GL) 91-18. THIS PLACED THE | | ASSOCIATED SUPPORTS IN AN UNANALYZED CONDITION. | | | | THE THREE SUPPORTS WERE ON THE LOOP FILL LINES, REACTOR COOLANT PUMP SEAL | | LEAK-OFF LINES, AND THE SEAL LEAK-OFF RELIEF PIPING TO THE PRESSURIZER | | RELIEF TANK. | | | | IN ADDITION, SUPPORT PS-2 ON THE CVCS LETDOWN LINE, UPSTREAM OF THE | | NON-REGENERATIVE HEAT EXCHANGER HAS BEEN IDENTIFIED AS NOT MEETING THE | | ORIGINAL AISC AND THE AMERICAN NATIONAL STANDARDS INSTITUTE (ANSI) DESIGN | | REQUIREMENTS. THE SUPPORT IS CONSIDERED WITHIN THE GL 91-18 OPERABILITY | | LIMITS, BUT OUTSIDE ITS ORIGINAL DESIGN BASIS. | | | | A DESIGN CHANGE PACKAGE (DCP) 2298 WAS INITIATED TO MODIFY THE LETDOWN LINE | | SUPPORT. THE OTHER THREE SUPPORTS WERE MODIFIED IN JULY, 1997 BY DCPs 2263 | | AND 2264, AND ARE NOW MEETING DESIGN REQUIREMENTS. ADDITIONAL EVALUATIONS | | OF SIMILAR SUPPORTS ARE ONGOING. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33101 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 10/17/97 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 15:17 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 10/17/97 | +------------------------------------------------+EVENT TIME: 13:00[CDT]| |NRC NOTIFIED BY: RICK PARLATO |LAST UPDATE DATE: 10/17/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER 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 +------------------------------------------------------------------------------+ | RCP SEAL WATER RETURN LINES COULD BE OVER STRESSED DURING CERTAIN EVENTS | | | | THE UNIT 1 SEAL WATER RETURN LINES FROM THE REACTOR COOLANT PUMPS TO THE | | CONTAINMENT PENETRATION MAY BE OVERSTRESSED DURING LOSS OF SEAL COOLANT | | EVENTS SUCH AS STATION BLACKOUT OR APPENDIX R SITUATIONS. WESTINGHOUSE HAS | | REVISED ITS CALCULATIONS FOR PRESSURES AND TEMPERATURES OF THIS PIPING | | BASED ON PLANT SPECIFIC PIPING AND SUPPORT CONFIGURATIONS. THE UNIT 2 | | EVALUATION REMAINED WITHIN OPERABILITY LIMITS. THE OVERSTRESSED CONDITION | | CANNOT OCCUR DURING CURRENT PLANT CONDITIONS (COLD SHUTDOWN). | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33102 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 10/17/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 16:00 [ET]| |RX TYPE: [1] CE |EVENT DATE: 10/17/97 | +------------------------------------------------+EVENT TIME: 14:35[CDT]| |NRC NOTIFIED BY: ERICK MATZKE |LAST UPDATE DATE: 10/17/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA 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 +------------------------------------------------------------------------------+ | NO ANALYSIS EXISTS FOR THE STATION BATTERIES' CAPACITY DURING DBAs | | | | IN RESPONSE TO THE 10 CFR 50.54f LETTER OF 10/9/97, THE FOLLOWING | | STATEMENTS WERE NOTED IN THE LICENSEE'S UPDATED SAFETY ANALYSIS REPORT | | (USAR). "THE CAPACITY OF THE STORAGE BATTERIES IN EACH OF THE TWO | | INDEPENDENT SYSTEMS IS ADEQUATE TO SUPPLY CONTINUOUS CONTROL POWER, AND | | INSTRUMENTATION REQUIRED FOR SAFETY FOR 8 HOURS WITHOUT OPERATION OF THE | | BATTERY CHARGERS." AND "THE CAPACITY OF THE STORAGE BATTERIES IN THE TWO, | | SEPARATE DC SYSTEMS IS ADEQUATE FOR UP TO 8 HOURS OPERATION OF CONTROL AND | | INSTRUMENTATION DEVICES REQUIRED IN THE EVENT OF A DBA, OR FOR REACTOR | | SHUTDOWN AND STANDBY, WITHOUT BATTERY CHARGER OPERATION." | | | | A SEARCH WAS CONDUCTED TO DETERMINE WHICH CALCULATION OR CALCULATIONS | | DEMONSTRATED THAT THESE STATEMENTS WERE TRUE. THE PREVIOUSLY MENTIONED | | STATEMENTS HAVE BEEN IN THE USAR SINCE INITIAL CONSTRUCTION. THE | | STATEMENTS IN THE 1972 FSAR ARE VERY SIMILAR TO THE CURRENT STATEMENTS. | | A CALCULATION DEMONSTRATING AN 8 HOUR CAPACITY FOR THE STATION BATTERIES | | DURING A STATION BLACKOUT IS AVAILABLE. HOWEVER, CALCULATIONS FOR DBAs, | | SUCH AS LOCA OR MSLB, HAVE NOT BEEN LOCATED WHICH DIRECTLY CONFIRM THESE | | USAR STATEMENTS. THE STATION BATTERIES ARE BEING CONSIDERED OPERABLE SINCE | | IN DESIGN ENGINEERING'S JUDGMENT THERE WILL BE VERY LITTLE DIFFERENCE | | BETWEEN THE DC LOAD DURING ANY DBA AND A STATION BLACKOUT. THE FACT THAT | | THE STATION BATTERY HAS EXCESS CAPACITY FROM ITS SURVEILLANCE TEST PROVIDES | | ADDITIONAL CONFIDENCE THAT THE FINAL ANALYSIS WILL BE POSITIVE. | | | | THE DESIGN ENGINEERING DEPARTMENT WILL BE DEVELOPING APPROPRIATE ANALYSIS | | AND OTHER SUPPORT DOCUMENTATION FOR THE USAR STATEMENTS. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1925 ON 10/17/97 BY POHL, TAKEN BY WEAVER * * * | | | | BECAUSE OF ADDITIONAL INFORMATION, WHICH WAS NOT AVAILABLE AT THE TIME THE | | ORIGINAL REPORT WAS MADE, IT HAS BEEN DETERMINED THAT THE STATION BATTERIES | | MAY NOT BE CAPABLE OF SUPPLYING THE 8 HOUR DESIGN CAPACITY IN ALL | | SCENARIOS. SPECIFICALLY, ANY DBA SCENARIO WHICH INCLUDES THE LOSS OF A | | STATION BATTERY CHARGER SUPPLYING ITS ASSOCIATED DC BUS. OPERATOR ACTION | | TO MINIMIZE DC LOADS IS CREDITED IN A STATION BLACK-OUT ACCIDENT; HOWEVER, | | THIS FORMAL WRITTEN GUIDANCE IS NOT PRESENT IN THE SITUATIONS WHERE A DBA | | EXIST WITH THE LOSS OF A STATION BATTERY CHARGER. | | | | AS A RESULT OF THE BATTERIES BEING DECLARED INOPERABLE, THE REQUIREMENTS OF | | TECH SPEC 2.7 (ELECTRICAL SYSTEMS) CANNOT BE MET. THIS PLACED THE PLANT IN | | A SIX HOUR SHUTDOWN LCO (TS 2.0.1). THE LCO WAS ENTERED AND EXITED AT 1755 | | CST BASED ON THE IMPLEMENTATION OF A COMPENSATORY MEASURE WHICH CONSISTS OF | | AN OPERATIONS MEMO WHICH DIRECTS OPERATOR ACTION TO MINIMIZE DC LOADS IN | | DBA CONDITIONS WHICH INCLUDE THE LOSS OF A BATTERY CHARGER. THE BATTERIES | | ARE NOW CONSIDERED OPERABLE. THE OPERATIONS OFFICER NOTIFIED THE R4DO | | (STETKA). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33103 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 10/17/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:04 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/16/97 | +------------------------------------------------+EVENT TIME: 17:30[CDT]| |NRC NOTIFIED BY: KURT BASNER |LAST UPDATE DATE: 10/17/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER 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 +------------------------------------------------------------------------------+ | CONTAINMENT PENETRATION PIPING NOT SUPPORTED - PENETRATION INOPERABLE | | | | DURING A PLANT WALKDOWN ON 10/15/97, PLANT PERSONNEL FOUND SAFETY RELATED | | LINE 2DT040-3/4" IMPROPERLY SUPPORTED. CALCULATIONS PERFORMED ON 10/16/97 | | INDICATED THAT AS A RESULT, THE ASSOCIATED CONTAINMENT PENETRATION WAS | | INOPERABLE. PERSONNEL FAILED TO RECOGNIZE THE REPORTABILITY ON 10/16/97. | | | | THIS LINE IS FROM THE REACTOR COOLANT DRAIN TANK THROUGH THE CONTAINMENT | | WALL TO THE AUTO GAS ANALYZER. THE LICENSEE OBSERVED ACTUAL DEFORMATION OF | | THE PIPING DUE TO ITS BEING UNSUPPORTED. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 33104 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SPEEDIE AND ASSOCIATES |NOTIFICATION DATE: 10/17/97 | | CITY: PHOENIX REGION: 4 |NOTIFICATION TIME: 16:10 [ET]| | COUNTY: STATE: AZ |EVENT DATE: 10/17/97 | |LICENSE#: 97-209 AGREEMENT: Y |EVENT TIME: 10:00[MDT]| | DOCKET: |LAST UPDATE DATE: 10/17/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |TOM STETKA RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: DAN KUHL | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT FROM ARIZONA. | | | | THIS REPORT WAS MADE TO THE NRC OPERATIONS CENTER BY NRC REGION IV | | PERSONNEL. | | | | ON 10/17/97, SPEEDIE AND ASSOCIATES NOTIFIED THE NRC OF THE THEFT OF TWO | | TROXLER MOISTURE/DENSITY GAUGES FROM TWO DIFFERENT LOCATIONS. THE THEFTS | | OCCURRED BETWEEN 1800 MDT ON 10/16/97 AND 0700 ON 10/17/97. BOTH GAUGES | | HAD BEEN CHAINED AND LOCKED IN THE OPEN BED OF PICKUP TRUCKS. TROXLER GAUGE | | MODEL 3411B, SERIAL NUMBER 4446, WAS STOLEN FROM 12601 KOSH STREET, | | PHOENIX; GAUGE MODEL 3440, SERIAL NUMBER 18490, WAS STOLEN FROM 408 W. | | PONTIAC STREET, PHOENIX. | | | | THE PHOENIX POLICE DEPARTMENT IS INVESTIGATING THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33105 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 10/17/97 | |UNIT: [1] [2] [ ] STATE: AL |NOTIFICATION TIME: 17:30 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/17/97 | +------------------------------------------------+EVENT TIME: 16:26[CDT]| |NRC NOTIFIED BY: JIM HUNTER |LAST UPDATE DATE: 10/17/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EOF COMMUNICATIONS LOST DURING MAINTENANCE. | | | | COMMUNICATION FROM THE ONSITE EMERGENCY OPERATIONS FACILITY (EOF) ARE | | UNAVAILABLE DUE TO MAINTENANCE. THE MAINTENANCE IS EXPECTED TO LAST LESS | | THAN ONE HOUR. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2219 ON 10/17/97 BY MURPHY, TAKEN BY WEAVER * * * | | | | MAINTENANCE HAS BEEN COMPLETED AS OF 2218 CDT. ALL COMMUNICATIONS HAVE | | BEEN RESTORED. THE OPERATIONS OFFICER NOTIFIED THE R2DO (PEEBLES). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33106 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 10/17/97 | |UNIT: [ ] [2] [ ] STATE: CA |NOTIFICATION TIME: 19:57 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/17/97 | +------------------------------------------------+EVENT TIME: 16:30[PDT]| |NRC NOTIFIED BY: GLENN GOELZER |LAST UPDATE DATE: 10/17/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OUTSIDE DESIGN BASIS - TWO TRAINS OF AUX SALT WATER NOT PROPERLY SEPARATED | | | | THE TWO TRAINS OF AUX SALT WATER ARE NOT SEPARATED BY A THREE HOUR FIRE | | BARRIER INSIDE A CABLE PULL BOX. A FIRE BARRIER IS PRESENT, BUT IT DOES | | NOT COVER THE FULL LENGTH OF THE INTERIOR OF THE PULL BOX. THIS CONDITION | | DOES NOT EXIST ON UNIT 1. AUX SALT WATER PROVIDES COOLING TO VARIOUS | | SAFETY RELATED LOADS. | | | | A CONTINUOUSLY MANNED FIRE WATCH HAS BEEN STATIONED NEXT TO THE PULL BOX | | WITH THE COVER REMOVED. LONG TERM CORRECTIVE ACTION WILL CONSIST OF | | INSTALLING A PROPER FIRE BARRIER IN THE PULL BOX. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 33107 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: GEOCORE |NOTIFICATION DATE: 10/18/97 | | CITY: WILLINGBORO REGION: 1 |NOTIFICATION TIME: 08:44 [ET]| | COUNTY: BURLINGTON STATE: NJ |EVENT DATE: 10/17/97 | |LICENSE#: 29-30411-01 AGREEMENT: N |EVENT TIME: 11:00[EDT]| | DOCKET: |LAST UPDATE DATE: 10/18/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MICHAEL MODES RDO | | |LARRY CAMPER (NMSS) EO | +------------------------------------------------+ | |NRC NOTIFIED BY: N. DUROBICH | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A TRUCK WAS STOLEN WHICH HAD A TROXLER MOISTURE DENSITY GAUGE INSIDE. UPON | | THE RECOVERY OF THE TRUCK THE TROXLER MOISTURE GAUGE WAS MISSING. | | | | A REPRESENTATIVE OF GEOCORE LOCATED A 1 NIAGARA LANE, WILLINGBORO, NEW | | JERSEY, REPORTED THE FOLLOWING EVENT: | | | | A MODEL 3430 TROXLER MOISTURE DENSITY GAUGE WAS IN ITS BOX (HAD RADIOACTIVE | | SIGNS ON THE BOX), DOUBLED LOCKED AND CHAINED TO THE SEAT OF A TRUCK. THE | | DRIVER GOT OUT OF THE TRUCK AND WENT INTO A HOTEL FOR ABOUT ONE HOUR. UPON | | COMING OUT OF THE HOTEL AROUND 1100 HOURS ON 10/17/97 HE DISCOVERED THAT | | HIS TRUCK CONTAINING THE TROXLER MOISTURE DENSITY HAD BEEN STOLEN. HE | | NOTIFIED THE SUFFOLK COUNTY POLICE DEPARTMENT OF LONG ISLAND, NEW YORK THAT | | HIS TRUCK HAD BEEN STOLEN. HIS TRUCK WAS RECOVERED BY THE SUFFOLK COUNTY | | POLICE DEPARTMENT AT APPROXIMATELY 1300 HOURS ON 10/17/97. HIS TRUCK HAD | | BEEN STRIPPED AND THE TROXLER MOISTURE DENSITY GAUGE WAS MISSING. THE | | TROXLER MOISTURE DENSITY GAUGE CONTAINS 10 MILLICURIES OF CESIUM-137 AND 40 | | MILLICURIES OF AMERICIUM-BERYLLIUM. THE SERIAL NUMBER OF THE SOURCE IS | | 25168. | | | | SEE HOO LOG BOOK FOR PHONE NUMBER OF THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 33108 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: HAMMOND FIRE DEPARTMENT |NOTIFICATION DATE: 10/18/97 | | CITY: HAMMOND REGION: 3 |NOTIFICATION TIME: 13:41 [ET]| | COUNTY: STATE: IN |EVENT DATE: 10/18/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 13:20[EDT]| | DOCKET: |LAST UPDATE DATE: 10/18/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JIM MCCORMICKBARGER RDO | | |LARRY CAMPER EO | +------------------------------------------------+JOSEPH GIITTER IRD | |NRC NOTIFIED BY: KOCHIS | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE HAMMOND CITY, INDIANA FIRE DEPARTMENT REPORTED A YELLOW COOLER BEING | | FOUND OFF THE ROAD IN THE 100 BLOCK OF 136th STREET. THE CONTAINER HAD A | | PLACARD MARKED RADIOACTIVE 2. THE CONTAINER IS CLOSED, BUT NOT LOCKED AND | | IT IS UNKNOWN IF THERE IS ANYTHING INSIDE. THE CONTAINER HAS TROXLER | | EMBOSSED ON THE SIDE OF THE CASE. THE FIRE DEPARTMENT HAS NOT OPENED THE | | CONTAINER AND THEY HAVE ISOLATED THE AREA. THE STICKER ON THE CONTAINER | | READS USDOT 7A TYPE RQ RADIOACTIVE MATERIAL NOS, SPECIAL FORM NOS 7 UN2974. | | OTHER IDENTIFICATION ON THE CONTAINER IS THE SERIAL NUMBER 26419 AND | | #6-3450. | | | | THE NATIONAL RESPONSE CENTER ALSO NOTIFIED THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33109 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 10/18/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 22:09 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 10/18/97 | +------------------------------------------------+EVENT TIME: 21:11[EDT]| |NRC NOTIFIED BY: RITTER |LAST UPDATE DATE: 10/18/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 DISCOVERED A DEAD SEAL IN THE CIRCULATING WATER PUMPHOUSE | | FOREBAY. | | | | THEY ARE MAKING THIS NOTIFICATION PURSUANT TO SECTION 4.1 OF THE | | ENVIRONMENTAL PROTECTION PLAN, APPENDIX B, OF THE TECH SPECS. THE NATIONAL | | MARINE FISHERIES SERVICE IN GLOUCESTER, MASS. WILL BE NOTIFIED ON 10/20/97. | | THE SEAL IS STILL IN THE FOREBAY, BUT NOT AFFECTING PLANT OPERATIONS. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33110 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/19/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 03:26 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/18/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:45[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/19/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JIM MCCORMICKBARGER RDO | | DOCKET: 0707002 |LARRY CAMPER (NMSS) EO | +------------------------------------------------+ | |NRC NOTIFIED BY: JOHN JORDAN | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE RECEIVED AN AUDIBLE AND VISUAL ALARM INDICATING STEAM SHUTDOWN AND | | CONTAINMENT OF AUTOCLAVE #4. NO URANIUM HEXAFLUORIDE LEAK. | | | | ON SATURDAY, OCTOBER 18, 1997, AT 1645 HOURS, THE OPERATORS AT THE X-343 | | URANIUM HEXAFLUORIDE FEED VAPORIZATION AND SAMPLING FACILITY RECEIVED AN | | AUDIBLE AND VISUAL ALARM INDICATING STEAM SHUTDOWN AND CONTAINMENT OF | | AUTOCLAVE #4. AUTOCLAVE #4 WAS OPERATING AT THE TIME IN MODE 4, URANIUM | | HEXAFLUORIDE CYLINDER FEEDING TO THE ENRICHMENT CASCADE. | | | | ESTABLISHED ALARM RESPONSE PROCEDURES WERE FOLLOWED TO ASSESS AUTOCLAVE #4 | | STATUS. IT WAS DETERMINED THE STEAM SHUTDOWN AND AUTOCLAVE CONTAINMENT | | RESULTED WHEN CHANNEL "A" OF A TWO CHANNEL PRESSURE SENSING INSTRUMENTATION | | (A "Q" SAFETY SYSTEM ITEM) ACTIVATED AT 22.3 POUNDS PER SQUARE INCH | | ABSOLUTE (psia) FOR SHELL INTERNAL HIGH PRESSURE. THE LIMITING CONTROL | | SETTING FOR THE PRESSURE SENSORS WAS 22.45 + OR - 1 (ALLOWABLE RANGE 21.45 | | TO 23.45) psia. | | | | THE AUTOCLAVE OPERATORS AND X-343 FIRST LINE MANAGER OBTAINED AUTOCLAVE | | CONDENSATE SAMPLES FROM CONDUCTIVITY CELLS A AND B. BOTH SAMPLES WERE | | NEGATIVE FOR URANIUM HEXAFLUORIDE-WATER REACTION PRODUCTS, INDICATING NO | | URANIUM HEXAFLUORIDE RELEASE HAD OCCURRED. | | | | THE AUTOCLAVE ALARMS WERE RESET AFTER VERIFYING ALL CONTAINMENT VALVES HAD | | OPERATED AS REQUIRED. THE AUTOCLAVE WAS OPENED FOR INSPECTION. NO ANOMALIES | | WERE NOTED. THE CYLINDER SAFETY VALVE WAS REOPENED, THE AUTOCLAVE WAS | | CLOSED, STEAM WAS RESTARTED, AND THE CYLINDER FEED CYCLE WAS CONTINUED. | | | | RECORDED AUTOCLAVE INTERNAL SHELL PRESSURE AND URANIUM HEXAFLUORIDE | | CYLINDER TEMPERATURE DATA INDICATED THAT FOLLOWING THE CYLINDER VALVE BEING | | OPENED TO INITIATE URANIUM HEXAFLUORIDE FEED TO THE ENRICHMENT CASCADE, THE | | CYLINDER TEMPERATURE DROPPED FROM ABOUT 214 DEGREES F TO ABOUT 195 DEGREES | | F. THE AUTOCLAVE STEAM LOADING REGULATOR INCREASED ITS STEAM LOAD SETTING | | FROM ABOUT 8 POUNDS PER SQUARE INCH GAUGE (psig) TO ABOUT 12 psig. IT IS | | BELIEVED THE HIGHER STEAM LOADING RATE RESULTED IN THE ALARM CONDITION | | BEFORE THE STEAM REGULATOR COULD RESET TO ITS LOWER STEAM LOADING POSITION. | | | | THE AUTOCLAVE SYSTEM ENGINEER WAS NOTIFIED OF THIS EVENT, AND THE AUTOCLAVE | | WAS DECLARED INOPERABLE AT 2319 HOURS. "AS FOUND" STEAM LOADING | | TESTING/SURVEILLANCE DATA WILL BE COLLECTED FOR EVALUATION. | | | | THERE WAS NO RELEASE OF HAZARDOUS MATERIALS OR RADIOLOGICAL EXPOSURES | | ASSOCIATED WITH THIS EVENT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE DEPARTMENT OF | | ENERGY OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33111 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 10/19/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 03:38 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/19/97 | +------------------------------------------------+EVENT TIME: 02:00[EDT]| |NRC NOTIFIED BY: SCOTT DAVIS |LAST UPDATE DATE: 10/19/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NUCLEAR CLOSED COOLING SYSTEM PENETRATION LEAKAGE EXCEEDED THE ALLOWABLE | | LEAK RATE LIMIT. | | | | DURING THE SIXTH REFUELING OUTAGE, A CONTAINMENT PENETRATION LLRT FAILURE | | CRITERIA WAS MET FOR NON-MAIN STEAM ISOLATION VALVE LEAKAGE. THE NUCLEAR | | CLOSED COOLING SYSTEM PENETRATION LEAKAGE EXCEEDED THE ALLOWABLE LEAK RATE | | LIMIT FOR TYPE B AND C VALVES (0.6 La) AND THE SECONDARY CONTAINMENT BYPASS | | LIMIT (0.0504 La). THE PENETRATION FAILURE WAS IDENTIFIED DURING ROUTINE | | SURVEILLANCE TESTING AND DURING AN OPERATIONAL CONDITION (i.e.,REFUELING) | | FOR WHICH THE TECHNICAL SPECIFICATION DID NOT APPLY. HOWEVER, IT CAN NOT BE | | POSITIVELY CONCLUDED THAT THIS CONDITION DID NOT EXIST DURING OPERATIONAL | | CONDITIONS 1, 2 OR 3. IF THE LLRT LEAKAGE EXISTED DURING THESE CONDITIONS, | | CONCURRENT WITH POSTULATED DESIGN BASIS ACCIDENTS, THEN THE CONDITION COULD | | HAVE BEEN SAFETY SIGNIFICANT. | | | | THE TOTAL INTEGRATED PENETRATION LEAKAGE WAS PROGRAMMATICALLY | | UNQUANTIFIABLE DUE TO A SINGLE PENETRATION WITH UNQUANTIFIABLE LEAKAGE. | | EXCLUDING THIS PENETRATION, TOTAL "AS FOUND" MINIMUM PATH LEAKAGE RATE WAS | | 5427.06 sccm (STANDARD CUBIC CENTIMETER PER MINUTE) FOR 0.06 La AND 3843.21 | | sccm FOR 0.0504 La. FOLLOWING REFUELING MAINTENANCE ACTIVITIES "AS LEFT" | | MAXIMUM PATH LEAKAGE RATE WAS 17248.20 sccm FOR 0.06 La AND 3072.45 sccm | | FOR 0.0504 La, WHICH IS LESS THAN THE TECHNICAL SPECIFICATION REQUIRED | | VALUE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33112 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 10/19/97 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 11:58 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/19/97 | +------------------------------------------------+EVENT TIME: 09:50[EDT]| |NRC NOTIFIED BY: RICHARD O'REAR |LAST UPDATE DATE: 10/19/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES 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 13 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP FOLLOWING A LOSS OF FEEDWATER DUE TO ISOLATION OF | | INSERVICE FEEDWATER HEATERS ON HIGH-HIGH LEVEL. | | | | "DURING UNIT 1 STARTUP, THE REACTOR WAS IN MODE 1, WITH THE TURBINE AT 1800 | | RPM. THE TURBINE GENERATOR WAS NOT CONNECTED TO THE GRID. STEAM GENERATOR | | LEVELS BEGAN DECREASING DUE TO ISOLATION OF THE INSERVICE FEEDWATER | | HEATERS. AUXILIARY FEEDWATER WAS MANUALLY INITIATED AND THE REACTOR WAS | | MANUALLY TRIPPED DUE TO DECREASING STEAM GENERATOR LEVELS AT 0950 EDT. | | ALL SYSTEMS RESPONDED AS REQUIRED WITH THE FOLLOWING EXCEPTION: 'A' MAIN | | FEEDWATER PUMP FAILED TO TRIP FOLLOWING MAIN FEEDWATER ISOLATION SIGNAL. | | THE FEEDWATER PUMP WAS MANUALLY TRIPPED. THE 'A' MFP PUMP WAS NOT IN | | SERVICE AT THAT TIME, (THE STANDBY FEEDWATER PUMP WAS IN SERVICE). | | THE FEEDWATER HEATERS ISOLATED ON HIGH-HIGH LEVEL. THE MAIN CONTROL ROOM | | ALARMS FOR HI FEEDWATER HEATER LEVEL DID NOT ALARM." | | | | ALL CONTROL RODS FULLY INSERTED FOLLOWING THE MANUAL TRIP. BOTH MOTOR | | DRIVEN AUXILIARY FEEDWATER PUMPS WERE STARTED TO MAINTAIN STEAM GENERATOR | | WATER LEVELS. THE LICENSEE WILL MAINTAIN THE UNIT IN MODE 3 PENDING | | CORRECTIVE ACTIONS FOLLOWING THEIR INVESTIGATION. DECAY HEAT IS BEING | | REJECTED TO THE MAIN CONDENSER. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33113 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 10/19/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 18:14 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 10/19/97 | +------------------------------------------------+EVENT TIME: 16:44[CDT]| |NRC NOTIFIED BY: MIKE MacLENNAN |LAST UPDATE DATE: 10/19/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER 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 98 POWER OPERATION | 98 POWER OPERATION | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A CONDITION WHICH COULD HAVE RESULTED IN A PARTIAL LOSS OF THE PRIMARY | | CONTAINMENT PRESSURE SUPPRESSION SAFETY FUNCTION WAS IDENTIFIED. | | | | "FOLLOWING A HISTORICAL REVIEW OF PAST OPERATING PRACTICES RELATED TO | | DEINERTING THE PRIMARY CONTAINMENT, IT WAS DETERMINED THAT QUAD CITIES | | STATION COULD HAVE BEEN IN A CONDITION DURING POWER OPERATION THAT COULD | | HAVE RESULTED IN THE PARTIAL LOSS OF THE PRIMARY CONTAINMENT PRESSURE | | SUPPRESSION SAFETY FUNCTION. | | | | "THIS CONDITION COULD HAVE RESULTED FROM HAVING BOTH THE DRYWELL AND TORUS | | 18" VENT VALVES OPEN SIMULTANEOUSLY SHORT DURATION AND THE 2" DRYWELL AND | | 18" TORUS VENT VALVES OPEN LONGER DURATION FOR DEINERTING PURPOSES, THEREBY | | CREATING A POSSIBLE SUPPRESSION POOL BYPASS PATH. IN THE EVENT A LOCA HAD | | OCCURRED DURING THIS TIME, THIS COULD HAVE ALLOWED AN INDETERMINATE AMOUNT | | OF DIRECT TORUS AIR SPACE PRESSURIZATION PENDING FULL CLOSURE OF THE VALVES | | FROM A GROUP II ISOLATION SIGNAL. THIS SCENARIO OF A SHORT TERM BYPASS OF | | THE SUPPRESSION POOL IS NOT ADDRESSED BY ANY KNOWN EXISTING ANALYSIS. | | | | "IN ADDITION, THE IMPLEMENTATION OF THE UPGRADED TECHNICAL SPECIFICATIONS | | REQUIRES THE TOTAL AMOUNT OF LEAKAGE BETWEEN THE SUPPRESSION CHAMBER AND | | DRYWELL BE LIMITED TO LESS THAN THE EQUIVALENT THROUGH A 1" DIAMETER | | ORIFICE AT A DIFFERENTIAL PRESSURE OF 1.0 PSID (TECH SPEC 3/4.7.K.3). IN | | THE PERIOD OF TIME THIS REQUIREMENT HAS BEEN IN PLACE (IMPLEMENTED IN | | SEPTEMBER 1996) QUAD CITIES STATION HAS DEINERTED BOTH THE DRYWELL AND | | TORUS AT LEAST ONE TIME (DURING THE LAST UNIT 2 SHUTDOWN FOR REFUELING IN | | FEBRUARY OF 1997). THEREFORE, THIS WOULD ALSO HAVE BEEN A CONDITION | | PROHIBITED BY TECHNICAL SPECIFICATIONS. IN APRIL OF 1997, QUAD CITIES | | PROCEDURES WERE CHANGED TO PREVENT RECURRENCE OF THIS UNDESIRABLE VALVE | | LINEUP." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33114 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 10/19/97 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 19:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/19/97 | +------------------------------------------------+EVENT TIME: 17:18[EDT]| |NRC NOTIFIED BY: JAMES ROBINSON |LAST UPDATE DATE: 10/19/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES 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 N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP INITIATED DURING HOT ROD DROP TESTING DUE TO > 12 STEP | | DISAGREEMENT BETWEEN THE DIGITAL ROD POSITION INDICATION (DRPI) AND DEMAND | | POSITION. | | | | "WHILE CONDUCTING HOT ROD DROP TESTING, WHILE PULLING THE INITIAL BANK OF | | SHUTDOWN RODS, A DISAGREEMENT IN DRPI VERSUS DEMAND OF GREATER THAN 12 | | STEPS WAS NOTED. THE OPERATING CREW ENTERED THE ABNORMAL OPERATING | | PROCEDURE AND IN COMPLIANCE WITH THE PROCEDURE OPENED THE REACTOR TRIP | | BREAKERS. THE SHUTDOWN BANK THAT WAS BEING WITHDRAWN WAS INSERTED. NO | | OTHER EMERGENCY ACTIONS WERE EXPECTED NOR OCCURRED." | | | | THE LICENSEE IS CONDUCTING AN EVENT REVIEW PRIOR TO RESUMING ROD DROP | | TESTING. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33115 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 10/19/97 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 19:35 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 10/19/97 | +------------------------------------------------+EVENT TIME: 16:29[CDT]| |NRC NOTIFIED BY: DON SMITH |LAST UPDATE DATE: 10/19/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 37 POWER OPERATION | 37 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HPCI DECLARED INOPERABLE FOLLOWING INVESTIGATION OF STEAM LINE DRAIN ALARM. | | | | "AT 1629CDT ON 10/19/97, UNIT 2 HIGH PRESSURE COOLANT INJECTION (HPCI) WAS | | DECLARED INOPERABLE AS A RESULT OF A STEAM LINE DRAIN SYSTEM MALFUNCTION. | | | | "DURING TROUBLESHOOTING (WRC 390999) OF THE 'HPCI TURBINE INLET DRAIN POT | | LEVEL HIGH (2-LA-73-5)' ALARM, IT WAS DETERMINED THAT THE ALARM WAS VALID. | | ACTION HAS BEEN INITIATED TO DETERMINE THE CAUSE OF THE DRAIN SYSTEM | | MALFUNCTION. | | | | "HPCI IS A SINGLE TRAIN SAFETY SYSTEM AND IS REPORTABLE WITHIN 4 HOURS IN | | ACCORDANCE WITH 10CFR50.72(b)(2)(iii) AS A CONDITION THAT ALONE COULD HAVE | | PREVENTED THE FULFILLMENT OF A SAFETY FUNCTION NEEDED TO MITIGATE THE | | CONSEQUENCES OF AN ACCIDENT. | | | | "THIS EVENT IS ALSO AN EVENT THAT REQUIRES A 30 DAY WRITTEN REPORT (LER) | | PER 10CFR50.73(a)(2)(v & vi)." | | | | WITH HPCI INOPERABLE, THIS PLACES UNIT 2 IS IN THE 7 DAY LCO A/S 3.5.E.2. | | ALL OTHER ECCS EQUIPMENT IS OPERABLE AT THIS TIME. THE LICENSEE INFORMED | | THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+