U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/22/94 - 07/25/94 ** EVENT NUMBERS ** 27295 27564 27565 27566 27567 27568 27569 27570 27571 27572 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27295 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 05/25/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 14:55 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/25/94 | +------------------------------------------------+EVENT TIME: 13:14[CDT]| |NRC NOTIFIED BY: DAVE KUSER |LAST UPDATE DATE: 07/22/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ROBERT DENNING EO | |NLCO TECH SPEC LCO A/S |BOB CALDWELL FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 93 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO BOTH EDGs BEING DECLARED INOPERABLE. | | | | THE FOLLOWING IS A TEXT OF A FACSIMILE FROM THE LICENSEE: | | | | "ON MAY 25, 1994 AT 1:14 PM A NOTIFICATION OF UNUSUAL EVENT WAS DECLARED | | WHEN BOTH DIESEL GENERATORS WERE DECLARED INOPERABLE DUE TO THE | | SURVEILLANCE TEST CONDUCTED EACH REFUELING OUTAGE NOT VERIFYING THE LOAD | | SHEDDING OF ALL LOADS ON THE CRITICAL 480 VOLT BUS. PROPER LOAD SHEDDING | | OF ALL 4160 VOLT LOADS IS VERIFIED DURING THE SEQUENTIAL LOADING TEST. | | THE PRINCIPAL 480 VOLT LOADS NOT VERIFIED TO BE SHED INCLUDE STATION AIR | | COMPRESSORS AND THE CRD PUMPS. THESE COMPONENTS ARE TRANSFERRED TO ANOTHER | | BUS DURING THE SURVEILLANCE TEST. INDIVIDUALLY, THE REMAINING LOADS ON THE | | CRITICAL 480 VOLT BUS ARE SMALL. | | | | IN ACCORDANCE WITH TECHNICAL SPECIFICATION REQUIREMENTS IN SECTION 3.5.F.2, | | A LOAD REDUCTION TO 25 PERCENT POWER WAS INITIATED. AN ENGINEERING | | EVALUATION OF THE CONDITION IS ONGOING. A FOLLOW-UP NOTIFICATION WILL BE | | MADE WHEN SUCH INFORMATION IS AVAILABLE." END OF TEXT. | | | | THE LICENSEE IS REDUCING POWER AT 100 MW(e) PER HOUR. THE LICENSEE | | CONSIDERS THE EDGs AVAILABLE. ALL ECCS AND RCIC ARE OPERABLE. THE WEATHER | | IN THE AREA IS CALM WITH NO FORECAST OF RAIN. THE PROBLEM WAS DISCOVERED | | DURING REVIEW OF UNDERVOLTAGE TESTING. THE LAST REFUELING OUTAGE ENDED IN | | JULY, 1993. THE LICENSEE IS INVESTIGATING CORRECTIVE ACTIONS AND IS | | PURSUING ENFORCEMENT DISCRETION WITH THE NRC TO STOP THE POWER DESCENSION. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR AND HAS INFORMED LOCAL AND | | STATE OFFICIALS IN ACCORDANCE WITH THEIR EMERGENCY PLAN. | | | | * * * UPDATE AT 2240 ON 5/25/94 FROM CAUL TAKEN BY SEBROSKY * * * | | THE REACTOR IS CURRENTLY AT 24% POWER AND THE LICENSEE PLANS TO SCRAM THE | | PLANT AT 2200 CDT PER THEIR NORMAL SHUTDOWN PROCEDURES. THE SHUTDOWN IS | | BEING DONE DUE TO BOTH EDGS BEING DECLARED INOPERABLE. THE LICENSEE WILL | | EXIT THE UNUSUAL EVENT WHEN THE PLANT REACHES COLD SHUTDOWN CONDITIONS. | | COLD SHUTDOWN IS EXPECTED TO BE REACHED ON 5/26/94. THE LICENSEE HAS BEEN | | IN CONTACT WITH REGION 4 OFFICIALS CONCERNING THE SHUTDOWN AND HAS INFORMED | | THE RESIDENT INSPECTOR. HOO NOTIFIED R4DO (POWERS) AND EO (VARGA). | | | | * * * UPDATE AT 0106 ON 5/27/94 FROM HITZEL TAKEN BY WEAVER * * * | | THE PLANT REACHED COLD SHUTDOWN AT 2357 CDT ON 5/26/94. THIS SATISFIES THE | | TECHNICAL SPECIFICATION ACTION STATEMENT FOR HAVING BOTH EMERGENCY DIESELS | | INOPERABLE. CONTRARY TO THE LAST UPDATE, THE UNUSUAL EVENT WILL NOT BE | | TERMINATED UNTIL AT LEAST ONE EDG IS MADE OPERABLE AS REQUIRED BY THEIR | | EMERGENCY PROCEDURES. NO TIME ESTIMATE WAS AVAILABLE. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR AS WELL AS STATE AND LOCAL GOVERNMENTS. | | HOO NOTIFIED R4DO (POWERS) AND EO (CHAFFEE). | | | | * * * UPDATE AT 1400 ON 5/27/94 FROM KUSER TAKEN BY SANDIN * * * | | THE CONTINUING INVESTIGATION HAS REVEALED THAT LOAD SHEDDING OF THE SERVICE | | WATER PUMPS, 4160 VOLT LOADS, IS NOT VERIFIED DURING THE SEQUENTIAL LOADING | | TEST. LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED R4DO (POWERS). | | | | * * * UPDATE AT 1734 ON 6/11/94 FROM HITZEL TAKEN BY KARSCH * * * | | THE FOLLOWING NOTIFICATION WAS MADE PURSUANT TO 10CFR50.72(b)(2)iiiD: | | "AS AN ELEMENT OF THE INVESTIGATION INTO THIS CONDITION, AN EVALUATION OF | | CONTACT TEST REQUIREMENTS NECESSARY TO SATISFY LOGIC SYSTEM FUNCTIONAL | | TESTING REQUIREMENTS SPECIFIED IN TECHNICAL SPECIFICATIONS FOR SAFETY | | RELATED SYSTEMS WAS PERFORMED. THIS EVALUATION REVEALED A NUMBER OF | | CONTACTS NOT VERIFIED BY SURVEILLANCE PROCEDURES. EACH CONTACT NOT TESTED | | WAS EVALUATED TO DETERMINE IF FAILURE TO ASSURE ITS OPERABILITY JEOPARDIZED | | COMPLIANCE WITH THE LOGIC SYSTEM FUNCTIONAL TEST DEFINITION SPECIFIED IN | | SECTION 1.0 OF THE TECH SPECS. | | | | AT 1430 CDT ON 6/11/94, THE SYSTEMS IDENTIFIED BELOW WERE DECLARED | | INOPERABLE DUE TO THE SURVEILLANCE TEST DEFICIENCY. | | SERVICE WATER REACTOR EQUIPMENT COOLING | | 4160 VAC BUS 1F 4160 VAC BUS 1G | | DIESEL GENERATOR 1 DIESEL GENERATOR 2 | | PROCEDURE CHANGES AND SPECIAL PROCEDURES ARE BEING DEVELOPED AND CONDUCTED | | TO ASSURE OPERABILITY OF THE LOGIC SYSTEMS. WHILE TECHNICALLY INOPERABLE, | | AND NOT REQUIRED TO BE OPERABLE UNDER THE PRESENT PLANT CONDITIONS, THE | | SYSTEMS ARE FUNCTIONAL AND AVAILABLE. THE ASSOCIATED SYSTEMS WILL NOT BE | | DECLARED OPERABLE UNTIL SATISFACTORY COMPLETION OF THE TESTS AND | | VERIFICATION OF THE RESULTS." | | | | THE LICENSEE HOPES TO COMPLETE TESTING ON ONE DIVISION'S EDG BY 6/13/94. | | AT THAT TIME THEY SHOULD BE ABLE TO EXIT THEIR UNUSUAL EVENT. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. HOO NOTIFIED R4DO (SANBORN). | | | | * * * UPDATE AT 1555 ON 06/14/94 BY HITZEL TAKEN BY ANDREWS * * * | | THE FOLLOWING INFORMATION WAS PROVIDED BY THE LICENSEE VIA FAX/PHONE: | | THIS IS THE SECOND FOLLOWUP NOTIFICATION TO THE NOTIFICATION MADE ON | | 5/25/94 @ 1314 CDT. AT THAT TIME, AN UNUSUAL EVENT HAD BEEN DECLARED WHEN | | BOTH DIESEL GENERATORS WERE DECLARED INOPERABLE DUE TO THE SURVEILLANCE | | TEST, CONDUCTED EACH REFUELING OUTAGE, NOT VERIFYING THE LOAD SHEDDING OF | | ALL LOADS ON THE CRITICAL 4160 AND 480 VOLT BUSES. INVESTIGATION REVEALED | | THAT LOAD SHEDDING OF THE SERVICE WATER BOOSTER PUMPS, 4160 LOADS, IS NOT | | VERIFIED DURING THE SEQUENTIAL LOADING TEST. LOAD SHEDDING OF ALL OTHER | | 4160 VOLT LOADS IS VERIFIED. THE PRINCIPLE 480 VOLT LOADS NOT VERIFIED TO | | BE SHED INCLUDE STATION AIR COMPRESSORS AND THE CRD PUMPS. THESE | | COMPONENTS HAD BEEN TRANSFERRED TO ANOTHER BUS DURING THE SURVEILLANCE | | TEST. INDIVIDUALLY, THE REMAINING LOADS ON THE CRITICAL 480 BUS ARE SMALL. | | | | ON 6/11/94, NPPD REPORTED IN A FOLLOWUP NOTIFICATION THAT AS AN ELEMENT OF | | THE INVESTIGATION INTO THIS CONDITION, AN EVALUATION OF CONTACT TEST | | REQUIREMENTS NECESSARY TO SATISFY LOGIC SYSTEM FUNCTIONAL TESTING | | REQUIREMENTS SPECIFIED IN THE TECHNICAL SPECIFICATIONS FOR SAFETY-RELATED | | SYSTEMS WAS PERFORMED. THIS EVALUATION REVEALED A NUMBER OF CONTACTS NOT | | VERIFIED BY SURVEILLANCE PROCEDURES. IN RESPONSE TO THIS DETERMINATION, | | SEVERAL SPECIAL TEST PROCEDURES WERE DEVELOPED & A NUMBER OF SURVEILLANCE | | TESTS WERE UPDATED TO TEST & VERIFY OPERABILITY OF THE CONTACTS & RELATED | | RELAYS. TESTING USING THESE PROCEDURES COMMENCED DURING THE WEEK OF 6/5/94. | | | | AT APPROXIMATELY 1100 CDT ON 6/14/94, DURING TESTING OF DIVISION 1 BREAKERS | | DESIGNED TO LOAD SHED ON A LOSS OF POWER, TWO 480 VAC BREAKERS FAILED TO | | TRIP AS REQUIRED. BOTH BREAKERS ARE DESIGNED TO TRIP IN LESS THAN 8.5 | | SECONDS. ONE BREAKER WHICH SUPPLIES POWER TO THE 1A SERVICE AIR COMPRESSOR | | TRIPPED APPROXIMATELY 100 SECONDS AFTER THE LOSS OF VOLTAGE CONDITION WAS | | IMPOSED. THE OTHER BREAKER WHICH SUPPLIES POWER TO VARIOUS LOADS | | ASSOCIATED WITH THE OFF-GAS SYSTEM NEVER TRIPPED. CALCULATIONS SHOW THAT | | THE ADDITIONAL LOADS WOULD HAVE RESULTED IN DIESEL GENERATOR LOADING | | OUTSIDE THE BOUNDARY OF THE CURRENTLY APPROVED DIESEL GENERATOR LOAD | | CALCULATIONS, RESULTING IN THE UNIT BEING OVERLOADED BY APPROXIMATELY 0.3%. | | THOUGH SLIGHTLY OVERLOADED, THROUGH THE USE OF ENGINEERING JUDGMENT, THE | | CONCLUSION HAS BEEN REACHED THAT THE DIESEL GENERATOR WOULD HAVE REMAINED | | FUNCTIONAL WITH NO IMPACT ON ITS DESIGN FUNCTION. | | | | TO ENSURE FUNCTIONALITY WITHIN THE CURRENT CALCULATED LOAD LIMITS, 480 VAC | | BREAKER 0G1 WAS OPENED & TAGGED. TESTING OF THE REMAINING CONTACTS & RELAYS | | ASSOCIATED WITH THE 4160 & 480 VAC UNDERVOLTAGE CONTACTS IS CONTINUING. | | | | AT APPROXIMATELY 1430 CDT ON 6/14/94, DURING TESTING OF THE 480 VOLT "G" | | SWITCHGEAR (DIVISION 2), THE BREAKERS FOR MCC-V AND MCC-MR FAILED TO MEET | | TEST REQUIREMENTS. THE FUNCTIONALITY OF 480 VOLT "G" SWITCHGEAR AND DIESEL | | GENERATOR #2 HAS BEEN VERIFIED BY ADDING THE MCC LOADS TO THE CURRENT LOAD | | CALCULATIONS. THE DIESEL AND 480 VOLT "G" SWITCHGEAR ARE NOT OVERLOADED | | AND REMAIN FUNCTIONAL. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. HOO NOTIFIED | | R4DO (YANDELL), EO (GRIMES). | | | | * * * UPDATE AT 0047 ON 7/22/24 BY HAKENEWERTH TAKEN BY WEAVER * * * | | THE UNUSUAL EVENT WAS TERMINATED AT 2330 CDT ON 7/21/94 WHEN THE #1 EDG WAS | | DECLARED OPERABLE. HOO NOTIFIED R4DO (JOHNSON), FEMA (DAMICO). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27564 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 07/22/94 | |UNIT: [1] [2] [ ] STATE: NY |NOTIFICATION TIME: 11:28 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 07/22/94 | +------------------------------------------------+EVENT TIME: 10:40[EDT]| |NRC NOTIFIED BY: BYRNE |LAST UPDATE DATE: 07/22/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM LAZARUS RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 90 POWER OPERATION | 90 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COMPROMISE OF SAFEGUARDS INFORMATION | | | | IMMEDIATE COMPENSATORY MEASURES HAVE BEEN TAKEN UPON DISCOVERY. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | DETAILS PROVIDED BY THE LICENSEE ARE CONTAINED IN THE HOO LOG. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27565 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 07/22/94 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 14:44 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 07/22/94 | +------------------------------------------------+EVENT TIME: 13:50[EDT]| |NRC NOTIFIED BY: NEUMAN |LAST UPDATE DATE: 07/22/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FLOYD CANTRELL 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 80 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THEY DISCOVERED THAT THE AMSAC (ATWS ACTUATION) | | REACTOR POWER PERMISSIVE WAS INCORRECTLY SET. | | | | ON 07/05/94 THE LICENSEE FOUND THAT THE AMSAC REACTOR POWER PERMISSIVE WAS | | SET AT 82% FULL POWER INSTEAD 45% FULL POWER. THIS ERROR WAS CORRECTED ON | | 07/05/94 AND THE CAUSE OF THIS INCORRECT SETTING WAS ATTRIBUTED TO AN | | INSTALLED MODIFICATION PACKAGE (THEY CHANGED THE REACTOR POWER VOLTAGE | | SETPOINT) AND CHANGES TO THE ASSOCIATED SURVEILLANCE PROCEDURES WERE NOT | | MADE TO REFLECT THE MODIFICATION. AT 13:50 ON 07/22/94 IT WAS DECIDED THAT | | THIS EVENT SHOULD HAVE BEEN REPORTED AS A CONDITION OUTSIDE THE DESIGN | | BASIS. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 27566 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ERIE FASTENER & INDUSTRIAL SUPPLY |NOTIFICATION DATE: 07/22/94 | | CITY: ERIE REGION: 1 |NOTIFICATION TIME: 15:00 [ET]| | COUNTY: STATE: PA |EVENT DATE: 07/22/94 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 07/22/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JOSEPH A. BAUER | | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEF 21.21(b)(2) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ERIE FASTENER & INDUSTRIAL SUPPLY, ERIE, PA. | | | | CRACKS WERE FOUND ON THREE BODY TO BONNET NUTS USED ON COPES-VULCAN AIR | | OPERATED VALVES. THE LICENSEE USES THESE VALVES FOR SAFETY RELATED | | APPLICATIONS AT THEIR BYRON AND BRAIDWOOD STATIONS. THE FAILURE OF TWO | | ADJACENT NUTS COULD JEOPARDIZE THE REACTOR COOLANT PRESSURE BOUNDARY. | | THE ASME CODE ACCEPTANCE CRITERIA FOR CLASS 1 BOLTING SPECIFIES THAT NO | | RADIAL INDICATIONS ARE ALLOWED. THIS REQUIREMENT WAS NOT MET. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27567 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 07/22/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 16:19 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 07/22/94 | +------------------------------------------------+EVENT TIME: 16:05[EDT]| |NRC NOTIFIED BY: RICHARD GAUZZA |LAST UPDATE DATE: 07/22/94 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM LAZARUS RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE FUEL OIL SUPPLY FOR THE EMERGENCY DIESEL GENERATORS (EDGs) DOES NOT | | MEET IEEE STANDARD 380-1971. | | | | THE EDGs' FUEL OIL SUPPLY DOES NOT MEET THE REQUIREMENT FOR SEVEN DAYS OF | | FUEL. THE LICENSEE FOUND THAT THEY CANNOT TAKE CREDIT FOR AN UNDERGROUND | | TANK THEY HAD BEEN USING BECAUSE IT DOES NOT MEET SEISMIC REQUIREMENTS. | | THEIR SUPPLY OF FUEL IN APPROVED TANKS IS 6.17 DAYS. THE LICENSEE WILL | | DEMONSTRATE THAT DUE TO CONSERVATISM IN ESTIMATES USE IN THEIR CALCULATIONS | | THE PRESENT DESIGN MEETS THE REQUIREMENTS OF THE STANDARD. THEY WILL | | REVISE THEIR FSAR AS NECESSARY. THE LICENSEE HAS INFORMED THE CONN. DEPT. | | OF EMERGENCY PREPAREDNESS AND WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27568 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 07/22/94 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 17:41 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 07/22/94 | +------------------------------------------------+EVENT TIME: 17:01[EDT]| |NRC NOTIFIED BY: KEN KYSER |LAST UPDATE DATE: 07/23/94 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |FLOYD CANTRELL RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JOSE CALVO EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |WITSBERGER FEMA | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN UNUSUAL EVENT WAS DECLARED DUE TO THE LOSS OF THE "A" EMERGENCY DIESEL | | GENERATOR (EDG) WITH THE "B" EDG ALREADY INOPERABLE. | | | | THE "B" EDG WAS DECLARED INOPERABLE AT 2155 ON 7/21/94 DUE TO DC CONTROL | | POWER PROBLEMS. THE "A" EDG WAS DECLARED INOPERABLE DUE TO LARGE FIELD | | VOLTAGE AND CURRENT SWINGS DURING TESTING. AT 1731, THE "B" EDG WAS | | STARTED AND IS RUNNING PROPERLY AFTER THE COMPLETION OF REPAIRS. | | THE LICENSEE EXPECTS TO TERMINATE THE UNUSUAL EVENT AT 1915 AFTER THE | | COMPLETION OF THE ENDURANCE RUN. THE LICENSEE HAS INFORMED STATE AND | | LOCAL AUTHORITIES AND WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2047 FROM WAYMAN TAKEN BY KARSCH * * * | | | | THE "B" EDG EXPERIENCED SOME SPIKING IN LOAD DURING ITS SURVEILLANCE TEST. | | THE LICENSEE IS SECURING FROM THE TEST WITH UNSATISFACTORY DATA. WITH BOTH | | EDGs INOPERABLE, THE LICENSEE IS IN TECH SPEC 3.8.1.1.f, WHICH HAS A 6 HOUR | | LCO. THE LICENSEE WILL COMMENCE A POWER REDUCTION AT 2 MW/MIN AT 2100 AND | | WILL REACH HOT STANDBY BY 0057 ON 7/23/94. IF ONE EDG CAN BE REPAIRED, THE | | LICENSEE WILL HOLD POWER WHILE THEY TEST THE EDG's OPERABILITY. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. HOO NOTIFIED R2DO (CANTRELL), | | EO (CALVO), AND FEMA (CANUPP). | | | | * * * UPDATE AT 2143 FROM WAYMAN TAKEN BY KARSCH * * * | | | | ANOTHER UNUSUAL EVENT HAS BEEN DECLARED DUE TO A TECH SPEC REQUIRED | | SHUTDOWN. THIS IS IN ADDITION TO THE UNUSUAL EVENT DUE TO BOTH EDGs BEING | | INOPERABLE. POWER REDUCTION BEGAN AT 2105. HOO NOTIFIED R2DO (CANTRELL), | | EO (CALVO), AND AEOD (BAILEY). | | | | * * * UPDATE AT 0233 ON 7/23/94 FROM WAYMAN TAKEN BY JOLLIFFE * * * | | | | MAINTENANCE TECHNICIANS TIGHTENED THE LINEAR REACTOR THROUGH-RODS ON THE | | #1A-SA 6.9 KV ELECTRICAL BUS. THIS LOOSE CONNECTION HAD GIVEN A FAULTY | | INPUT SIGNAL TO THE VOLTAGE REGULATOR WHICH CAUSED THE FIELD VOLTS AND AMPS | | SPIKING. | | | | AT 0212 ON 7/23/94, LICENSEE SATISFACTORILY TESTED THE "A" EDG, DECLARED | | IT OPERABLE, EXITED TECH SPEC 3.8.1.1.f, STOPPED THE POWER REDUCTION, AND | | TERMINATED BOTH UNUSUAL EVENTS. | | | | LICENSEE IS STILL INVESTIGATING THE PROBLEMS WITH THE "B" EDG. AT 2155 ON | | 7/21/94, LICENSEE HAD ENTERED TECH SPEC LCO A/S 3.8.1.1.b WHICH REQUIRES | | THE "B" EDG TO BE RESTORED TO OPERABLE STATUS WITHIN 72 HOURS. | | | | THE PLANT IS STABLE AT 18% POWER. LICENSEE INTENDS TO BEGIN INCREASING | | POWER. | | | | LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT INSPECTOR | | OF THE TERMINATION OF BOTH UNUSUAL EVENTS. | | | | HOO NOTIFIED R2DO CANTRELL, NRR EO CALVO, AND FEMA MOSTELLER OF THE | | TERMINATION OF BOTH UNUSUAL EVENTS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27569 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 07/23/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 14:28 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/23/94 | +------------------------------------------------+EVENT TIME: 00:20[CDT]| |NRC NOTIFIED BY: DOUG HITZEL |LAST UPDATE DATE: 07/23/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON 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 +------------------------------------------------------------------------------+ | CONTROL ROOM FAILED PRESSURIZATION SURVEILLANCE | | | | "AT 0020 CDT ON 7/23/94 THE SURVEILLANCE PROCEDURE FOR CONTROL ROOM (CR) | | ENVELOPE PRESSURIZATION WAS COMPLETED WITH RESULTS NOT MEETING ACCEPTANCE | | CRITERIA STATED IN A RECENT COMMITMENT TO THE NRC (LETTER DATED 7/20/94). A | | PRESSURE OF 0.03 INCHES WATER GAUGE IS REQUIRED IN THE CONTROL ROOM AND | | CABLE SPREADING ROOM. THE CABLE SPREADING ROOM SATISFIED THIS REQUIREMENT, | | HOWEVER, THE CONTROL ROOM HAD A POSITIVE PRESSURE OF 0.01 INCHES WATER | | GAUGE. THE CR EMERGENCY FILTER SYSTEM WAS ALREADY INOPERABLE FOR A DESIGN | | BASIS CONCERN WHICH HAD BEEN PREVIOUSLY REPORTED ON 6/23/94. | | | | UPON REVIEW, IT WAS DETERMINED THAT DUE TO THE DIFFERENCES FOR THE PRESENT | | STATUS OF INOPERABILITY, NOTIFICATION FOR A SURVEILLANCE FAILURE WAS | | REQUIRED. INVESTIGATION TO DETERMINE THE CAUSE OF THIS EVENT IS ON GOING. | | THE RESULTS OF THIS INVESTIGATION WILL BE REPORTED IN A SUPPLEMENT TO LER | | 94-006." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | SEE EVENT #27444 FOR A RELATED EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27570 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 07/24/94 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 04:45 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/23/94 | +------------------------------------------------+EVENT TIME: 18:38[EDT]| |NRC NOTIFIED BY: RUSHTON |LAST UPDATE DATE: 07/24/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FLOYD CANTRELL 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 HOT STANDBY | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -UNIT 2 SHUTDOWN TO REPAIR RCS DRAIN VLV SOCKET WELD PRESSURE BOUNDARY LEAK | | | | ON 07/23/94, WITH UNIT 2 AT 100% POWER, LICENSEE DETERMINED THAT THE CLOSED | | REACTOR COOLANT SYSTEM LOOP 3 INTERMEDIATE LEG DRAIN VALVE (#2-1201-U4-030) | | WAS LEAKING. | | | | AFTER INSPECTING THE VALVE WITH A CAMERA MOUNTED ON A ROBOT, LICENSEE | | DETERMINED THAT THE VALVE WAS LEAKING THROUGH ITS PACKING AND THAT THIS | | UNIDENTIFIED LEAK RATE WAS LESS THAN 0.3 GPM. TECH SPEC UNIDENTIFIED LEAK | | RATE LIMIT IS 1.0 GPM. | | | | AT 0820 ON 07/23/94, LICENSEE BEGAN TO SHUT UNIT 2 DOWN FROM 100% POWER TO | | REMOVE THE LAGGING AROUND THE VALVE, INSPECT THE VALVE, & REPAIR THE LEAK. | | | | AT 1629 ON 07/23/94, UNIT 2 ENTERED MODE 3 (HOT STANDBY). | | | | AT 1838 ON 07/23/94, AFTER REMOVING THE LAGGING AROUND THE VALVE AND | | INSPECTING THE LEAK, LICENSEE DETERMINED THAT THE VALVE SOCKET WELD WAS | | LEAKING AND CLASSIFIED THE LEAK AS A REACTOR COOLANT SYSTEM PRESSURE | | BOUNDARY LEAK. | | | | TECH SPEC LCO A/S 3.4.6.2.a REQUIRES LICENSEE TO PLACE UNIT 2 IN AT LEAST | | HOT STANDBY MODE WITHIN 6 HOURS OF DETERMINING ANY REACTOR COOLANT SYSTEM | | PRESSURE BOUNDARY LEAKAGE AND COLD SHUTDOWN MODE WITHIN THE FOLLOWING 30 | | HOURS. | | | | AT 0415 ON 07/24/94, LICENSEE DETERMINED THIS EVENT TO BE REPORTABLE TO | | THE NRC AS A 10CFR50.72 ONE HOUR TECH SPEC REQUIRED PLANT SHUTDOWN REPORT. | | | | AT 0419 ON 07/24/94, UNIT 2 ENTERED MODE 5 (COLD SHUTDOWN). | | | | LICENSEE WILL REPAIR THE VALVE AND ESTIMATES RESTARTING UNIT 2 ON 07/28/94. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27571 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 07/25/94 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 02:23 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/25/94 | +------------------------------------------------+EVENT TIME: 00:11[CDT]| |NRC NOTIFIED BY: KRUGER |LAST UPDATE DATE: 07/25/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - 1 OF 3 EDGs AUTO STARTED WITH UNIT 2 AT 100% POWER FOR UNKNOWN REASONS - | | | | AT 0011 (CDT), 1 OF 3 UNIT 2 EDGs (ESF EDG #22) AUTO STARTED IN THE | | "TEST/NON-EMERGENCY" MODE FOR UNKNOWN REASONS. | | | | UNIT 2 WAS AT 100% POWER AND NO TESTING, MAINTENANCE, OR OTHER WORK | | ACTIVITIES WERE BEING PERFORMED AT THE TIME. | | | | THERE WERE NO ONSITE OR OFFSITE ELECTRICAL PERTURBATIONS AND NO ADVERSE | | WEATHER CONDITIONS WERE PRESENT AT THE TIME. | | | | AT 0031 (CDT), LICENSEE SHUT THE EDG DOWN IN THE "AUTO/STANDBY" MODE. | | | | LICENSEE IS INVESTIGATING THE CAUSE OF THE UNEXPECTED EDG AUTO START. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | NOTE: SEE EVENT #27366 ON 06/07/94 FOR A RELATED EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27572 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 07/25/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 03:53 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 07/25/94 | +------------------------------------------------+EVENT TIME: 01:47[EDT]| |NRC NOTIFIED BY: MULLIN |LAST UPDATE DATE: 07/25/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM LAZARUS RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | -INADVERTENT START OF THE 'B' CHARGING PUMP WHILE UNIT 2 IS AT 100% POWER- | | | | WHILE SWAPPING RUNNING CHARGING PUMPS FROM THE 'A' PUMP TO THE 'C' PUMP, | | THE 'B' CHARGING PUMP INADVERTENTLY STARTED AS THE CONTROL ROOM OPERATOR | | MOVED THE CHARGING PUMP SELECTOR SWITCH FROM POSITION 1/2 TO POSITION 2/3. | | | | CONTROL ROOM OPERATORS STOPPED THE 'B' CHARGING PUMP. | | | | LICENSEE IS INVESTIGATING THE CAUSE AND DETERMINING CORRECTIVE ACTIONS. | | | | LICENSEE SUSPECTS THAT THE CHARGING PUMP SELECTOR SWITCH IS WORN AND NEEDS | | TO BE REPLACED. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+