U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/20/96 - 02/21/96 ** EVENT NUMBERS ** 29986 29999 30000 30001 30002 30003 30004 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29986 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 02/16/96 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 16:29 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/16/96 | +------------------------------------------------+EVENT TIME: 15:57[EST]| |NRC NOTIFIED BY: ROGER WEST |LAST UPDATE DATE: 02/20/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING 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 +------------------------------------------------------------------------------+ | - PRESENT RAD MONITOR LOCATION DOES NOT MEET REQUIREMENTS OF 10 CFR 70.24 - | | | | A LICENSEE PRELIMINARY CALCULATION INDICATES THAT A RAD MONITOR PRESENTLY | | LOCATED OUTSIDE THE NEW FUEL VAULT DOOR WOULD NOT DETECT A CRITICALITY IN | | THE NEW FUEL ASSEMBLIES AS THEY WERE LOADED INTO THE NEW FUEL VAULT BECAUSE | | OF THE SHIELDING PROVIDED BY THE VAULT CONCRETE WALLS. THUS, THE EXISTING | | RADIATION MONITORING CAPABILITIES FOR A CRITICALITY IN THE NEW FUEL VAULT | | DO NOT APPEAR TO MEET THE REQUIREMENTS OF 10 CFR 70.24, CRITICALITY | | ACCIDENT REQUIREMENTS. | | | | AS AN INITIAL CORRECTIVE ACTION, THE LICENSEE HAS MOVED A NEW FUEL ASSEMBLY | | TO A POSITION INSIDE THE VAULT THAT IS CLOSEST TO THE VAULT DOOR. BASED | | ON LICENSEE PRELIMINARY CALCULATIONS, THIS NEW FUEL ASSEMBLY LOCATED NEAR | | THE RAD MONITOR WILL ENABLE THE RAD MONITOR TO DETECT A CRITICALITY INSIDE | | THE VAULT BASED ON THE SOURCE TERM GUIDANCE CONTAINED IN 10 CFR 70.24. THE | | LICENSEE IS IN THE PROCESS OF DETERMINING PERMANENT CORRECTIVE ACTIONS. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | *** UPDATE 02/20/96 @ 1319 EST BY R. WEST TAKEN BY MACKINNON *** | | | | IT HAS BEEN DISCOVERED THAT THE NEW FUEL VAULT CRITICALITY MONITOR ALARM | | SETPOINT EXCEEDED THE VALUE NEEDED TO ENSURE THAT A CRITICALITY WOULD BE | | DETECTED BASED ON PRELIMINARY CALCULATIONS AND GIVEN THE MODIFIED NEW FUEL | | ASSEMBLY ARRANGEMENT. THE MONITOR'S ALARM SETPOINT HAS BEEN REDUCED FROM | | 1 R/HOUR TO 5 mR/HOUR. THIS WILL ALLOW THE MONITOR TO DETECT A CRITICALITY | | BASED ON THE SOURCE TERM GUIDANCE IN 10 CFR 70.24. THE LICENSEE INFORMED | | THE NRC RESIDENT INSPECTOR OF THIS UPDATE. THE NRC OPERATIONS CENTER | | NOTIFIED THE R3DO (B. J. HOLT). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29999 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/20/96 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 18:48 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/20/96 | +------------------------------------------------+EVENT TIME: 18:18[EST]| |NRC NOTIFIED BY: BECKER |LAST UPDATE DATE: 02/20/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL RULAND RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS |BRUCE BOGER EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION 3.0.3 ENTRY AFTER HIGH PRESSURE SAFETY INJECTION | | (HPSI) SYSTEM WAS DECLARED INOPERABLE DUE TO POTENTIAL CLOGGING OF THE HPSI | | THROTTLE VALVES DURING THE CONTAINMENT SUMP RECIRCULATION PHASE | | | | DURING REVIEW OF A PACIFIC GAS AND ELECTRIC OPERATIONAL EXPERIENCE REPORT | | CONCERNING POTENTIAL CLOGGING OF THE EMERGENCY CORE COOLING (ECC) SYSTEM | | THROTTLE VALVES, THE LICENSEE DETERMINED THAT HPSI VALVES 2-SI-616, | | 2-SI-626, 2-SI-636, 2-SI-646, 2-SI-617, 2-SI-627, 2-SI-637, AND 2-SI-647 | | ARE SUSCEPTIBLE TO SIMILAR CLOGGING. THIS IS BASED ON THE FOLLOWING: | | 1) THE CONTAINMENT SUMP SCREEN OPENING IS 0.187" AND 2) THE HPSI INJECTION | | VALVES' OPENINGS ARE 0.125" AT SEAT-TO-PLUG INTERFACE AND HAVE 4 ISOSCELES | | TRIANGLE SHAPED OPENINGS WITH A MAXIMUM DIMENSION OF 0.187". THUS, THE | | VALVE WILL NOT ALLOW FOREIGN MATERIAL PARTICLES OF 0.187" DIAMETER TO PASS. | | THIS POTENTIAL CLOGGING COULD RESULT IN A PARTIAL OR COMPLETE LOSS OF | | POST-ACCIDENT HPSI CORE COOLING FLOW. | | | | BASED ON THIS POTENTIAL PLUGGING, TECHNICAL SUPPORT PERSONNEL DETERMINED | | THAT THE HPSI THROTTLE VALVES ARE SUBJECT TO A COMMON MODE FAILURE | | (PLUGGING AND LOSS OF CORE COOLING FLOW) AND SHOULD BE CONSIDERED | | INOPERABLE PENDING COMPLETION OF FURTHER STUDIES AND/OR REPAIRS. THE | | LICENSEE DECLARED THE HPSI PUMPS INOPERABLE AND ENTERED TECHNICAL | | SPECIFICATION 3.0.3 (HOT SHUTDOWN CONDITION IN 6 HOURS AND COLD SHUTDOWN | | CONDITION IN THE FOLLOWING 24 HOURS). UNIT 2 SHOULD BE SHUT DOWN BY 2300. | | ALL OTHER ECC SYSTEMS ARE FULLY OPERABLE, THE EMERGENCY DIESEL GENERATORS | | ARE OPERABLE, AND THE ELECTRICAL GRID IS STABLE. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND PLANS TO MAKE A PRESS | | RELEASE. THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30000 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/20/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 19:28 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/20/96 | +------------------------------------------------+EVENT TIME: 19:10[EST]| |NRC NOTIFIED BY: BIJIARELLI |LAST UPDATE DATE: 02/20/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL RULAND 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AT THE PRESENT TIME, THE LICENSEE CANNOT CONFIRM THAT UNIT 1 DOES NOT HAVE | | BORAFLEX DEGRADATION OF SPENT FUEL RACK SUPER MODULE #10. THIS | | MEANS THAT THE LICENSEE CANNOT CONFIRM THAT RACK #10 MEETS TECHNICAL | | SPECIFICATION 5.5.b (Keff OF SPENT FUEL POOL RACKS <0.9). | | | | WHILE REVIEWING THE PERFORMANCE OF SPENT FUEL RACKS WHICH WERE TESTED IN | | SEPTEMBER 1995, THE LICENSEE COULD NOT CONFIRM THAT TECHNICAL SPECIFICATION | | 5.5.b (Keff OF THE SPENT FUEL POOL RACKS <0.9) WAS MET FOR SPENT FUEL POOL | | RACK #10 (CALLED SUPER MODULE #10). THE SPENT FUEL POOL HAS 10 RACKS IN | | IT, AND THE LICENSEE HAS CONCERNS ABOUT THE POSSIBILITY OF BORAFLEX | | DEGRADATION CAUSED BY EROSION IN SUPER MODULE #10 RACK. AT THE PRESENT | | TIME, RACK #10 HAS NEW FUEL IN IT FOR THE NEXT REFUELING OUTAGE AND SOME | | OLD FUEL FROM A COUPLE OF FUEL CYCLES AGO. THE LICENSEE STATED THAT A HIGH | | GAMMA FLUX IS NEEDED TO CAUSE THE BORAFLEX TO DEGRADE, AND AT THE PRESENT | | TIME, RACK #10 IS NOT SUBJECTED TO A HIGH GAMMA FLUX. IN ADDITION, THE | | LICENSEE IS CONSIDERING INSTALLING NEUTRON MONITORS IN SUPER MODULE #10 | | RACK. | | | | THE LICENSEE NOTIFIED THE STATE AND LOCAL COUNTIES OF THIS EVENT. THE NRC | | RESIDENT INSPECTOR WAS INFORMED OF THE EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30001 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 02/20/96 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 19:47 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 02/20/96 | +------------------------------------------------+EVENT TIME: 18:00[CST]| |NRC NOTIFIED BY: VERCELLI |LAST UPDATE DATE: 02/20/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |B. J. HOLT 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 3 | N Y 99 POWER OPERATION | 99 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DEFICIENCY FOUND IN THE PROCEDURAL STEPS TO ABNORMAL OPERATING PROCEDURE | | DGA-12 (STATION BLACKOUT). | | | | WHILE REVISING ABNORMAL OPERATING PROCEDURE #DGA-12 FOR A STATION BLACKOUT | | MODIFICATION, A SYSTEM ENGINEER FOUND A DEFICIENCY WITH THE CONTROL ROOM | | VENTILATION ISOLATION STEPS. THE PROCEDURE, AS WRITTEN, WOULD NOT ALLOW | | THE CONTROL ROOM EMERGENCY FILTRATION SYSTEM TO OPERATE AND PRESSURIZE THE | | CONTROL ROOM TO 0.125" AS REQUIRED IN THE DESIGN BASES AND SECTION 6.4 | | (RESTORE WITHIN 40 MINUTES) OF THE UPDATED FINAL SAFETY ANALYSIS REPORT | | DURING A DESIGN BASIS ACCIDENT. THE PROBLEM IS ON A LOSS OF OFFSITE | | POWER/LOSS OF COOLANT DESIGN BASES ACCIDENT, POWER IS LOST TO THE TOXIC GAS | | ANALYZER WHICH FAILS SAFE (ISOLATES). THIS PLACES THE CONTROL ROOM IN | | ISOLATION WITHOUT THE ABILITY TO PRESSURIZE. THIS PLACES UNIT 3 IN A | | 14-DAY ADMINISTRATIVE TECHNICAL REQUIREMENT TO RESTORE THE CONTROL ROOM | | EMERGENCY FILTRATION SYSTEM TO OPERABLE STATUS OR TO PLACE UNIT 3 IN A | | CONDITION WHERE SECONDARY CONTAINMENT IS NOT REQUIRED. THE LICENSEE WILL | | MAKE A PROCEDURAL CHANGE WHICH WILL ADD STEPS TO UNISOLATE THE TOXIC GAS | | MONITOR WITHIN 40 MINUTES. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |IRRETRIEVABLE WELL LOGGING SOURCE | |EVENT NUMBER: 30002 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ARCO ALASKA INCORPORATED |NOTIFICATION DATE: 02/20/96 | | CITY: NORTH SLOPE BRO REGION: 4 |NOTIFICATION TIME: 20:14 [ET]| | COUNTY: STATE: AK |EVENT DATE: 02/17/96 | |LICENSE#: 420009003 AGREEMENT: N |EVENT TIME: 16:40[YT ]| | DOCKET: |LAST UPDATE DATE: 02/20/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHRIS VANDENBURGH RDO | | |DON COOL (NMSS) EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KEN TURNER | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |EIRR 39.77(c) WELL LOGGING SOURCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | KEN TURNER, THE RADIATION SAFETY OFFICER FOR SCHLUMBERGER TECHNOLOGY CORP., | | IS REQUESTING PERMISSION TO ABANDONED TWO WELL LOGGING SOURCES. | | | | TWO AMERICIUM-241 WELL LOGGING SOURCES (50 ęCi AND 4.5 ęCi) ARE STUCK IN A | | WELL ABOUT 8,200 FEET UNDERGROUND. THE SOURCES ARE REFERENCE SOURCES FOR | | THE ELECTRONIC PORTION OF A WELL LOGGING TOOL. THE WELL IS LOCATED AT THE | | KUPARUK RIVER UNIT ON THE NORTH SLOPE NEAR BARROW, ALASKA. THE WELL NUMBER | | IS 3H-28A, AND THE WELL IS OWNED BY ARCO ALASKA INCORPORATED. PERMISSION | | TO ABANDONED THE SOURCES HAS BEEN REQUESTED. THE WELL WILL BE CEMENTED UP | | FROM THE SOURCES TO THE 7,786 FOOT LEVEL. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30003 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 02/21/96 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 00:57 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/20/96 | +------------------------------------------------+EVENT TIME: 22:25[EST]| |NRC NOTIFIED BY: W. L. BARGERON |LAST UPDATE DATE: 02/21/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 92 POWER OPERATION | 92 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION 3.0.3 ENTRY - INOPERABILITY OF UNIT 1 NUCLEAR | | SERVICE COOLING WATER (NSCW) DUE TO THE DISCOVERY OF CRACK INDICATIONS IN | | THE PUMP DISCHARGE LINES NEAR A WELDED CONNECTION (A CONDITION WHICH COULD | | HAVE RESULTED IN THE FAILURE OF BOTH TRAINS OF NSCW DURING A POSTULATED | | SEISMIC EVENT) | | | | AT 1810 ON FEBRUARY 20, 1996, THE LICENSEE DECLARED UNIT 1 NSCW TRAIN 'B' | | INOPERABLE AND ENTERED A 72-HOUR TECHNICAL SPECIFICATION LIMITING CONDITION | | FOR OPERATION (LCO) FOLLOWING THE DISCOVERY OF CRACK INDICATIONS IN THE | | PUMP DISCHARGE LINES NEAR A WELDED CONNECTION AND FOLLOWING THE SUBSEQUENT | | ENGINEERING EVALUATION. INSPECTION OF UNIT 1 NSCW TRAIN 'B' WAS INITIATED | | AFTER THE DISCOVERY OF SIMILAR CRACK INDICATIONS IN THE UNIT 1 NSCW TRAIN | | 'A' DISCHARGE LINES ON FEBRUARY 19, 1996. (WHEN SMALL LINEAR CRACK | | INDICATIONS WHICH WERE NOT LEAKING WERE DISCOVERED ON TRAIN 'A' ON FEBRUARY | | 19, 1996, AN INTERIM OPERABILITY DETERMINATION WAS MADE UNTIL FURTHER | | ENGINEERING EVALUATION COULD EITHER PROVE OR DISPROVE OPERABILITY, AND | | REPAIRS WERE COMMENCED.) | | | | THERE ARE 3 PUMPS PER TRAIN IN THE NSCW DESIGN, AND THE UNIT 1 DESIGN IS | | CONDUCIVE TO FATIGUE CRACKING AS EVIDENCED ON ALL 6 PUMPS. BASED ON | | ENGINEERING EVALUATION BEING UNABLE TO CONCLUDE THAT TRAIN 'A' NSCW WOULD | | PERFORM ITS SAFETY FUNCTION AFTER A SEISMIC EVENT, THE LICENSEE ENTERED | | TECHNICAL SPECIFICATION 3.0.3 AT 2225 ON FEBRUARY 20, 1996. THIS TECHNICAL | | SPECIFICATION WAS EXITED AT 2242, WHEN SUFFICIENT REPAIRS WERE COMPLETED ON | | TRAIN 'A' NSCW TO RESTORE THE SYSTEM TO OPERABLE STATUS. THE 72-HOUR LCO | | FOR TRAIN 'B' IS STILL IN EFFECT, AND REPAIRS ARE UNDERWAY. THIS TECHNICAL | | SPECIFICATION LCO IS NOT CASCADED TO THE EMERGENCY DIESEL GENERATORS. ONLY | | TWO PUMPS ARE REQUIRED TO MEET MINIMUM FLOW REQUIREMENTS, AND THE EMERGENCY | | DIESEL GENERATOR ASSOCIATED WITH THE INOPERABLE NSCW TRAIN CURRENTLY HAS | | FLOW THROUGH IT AND IS CONSIDERED TO BE OPERABLE. IN ADDITION, THE | | LICENSEE IS DEVELOPING A PLAN TO EVALUATE THE NSCW PIPING ON UNIT 2. THE | | UNIT 2 PIPING IS NEWER, AND THE UNIT 2 NSCW SYSTEM HAS A DIFFERENT | | GEOMETRY. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30004 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 02/21/96 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 03:34 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 02/21/96 | +------------------------------------------------+EVENT TIME: 01:40[EST]| |NRC NOTIFIED BY: STEPHEN DAVIS |LAST UPDATE DATE: 02/21/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RULAND 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL SINGLE FAILURE CONCERNS WHICH COULD IMPACT TRAIN 'A' AND 'B' | | ENGINEERED SAFEGUARDS FEATURES (ESF) ACTUATION CIRCUITRY WHILE THE UNIT IS | | IN COLD SHUTDOWN DUE TO A LACK OF SEPARATION BETWEEN TRAIN 'A' AND TRAIN | | 'B' COMPONENTS | | | | DURING REVIEW OF AN EXTENT OF CONDITION EVALUATION, ENGINEERING IDENTIFIED | | THAT THE TWO CONTAINMENT ISOLATION PHASE 'B' ACTUATION PUSH BUTTONS LOCATED | | IN THE CONTROL ROOM ARE NOT SEPARATED OR MODULARIZED AS REQUIRED. EACH | | PUSH BUTTON ACTUATES THE CONTAINMENT ISOLATION PHASE 'B' RELAYS IN BOTH | | TRAINS 'A' AND 'B'. WIRES FROM BOTH TRAINS 'A' AND 'B' ARE TERMINATED ON | | THE CONTACT BLOCKS OF BOTH PUSH BUTTONS AND COME INTO CONTACT BEFORE THEY | | EXIT THE PANEL. THE TWO PUSH BUTTONS ARE LOCATED APPROXIMATELY ONE INCH | | APART. POWER SUPPLIES TO THE PHASE 'B' ISOLATION RELAYS ARE COMMON WITH | | ALL OTHER ESF RELAYS. DUE TO A LACK OF SEPARATION BETWEEN TRAIN 'A' AND | | TRAIN 'B' COMPONENTS, THERE ARE POTENTIAL SINGLE FAILURE CONCERNS WHICH | | COULD IMPACT TRAIN 'A' AND TRAIN 'B' ESF ACTUATION CIRCUITRY. THIS IS | | STILL UNDER EVALUATION BY ENGINEERING. | | | | THE UNIT IS NOT IN ANY TECHNICAL SPECIFICATION LIMITING CONDITIONS FOR | | OPERATION AT THIS TIME BECAUSE IT IS IN A COLD SHUTDOWN CONDITION. ONE | | RESIDUAL HEAT REMOVAL PUMP AND ONE REACTOR COOLANT PUMP ARE CURRENTLY IN | | SERVICE. THE EMERGENCY DIESEL GENERATORS ARE ALSO AVAILABLE. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+