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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17309A9961999-06-30030 June 1999 Rev 35 to HP-90, Emergency Equipment. ML17309A9941999-06-17017 June 1999 Rev 1 to COP-06.06, Guidelines for Collecting Post Accident Samples. ML17241A3541999-06-0101 June 1999 Proposed Tech Specs Section 3.5.2,allowing Up to 7 Days to Restore Inoperable LPSI Train to Operable Status ML17309A9951999-05-27027 May 1999 Rev 0 to COP-06.11, Establishing Remote Lab for Analyses of Accident Samples. ML17241A3451999-05-24024 May 1999 Proposed Tech Specs 3/4.5.1 Re Safety Injection Tanks ML17229B0711999-03-19019 March 1999 Proposed Tech Specs Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity, Per Soluble Boron Credit ML17229B0441999-03-0202 March 1999 Cycle 11 Reactor Startup Physics Testing Rept. with 990304 Ltr ML17229B0201999-02-23023 February 1999 Proposed Tech Specs 3/4.1.2.9 Re Reactivity Control sys- Boron Dilution ML17229B0361998-12-22022 December 1998 Rev 20 to Procedure C-200, Odcm. ML17229A9551998-12-16016 December 1998 Proposed Tech Specs Pages Revising Administrative Controls & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position ML17229A9161998-11-25025 November 1998 Proposed Tech Specs Pages,Replacing Insert-A,attachment to 971231 Submittal & Revises LCO 3.4.9.11 & Associated Bases ML17229A9251998-11-22022 November 1998 Proposed Tech Specs Revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1 ML17229A9131998-11-19019 November 1998 Proposed Tech Specs,Revising Administrative Contols TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position ML20155C3061998-10-29029 October 1998 Proposed Tech Specs Pages Revising Terminology Used in Notation of TS Tables 2.2-1 & 3.3-1 Re Implementation & Automatic Removal of Certain Reactor Protection Sys Trip Bypasses ML20153G0781998-08-26026 August 1998 Rev 19 to Plstqp, Guard Training & Qualification Plan ML17229A8441998-08-24024 August 1998 Proposed Tech Specs Removing Obsolete License Conditions & Incorporating Revs Which Clarify Component Operations That Must Be Verified in Response to Containment Sump Recirculation Actuation Signal ML17229A7731998-06-15015 June 1998 Proposed Tech Specs Pages 6-20,6-20a & 6-20c,correcting Info Supplied by Fuel Vendor Relative to Titles of Approved TRs That Are Referenced in Proposed TS 6.9.1.11.b ML17229A7601998-06-0303 June 1998 Proposed Marked Up TS Pages Modifying Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1 to Provide for Use of Lab Gas Partitioner to Periodically Analyze Concentration of Oxygen in Svc Waste Gas Decay Tank ML17229A7441998-05-27027 May 1998 Proposed Tech Specs Providing for More Efficient Use of on- Site Mgt Personnel in Review & Approval Process for Plant Procedures ML17229A7481998-05-27027 May 1998 Proposed Tech Specs Section 3.5.1,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions ML17229A7511998-05-27027 May 1998 Proposed Tech Specs Section 6.2.2.f,revised to Allow for Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews ML17229A6751998-03-27027 March 1998 Cycle 15 Reactor Startup Physics & Replacement SG Testing Rept. W/980402 Ltr ML17229A6501998-03-0303 March 1998 Proposed Tech Specs 3.4.7 Re RCS Chemistry/Design Features/ Administrative Controls ML17229A6381998-02-12012 February 1998 Rev 19 to C-200, Offsite Dose Calculation Manual. ML17229A6151998-01-12012 January 1998 Rev 0 to ISI-PSL-1, St Lucie Nuclear Plant Unit 1 ISI Plan. ML17229A6141998-01-12012 January 1998 Rev 0 to ISI-PSL-1, Third Interval ISI Program for St Lucie Nuclear Power Plant,Unit 1. ML17229A5691997-12-31031 December 1997 Proposed Tech Specs Pages Modifying TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity ML17309A9131997-12-29029 December 1997 Proposed Tech Specs Modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17229A5851997-12-12012 December 1997 Rev 0 to ADM-29.01, IST Program for Pumps & Valves. ML17229A5491997-12-0101 December 1997 Proposed Tech Specs Revising Units 1 & 2 EPP Section 4, Environ Conditions & Section 5, Administrative Procedures to Incorporate Proposed Terms & Conditions of Incidental Take Statement Included in Biological Opinion ML17309A9171997-11-26026 November 1997 Rev 0 to PSL-ENG-SENS-97-068, Spent Fuel Pool Dilution Analysis. ML17229A5931997-09-26026 September 1997 Rev 4 to Procedure QI-5-PSL-1, Preparation,Rev,Review/ Approval of Procedures. ML17229A5921997-09-18018 September 1997 Rev 0 to Procedure ADM-17.11, 10CFR500.59 Screening. ML20211Q5841997-09-10010 September 1997 Rev 18 to Training & Qualification Plan ML17229A4621997-08-22022 August 1997 Proposed Tech Specs Pages,Revising Specification 4.0.5 Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Control Section 6.8 ML17229A4341997-08-0101 August 1997 Proposed Tech Specs,Extending semi-annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996 & Associated SE ML17309A8951997-06-11011 June 1997 Rev 0 to PL-CNSI-97-004, Transportation & Emergency Response Plan for St Lucie Unit 1 SG Project. ML17229A3601997-05-29029 May 1997 Proposed Tech Specs Incorporating Administrative Changes That Improve Consistency Throughout TSs & Related Bases ML17229A2981997-03-0606 March 1997 Final Analysis of Radiological Consequences of Main Steam Line Break Outside Containment for St Lucie Unit 1 NPP Using NUREG-0800 Std Review Plan 15.1.5 App A. ML17229A1831996-12-20020 December 1996 Proposed Tech Specs Re Safety Limits & Limiting Safety Sys Settings ML17229A1611996-12-0909 December 1996 Proposed Tech Specs 1.9a Re Core Operating Limits Rept ML17229A1191996-10-31031 October 1996 Proposed Tech Specs 6.0 Re Administrative Controls ML17229A1111996-10-30030 October 1996 Proposed Tech Specs 3/4.9.9 Re Containment Isolation Sys & 3/4.9.10 Re Water level-reactor Vessel ML17229A1061996-10-28028 October 1996 Proposed Tech Specs 1.6 Re Channel Functional test,1.7 Re Containment Vessel integrity,1.8 Re Controlled leakage,1.9 Re Core alteration,3/4.6 Re Containment Systems & 3/4.6.1 Re Containment Vessel ML17229A1091996-10-28028 October 1996 Proposed Tech Specs Rev to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria ML17229A0951996-10-24024 October 1996 Rev 0 to 00000-OSW-16, In-Situ Pressure Test Results for St Lucie Unit 1 Spring 1996 Outage. ML17229A0861996-10-18018 October 1996 Startup Physics Testing Rept. W/961018 Ltr ML17229A2441996-09-23023 September 1996 Rev 18 to Offsite Dose Calculation Manual (Odcm). ML17228B5641996-07-15015 July 1996 Revised Tech Specs Re Core Alteration Definition ML17229A0961996-06-12012 June 1996 Rev 0 to TR-9419-CSE96-1101, Test Rept - SG Tube In-Situ Hydrostatic Pressure Test Tool Hydro Chamber Pressure Determination. 1999-06-30
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17309A9961999-06-30030 June 1999 Rev 35 to HP-90, Emergency Equipment. ML17309A9941999-06-17017 June 1999 Rev 1 to COP-06.06, Guidelines for Collecting Post Accident Samples. ML17309A9951999-05-27027 May 1999 Rev 0 to COP-06.11, Establishing Remote Lab for Analyses of Accident Samples. ML17229B0361998-12-22022 December 1998 Rev 20 to Procedure C-200, Odcm. ML20153G0781998-08-26026 August 1998 Rev 19 to Plstqp, Guard Training & Qualification Plan ML17229A6381998-02-12012 February 1998 Rev 19 to C-200, Offsite Dose Calculation Manual. ML17229A6151998-01-12012 January 1998 Rev 0 to ISI-PSL-1, St Lucie Nuclear Plant Unit 1 ISI Plan. ML17229A6141998-01-12012 January 1998 Rev 0 to ISI-PSL-1, Third Interval ISI Program for St Lucie Nuclear Power Plant,Unit 1. ML17229A5851997-12-12012 December 1997 Rev 0 to ADM-29.01, IST Program for Pumps & Valves. ML17229A5931997-09-26026 September 1997 Rev 4 to Procedure QI-5-PSL-1, Preparation,Rev,Review/ Approval of Procedures. ML17229A5921997-09-18018 September 1997 Rev 0 to Procedure ADM-17.11, 10CFR500.59 Screening. ML20211Q5841997-09-10010 September 1997 Rev 18 to Training & Qualification Plan ML17309A8951997-06-11011 June 1997 Rev 0 to PL-CNSI-97-004, Transportation & Emergency Response Plan for St Lucie Unit 1 SG Project. ML17229A2981997-03-0606 March 1997 Final Analysis of Radiological Consequences of Main Steam Line Break Outside Containment for St Lucie Unit 1 NPP Using NUREG-0800 Std Review Plan 15.1.5 App A. ML17229A2441996-09-23023 September 1996 Rev 18 to Offsite Dose Calculation Manual (Odcm). ML17229A0971996-06-10010 June 1996 Rev 0 to TP-9419-CSE96-2104, Steam Generator Tube In-Situ Hydrostatic Pressure Test Tool Hydro Chamber Pressure Determination. ML20137P3651996-05-20020 May 1996 Rev 5 to Procedure 1-1220055, Calibration of Area Radiation Monitoring Sys (Arms) ML17228B4921996-04-22022 April 1996 FPL St Lucie Unit 1 SG Program. ML20137P3381996-03-0404 March 1996 Rev 0 to Procedure 1-1400207, Calibr of Containment Process Monitor ML20137K6111995-12-0707 December 1995 Auxiliary Feedwater Pump 1C Disassembly Insp & Reassembly Mechanical Maint Procedure for St Lucie Plant,Unit 1 ML17228B3461995-11-16016 November 1995 Rev 0 to Plant Administrative Procedure 2-0010024, Inservice Testing Program for Pumps & Valves. ML20137P3061995-08-31031 August 1995 Rev 2 to Procedure 2-1220057, Functional Testing of RM-80 Power Supply Assemblies ML17228B0491995-02-0303 February 1995 Rev 0 to Subsequent Inservice Exam Plan for Pressurizer Instrument Nozzles. ML17228B0171995-01-0606 January 1995 Rev 5 to Second 10-Yr ISI Interval IST Program for Pumps & Valves St Lucie Nuclear Power Plant Unit 1. ML17228A8811994-09-28028 September 1994 Rev 0 to PSL-200-AOA-94-1, St Lucie Nuclear Plant,Unit 2 ISI Interval Request for Authorization of Alternative Exam. W/Attachment Re Implementation of Reg Guide 1.150 ML20137M1611994-09-15015 September 1994 Rev 2 to Procedure 1-1220053, Calibr of Control Room Outside Air Intake Monitors ML20080M4881994-06-14014 June 1994 Rev 15 to Chemistry Procedure C-200, Odcm ML20080M4791994-01-14014 January 1994 Rev 14 to Chemistry Procedure C-200, Odcm ML17228A4621994-01-14014 January 1994 Rev 4 to Second Ten-Yr ISI Interval IST Program. ML17228A2471993-07-24024 July 1993 Rev 0 of PSL-201, St Lucie Nuclear Power Plant,Unit 2 Second ISI Interval ISI Selected Component Schedule. ML17228A2461993-07-24024 July 1993 Rev 0 of PSL-200, St Lucie Nuclear Power Plant,Unit 2 Second ISI Interval Program Plan & Schedule from 930808- 200808 ML20137P3551993-03-0808 March 1993 Rev 1 to Procedure 1-1220055, Calibration of Area Radiation Monitoring Sys (Arms) ML17227A6011992-08-11011 August 1992 Rev 2 to JNS-PSL-204, First Ten-Year Inservice Inspection Interval Inservice Testing Program for Pumps & Valves, St Lucie Nuclear Power Plant,Unit 2. ML20141M4901992-07-30030 July 1992 Rev 14 to Training & Qualification Plan ML20137P3431992-04-10010 April 1992 Rev 1 to Procedure 1-1220053, Calibration of Control Room Putside Air Intake Monitors ML17223B2931991-10-10010 October 1991 Rev 3 to JNS-PSL-203, Second 10-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves,St Lucie Nuclear Power Plant,Unit 1. ML20137P2971991-07-0303 July 1991 Rev 1 to Procedure 2-1120070, Containment High Range Radiation Monitor Calibration ML20070T9761991-03-12012 March 1991 Rev 10 to Training & Qualification Plan ML17223A5771990-03-0707 March 1990 Rev 10 to Emergency Procedure 1-0030143, Total Loss of Ac Power. ML17223A4501989-12-15015 December 1989 Rev 2 to JNS-PSL-203, Second 10-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves. ML17308A1901988-08-24024 August 1988 Vols 1 & 2 to Rev 0 to JNS-PSL-100, St Lucie Plant Unit 1 Second 10-Yr Insp Plan. ML17221A7041988-04-0404 April 1988 Rev 0 to Pump & Valve Inservice Test Program. ML17342B0641987-12-30030 December 1987 Rev 1 to Independent Mgt Appraisal Program Plan for Florida Power & Light Co. ML17308A1831987-09-0202 September 1987 Rev 0 to Inservice Insp Second 10-yr Summary Program. ML17221A3781987-08-11011 August 1987 Inservice Testing Program,Section I,Valve Test Program & Section Ii,Pump Test Program. ML17221A3961987-01-28028 January 1987 Rev 1 to St Lucie Unit 1,Extraction Steam Piping Insp Program Guidelines. ML17347A2241986-12-22022 December 1986 Emergency Plan Implementing Procedures,Including Procedure 1101, Duties of Emergency Control Officer,Offsite Emergency Organization & Procedure 1102, Duties of Recovery Officer,Offsite Emergency.... W/861222 Ltr ML17216A6651986-06-17017 June 1986 Rev 4 to Maint Procedure 2-0910053, 12-Month Test of Automatic Load Sequence Relays. ML17216A6661986-03-26026 March 1986 Rev 5 to Maint Procedure 2-2200063, 2B Emergency Diesel Electrical Insp. ML17216A6671986-03-26026 March 1986 Rev 4 to Maint Procedure 2-2200062, 2A Emergency Diesel Electrical Insp. 1999-06-30
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ATTACHMENT f1Page1of9EMERGENCY PROCEDURE 1-OO3O142, REV.(DRAFT)ASFLORIDAPOWER6LIGHTCOMPANYSTeLUCIEUNIT1EMERGENCY OPERATING PROCEDURE 1&030142REVISION(DRAFT)ALTERNATE SHUTDOWNASTOTALNOiOFPAGES983105.70224 831007PDRADQCK05000335FPDR Page2of9FLORIDAPOWER6LIGHTCOMPANYST+LUCIEUNIT1EMERGENCY OPERATING PROCEDURE 1-0030142, REVI$ION(DRAFT)ALTERNATE SHUTDOWNI0SCOPE:Thisprocedure providesinstructions forplacingtheplantinasafecondition whenoperations cannotsafelybeconducted fromtheControlRoomduetoafireintheControlRoomand/orCableSpreading Room20SYMPTOMS:
Conditions existsuchthatoperations cannotbesafely-conducted fromtheContxolRoomduetoafire,3e0AUTOMATIC ACZIONS:None4o0IMMEDIATE OPERATORACTION:ACTION4~1ManuallytriptheReactor,Turbine,andReactorCoolantPumpspriortoleavingtheControlRoom,ifpossiblei NOTES4~1PushbuttonsandcontrolswitchesonRTGB-101, 103and104'i2Announceevacuation oftheControlRoomoverthePA~system~4i3Implement theEmergency Plan,asnecessary, inaccordance withEPIP3100021E, "DutiesandResponsibilities oftheEmergency Coordinator"
~4i4Evacuateallpersonnel fromtheControlRoomi ST~LUCIEUNIT1EMERGENCY OPERATING PROCEDURE 1-0030142, REVISION(DRAFT)ALTERNATE SHUTDOWNPage3of9AS5>>0SUBSEUENTACTIONS:5~1Manandtakecontrolofstationsasfollows:CHECK1~ReactorControl0erator"A"-HotShutdownPanel>>A>>Establish communications ontheSoundPowerPhoneSystem>>BEMonitoravailable plantparameters ontheHotShutdownPanel>>"NOTEIfthefireisintheCableSpreading Room,controlofthereactorandotherplantcomponents mustbedoneutilizing only"B"traincomponents C>>Startmotororsteam-driven AFWPumpsandfeedtheS/Gsasrequired>>
CAUTIONSlowlyopenAFWvalvestoS/Gstopreventdecreasing Pressurizer levelduetoexcessive cooldownD>>ControlPressurizer pressureandlevelbymanualcontrolofPressurizer heaters,auxiliary sprayvalves,andletdownvalves>>
SToLUCIEUNIT1EMERGENCY OPERATING PROCEDURE 1-0030142, REVISION(DRAFg)ALTERNATE SHUTDOWNPage4of9AS5<<0SUBSEGENTACTIONS:(continued) 5~1(continued) 2~Assistant NuclearPlantSurvisor-Electrical Equipment Room,ReactorAuxiliary Building-43"Elevation AiOpenorcheckopenReactorTripBreakersTCB-1'hrough 8,ifpossible~
BEPlaceisolation switchesintheISOLATEpositiononthefollowing switchgear intheorderlisted:NOTEIsolation switchlistsarepostedonrespective switchgear cabinetsthroughout plant480VBus1A3Pressurizer heaters8480VBus1B3Pressurizer heaters8480VLoCo1A24160VBus1A3480VMCC1A5480VMCC1A6480VLeC~1B24160VBus1B3480VMCC1B6480VMCC1B5480VMCClABIsolation Panel1ABIsolation PanelIAIsolation Panel1BEvacuation AlarmIsolatePanelCeAssistReactorControlOperator"A"inmonitoring unitparameters fromtheHotShutdownPanels8Onlyifaccessible (duetolocationoffire)~
yAeePage5of9ASST>>LUCIEUNIT1EMERGENCY OPERATING PROCEDURE 1-0030142, REVISION(DRAPT)ALTERNATE SHUTDOWN5,0SUBSEUENTACTIONS:(continued) 5>>l(continued) 3~ReactorControl0rator"B"-TurbineOperating Level>>A>>LocallytriporverifytheTurbinehastrippedCNECKB>>VerifyTurbineStopValvesandControlValvesareshutIfnot,initiateTurbineTripfromTurbinefrontstandard>>
C~ProceedtoTurbineBuildingSwitchgear Roomandestablish communications ontheSoundPoweredPhonecircuit>>D>>Placeisolation switchesintheISOLATEpositionforbusfeederbreakersasfollows:NOTEIsolation switchlistsarepostedonrespective switchgear cabinets>>
4160VSwgr,lA24160VSwgr>>1B26900VSwgr>>1A16900VSwgr>>1BlE>>Stop1Aand1BMainPeedwater Pumps,1Aand1BHeaterDrainPumpsandoneCondensate Pumpbyopeningtheirrespective breakers>>
CAUTIONEnsurethatoneCondensate Pumpremainsinserviceifoff-sitepoweravailable>>
ST>>LUCIEUNIT1EMERGENCY OPERATING PROCEDURE 1-0030142, REVISION(DRAFT)ALTERNATE SHUTDOWNPage6of9AS5,0SUBSEUENTACTIONS:(continued) 51(continued) 4,Nuclear0rator-ReactorAuxiliary Building>>
A>>PlaceisolateswitchesinISOLATE/LOCAL positiononthefollowing switchgear:
NOTEIsolation switchlistsarepostedonrespective switchgear cabinets>>
4160VSwgr,1AB480V.LoadCenterlABBEProceedtotheDieselGenerator Buildingandplaceisolation switcheson1Aand1BDieselControlPanelsinISOLATEpositionOTEIsolation switchlistsarepostedonrespective switchgear cabinetsC>>ProceedtotheChargingPumpareaandestablish communications ontheSoundPoweredPhonecircuit,A>>MustertheFireTeamcomprised ofatleastfive(5)individuals fromthefollowing classifications:
WatchEngineerNuclearTurbineOperator(Unit.1)NuclearTurbineOperator(Unit2)Associate NuclearPlantOperator(ANPO)Radiation Protection Man(RPM)BEProceedtofightthefireinaccordance withplantprocedures andfirefightingstrategies>>
5,2MaintainPressurizer levelatapproximately 33Kindicated levels STeLUCIEUNIT1EMERGENCY OPERATING PROCEDURE 1-0030142, REVISION(DRAFT)ALTERNATE SHUTDOWNPage7of9AS5,0SUBSEUENTACTIONS:(continued) 5i3MaintainPressurizer pressureatapproximately 2100psiabyuseofauxiliary spraysiNOTEIfPressurizer auxiliary sprayactuateswithPressurizer/spray linetemperature 5T>200oF,recordasperAP0010134'4Verifynaturalcirculation coolingofRCSbymaintaining RCStemperature atorbelow532F(lAcoldlegtemperature) byuseofAtmospheric SteamDumps,Sfoperable, 5,5Whenconditions havestabilized aftertheplanttrip,maintainor~slowlincreaseN/Glevelsbyoperation oftheAFWPumpsanddischarge valvestotheS/Gs+CAUTIONIfdecreasing RCStemperature and/orPressurizer leveloccurs,considerdecreasing AFWflowtotheS/Gs,Si6IsolateS/Gblowdownbymanuallyclosingisolation valvesattheClosedBlowdownHeatExchangersi 5+7WhenTurbinespeeddecreases to"0"RPM,verifythattheTurningGearOilPumpandtheturninggearareinoperation 5,8Whenconditions permit,reoccupytheControlRoomiReturnisolation switchestoNORMAL.forswitchesandcontrolsthatareoperational andmaintaintheUnitatHotStandbyuntilacompleteevaluation hasbeenmadee5m9IfcontrolcannotberestoredtotheControlRoom,makepreparations toplacetheUnitinaColdShutdowncondition byutilizing OP1-0030127, "ReactorPlantCooldown-HotStandbytoColdShutdown,"
asaguideandsubstituting localmanualoperations whererequirede
~NOTEPriortodepressurization below1600psia,amanualblockingofallequipment associated withSIASmustbeaccomplished topreventSIASactuationi ST,LUCIEUNIT1EMERGENCY OPERATING PROCEDURE 1-0030142, REVISION(DRAFT)ALTERNATE SHUTDOWNPage8of9AS6oOPURPOSEANDDISCUSSION:
Thisprocedure providesinstructions forplacingtheplantinasafecondition whenoperations cannotsafelybeconducted fromtheControlRoomduetoafireintheControlRoomand/orCableSpreading RoomTheReactor,Turbine,andReactorCoolantPumpsaremanuallytrippedpriortoleavingtheControlRoom,ifpossible, orlocallyfromtheReactorTripSwitchgear, Turbinefrontstandard, and6i9KVSwitchgeari Aheatsinkisprovidedbyautomatic steamdumptotheCondenser and/ortoatmosphere Levelismaintained inthe'S/Gsbymanualcontrolofauxiliary feedwater valveswithflowfurnished bytheAFWPumps~Pressurizer levelandpressurearemaintained bymanualcontrolofPressurizer heaters,auxiliary sprayvalves,andletdownvalves,andaremonitored attheHotShutdownPanel+Isolation switcheslocatedintheReactorAuxiliary BuildingElectrical Equipment Room,TurbineBuildingSwitchgear Room,DieselGenerator Rooms,andReactorAuxiliary BuildingaremanuallyselectedtotheISOLATEpositiontopreventinadvertant operation ofvitalequipment duetopossibleelectrical malfunction intheunattended ControlRoomAcopyofthisprocedure willbepostedateachmannedoperating stationrequiredforplantshutdownfromoutsidetheControlRoom~Alistingofisolation switcheswillbepostedoneachofthefollowing panels,MCCs,anddistribution buses2~3~4~5~6~7~LoadCenterslA2,1B2,1A5,1B9,lAB,1A6,1B6Isolation PanelslA,1B,IABMCClA5,1A6,1B5,1B&4160VBuses1A3,1B3,lAB4160VBuses1A2,IB26900VBuseslA1,1BlDieselGenerator lAand1BControlPanelsTheNuclearPlantSupervisor willutilizeadditional personnel asavailable toassistinrequiredsubsequent actionso ST+LUCIEUNIT1EMERGENCY OPERATING PROCEDURE 1-0030142, REVISION(DRAFT)ALTERNATE SHUTDOWNPage9of9AS7,0
REFERENCES:
7elEOP10030141,"ControlRoomInaccessibility"
>>72St~LucieUnit1Technical Specificationsi 7.310CFR50,AppendixR.80RECORDS:8~1Acompleted, initialed copyofthisprocedure shallberetainedintheplantfilesi9'REVIEWANDAPPROVAL:
ReviewedbyFacilityReviewGroupApprovedbyRevisionReviewedbyPRGApprovedbylantManagerPlantManager191919EP1-0030142 Revision(draft)TotalNoofPages9 TABLE1PAGE1OF4ISOLATION SWITCHESAVAILABLE FORALTERNATE SHUTDOWN-STLUCIF.UNITNO1PANELORPOWERCENTERIsolation Panel1AIsolation PanellBPLANTLOCATIONA-SwgrRoomB-SwgrRoomFIRE70NE60SWITCHDESIGNATIONSS/189-1SS/158SS-3/603Ss-l/603Ss-l/380SS/130SS-1/157SS/189-2SS-2/157SS-4/604SS-2/603SS-2/380COMPONENT AuxilfarySprayValveLetdown&SprayVa1vesControlSGlAPress&LevelIndfcatfon SG1AAtmSteamDumpControlSG1ALevel(WfdeRange>Pressurfzer level&PressIndT.etdownIsolatfon ValveV-1402,PORVI-SF.-02-01, ChargingLfneIsoAuxflfary SprayValveLetdownStopValveSG18Press&T.evelIndfcatfon SG18AtmSteamPumpControlSG18Level(WideRange>Pressurfzer Level&PressIndV-1404,PORVeIsolation PanellABIsolation PanelCableSpreadRoomCommunications Room5773SS/631SS/632AFWPumplCTurbfneIndAFWPump1CStopValveFfreAlarm/SfteFvac-ControlControlRoomPACodeCallDGlAControlPanelDGBuf1dinglAVoltageControlFrequency ControlStartCfrcuftDGlBControlPanelDGBuf1ding1BVoltageControlFrequency ControlStartCfrcuftMCClA5A-SwgrBoom60V-2514,BAMPtoCbrgrPumpsMV-14-6,FanCoo>erCCWInletMV-4-8,FanCoolerCCWOutletMV-09-9,AFWPumplADfscharge in>nnwoAmr.vr PAGE2OF4~~0TABLE1ISOLATION SWITCHESAVAILABLE FORALTERNATE SHUTDOWN(Cont'd)STLUCIEUNITNO1PANELORPOWERCENTERMCC1B5MCCC1A6MCClB6MCC-1ABPLANTLOCATIONB-SwgrRoomA-SwgrRoomB-SwgrRoomCableSpreadRoomFIRE70NE566057SWITCHDESIGNATIONCOMPONFNT V-2508,8AMT18GravityFeedV-250~,BAMTlAGravityFeedMV-14-5,FanCoolerCCWInletMV-14-7,FanCoolerCCWOutletMV-OO-10, AFWPump18Discharge MV-09-14, AFWCrossTieV-2504,RWTtoChargingPumpsV-1405,PORVBlockBAMP1ABAMP1BHVA-3A,ControlRoomACHVA-6A,ShieldBuildingExhHVE-'13A, ContRoomBoosterHVA-38,ContRoomACHVF.-68,Shield8uildingFxhHVE-138,ContRoomBoosterHVA-3C,ContRoomACMV-0'l-ll, AFWpumplCDischarge MV-QO-17, AFWPump1CDischarge MV-08-1'1, AFWPump>urbSupplyMV-08-14, AIWPumpTurbSupplyMV-14-1,C(WDischarge MV-14-2,CCWDischarge MV-14-3,CCWDiscbargeMV-14-4,COPDischarge 480VSwgr1A2A-SwgrRoom60SSTransformer 1A2BusTieto480V1A8AirRecircFanHVS1AAirRecircFanHVS18ChargingPump1A TABLE1PAGE3OF4~~ISOLATION SWITCHESAVAILABLE FORALTERNATE SHUTDOWN(Cont'd)STLUCIF.UNITNO1PANELORPOWERCENTER480VSwgr1B2480VSwgrlAB480UBus1A3480VBus1B34.16kVBuslA3PLANTLOCATIONB-SwgrRoomAB-SwgrRoomCableSpreadRoomCableSpreadRoomA-SwgrRoomFIREZONE47575760SWITCHDESIGNATIONCOMPONENT SSTransformer 1H2HusTfeto480VlABAfrRecfrcFan1CAfrRecfrcFan19CbargfngPump1HHusTfeto480VSwgr1A2Hus<feto480VSwgr182CbargfngPumplCHeater.HankP-1HeaterBankB-1HeaterBan'kH-2HeaterHankH-3HeaterBankP-2HeaterHankH-4HeaterHankH-5HeaterBankB-6AHPSIPumpALPSIPumpAContSprayPumpFeedtoPressHtrTrans1AACompCoolfngWtrPumpAIntakeCool.fngWtrPumpFeedto4.16kVSwgrlABFeedFrom4.16kUHus1A2Feedto4.16kVStaSerTrans1A2FeedfromFmergDfese1AAAuxflfary Feedwater Pump TABLE1PAGF.4OF4~~t~ISOLATION SWITCHESAVAILABLE FORALTERNATF.
SHUTDOWN(Cont'd'l STLUCIEUNITNO1PANELORPOWERCENTER4.16kVBus1834.16kVBuslAB4.16kVBus1A24.16kVBus1826.9kVBus1Al6.'9kVBus181PLANTLOCATION8-SwgrRoomAB-SwgrRoomTurbineBufldfngTurbineBuildingTurbineBufldingTurbineBuildingFIRE7.0NE564721222122SWITCHDESIGNATTON8HPSIPump8LPSIPump8ContSprayPumpFeedtoPressHtrTrans188CompCoolingWtrPump8IntakeCoolfng-WtrPumpFeedto4.16kVSwgr1ABFeedfrom4.16kVBus182Feedto4.16kVStaSerTrans182FeedfromEmergDfesel88Auxflfary Feedwater PumpCHPSIPumpCCompCoolfngWtrPumpCIntakeCoolingWtrPump'eedfrom4.16kVBuslA3Feedfrom4.16kVBus183Feedto4.16kVStaSerTrans1AlFeedfromSUTranslAFeedto4.16kVSwgrlA3Feedto4.16kVStaSerTrans181FeedfromSUTrans18Feedto4.16kVSwgr183FeedfromSUTrans1AFeedfromSUTrans18 0502seFLORIDAPOWER6LIGHTCOMPANYSTLUCIEPLANT-UNITNO~1ALTERNATIVE SHUTDOWNe)Attachment loutlinesthebasicstepsrequiredtobringtheplanttocoldshutdownfromoutsidetheControlRoom.Thisprocedure hasbeendeveloped toinstructplantoperators inthespecifi'c tasksrequiredtoeffectsafeshutdown.
f)'hemanpoweravailable toperformsafeshutdownfunctions aswellfiresisdescribed inAttachment l..~r.(y-c-5g)Testswillbeperformed periodically andthattheequipment-cannot
-be-operated-from-th
,that-the-equipmen~
tocratefrfromtheHotShutdown-.Panel-when.
transfer-swah position.
on(gg~(+F~)yPP)IasfightChh)Technical Specifications willbepreparedtocoverallnewisolation/
transferswitchesaddedforalternative shutdown.
~i)Onlyexistingcomponents andsystemswillbeemployedforalternative shutdown.
Assuch,verification ofsystemcapabilities isnotrequired.
Circuitry modifications willbeconsistent withexistingdesigncriteria.
j)Nocreditistakenforrepairofdamagedcoldshutdownequipment.
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