ML17347B337

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Advises That Ref Matl Re Operator Exam Scheduled for Wk of 891106 Shipped to Listed Address,Per NRC 890831 Request. Examiners Should Return Ref Matl to Facility After Exam,To Be Maintained for Next Exam Cycle
ML17347B337
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 09/13/1989
From: Woody C
FLORIDA POWER & LIGHT CO.
To: Casto C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
L-89-334, NUDOCS 8909200241
Download: ML17347B337 (27)
v • d • e


Text

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ACCELERATED 1>1WRIBUT306 DEMONSTRATION SY~Eg REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8909200241 DOC.DATE: 89/09/13 NOTARIZED: NO DOCKET g FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION WOODY,C.O. Florida Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION CASTO,C.W. Region 2, Ofc of the Director

SUBJECT:

Advises that ref matl re operator exam scheduled for wk of 891106 shipped to listed address,per NRC 890831 request.

DTSTRTBUTTON CODE: IE42D COPTES RECETVED:LTR TITLE: Operator Licensing Examination Reports i ENCL ~ STSE: Rk NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 PD 1 1 EDISON,G 1 1 INTERNAL: AEOD/DSP/TPAB 1 1 NRR SHANKMAN,S 1 1 NRR/DLPQ/HFB 10 1 1 /DLQQ/OLB 10 1 1 NUDOCS-ABSTRACT 1 1 REG FILE 02 1 1 RGN2 FILE 01 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 . 1 NOIR ZO ALL t RZKSlt RZCZPIIÃIS PURSE HELP US I0 REDUCE HASTE'. 02KACI', 'IHE DOCUMEPZ CONTROL DESKS RXN Pl-37 (EXT. 20079) TO EIiZMIIRXB YOUR NAME HKH DIPHKSOTICN LISTS P5R DOCQKMIS RÃJ DOMPT NEED)

TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 12

P.O. Box14000, Juno Beach, FL 33408-0420 SEPTEQBER i 3 1989 L-89-334 10 CFR 55 Mr. Charles W. Casto, Acting Chief Operator Licensing Section, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, N. W., Suite 2900 Atlanta, GA 30323

Dear Mr. Casto:

Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Operator License Examinations Scheduled for Week of November 6 1989 Florida Power & Light Company (FPL) has shipped the reference material requested by an NRC letter dated August 31, 1989 to the examiners and addresses listed below:

Attn: Dim Morman U. S. Nuclear Regulatory Commission, Region II 101 Marietta Street, N. W., Suite 2900 Atlanta, Georgia 30323 Attn: Bob Grul Battele Pacific N. W. Labs Sigma 3 Building 13000 Area 3160 George Washington Way Richland, WA 99352 The reference material was shipped by Federal Express to NRC Region II and Battele Pacific N.W. Labs on September 6, 1989, from the Turkey Point Plant. An index of the reference material is attached for your information.

The examiners are requested to return the reference material to the Turkey Point Plant Training Staff, after the exam, so maintained current for the next exam cycle.

it can be 890920024i 8909i8 PDR ADOCK 05000250 V PDC an FPL Group company

L-89-334 Page 2 Should you require any additional information, please contact Mr.

Paul J. Baum at (305) 246-1300.

Very truly yours, C. 0. Woody Acting Senior Vice President Nuclear COW/JRH/cm Attachment cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Bob Grul, Battele Pacific N. W. Labs Document Control Desk, USNRC

Page 1

SUMMARY

OF REFERENCE MATERIAL 7echnical Specifications and 0-ADM-021 Technical Specification complementation Procedure Unit 3 Plant Curve Book Precautions, Limitations, and Setpoints Document Special Enstructions Book Radiation Protection Manual and RWP Procedure Transient and Accident Analysis Text Mitigating Core Damage Text

  • System Descriptions

+Siaulator Training Materials Lesson Plans Systems Pxocedures Transient and Accident Analysis Mitigating Core Damage Question Bank Systeas Procedures Transient and Accident Analysis Miti;gating Core Damage

  • JPM's Plant Dra~ings Primary Systems Secondary Systems Logics Controls

Page 2 Original and Upgrade Procedure Index

+Original Administrative Procedures

  • Original Operating Procedures
  • Original Off-Normal Procedures
  • Upgrade Administrative Procedures
  • Upgrade Unit 3 and Common Operating Procedures

>Upgrade Unit 3 General Operating Procedures

+Upgrade Unit 3 and Common Off-Normal Operating Procedures

  • Fuel Handling Procedures
  • Annunciator Procedures
  • Emergency Plan Implementing Procedures
  • Unit 3 Emergency Operating Procedures
  • Unit 3 Emergency Operating Procedures Basis Documents
  • - Detailed Lists included on subsequent pages

TVRK POINT NVCLEAR TRAINING APARTMENT SY5TEIVI-OESCRIPTION5 50 Final No. Rev. No. Approval TITLE Date 2 01/07/89 Reactor. Vessel and Internals 3 2 11/22/88 Incore Instrumentation 4 4 06/20/89 Excore Nuclear Instrumentation 5 5 06/14/89 Full Length Rod Control 6 3 07/12/89 Rod Position Indication System 7 3 12/14/88 Reactor Coolant System 8 2 01/06/89 Reactor Coolant Pumps 9 4 06/02/89 Pressurizer and Relief System 11 3 11/16/88 Steam Generator 13 3 08/11/88 Chemical & Volume Control System 21 5 02/28/89 Emergency Core Cooling System 25 5 06/20/89 Containment Spray 28 3 05/16/89 Containment Post Accident Monitoring & Post Accident Sampling System 40 3 02/28/89 Component Cooling Water 3 10/03/88 Fuel Handling System 63 3 08/22/88 Reactor Protection and Safeguards Actuation System 68 4 08/24/88 Radiation Monitoring and Protection 90 2 12/07/88 Electrical Heat Tracing System 102 2 08/15/88 Steam Generator Blowdown System 104 4 09/29/88 Main and Extraction Steam System 105 .3 12/14/88 Steam Dump System 112 4 06/17/88 Condensate and Feedwater Systems 117 10 06/23/89 Auxiliary Feedwater System 123 3 06/14/89 Condenser and Circulating Water System 127 2 10/10/88 Main Turbine Control 130 5 02/17/89 Turbine, Turbine Oil, and Gland Seal Systems 132 3 02/27/89 Turbine Plant Cooling Water System 137 4 02/28/89 Emergency Diesel Generator and Auxiliaries 139 2 10/10/88 Main Generator and Controls 140 2 11/22/88 Main Power Distribution 144 3 10/12/88 120 VAC & 125 VDC Distribution System 153 4 02/28/89 Fire and Service Water 155 8 07/17/89 Plant Air Systems 165 6 08/21/89 Intake Cooling Water 166 4 06/14/89 Ventilation System and AirConditioning 170 3 10/18/88 Emergency Load Sequencer/Bus Stripping 176 3 02/23/89 Fire Protection'and Alarm System

INITIAL COND IT IONS 1 SPECIFIC FAILURE CAPAB I LIT IES 2 CAUSE AND EFFECTS 3

'GENERIC FAILURE CAPABILITIES 4 TURKEY POINT SIMULATOR TRAINING MATERIALS FAILURE ACTIVATION METHODS 5 MODELING PROBLEMS 6 TABLE OF CONTENTS PERFORMANCE TEST DISCREPANCIES SIMULATOR . PLANT DIFFERENCES DEGRADED PRESSURE CONTROL Cc HEAT REMOVAL SCENARIOS SIMULATOR INSTRUCTOR MANUAL 10 SIMULATOR TRAINING SCENARIOS 11 SIMULATOR EVhLUhTION SCENARIOS 12

JOB PERFORMANCE MEASURES (JPM) 1005018100- TRANSFER FROM AUXILIARYTRANSFORMER TO STARTUP TRANSFORMER 1005020300 POWER "C" 4 KV BUS FROM CRANKXNG DIESELS 1005021300 POWER "C" 4 KV BUS FROM OPPOSITE UNXT'S TRANSFORMER 1005023300 POWER A OR B BUS FROM CRANKING DXESELS VIA C BUS 1005024100 TRANSFER FROM THE STARTUP TRANSFORMER TO THE AUXILIARY TRANSE 1023014500 MANAGE DIESEL LOADING BASED ON ONE EDG FAILURE CONCUEGKNT WI'I 1023015500 RECOVER FROM AN EMERGENCY DIESEL GENERATOR AUTO START FAILURE 1028002100 PERFORM AN E.C P.

1028004100 DETERMINE SHUTDOWN MARGIN 1028006100 DAMPEN XENON OSCILLATION 1028007200 INDUCE XENON OSCILLATION 1028009500 RESPOND TO ATWS 1028010300 PERFORM A DROPPED ROD RECOVERY 1028014300 RESET BANK OVERLAP 1028016300 RECOVER MXSALIGNED CONTROL ROD If 1028022100 CONDUCT A 1/M PLOT 1028023300 INVESTIGATE ROD CONTROL SYSTEM URGENT FAILURE 1028025300 RESPOND TO CONTINUOUS ROD WITHDRAWAL 1028026300 RESPOND TO CONTINUOUS ROD INSERTXON 1028030300 RESPOND TO IMMOVABLE RCC 1028032200 BYPASS REACTOR TRIP BRPJOKRS 1041004100 COOL DOWN THE PRESSURIZER 1041005100 PURGE THE PRT (FEED AND BLEED) 1041006100 ADJUST PRESSURIZER PRESSURE SETPOZNT 1041007200 PERFORM RCS OVERPRESSURE TEST 1041010100 EQUALIZE RCS/PER BORON CONCENTRATIONS 1041011100 DRAIN DOWN PRESSURIZER RELIEF TANK 1041012100 REDUCE PRT TEMPERATURE 1041021100 VENT THE PRT 1041023100 VERIFY PROPER SPRAY VALVE ACTUATION 1041063100 PURGE THE PRT (MAJOR GAS VOLUME) 1041064300 VERIFY NATKULL CIRCULATION FROM THE ALTERNATE SHUTDOWN PM L f

JOB PERFORMANCE MEASURES (JPM) 1046003100 RECIRCULATE BORIC ACID STORAGE TANKS 1046006100 BLEND TO THE RWST 1046007100 BORATE THE RCS VZA THE BLENDER 1046008300 EMERGENCY BORATE THE RCS (MOV 350) 1046010100 MANUALLY MA.'KEUP To THE RCS 1046013100 DILUTE THE REACTOR COOLANT SYSTEM BORON CONCENTRATION 1Q46029100 SET UP BLENDER FOR AUTOMATIC OPERATION 1046049300 RECOVER FROM FAXLURE OF FCV-113A AND/OR BLENDER STATXON 1046054300 DIRECT PERFORMANCE OF POST ACCIDENT RCS CHEMICAL INJECTION 1049001200 TEST REACTOR PROTECTION SYSTEM 1049002300 TRIP A FAILED INSTRUMENT BISTABLE MANUALLY 1050004300 RESPOND TO LOSS OF RHR SYSTEM WITH RCP'S AVAILABLE (MODE 1050005500 ALXGN RHR FOR COLD LEG RECXRCULATION 1050007300 RESPOND TO LOSS OF RHR SYSTEM W/0 RCP'S (MODE 3 TO MODE 5 TK 1050008300 RESPOND To LOSS OF RHR SYSTEM - RCS DRAINED AND OPEN 1051018300 MANUALLY CLOSE INSTRUMENT AXR BLEED VALVE 1053001100 SHUTDOWN CONTAINMENT PURGE SYSTEM 10530021QO INITIATE (AUTHORIZE) CONTAINMENT PURGE 1059003100 ADJUST HIGH FLUX AT SHUTDOWN ALARM 1059005200 PERFORM A MANUAL CALIBRATION OF THE NIS 1059007100 REMOVE A SOURCE RANGE CHANNEL FROM SERVXCE 1059017200 TEST SOURCE RANGE NZS CHANNEL (REACTOR SHUTDOWN) 1059024300 RESPOND TO LOSS OF INTERMEDIATE RANGE INSTRUMENTATION 1059025300 RESPOND To LOSS OF SOURCE RANGE INSTRUMENTATION 1059029300 RESPOND To A SOURCE RANGE NZS MALF'UNCTION (MODE 6) 1062012500 ALIGN SAFETY INJECTION FOR HOT LEG RECIRC 1062013500 ALZGN SAFETY INJECTION FOR COLD LEG RECZRC 1063008500 VERIFY SAFETY XNJECTZON OPERATION 1064002100 FILL THE ACCUMULATORS 1064003100 DRAXN THE ACCUMULATORS 1064004100 XNCREASE ACCUMULATOR PRESSURE (HXGH PRESSURE SOURCE) 1064005100 REDUCE ACCUMULATOR PRESSURE

JOB PERFORMANCE MEASURES (JPM) 1064010200 PERFORM ACCUMULATOR BACKLEAKAQE TEST 1071013500 XSOLATE STEAM GENERATOR SLOWDOWN 1074036500 CLOSE FEEDWATER CONTROL AND BYPASS VALVES 1075002300 CONTROL STEAM GENERATOR LEVEL LOCALLY WITH AUXILIARY FEEDWATE 1094001500 PLACE POST ACCIDENT HYDROGEN MONITOR ZN SERVICE 1200001500 RESPOND TO UNIT TRIP 1200022500 DX'AGNOSE CAUSE OF SAFEGUARDS ACTUATION 1200060500 PERFORM POST ACCXDENT CONTAINMENT VENTING 2001011400 REPORT SIGNIFICANT EVENTS 2001012400 MAKE PROTECTIVE ACTION RECOMMENDATIONS 2001013400 MAKE EMERGENCY NOTIFICATIONS 2016007400 RESPOND TO A PLANT FIRE 2201019400 CLASSIFY PLANT EMERGENCY 2201022400 RESPOND TO A MEDICAL EMERGENCY 3028023300 ZNVESTXGATE ROD CONTROL SYSTEM URGENT FAILURE 3028039300 INVESTIGATE ROD CONTROL SYSTEM NON-URGENT FAILURE 14002009500 TRIP THE GENERATOR FROM THE SWZTCHYARD 14003008100 PLACE A DEENERGIZED BATTERY CHARGER ZN STANDBY

.14003009100 DEENERGIZE A STANDBY BATTERY CHARGER 14003012100 PLACE A VZTAL INVERTER ZN STANDBY 14003013100 DEENERGIZE A STANDBY VITAL INVEIGLER 14003014100 PLACE A NON-VITAL INSTRUMENT ZWTERTER ZN SERVXCE 14003015100 REMOVE A NON-VITAL INSTRUMENT XNVERTER FROM SERVXC 14003016100 TRANSFER VITAL LOAD BETWEEN ZNVERTERS 14003017100 TRANSFER INSTRUMENT BUS FROM INVERTER TO CVT 14003018100 TRANSFER INSTRUMENT BUS FROM CVT TO I&PERTER (INTERNAL TRANSF:

14003023500 PERFORM 125 VDC BUS SHEDDXNG(BLACKOUT IN PROGRESS) 14003024100 'SHXFT BATTERY CHARGERS 14003025100 TRANSFER INSTRUMENT BUS LOAD FROM CVT TO SPARE INV 14003026100 TRANSFER INSTRUMENT BUS LOAD FROM CVT TO NORMAL XNVERTER 14005009100 RACK-ZN C BUS 4KV BREAKERS 14005010100 RACKET C BUS 4KV BREAlG5%

JOB PERFORMANCE MEASURES (JPM) 14005011100 RACK-ZN A/B BUS 4KV BREAKERS 14005012100 RACK-OUT A/B BUS 4KV BEKMERS 14005019100 OPERATE 4 KV BRFMZR LOCALLY 14005020300 POWER C 4KV BUS FROM CRANKING DZESELS 14005023300 POWER A OR B BUS FROM CRANKING DIESELS VIA C BUS 14006008100 RACK-IN 480 VOLT LOAD CENTER BREAKER 14006009100 RACK-OUT 480 VOLT LOAD CENTER BRFAKEK 14007004300 MANUALLY INITIATE TELEMAND TRANSFER 14007008300 MANUALLY INITIATE TELEMAND TRANSFER (OPERATION OF MANUAL BR 14008028500 ISOLATE CV-2201 (SI WITH ONE OPERATING ZCW PUMP) 14013016100 STARTUP DIESEL INSTRUMENT AZR COMPRESSOR 14023003100 START AND SYNCHRONIZE THE EDG LOCALLY 14028003 100 STARTUP A ROD DRIVE MOTOR GENERATOR SET 14028009500 RESPOND TO ATWS 14028018100 SHUTDOWN A ROD DRIVE MOTOR GENERATOR SET 14028020100 PARALLEL MOTOR GENEEUkTOR SETS 14028028100 RACK-IN REACTOR TRIP,BREAKERS 14028029100 RACK-OUT REACTOR TRIP BRKQCERS 14071013500 LOCALLY ISOLATE BLOWDOWN 14074036500 CLOSE MAIN FEEDWATER CONTROL AND BYPASS VALVES LOCALLY 14075011100 RESET AUX FW PUMP OVERSPEED TRIP LATCH 14200056500 RE ENERGIZE BACKUP HEATERS ON EMERGENCY DIESEL GENERATOR 24006008100 RACK ZN FRG 480V LOAD CENTER BREAKS 24006009100 RACK OUT FOG 480V LOAD CENTER BKUQKR 24041065300 LOCALLY ISOLATE RCP SEAL COOLING 24046039300 MANUALLY EMERGENCY BORATE (356) 24046052500 PERFORM POST ACCIDENT R C S CHEMICAL INJECTION 24051018300 LOCALLY CLOSE THE CONTAINMENT INSTRUMENT AZR BLEED VALVE CV.

24062019100 CLOSE SIT INLET ISOLATION VALVES 24094001500 PLACE POST-ACCIDENT HYDROGEN MONITOR IN SERVICE 24200056500 REENERGIZE BACKUP HEATERS ON THE EMERGENCY DIESEL GENERATOR 24200060500 PERFORM POST ACCIDENT CONTAINMENT VENTING

ORIGINALADMINISTRATIVEPROCEDURES 0103.4 '7/2(/89 In Plant Equi~t Clearance Orders 0103.12 3/31/89 Notification of Significant, Events to NRC 0103.36 3/10/87 Control of Operator Aids and Temporary Information tags 0103.41 12/11/86 Caution Tag Clearance Procedure 0109.3 3/29/89 On the Spot Chcmges to Procedures 0109.6 8/4/87 Temporary Procedures

ORIGINALOPERATING PROCEDURES 0204.2 Periodic Tests, Checks> and Operating Evoluticas 1009.12'/27/89 8/24/88 Ected Critical'aaditicaa 1009.3 4/19/89 Sbutdc~ Margin Calculatiaa 1009.4 5/28/88 Qyec'aticea Within Flux Differecme Target Band 5163. 5/19/89 Naate Diapcaal S~tcm - Caetrelled Licyxid RelecLse th OP 5523.1 5/30/89 Matte DiaZaeal Syataa - Gas Decuma Tank, Ccatrollec Bebmae to Ataceykmre OP 14004.8 6/14/8S Use of the CgP56 - Ermdeymte Core Cooling Hector

ORIGINALOFF-NORMAL OPERATING PROt EDURES 0208.14 5/12/89 Deviation or Failure of Reactor Protection and Safety ReLated Began Inatx~itation Cmaaels 1108.1 5/16/89 Reactor Coolant Rap Off-Norjaal CoExkf.ticea 1208.1 7/27/89 Pressurizer Power Operated Relief Systea " (Reliefs az KV's) - Halfmction 1568.1 4/7/88 Seccedary Chmisi ~ - Operator Actices in tbe Event Deviation frca

- Halfmetim L'ts c CtKP 2608.2 5/26/88 CVCS ~~ Barm Ceacentratim Cantrol Systea CMP 3108.2 5/16/89 High hctivity in Caegxma& Cooling Rater CMP 3208.1 3/30/89 Malfunction of Reaickal Heat 1 <<aeval System ONOP 3308.1 0/30/89 Turbine Plant Cooling Water Malfunction ONOP 3408.1 5/1&/89 Intake Cooling Water - Malfunction ONOP 340&.2 1/24/&9 Intake Cooling Water - Failure Due to Transport of Heav Loads ONOP 5168.5 8/10/89 Waste Holdup Tank-Pump Back System ONOP 5508.2 4/7/87 WDS - Off Normal Operation, Gaseous Waste Disposal Syste ONOP 7308.1 3/24/89 Halfunction of the Auxiliary Feedwater Systew ONOP &608.1 4/9/87 Generator Radio Prequel~ Honitor (Unit 4 Only)

ONOP 9108.1 7/28/86 Hain Transformer - Halfunction ONOP 9208.1 10/30/86 Auxiliary Transforaar - Malfunction ONOP 9308.1 4/6/89 Startup former - Malfunction ONOP 930&.2 4/9/87 "C" Bus Transformer - Malfunction ONOP 9408.1 2/10/88 Loss of "A" or "B" 4KV Bus ONOP 9408.2 6/30/88 .Energizing 4KV Buses Using the Cratdcing Diesels Bus Yi Lines or'Startup Transformer fraa the Opposite Unit 9408.3 4/6/89 Loss of Voltage to "C" 4160 Volt Bus 9608.1 3/24/89 125 V DC Systee - Location of Grounds 960&o2 8/17/88 Auxiliary 125V DC Systea - Location of Grounds 10308.1 4/28/89 Control Building Heating Ventilation and Air Coaditionirq Systea (HVAC) 11108.1 5/24/89 Process RacBatim Monitor - Off-Normal CceQtice Opera-tion 11208.1 5/28/87 Area Radiation Monitoring Systea (ARCS) OffWeruai Operation 12308.2 10/22/87 Pcs)er Range Nuclear Instrummtatim Verification of Upper) Lever) and Cannel ~riation Ala~

15608.2 3/2/89 Inst+,ment Air Dryer Malfunction 16708.1 7/24/88 Spent Peel Cask 3M~pmmy Cooling

UPGRADE ADMINISTRATIVEPROCEDURES O-AD.'l-031 8/31/88 Independent Verification 0-ADA-200 ~i/28/89 Conduct of Operations 0-ADA-201 3/10/89 Upgrade Operations Procedure Usage 0-ADM-202 ~ 4/17/89 Shift Relief and Turnover 0-ADA-203 7/13/89 Shift Operating Practices O-ARf-204, ti3/89 Operations Varrative Logbooks 0-ADH-207 9/30/88 Operations Instructions in the Event of a Situation riot Addressed by Procedure 0-ADH-o03 5/20/89 . Control and Use of Temporary System Alterations

UPGRADE UNIT 3 AND COMMON OPERATING PROCEDURES 0~003.1 4/4/89 125V Vital DC Syatea 0~003. 2 4/26/89 125V Auxiliary DC Syatea

~003. 3 4/4/89 120V Vital Instrument AC Syatea O~M03.4 4/26/89 AmgQisry 120V AC Syat~

3WEM05 5/22/89 4160 Volt Busea A and B 3~&05. 1 5/22/89 4160 Volt Bua C 3~006 6/1/89 480 Volt Srktchgcar Syatca 3~07 4/27/88 480 Volt Hotar Control Centers 3~08 7/13/89 Turbine Plant Coolie Water 3~13 5/30/8$ Instruct Air Syatea 3~19 8/3/89 Intake Cooling Water Syatca 0~&23 7/20/&9 E~isacy Diesel Qacmcatar 0~25 3/22/8$ Central Raaa Ventilation Syatea 3~30 4/28/89 CcQg~lt Cooling Water Syatem 3~38.23 3~041.1 3~~1.2 9/24/87 4/4/89 4/4/89 Rector Coolant Pressurimer ~aaticm

~

Fuel Transfer Syatea - Narasl Operatice 3~41. 3 3~~1o4 3~~1. 7 3~-041.8 4/5/88 4/6/89 3/24/89 E

0 IEttC Drafting the Reactor

~

rsseuriser Relict Tank Coagulant Syatea 7/27/89 Filling and Venting the Reactor Coolant System 3~-041.9 6/14/89 Reduced Inventory'perations 0~-046 7/11/89 CVCS - Boron Concentration Control 3WP-047. 6/23/89 CVCS - Charging and Letdown OW-048 4/12/89 Heat Tracing System 3~50 3/24/89 Residual Heat Removal System 0~&51. 2 7/18/87 Post Accident Containment Vent System 0~&53 4/ll/89 Containment Purge System 3~&55 4/26/89 Bnergency Containmcnt Cooling and Filtering System 3-OP-057 6/16/89 Contaimmnt Normal Ventilation and Cooling System 3WP&61. 3 12/2/88 Reactor Coolant Drain Tank 3~~2 4/4/89 Safety Injection 3~64 4/13/89 Safety Injection AccuaaQatars 3~67 5/12/89 Process Radiation Hanitoring System 3~M68 2/2/89 Cantaimlent Spray Syatea 3~71 4/6/89 Stcam Gerwrator Blowdown Recovery Systee 3~&72 4/28/89 Hain Stcaa System 3~73 3/24/89 Condensate Systca 0~074. 1 5/12/89 StmxSy S/Q Fcedmtcr System 3~75 3/24/89 Auxiliary Fcechatcr Syatea 3~87 4/6/89 Turbine Lube Oil Syatca 3~89 7/13/89 Hain Turbine 3~94 3/24/89 Cantai~nt Past Accident Hanitaring Systems

UPGRADE UNIT3 GgNERAI OPERATING PROCEDURES r

3~-103 7/20/89 Power Operation to Hot Standby 3~-301 I /13/89 Hot Stmxiby to Power Operation 3~P-305 8/15/89 Hot Standby to Cold Shutdown 3~-503 7/20/89 Cold Shutdown to Hot Standby

UPGRADE UNIT 3 AND COMMON OFF-NORMAL OPERATING P ROCEDURES 3~-003.4'~-003.5 o/8/89 Loss of DC Bus 3D01 (3A) 5/8/89 Loss of DC Bus 4D23 (3B)Loss of DC Bus 3D01 (4D01) 3~-003.6 8/10/89 Loss of 120V Vital Instrunent Panel 3P06 3~P-003.7 8/10/89 Loss of 120V Vital Instrument Panel 3P07 3~-003.8 1/12/88 Loss of 120V Vital Instnamnt Panel 3P08 3~-003.9 8/10/89 Loss of 120V Vital Instrument Panel 3P09 3~-004 5/24/89 Loss of Offsite Power 3~-004.1 3/18/86 Restoration of Electrical Systems Following the Recover.

of Offsite Power 3~-005.4 1/22/88 4KV Bus 3A or 3B Grocsxi 0~-013 4/6/89 Loss of Instr~st Air 3~&14 5/31/89 Main'ondec~r Loss of Vacuxaa 0~-016.2 6/9/89 Response to Spurious Actuation of a Fire/Isolation Damper 0~&16. 7 8/10/89 Screen Wash Zhergency Makeup to the Fire Protectior.

System 0~-016.8 o/6/89 Response to a Fire/Smoke Detection System Alarm 3~-016.9 6/14/89 Response to a Reported Fire in the Charging Pump Roaa, HCC B Rooa, Cable SpreacUing Room or Control Roaa OWNQP-023. 2 7/13/89 Baergency Diesel Generator 0~-025.2 9/1/88 Loss of Control Roca Ventilation System (CPS)

Air Conditioining 3 WHOP-028 8/8/89 Reactor Control System Halfunction 3~~28. 1 2/15/89 RCC Misaligmmnt 3WHOP-028. 2 4/io/89 RCC Position Indication Malfunction 3~OP-028. 3 10/26/88 Dropped RCC 3WHOP-030 '5/16/89 Loss of CcmpcNMNst Cooling Water 3&NXM33.1 2/11/88 Spent Fuel Pit (SFP) Cooling System Malfunction 3~-033.2 3/24/89 Refueling Cavity Seal Failure 3~P-033.3 8/10/89 Accidents Involving New or Spent Fuel 3~P-038.1 9/15/87 Fuel Transfer System Manual/Emergency Operation 3~P-041.3 7/27/89 Excessive Reactor Coolant System Leakage 3~P-041.4 6/29/89 Excessive Reactor Coolant System Activity 3~&41.5 8/10/89 Pressurizer Pressure Control Halfunction 3~&41. 6 7/27/89 Pressurizer Level Control Halfunction 3~-046.1 7/6/89 Emergency Boration 0~-046.3 7/12/88 Loss of Boration 3~-047 1 F o/24/89 of Charging Flow in Flowpath(s)'oss Modes 1 'Ihrough 3 0~-048 4/12/89 Off-Normal Critical Heat Tracing System Temperature 3~-049 o/20/88 R~mrgizing Safeguard Racks After Loss of Single Power Supply 3~-050 3/30/89 Loss of RHR 3~-053 5/31/89 Loss of Containaant Integrity 3~-059.4 6/30/89 Excessive dacial Flux Differecx:e 3~&59. 5 2/25/88 Source Range Nuclear Instnematation Halfunctian 3~QP-059. 6 5/11/88 Backup NIS (Gamm Hetrics) Malfurmtion 3EMP59. 7 1/9/89 IntermcU.ate Range Nuclear Instrumatatica Malfunction 3~&59.8 9/21/88 Power Range Nuclear Instrumatation Malfunction 3~W67 5/16/89 Xzmctvertent Release of Radioactive Gas 0~-067.2 5/30/89 Inadvertent Release of Radioactive Liquid

"~P-071 7/6/89 Gteaa Generator ~i Leak 0~-074.1 7/27/89 Standby Steam Gcamrator Feedwater System Operation With Loss of Offsite Power and Loss of Amciliary Feedwater 3~~89 10/20/88 TUrbine Ruaback 3~~4 4/26/89 Al  %

Mcaktoring hd 3~OP-100 7/20/89 Fast Load Reductim O~KP-105 7/13/89 Control Roaa Evacamtica

~FUEL HANDLINGPROCEDURES ~

QP 16000.1 4/7/89 Lfaitaticas and Preoauticxm for Handling Fuel Asscablics QP 16200 lg/3/St Manipu1atcc Craz>> - Operating Instrc~icxm

ANNUNCIATORPROCEDURES CHEAP 0208. 3 8/22/89 Annunciator List - Panel A - Reactor Coolant QNP 0208. 4 11/25/88 Annunciator List - Panel B - Reactor Panel QNQP 0208. 5 8/22/89 Annxumiator List - Panel C - Steaa Generator and Reacto:

Trips (MP 0208.6 8/22/89 Annunciator List - Panel D - Condensate and Feecheater CMP 0208. 7 8/22/89 Annunciator List - Panel E - Turbine Generator C5CP 0208. 8 8/22/89 Annunciator List - Panel F - Electrical CAP 0208. 9 8/22/89 Annunciator List - Panel 6 - Miscellmmous CNCP 0208. 10 8/22/89 Atnunciator List - Panel H - Safety Injection an Auxiliary CMP 0208.11 8/22/89 AnzRQx'.iator List - Panel. I - Station Service CNCP 0208. 12 8/22/89 Anamciator List - Panel X - Cceaa

- %ate/Borca Panels

-List CNP 0208.13 4/26/89 Ammmciator CAP 0208,15 6/14/89 Annmmiator GeIMral CtKP 0208.16 8/22/89 Anmnciatar List - Panel J - Aaaciliary Electrical Pc~

QKP 0208 '8 3/24/89 Acaxnciator List - Caadmsate Poliskdag Systea Panel C5CP 0208.19 8/22/84 Auamciator List - Process Caatrol Panel&-46

EPIP 20101 5/5/89 Duties of Emergency Coordinator EPIP 20102 9/2//88 Duties ef an Individual Who Discovers an Emergency Condition IP 20104 11/2/88 Duty Call Notifications/Staff Augmentation EPIP 20105 5/11/88 Emergency Respcese Facilities EPIP 20106 5/25/89 Natural Emergencies EPIP 20107 3/24/89 Fire/Explosion Emergencies EPIP 20109 10/11/88 Criteria For, and Conduct of Local Evacuations EPIP 20110 6/19/89 Criteria For and Cotxiuct of Owner Controlled Area Evacuation EPIP 20111 11/2/88 Retry EPIP 20112 4/17/89 Ccaxaa6cations Network EPIP 20125 11/19/88 Qn-Site Emergency Qrganination EPIP 20126 4/4/89 Off-Site Dose Calculations

UNIT 3 EMERGENCY OPERATING'PROCEDURES 3-EOP-E-0 ZC/Zf/ZC Reactor Trip or Safety Injection 3-EDP-E-1 :wf/ZC/ZC Loss of Reactor or Secondary Coolant 3-EOP-E-2 ZC/ZC/ZC Faulted Steam Generator Isolation 3-EOP-E-3 ZC/ZC/ZC Steam Generator Tube Rupture 3-EOP-ECA-0.0 ZC/.CC/ZC Loss of All AC Power 3-EDP-ECA-0. 1 ZC/ZC/ZC Loss of All AC Power Recovery Without SI Required 3-EOP-EGA-0. 2 ZC/ZC/ZC Loss of All AC Power Recovery With SI Required 3-EDP-ECA-1. 1 ZC/ZC/ZC Loss of Emergency Coolant Recirculation 3-EOP-ECA-1 2 ~ ZC/XX/ZC LOCA Outside Containment 3-EOP-ECA-2.1 Zf/ZC/ZC Uncontrolled Depremrurization of All Steam Generators 3-EOP-ECA-3.1 ZQ'ZQ'XX SCIL With Loss of Reactor Coolant-Subcooled Recovery Desired 3-EOP-ECA-3. 2 ZC/ZC/ZC SGTR With Loss of Reactor Coolant-Saturated Recovery Desired 3-HP-ECA-3.3 ZC/3K/ZC SGTR Without Pressurizer Pressure Control 3-EDP"ES-O.O ZC/KQZC Rediagnosis 3-EDP-ES-0.1 ZC/XX/ZC Reactor Trip Response 3-HP-ES-O, 2 'X/XX/XX Natural Circulation Cooldown 3-HP-ES-O. 3 ZC/ZC/!K Natural Circulaticm Cooldowa With Steaa Void in With RVLHS (QSPDS) 3-EOP-ES-0. 4 natural Circulaticm Cooldown With Steaa Void in Vessel (Without RVIAS) 3-EOP-ES-1 ~ 1 !QC/ZC/!K SI Termination 3-HP-ES-1. 2 XX/XX/ZC Post UXA Cooldown and Depressurization 3-EOP-ES-1. 3 XX/XX/XX Trmmfer to Cold Leg Recirculation 3-K)P-ES-1. 4 XX/ZC/XX Tnmsfer to Hot Leg Recirculation 3-EOP-ES-3>>

3-EDP-Ei-3. 2 1 ZC/!K/ZC XX/XX/XX Post-SGIR Cooldown Using Backf Post-SGIR Cooldown Using Blowdown ill 3-EOP-ES-3. 3 ZC/!K/ZC Post-SGTR Cooldown Using Steaa Dump 3-HP-F-0 ZC/ZC/!K Critical Safety Function Status Trees 3-HP-FRW>> 1 ZNQNK Reeganse to Inadecymte Core Cooling 3-HP-FR%. 2 Zf/X&K Respcc~e to Degraded Core Cooling 3-EDP-FRW>> 3 ZC/!QC/ZC Response to Saturated Core Cooling 3-HP-FRW>>

3"EOP-FRW. 2 3-HP-FRW. 3 1 Zf/ZNK

!QC/)QC/ZC

!QNQf/ZC Response to Loss of Seccedary Heat SMr, Rnq~e to S~Gemretar Resgxmae to 0verprer Steaa. Generator High Level

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3-EOP-FR-H>> 4 ZC/XX/ZC Response to Loss of No~1 Steea Release Capabilities 3-HP-FR-H>> 5 XX/ZNK Bespoke to Steaa Gamrator Low Level 3-EDP-FR-I. 1 Zf/Zf/ZC Response to High Pressurizer Level 3-EOP-FR-I. 2 :G/ZC/ZC Response to Low Pressurizer Level 3-EOP-FR-I. 3 Response to Voids in Reactor Vessel 3 "EOP-FR"P . 1 Response to Imu.nent Pressurizer Thermal Shock Condition 3-EOP-FR-P.2 ZC/ZC/ZC Response to Anticipated Pressurized Theraal Shock Condition 3-EOP-FR-S.1 Response to Nuclear Power Generation/ATWS 3-EOP-FR"S.2 ZC/ZQ'ZC Response to Loss of Core Shutdown 3-HP-FR-Z. 1 Response to High Containment Pressure 3-EOP-FR-Z. 2 ZC/ZC/ZC Response to Containaant Flooding 3-EOP-FR-Z. 3 ZC/ZC/ZC ,Response to High Containment Radiation Level

UNIT3 MERGENCY OPERATING PROCEDURES

. BASIS DOCUMENTS 3-BD-EOP-E-0 4C/'CC/XX Reactor Trip or Safety Injection 3-BD-EOP-E-1 ZC/ZC/XX Loss of Reactor or Secoadax~ Coolant 3-BD-EOP-E-2 <C/XC/XX Faulted Steam Generator Isolation 3-BD-EOP-E-3 ZC/ZC/XX Steam Generator Tube Rupture 3-BD-EOP-ECA-0.0 XC/ZC/MC Loss of All AC Power 3-BD-EOP-ECA-0.1 :aVhC/XX Loss of All AC Power Recovery Without SI Required 3-BD-KP-ECA-0.2 XC/.'K/3lX Loss of All AC Power Recovery With SI Required 3-BD-EOP-ECA-F 1 ZC/ZC/M Loss of Emergency Coolant Recirculation 3-BD-EOP-ECA-1.2 ZC/.'GC/XX LOCA Outside Containment 3-BD-EOP-ECA-2.1 ZC/3Z/ZC Uncontrolled Depressurization of All Steam Genera-tors 3-BD-KIP-ECA-3. 1 ZC/XC/XX SGTR With Loss of Reactor Coolant-Subcooled Recovery 3-BD-BDP-ECA-3. 2 XX/XVXX SGTR With Loss of Reactor Coolant-Saturated Recovery Desired 3-BD-KP-ECA-3. 3 XX/XX/XK SGTR Without Premsurizer Pressure Control 3-BD-83P-ES-0. 0 3GC/XG~ Rediagnoeis 3-BD-KP-M-0,1 XX/XC/XX Reactor Trip Respecxse 3-BD-KP-ESW. 2 XVX2KCC Natural Circulation Cooldown 3-BD-KjP-ES-0. 3 XX/XX/XX Natural Circulation Cooldown With Steam Void in Vessel With RVIAS (QiPGS) 3-BD-KP-ES"0. 4 Natural Circulation Cooldown With Steam Void in Vessel (Without RVlAS) 3-BD-KP-FS-1. 1 XX/ZC/XX SI Termination 3-BD-KP-ES-1. 2 !GNQKGC Post QXA Cooldawa and Depressurization 3-BD-KP-ES-1. 3 XX/ZC/XX Transfer to Cold Leg RecMmlation 3 "BD-KP-ES-1. 4 XX/AC/XX Transfer to Hot Leg Recirculation 3-BD-KP-ES-3. 1 XX/XX/XX Post-SOIR Cooldawn Using Backfill 3-BD-KP-ES-3. 2 XK/Zf/PGC Post-~ Cooldawn Using Blowctawn 3-BD-KP-ES-3, 3 XX/XX/XX Post-SGIR Cooldawn Using Steaa Duap 3-BD-KP-F<

3-BD-KP-FRW 1 o ZKQVXC XX/XNGC CriticaL Safety Function Statue Re~rezw.

~~

to Iaahsquate Care Cooling 3-BD-KP-FRW. 2 XÃGfjKK Resp~ to Degrade Core CoojLh+

3-BD-83P-FRW. 3 XX/XK/XK Respaaee to Saturated Care Cooling 3-BD-KP-FRW. 1 XX/XKK ~ause to Lose of Secondary Seat Sink 3-BD-KP-FR-H. 2 ZNQZK 3-BD-KjP-FR"H. 3 XX/XNGC Resume to Steaa Generator High Level 3-BD-KP-FR-Ho 4 ZNG4QK Respaaee to Lace of Naraal Steaa Release Capabili-ties 3 "BD-KP-FR-Ho 5 Response to Steea Gsaerator Lur Level 3-BD-KP-FR-I. 1 Respaaee to High Preeeuriser Level 3-BD"KP-FR"I.2 RespaElse to Loll Pressuriser IAhh$1 3-BD-KP-FR-I. 3 Reepanee to Voids ha Reach'eaeel 3-BD-KP-FR-P. 1 Reslxese to ~hue Preesurixer 'Hernial Shock Ccixkiticaa

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3-BD-KP-FR-P. 2 .Respaa~ to hnticipatsd Pressurized '1henaal Bxcak

'clxiitica of ~ ~doll 3-BD-KP-FR-S. 1 ZNGKGC 'eepacme to Nuel~ E&ar Generation/hIWS 3"BD-KP-FR-S. 2 3-BD-KP-FR-Z. 1 3 BD-KP-FR-Z. 2 XX/:le GC XXfXWCK XNCXnCK Respaclse Respcime

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to to Loss Caatai wmt i

Plooding 3-BD-KP-FR Ze 3 ZNGVXK RUh Mlt ti

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