ML17348A517

Forwards Ref Matl in Preparation for Operator License Exams Scheduled for Wk of 901029,per NRC 900628 Request

ML17348A517
Person / Time
Site:	Turkey Point
Issue date:	08/24/1990
From:	Harris K FLORIDA POWER & LIGHT CO.
To:	Castro C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
L-90-310, NUDOCS 9009040159
Download: ML17348A517 (46)

Text

ACCELERATED DISTMBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9009040159 DOC.DATE: 90/08/24 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 HARRIS,K.N. Florida Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION CASTRO,C.W. Region 2 (Post 820201)

SUBJECT:

Forwards ref matl in preparation for operator license exams scheduled for wk of 901029,per NRC 900628 request.

DISTRIBUTION CODE: M003D COPIES RECEIVED: LTR TITLE: Operator Requalification Program f ENCL f SIZE: 9$

NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 0 PD2-2 PD 1 1 EDISON,G 1 1 INTERNAL: AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 N~ * .

IL Q/LHFB11 01 1

1 1

1 NRR/DLPQ/LOLB10 RGN2 1

1 1 1

EXTERNAL: NRC PDR 1 1 NSIC 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUfvIENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL 10

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0 P.O. B@lglOII200iggL, 33102-0100 L-90-310 Mr. Charles W. Casto, Chief Operator Licensing Section 2I Region II U. S. Nuclear Regulatory Commission 101 Marietta Streets N W I 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 October 29, 1990 This letter is notification of the Florida Power a Light Company (FPL) shipment of reference material requested by NRC letter dated June 28, 1990, to the examiner and address listed below:

Attn: Mr. J. Moorman U. S. Nuclear Regulatory, Commission, Region II 101 Marietta Street, N. W., Suite 2900 Atlanta, Georgia 30323 No material for the fundamentals examination was included per a discussion with Mr. J. Moorman (NRC) on August 14, 1990.

The reference material was shipped, by Federal Express to NRC Region II, on August 22, 1990. An index of the reference material is attached for your information.

The examiners are requested to retain the reference material so it can be used during the license examination scheduled for January 1991.

FPL will update the material prior to the January examination.

Should you require any additional information, please contact Mr. R.

W. Lindsey at (305) 246-6649.

Very truly yours, de' K ~ N Harris Pla Vice President Turkey Point Plant Nuclear KNH:RWL:jk PTN-TRNG-90-307 Attachment CC: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Document Control Desk, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant 9009040159 900S24 PDR ADOCK 05000250 V PDC an FPL Group company go~3

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BOOK 1 ADMINISTRATIVE PROCEDURES E

NEW STYLE PROCEDURES 0-ADM-031 06/05/90 Independent Verification 0-ADM-200 02/09/90 Conduct of Operations 0-ADM-201 11/24/89 Upgrade Operations Procedure Usage 0-ADM-202 01/11/90 Shift Relief and Turnover 0-ADM-203 03/27/90 Shift Operating Practices 0-ADM-204 09/06/90 Operations Narrative Logbooks 0-ADM-207 09/30/88 Operations Instructions in the Event of a Situation Not Addressed by Procedure 0-ADM-211 09/12/90 Emergency and Off Normal Procedure Use 0-ADM-503 05/01/90 Control and Use of Temporary System Alteration 0-ADM-701 06/15/90 Plant Work Order Preparation OLD STYLE PROCEDURES AP-0103.4 03/29/90 In Plant Equipment Clearance Orders AP-0103.12 03/31/89 Notification of Significant Events to NRC AP-0103.6 03/15/90 Control of Operator Aids and Temporary Information Tags AP-0109.3 05/17/90 On The Spot Changes to Procedures AP-0109.6 08/04/87 Temporary Procedures

BOOK 2

'UPGRADE UNIT 3 GENERAL OPERATING PROCEDURES 3-GOP-103 06/27/90 Power Operation to Hot Standby 3-GOP-301 07/26/90 Hot Standby to Power Operation 3-GOP-305 06/19/90 Hot Standby to Cold Shutdown 3-GOP-503 06/15/90 Cold Shutdown to Hot Standby

BOOK 3 OPERATING PROCEDURES NEW STYLE PROCEDURES O-OP-003.1 01/19/90 125 V Vital DC System O-OP-003.2 06/14/89 125 V Auxiliary DC System O-OP-003.3 03/30/90 120 V Vital Instrument AC System O-OP-003.4 04/26/89 Auxiliary 120 V AC System 3-OP-005 06/07/90 4160 Volt Buses A and B 3-0P-005.1 05/22/89 4160 Volt Bus C 3-OP-006 06/07/90 480 Volt Switchgear System 3-OP-007 07/05/90 480 Volt Motor Control Centers 3-OP-008 01/05/90 Turbine Plant Cooling Water 3-OP-013 07/26/90 Instrument Air System 3-OP-019 07/12/90, Intake Cooling Water System 0-OP-023 07/20/90 Emergency Diesel Generator 0-OP-025 04/18/90 Control Room Ventilation System

BOOK 4 OP'S (CONT.)

3-OP-030 07/15/90 Component Cooling Water System 3-0P-038.23 03/27/90 Fuel Transfer System Normal Operation 3-0P-041.1 04/25/90 Reactor Coolant Pump 3-0P-041.2 04/25/90 Pressurizer Operation 3-0P-041.3 10/31/89 Pressurizer Relief Tank 3-0P-041.4 05/22/90 Overpressure Mitigating System 3-OP-041.7 05/17/90 Draining the Reactor Coolant System 3-OP-041.8 05/01/90 Filling and Venting the Reactor Coolant System 3-0P-041.9 05/08/90 Reduced Inventory Operations 0-OP-046 02/26/90 CVCS Boron Concentration Control 3-OP-047 04/25/90 CVCS Charging and Letdown 0-OP-048 04/12/89 Heat Tracing System 3-OP-050 06/05/90 Residual Heat Removal System O-OP-051.2 07/18/87 Post Accident Containment Vent System 0-OP-053 04/18/89 Containment Purge System 3-OP-055 11/24/89 Emergency Containment Cooling and Filtering System 3-OP-057 07/05/90 Containment Normal Ventilation and Cooling System 3-0P-061.3 12/02/88. Reactor Coolant Drain Tank 3-OP-062 04/25/90 Safety Injection 3-OP-064 09/25/89 Safety Injection Accumulators 3-OP-067 04/17/90 Process Radiation Monitoring System

BOOK 5 OP'S (CONT.)

3-OP-068 02/02/89 Containment Spray System 3-OP-071 05/03/90 Steam Generator Blowdown Recovery System 3-OP-072 04/18/90 Main Steam System 3-OP-073 06/22/89 Condensate System O-OP-074.1 05/12/89, Standby S/G Feedwater System 3-OP-075 04/18/90 Auxiliary Feedwater System 3-OP-087 03/16/90 Turbine Lube Oil System 3-OP-089 06/27/90 Main Turbine 3-OP-094 01/19/90 Containment Post Accident Monitoring Systems OLD STYLE PROCEDURES OP-204.2 05/29/90 Periodic Tests, Checks, and Operating Evolutions OP-5163.2 03/30/90 Waste Disposal System Controlled Liquid Release to the Circulating Water OP-5523.1 05/03/90 Waste Disposal System Gas Decay Tank, Controlled Release to Atmosphere

BOOK 6 OFF-NORMAL OPERATING PROCEDURES NEW STYLE PROCEDURE ONOPS 3-0NOP-003.4 04/17/90 Loss of DC Bus 3D01 (3A) 3-0NOP-003.5 04/17/90 Loss of DC Bus 4D23 (3B) Loss of DC Bus 3D01 (4D01) 3-0NOP-003.6 08/10/89 Loss of 120 V Vital Instrument Panel 3P06 3-ONOP-003.7 03/29/90 Loss of 120 V Vital Instrument Panel 3P07 3-0NOP-003.8 03/30/90 Loss of 120 V Vital Instrument Panel 3P08 3-0NOP-003.9 12/19/90 Loss of 120 V Vital Instrument Panel 3P09 3-ONOP-004 05/31/90 Loss of Offsite Power 3-0NOP-004.1 01/19/90 Restoration of Electrical Systems Following the Recovery of Offsite Power 3-0NOP-005.4 01/22/88 4KV Bus 3A or 3B Ground 0-ONOP-013 04/18/90 Loss of Instrument Air 3-ONOP-014 12/12/89 Main Condenser Loss of Vacuum O-ONOP-016.2 10/13/89 Response to Spurious Actuation of a Fire/Isolation Damper O-ONOP-016.7 08/10/89 Screen Wash Emergency Makeup to the Fire Protection System O-ONOP-016.8 06/19/90 Response to a Fire/Smoke Detection System Alarm 3-0NOP-016.9 06/14/89 Response to a Reported Fire in the Charging Pump Room, MCC B Room, Cable Spreading Room or Control Room O-ONOP-016.10 04/17/90 Pre-Fire Plan Guidelines and Safe Shutdown Manual Actions O-ONOP-023.2 04/18/90 Emergency Diesel Generator O-ONOP-025.2 10/26/89 Loss of Control Room Ventilation System (CRVS) Air Conditioning O-ONOP-025.3 06/07/90 DC Equipment and Inverter Rooms Supplemental Cooling 3-ONOP-028 08/08/89 Reactor Control System Malfunction 3-0NOP-028.1 03/29/90 RCC Misalignment 3-0NOP-028.2 04/24/89 RCC Position Indication Malfunction 3-0NOP-028.3 10/26/88 Dropped RCC 3-ONOP-030 06/06/90 Loss of Component Cooling Water 3-0NOP-033.1 01/19/90 Spent Fuel Pit (SFP) Cooling System Malfunction 3-0NOP-033.2 03/24/89 Refueling Cavity Seal Failure 3-ONOP-033.3 08/10/89 Accidents Involving New or Spent Fuel 3-0NOP-038.1 09/15/87 Fuel Transfer System Manual/Emergency Operation 3-0NOP-041.3 07/27/89 Excessive Reactor Coolant System Leakage 3-ONOP-041.4 06/29/89 Excessive Reactor Coolant System Activity 3-0NOP-041.5 08/10/89 Pressurizer Pressure Control Malfunction

3-ONOP-041.6 01/30/90, Pressurizer Level Control Malfunction 3-ONOP-046.1 07/06/89 Emergency Boration O-ONOP-046.3 02/05/90 Loss of Boration Flowpath(s)

O-ONOP-047.1 12/21/89 Loss of Charging Flow in Modes 1 Through 3 0-ONOP-048 04/12/89 Off-Normal Critical Heat Tracing System Temperature 3-ONOP-049 05/20/88 Re-energizing Safeguard Racks After Loss of Single Power Supply 3-ONOP-050 04/25/90 Loss of RHR 3-ONOP-053 05/31/89 Loss of Containment Integrity

BOOK 7 ONOP'S (CONT.)

3-0NOP-059.4 06/30/89 Excessive Axial Flux Difference 3-0NOP-059.5 05/29/90 Source Range Nuclear Instrumentation Malfunction 3-0NOP-059.6 05/29/90 Backup NIS (Gamma Metrics) Malfunction 3-0NOP-059.7 01/09/89, Intermediate Range Nuclear Instrumentation Malfunction 3-0NOP-059.8 07/05/90 Power Range Nuclear Instrumentation Malfunction 3-ONOP-067 05/16/89 Inadvertent Release of Radioactive Gas O-ONOP-067.2 05/30/89 Inadvertent Release of Radioactive Liquid 0-ONOP-071 07/06/89, Steam Generator Tube Leak O-ONOP-074.1 07/05/90 Standby Steam Generator Feedwater System Operation With Loss of Offsite Power and Loss of Auxiliary Feedwater 3-ONOP-089 07/15/90 Turbine Runback 3-ONOP-094 12/07/89 Alternative Methods for Containment Post Accident. Monitoring 3-0NOP-094.1 01/18/90 Post-Accident Hydrogen Monitor Startup O-ONOP-094.2 01/17/89 Post Accident Monitoring and Post Accident Sampling Heat Trace Malfunction 3-0NOP-099.1 11/09/89 Response to a Metal Impact Monitor Alarm 3-ONOP-100 10/27/89 Fast Load Reduction 0-ONOP-105 04/19/90 Control Room Evacuation OLD STYLE PROCEDURE ONOPS 05/12/89 Deviation or Failure of Reactor Protection and Safety Related Hagan Instrumentation Channels ONOP-1108.1 06/06/90 Reactor Coolant Pump Off-Normal Conditions ONOP-1208.1 05/03/90 Pressurizer Power Operated Relief System (Reliefs and MOV's) Malfunction ONOP-1568.1 04/06/90 Secondary Chemistry Operator Actions in the Event of Deviation from Limits ONOP-2608.2 05/26/88 CVCS Malfunction of Boron 01/30/90'NOP-0208.14 Concentration Control System ONOP-3108.2 10/10/89 High Activity in Component Cooling Water ONOP-3208.1 06/28/90 Malfunction of Residual Heat Removal System ONOP-3308.1 04/17/90 Turbine Plant Cooling Water Malfunction ONOP-3408.1 '5/22/90 Intake Cooling Water Malfunction ONOP-3408.2 01/24/89 Intake Cooling Water Failure Due to Transport of Heavy Loads ONOP-5168.5 10/03/89 Waste Holdup Tank Pump Back System ONOP-5508.2 02/21/90 WDS Off Normal Operation, Gaseous Waste Disposal System ONOP-7308.1 Malfunction of the Auxiliary Feedwater

ONOP-8608.1 02/13/90 Generator Radio Frequency Monitor (Unit 4 Only)

ONOP-9108.1 01/11/90 Main Transformer Malfunction ONOP-9208.1 03/30/90 Auxiliary Transformer Malfunction ONOP-9308.1 04/06/89 Startup Transformer Malfunction ONOP-9308.2 01/30/90 "C" Bus Transformer Malfunction ONOP-9408.1 01/19/90 Loss of trAit or iiBii 4KV Bu ONOP-9408.2 01/18/90 Energizing 4KV Buses Using the Cranking Diesels Bus Tie Lines or Startup Transformer from the Opposite Unit ONOP-9408.3 01/18/90 Loss of Voltage to "C" 4160 Volt Bus ONOP-9608.1 06/28/90 125 V DC System Location of Grounds ONOP-9608.2 08/17/88 Auxiliary 125 V DC System Location of Grounds ONOP-10308.1 12/19/89 Control Building Heating, Ventilation and Air Conditioning System (HVAC)

ONOP-11108.1 02/21/90 Process Radiation Monitor Off Normal Condition Operation ONOP-11208.1 03/16/90 Area Radiation Monitoring System (ARMS)

Off Normal Operation ONOP-12308.2 10/02/89 Power Range Nuclear Instrumentation Verification of Upper, Lower, and Channel Deviation Alarms ONOP-15608.2 03/16/90 Xnstrument Air Dryer Malfunction ONOP-16708.1 01/05/90 Spent Fuel Cask Emergency Cooling

BOOK 8 ANNUNCIATOR PROCEDURES ONOP-0208.3 06/05/90 Annunciator List Panel A Reactor Coolant ONOP-0208.4 12/21/89 Annunciator List Panel B Reactor Panel ONOP-0208.5 02/09/90 Annunciator List 'anel C Steam Generator and Reactor Trips ONOP-0208.6 08/22/89 Annunciator List Panel D Condensate and Feedwater ONOP-0208.7 01/30/90 Annunciator List Panel E Turbine Generator ONOP-0208.8 07/20/90 Annunciator List Panel F Electrical ONOP-0208.9 03/29/90 Annunciator List Panel G Miscellaneous ONOP-0208.10 03/30/90 Annunciator List Panel H Safety Injection and Auxiliary ONOP-0208.11 04/18/90 Annunciator List Panel I Station Service ONOP-0208.12 05/01/90 "

Annunciator List Panel X Common ONOP-0208.13 04/26/89 Annunciator List Waste Boron Panels ONOP-0208.15 06/14/89 Annunciator General ONOP-0208.16 08/22/89 Annunciator List Panel J Auxiliary Electrical Power ONOP-0208.18 03/24/89 Annunciator List. Condensate Polishing System Panel ONOP-0208.19 08/22/84 Annunciator List Process Control Panel C-46

BOOK 9 UNIT 3 EMERGENCY OPERATING PROCEDURES 3-EOP-E-0 04/19/90 Reactor Trip or Safety Injection 3-EOP-ES-O.O 01/16/90 Rediagnosis 3-EOP-ES-0.1 04/19/90 Reactor Trip Response 3-EOP-ES-0.2 04/19/90 Natural Circulation Cooldown 3-EOP-ES-0.3 04/19/90 Natural Circulation Cooldown With Steam Void In Vessel With RVLMS (QSPDS) 3-EOP-ES-0.4 04/19/90 Natural Circulation Cooldown With Steam Void In Vessel (Without RVLMS) 3-EOP-E-1 04/19/90 Loss of Reactor or Secondary Coolant 3-EOP-ES-1.1 04/19/90 SI Termination 3-EOP-ES-1.2 04/19/90 Post LOCA Cooldown and Depressurization 3-EOP-ES-1.3 04/19/90 Transfer to Cold Leg Recirculation 3-EOP-ES-1.4 01/16/90 Transfer to Hot Leg Recirculation 3-EOP-E-2'-EOP-E-3 04/19/90 Faulted Steam Generator Isolation 04/19/90 Steam Generator Tube Rupture 3-EOP-ES-3.1 04/19/90 Post-SGTR Cooldown Using Backfill 3-EOP-ES-3.2 04/19/90 Post-SGTR Cooldown Using Blowdown 3-EOP-ES-3.3 04/19/90 Post-SGTR Cooldown Using Steam Dump 3-EOP-ECA-O.O 04/19/90 Loss of All AC Power 3-EOP-ECA-0.1 04/19/90 Loss of All AC Power Recovery Without SI Required 3-EOP-ECA-0.2 04/19/90 Loss of All AC Power Recovery With SI Required 3-EOP-ECA-1.1 04/19/90 Loss of Emergency Coolant Recirculation 3-EOP-ECA-1.2 04/19/90 LOCA Outside Containment 3-EOP-ECA-2.1 04/19/90 Uncontrolled Depressurization of All Steam Generators 3-EOP-ECA-3.1 04/19/90 SGTR With Loss of Reactor Coolant-Subcooled Recovery Required 3-EOP-ECA-3.2 04/19/90 SGTR With Loss of Reactor Coolant Saturated Recovery Desired 3-EOP-ECA-3.3 04/19/90 SGTR Without Pressurizer Pressure Control Critical Safety Function Status Trees

'-EOP-F-0 01/16/90 3-EOP-FR-S.1 04/19/90 Response to Nuclear Power Generation/ATWS 3-EOP-FR-S.2 01/16/90 Response to Loss of Core Shutdown 3-EOP-FR-C.1 04/19/90 Response to Inadequate Core Cooling 3-EOP-FR-C.2 04/19/90 Response to Degraded Core Cooling 3-EOP-FR-C.'3 04/19/90 Response to Saturated Core Cooling 3-EOP-FR-H.1 04/19/90 Response to Loss of Secondary Heat Sink 3-EOP-FR-H.2 01/16/90 Response to Steam Generator Overpressure 3-EOP-FR-H.3 01/16/90 Response to Steam Generator High Level 3-EOP-FR-H.4 01/16/90 Response to Loss of Normal Steam Release Capabilities 3-EOP-FR-H.5 01/16/90 Response to Steam Generator Low Level 3-EOP-FR-P.1 04/19/90 Response to Imminent Pressurized Thermal Shock Condition 3-EOP-FR-P.2 01/16/90 Response to Anticipated Pressurized Thermal Shock Condition

3-EOP-FR-Z.1 05/11/90 Response to High Containment Pressure 3-EOP-FR-Z.2 11/01/89 Response to Containment Flooding 3-EOP-FR-Z.3 Ol/16/90 Response to High Containment Radiation Level 3-EOP-FR-I.1 04/19/90 Response to High Pressurizer Level 3-EOP-FR-I.2 04/19/90 Response to Low Pressurizer Level 3-EOP-FR-I.3 11/02/89 Response to Voids in Reactor Vessel

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BOOK 10 UNIT 3 EMERGENCY OPERATING PROCEDURES BASIS DOCUMENTS 3-BD-EOP-E-0 04/19/90 Reactor Trip or Safety Injection 3-BD-EOP-ES-O.O 01/16/90 Rediagnosis BD-EOP-ES-0.1 01/16/90 Reactor Trip Response 3-BD-EOP-ES-0.2 04/19/90 Natural Circulation Cooldown 3-BD-EOP-ES-0.3 04/19/90 Natural Circulation Cooldown With Steam Void in Vessel With RVLMS (QSPDS) 3-BD-EOP-ES-0.4 04/19/90 Natural Circulation Cooldown With Steam Void in Vessel (Without RVLMS) 3-BD-EOP-E-1 01/16/90 Loss of Reactor or Secondary Coolant 3-BD-EOP-ES-1.1 01/16/90 SI Termination 3-BD-EOP-ES-1.2 01/16/90 Post LOCA Cooldown and Depressurization 3-BD-EOP-ES-1.3 01/16/90 Transfer to Cold Leg Recirculation 3-BD-EOP-ES-1.4 01/16/90 Transfer to Hot Leg Recirculation 3-BD-EOP-E-2 01/16/90 Faulted Steam Generator Isolation '

BOOK 11 EOP BASIS DOCUMENTS (CONT.)

3-BD-EOP-E-3 10/16/90 Steam Generator Tube Rupture 3-BD-EOP-ES-3.1 04/19/90 Post-SGTR Cooldown Using Backfill 3-BD-EOP-ES-3.2 01/16/90 Post-SGTR Cooldown Using Blowdown 3-BD-EOP-ES-3.3 01/16/90 Post-SGTR Cooldown Using Steam Dump 3-BD-EOP-ECA-O.O 04/19/90 Loss of All AC Power 3-BD-EOP-ECA-0.1 01/16/90 Loss of All AC Power Recovery Without SI Required 3-BD-EOP-ECA-0.2 04/19/90 Loss of All AC Power Recovery With SI Required 3-BD-EOP-ECA-1.1 04/19/90 Loss of Emergency Coolant Recirculation 3-BD-EOP-ECA-1. 2 01/16/90 LOCA Outside Containment 3-BD-EOP-ECA-2.1 04/19/90 Uncontrolled Depressurization of All Steam Generators 3-BD-EOP-ECA-3.1 01/16/90 SGTR With Loss of Reactor Coolant-Subcooled Recovery 3-BD-EOP-ECA-3.2 01/16/90 SGTR With Loss of Reactor Coolant Saturated Recovery Desired

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J

BOOK 12 EOP BASIS DOCUMENTS (CONT.)

3-BD-EOP-ECA-3.3 04/19/90 SGTR Without Pressurizer Pressure Control 3-BD-EOP-F-0 01/16/90 Critical Safety Function Status Trees 3-BD-EOP-FR-S.1 01/16/90 Response to Nuclear Power Generation/ATWS 3-BD-EOP-FR-S.2 01/16/90 Response to Loss of Core Shutdown 3-BD-EOP-FR-C.1 01/16/90 Response to Inadequate Core Cooling 3-BD-EOP-FR-C.2 01/16/90 Response to Degraded Core Cooling 3-BD-EOP-FR-C.3 01/16/90 Response to Saturated Core Cooling 3-BD-EOP-FR-H.1 04/19/90 Response to Loss of Secondary Heat Sink 3-BD-EOP-FR-H.2 01/16/90 Response to Steam Generator Overpressure 3-BD-EOP-FR-H.3 01/16/90 Response to Steam Generator High Level 3-BD-EOP-FR-H.4 01/16/90 Response to Loss of Normal Steam Release Capabilities 3-BD-EOP-FR-H.5 01/16/90 Response to Steam Generator Low Level 3-BD-EOP-FR-P.1 04/19/90 Response to Imminent Pressurized Thermal Shock Condition 3-BD-EOP-FR-P.2 01/16/90 Response to Anticipated Pressurized Thermal Shock Condition 3-BD-EOP-FR-Z.1 05/11/90 Response to High Containment Pressure 3-BD-EOP-FR-Z.2 01/16/90 Response to Containment Flooding 3-BD-EOP-FR-Z.3 01/16/90 Response to High Containment Radiation Level 3-BD-EOP-FR-I.1 04/19/90 Response to High Pressurizer Level 3-BD-EOP-FR-I.2 01/16/90 Response to Low Pressurizer Level 3-BD-EOP-FR-I.3 01/16/90 Response to Voids in Reactor Vessel

BOOK 13 EMERGENCY PLAN IMPLEMENTING PROCEDURES EPIP-20101 02/02/90 Duties of Emergency Coordinator EPIP-20102 09/27/88 Duties of an Individual Who Discovers an Emergency Condition EPIP-20104 02/27/90 Duty Call Notification/Staff Augmentation EPIP-20105 11/07/89 Emergency Response Facilities EPIP-20106 11/07/89 Natural Emergencies EPIP-20107 03/24/89 Fire/Explosion Emergencies 04/24/90 Criteria For, and Conduct of Local EPIP-20109'PIP-20110 Evacuations 06/19/89 Criteria For, and Conduct of Owner Controlled Area Evacuation EPIP-20111 11/07/89 Re-entry EPIP-20112 04/17/89 Communications Network EPIP-20125 04/24/90 On-site Emergency Organization EPIP-20126 04/04/89 Off-site Dose Calculations

BOOK 14 FUEL HANDLING PROCEDURES OP-16000.1 04/02/90 Limitations and Precautions for Handling Fuel Assemblies OP-16200 12/03/88'anipulator Crane Operating Instructions HEALTH PHYSICS PROCEDURE 0-ADM-600 07/12/90 Health Physics Manual SURVEILLANCE PROCEDURES O-OSP-023.1 7/20/90 Diesel Generator Operability Test 3-OSP-041.1 5/17/90 Reactor Coolant Leak Rate Calculation 3-0SP-059.5 4/18/90 Power Range Nuclear Instrumentation Shift Checks and Daily Calibrations 3-0SP-59.6 1/23/90 High Flux at Shutdown 3-OSP-075.1 4/18/90 Auxiliary Feedwater Train 1 Operability Verification

BOOK 15 SYSTEM DESCRIPTIONS SDg REV DATE TITLE 2 4 01/07/89 Reactor Vessel and Internals 3 3 04/19/90 Incore Instrumentation 4 5 04/19/90 Excore Nuclear Instrumentation 5 5 06/14/90 Full Length Rod Control 6 4 05/22/90 Rod Position Indication 7 5 04/26/90 Reactor Coolant System 8 3 11/17/89 Reactor Coolant Pumps 9 7 04/24/90 Pressurizer and Relief System 11 3 11/16/88 Steam Generator

BOOK 16 SYSTEM DESCRIPTIONS (CONT.)

SDg REV DATE TITLE 13 6 05/31/90 Chemical S Volume Control System 21 6 05/15/90 Emergency Core Cooling System 25 5 06/20/89 Containment Spray 26 2 11/30/88 Containment Building 28 4 12/11/89 Containment. Post Accident Monitoring and Post Accident Sampling System 29 6 11/08/89 Containment Ventilation and Heat Removal System 40 3 02/28/89 Component Cooling Water 41 3 01/16/90 Fuel Pool Cooling, Purification and Ventilation 44 5 06/07/90 Fuel Handling System 48 3 10/25/89 Primary Makeup and Demineralized Water System 63 4 01/15/90 Reactor Protection and Safeguards Actuation System 68 5 10/10/89 Radiation Monitoring and Protection 90 2 12/07/88 Electrical Heat Tracing 104 5 11/01/89 Main and Extraction Steam System

! ~ g BOOK 17 SYSTEM DESCRIPTIONS (CONT.)

SDP REV DATE TITLE 105 4 03/07/90 Steam Dump System 111 3 09/09/88 Feedwater Heater Vents and Drain System 112 5 06/14/90 Condensate and Feedwater System 117 12 07/11/90 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 System 132 5 05/16/90 Turbine Plant Cooling Water System 137 5 10/16/89 Emergency Diesel Generator and Auxiliaries 139 3 10/26/89 Main Generator and Controls 140 3 03/19/90 Main Power Distribution 144 4 10/02/89 120 VAC 6 125 VDC Distribution System

BOOK 18 SYSTEM DESCRIPTIONS (CONT.)

SDP REV DATE TITLE 153 4 02/28/89 Fire And Service Water 155 8 07/17/89 Plant Air Systems 160 2 02/17/89 Screenwash and Intake Structure 165 8 05/30/90 Intake Cooling Water System 166 5 05/04/90 Ventilation System and Air Conditioning 170 4 05/04/90 . Emergency Load Sequencer/Bus Stripping 176 3 02/23/89. Fire Protection and Alarm System

BOOK 19 SYSTEM DESCRIPTION LESSON PACKAGES SDg DATE LP -Num. TITLE 2 09/23/88 6900102 Reactor Vessel and Internals 3 11/20/89 6900103 Incore Instrumentation 4 06/25/90 6900104 Excore Nuclear, Instrumentation 5 07/26/88 6900105 Full Length Rod Control 6 06/06/90 6900106 Rod Position Indication 7 04/18/90 6900107 Reactor Coolant System 8 11/16/89 6900108 Reactor Coolant Pumps 9 01/23/90 6900109 Pressurizer and Relief System 11 10/19/88 6900111 Steam Generator

BOOK 20 SD LESSON PACKAGES (CONT.)

SDg DATE LP Num. TITLE 13 05/30/90 6900113 Chemical & Volume Control System 21 01/24/90 6900121 Emergency Core Cooling System 25 06/16/89 6900125 Containment Spray 26 02/09/90 6900126 Containment Building 28 07/03/90 6900128 Containment Post Accident Monitoring and Sampling System 29 06/08/89 6900129 Containment Ventilation and Heat Removal System 40 05/01/90 6900140 Component Cooling Water 41 01/16/90 6900141 Fuel Pool Cooling, Purification and Ventilation 44 05/15/90 6900144 Fuel Handling System 48 10/16/89 6900148 Primary Makeup and Demin Water 63 11/20/89 6900163 Reactor Protection and Safeguards Actuation System 68 09/25/89 6900168 Radiation Monitoring and Protection

t BOOK 21 SD LESSON PACKAGES (CONT.)

SDg DATE LP Num. TITLE 90 08/08/88 6900112 Electrical Heat Tracing 104 10/29/89 6900117 Main and Extraction Steam System 105 11/16/88 6900118 Steam Dump System 111 09/15/88 6900120 Feedwater Heater Vents and Drain 112 06/14/90 6900122 Condensate and Feedwater System 117 10/03/89 6900123 Auxiliary Feedwater System 123 05/26/89 6900131 Condenser and Circulating Water 127 06/16/88 6900132 Main Turbine Control 130 11/30/88 6900133 Turbine, Oil, and Gland Seal 132 04/17/90 6900134 Turbine Plant Cooling Water System 137 11/08/89 6900136 Emergency Diesel Generator and Auxiliaries 139 10/10/89 6900137 Main Generator and Controls 140 03/01/90 6900138 Main Power Distribution 144 03/14/89 6900139 120 VAC & 125 VDC Distribution 153 01/09/89 6900143 Fire And Service Water

BOOK 22.

SD LESSON PACKAGES (CONT.)

SDg DATE LP Num. TITLE 155 05/11/90 6900145 Plant Air Systems 160 10/02/88 6900152 Screenwash and Intake Structure 165 07/11/90 6900154 Intake Cooling Water System 166 04/30/89 6900155 Ventilation and Air Conditioning 170 02/08/90 6900157 Emergency Load Sequencer/Bus Stripping 176 01/04/89 6900159 Fire Protection and Alarm System

BOOK 23 SYSTEMS EXAM BANK QUESTIONS SDg LP Num. TITLE 2 6900102 Reactor Vessel and Internals 3 6900103 Incore Instrumentation 4 6900104 Excore Nuclear Instrumentation 5 6900105 Full Length Rod Control 6 6900106 Rod Position Indication 7 6900107 Reactor Coolant System 8 6900108 Reactor Coolant Pumps 9 6900109 Pressurizer and Relief System 11 6900111 Steam Generator 13 6900113 Chemical 6 Volume Control System 21 6900121 Emergency Core Cooling System 25 6900125 Containment Spray 26 6900126 Containment Building 28 6900128 Containment Post Accident Monitoring and Sampling System 29 6900129 Containment Ventilation and Heat Removal System 40 6900140 Component Cooling Water 41 6900141 Fuel Pool Cooling, Purification and Ventilation 44 6900144 Fuel Handling System 48 6900148 Primary Makeup and Demin Water 63 6900163 Reactor Protection and Safeguards Actuation System

BOOK 24 SYSTEMS EXAM BANK (CONT.)

SDg LP Num. TITLE 68 6900168 Radiation Monitoring and Protection

'90 6900112 Electrical Heat Tracing 104 6900117 Main and Extraction Steam System 105 6900118 Steam Dump System 111 6900120 Feedwater Heater Vents and Drain 112 6900122 Condensate and Feedwater System 117 6900123 Auxiliary Feedwater System 123 6900131 Condenser and Circulating Water 127 6900132 Main Turbine Control 130 6900133 Turbine, Oil, and Gland Seal 132 6900134 Turbine Plant Cooling Water System 137 6900136 Emergency Diesel Generator and Auxiliaries 139 6900137 Main Generator and Controls 140 6900138 Main Power Distribution 144 '900139 120 VAC & 125 VDC Distribution 153 6900143 Fire And Service Water 155 6900145 Plant Air Systems 160 6900152 Screenwash and Intake Structure 165 6900154 Intake Cooling Water System 166 6900155 Ventilation and Air Conditioning 170 6900157 Emergency Load Seguencer/Bus Stripping 176 6900159 Fire Protection and Alarm System

BOOK 25 UNIT 3 EMERGENCY OPERATING PROCEDURES LESSON PACKAGES 3-EOP-E-0 01/25/90 6900321 Reactor Trip or Safety Injection 3-EOP-ES-O.O 01/30/90 6900322 Rediagnosis 3-EOP-ES-0.1 07/27/90 6900323 Reactor Trip Response 3-EOP-ES-0.2 07/27/90 6900324 Natural Circulation Cooldown 3-EOP-ES-0.3 07/23/90 6900325 Natural Circulation Cooldown With Steam Void In Vessel With RVLMS (QSPDS) 3-EOP-ES-0.4 07/23/90 6900326 Natural Circulation Cooldown With Steam Void In Vessel (Without RVLMS) 3-EOP-E-1 02/05/90 6900327 Loss of Reactor or Secondary Coolant 3-EOP-ES-1.1 02/16/90 '900328 SI Termination 3-EOP-ES-1.2 07/14/90 6900329 Post LOCA Cooldown Depressurization

BOOK 26 EOP LESSON PACKAGES (CONT.)

3-EOP-ES-1.3 02/15/90 6900330 Transfer to Cold Leg Recirculation 3-EOP-ES-1.4 02/16/90 6900331 Transfer to Hot Leg Recirculation 3-EOP-E-2 01/29/90 6900334 Faulted Steam Generator Isolation 3-EOP-E-3 03/28/90 6900339 Steam Generator Tube Rupture 3-EOP-ES-3.1 01/25/90 6900340 Post-SGTR Cooldown Using Backfill 3-EOP-ES-3.2 01/25/90 6900341 Post-SGTR Cooldown Using Blowdown 3-EOP-ES-3.3 01/30/90 6900342 Post-SGTR Cooldown Using Steam Dump 3-EOP-ECA-O.O 01/27/90 6900348 Loss of All AC Power 3-EOP-ECA-0.1 02/10/90 6900349 Loss of All AC Power Recovery Without SI Required 3-EOP-ECA-0.2 02/08/90 6900350 Loss of All AC Power Recovery With SI Required

BOOK 27 EOP LESSON PACKAGES (CONT.)

3-EOP-ECA-1.1 02/12/90 6900332 Loss of Emergency Coolant Recirculation 3-EOP-ECA-1.2 02/05/90 6900333 LOCA Outside Containment 3-EOP-ECA-2.1 03/28/90 6900335 Uncontrolled Depressurization of All Steam Generators 3-EOP-ECA-3.1 01/25/90 '900343 SGTR With Loss of Reactor Coolant Subcooled Recovery Required 3-EOP-ECA-3.2 01/25/90 6900344 SGTR With Loss of Reactor Coolant Saturated Recovery Desired 3-EOP-ECA-3.3 01/30/90 6900345 SGTR Without. Pressurizer Pressure Control 3-EOP-F-0 02/03/90 6900353 Critical Safety Function Status Trees 3-FR-S.1,2 04/19/90 6900346 Response to Nuclear Generation/ATWS 3-FR-C.1-3 07/23/90 6900347 Response to Xnadequate Core Cooling

BOOK 28 EOP LESSON PACKAGES (CONT.)

3-FR-H.1-5 04/19/90 6900337 Response to Loss of Secondary Heat Sink 3-FR-P.1,2 04/19/90 6900336 Response to Imminent Pressurized Thermal Shock Condition 3-FR-Z.1-3 05/11/90 6900338 Response to High Containment.

Challenges 3-FR-I.1-3 04/19/90 6900351 Response to RCS Integrity Challenges

BOOK 29 ADMINISTRATIVE PROCEDURE LESSON PACKAGES NEW STYLE PROCEDURE LESSON PACKAGES ADM-200 06/04/90 6900025 Conduct of Operations ADM-202 02/27/90 6900022 Shift Relief and Turnover ADM-203 10/24/88 6900024 Shift Operating Practices ADM-204 04/04/90 6900023 Operator's Narrative Logs ADM-701 04/05/90, 6900007 Plant Work Orders OLD STYLE PROCEDURE LESSON PACKAGES AP-103.4 04/06/90 6900008 In-Plant Equipment Clearance Orders AP-103.8 02/08/88 6900013 Shutdown Rate Limits AP-103.12 08/09/89 6900006 Notification of Significant Events AP-109.3 06/11/90 6900010 On the Spot .Changes OFF-NORMAL OPERATING PROCEDURE LESSON PACKAGES NEW STYLE ONOPS LESSON PACKAGES ONOP-004 04/16/90 6900255 Loss of Off-Site Power ONOP-28.X 07/10/90 6900207 Rod Control System Malfunctions ONOP-30 07/12/90 6900229 Loss of Component Cooling Water ONOP-41.3 10/21/89 6900212 Excessive RCS Leakage ONOP-41.4 08/17/89 6900228 Excessive RCS Activity ONOP-41.5 08/17/89 6900204 Pressurizer Pressure Control Malfunction ONOP-41.6 05/01/89 6900254 Pressurizer Level Control Malfunction ONOP-46. 1 11/21/88 6900232 Emergency Boration ONOP-46.3 04/19/88 6900233 Loss of Boration Flowpaths ONOP-47.1 02/20/90 6900234 Loss of Charging in Modes 1-3 ONOP-59.X 11/22/88 6900206 Nuclear instrumentation Malfunctions ONOP-67&71 08/17/89 6900236 Steam Generator Tube Leak &

Inadvertant Radioactive Gas Release ONOP-89 10/08/88 6900248 Turbine Runback ONOP-94 10/08/88 6900249 Alternate Means for Monitoring CPAMS ONOP-100 10/10/89 6900239 Fast Load Reduction ONOP-105 07/10/90 6900252 Control Room Evacuation

gl ~

OLD STYLE ONOPS LESSON PACKAGES ONOP-208.14 07/28/88 6900243 Failure of Instrumentation ONOP-1208.1 11/08/89 6900241 PORV Malfunction ONOP-2608.2 01/20/90 6900235 CVCS Boron Control System Malfunction ONOP-3108.2 07/25/88 6900238 High Activity in Component Cooling Water ONOP-3308.1 07/11/90'900217 Turbine Plant Cooling Water Malfunction ONOP-3408.1 05/01/90 6900215 Intake Cooling Water Malfunction ONOP-3408.2 01/18/88 6900216 Intake Cooling Water / Failure of the System ONOP-9408.X 04/28/90 6900244 Malfunction of the 4kv Systems including Cranking Diesels ONOP-1108.1 07/12/90 6900205 Reactor Coolant Pump Malfunctions ONOP-11108.1 08/12/88 6900242 Process Radiation Monitoring ONOP-11208.1 07/25/246 6900246 Area Radiation Monitoring

ADDITION MATERIAL BOOK 30 Technical Specifications BOOK 31 Plant Curve Book BOOK 32 Setpoint Document / Special Instructions BOOK 33 JPM's Sequence Numbers 1 through 82 BOOK 34 JPM's Sequence Numbers 83 through 153 BOOK 35 Simulator Information BOOK 36 Simulator Senarios BOOK 37 Reactor Operator / Senior Reactor Operator Task Lists BOOK 38 Emergency Operating Procedure Exam Bank BOOK 39 Admin / ONOP / EPIP Exam Bank BOOK 40 Complete Procedure Index (Upgrade and Original Plant Drawings / Logics 6 Control Diagrams