ML20214K583

Forwards List of Documents Sent to NRC for Preparing Licensing Exams Scheduled During Wk of 870713-17.Documents Should Be Returned Upon Completion.Operations Mgt Procedure 2-1, Duties of Reactor Operators on Control... Included

ML20214K583
Person / Time
Site:	Oconee
Issue date:	05/19/1987
From:	Tucker H DUKE POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8705290006
Download: ML20214K583 (10)

Text

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DUKE POWER GOMPANY v.o. nox aman CHAMLOTTE, N.C. 2H242 HALB. TUCKER retsenons m apassment (704) 073-4tKH sces.saa emoocceson l

May 19, 1987 T

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,10' U. S. Nuclear Regulatory Commission Attention: Document Control Desk k

s Washington, D. C. 20555

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Subject:

Oconee Nuclear Station Licensing Examinations Dear Sir Please find attached a list of documents which were sent to the NRC for preparing the Licensing Examinations which are scheduled during the week of July 13 through July 17, 1987 at Oconee. Upon completion of use of these documents, please return them to l

Duke Power Company Oconee Training Center Attention: Dale Tidwell l

Highway 183 l

Seneca South Carolina 29678 Please note that the Operations' Management Procedure 2-1 " DUTIES OF THE REACTOR OPERATORS ON THE CONTROL BOARD AND THE SRO IN THE CONTROL ROOM" has been included.

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If there are any questions or further information required, please feel free to contact us.

l Very truly yours, I

c Hal B. Tucker WHM/36/sbn h

Attachment 8705290006 870519 PDR ADOCK 05000269 y

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U. S. Nucle:r Regulcttry Comuniccion May 19, 1987 Page Two xc:

Mr. Bill Dean U. S. Nuclear Regulatory Cossaission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Ms. Helen Pastis Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commaission Washington, D. C.

20555 Mr. Bryan Core Battelle/ Pacific Northwest Laboratory Sigma 3 Building P. O. Box 999 Richland, Washington 99352 Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Comunission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. J. C. Bryant NRC Resident Inspector Oconee Nuclear Station i

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1 ATTACHMENT 1 TOPIC 1 - REACTOR THEORY Fission Process Neutron Multiplication Formula Subcritical Multiplication Reactivity Coefficients Fission Product Poisons

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Installed Poisons Reactor Kinetics Reactivity Balance Control Power Distribution l

LCO-Mod. Temp. Coeff. of Reactivity LCO-Low Power Physics Testing Restrictions LCO-Shutdown Margin LCO-Cont. Rod GP. and Power Dist. Limits l

TOPIC 2 THERMO/ HEAT TRANSFER / FLUID FLOW Steam Tables & Mollier Diagram TOPIC 3 CHEMISTRY Primary Chemistry Radiolytic Chemistry l

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TOPIC 4 RADIATION / RADIATION CONTROLS

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Area Radiation Monitors TOPIC 6 ELECTRICAL Keowce Hydro Generator Main Power Distribution Emergency Power Distribution Vital Instrument & Control Power D.C. Power Distribution SSF-Dierel & Generator SSF-Electrical Power System

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I TOPIC 7 SECONDARY SUPPORT SYSTEMS 4

1 Low Pressure Service Water Sys.

j High Pressure Serv. Water Sys.

Instrument Air System 4

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TOPIC 8 STEAM / TURBINE GENERATOR Once-Thru Steam Generator I

j Main Steam System Condenser Circulating Water System l

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TOPIC 9 CONDENSATE & FEEDWATER i

Condensate System Feedwater System

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Emergency Feedwater System i

SSF-Auxiliary Serv. Water Sys.

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TOPIC 10 PRIMARY NUCLEAR SYSTEMS l

i Reactor Coolant System i

Coolant Pump Motors j

Coolant Pump Seals i

High Pressure Injection Sys.

j Pressurizer i

Core Design & Construction Control Element Design l

Control Rod Drive Mechanism Low Pressure Injection Sys.

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Reactor Building Spray Reactor Building Cooling Sys.

1 Penetration Room Ventilation Core Flood System i

Component Cooling Sys.

l Hydrogen Detection & Control j

SSF-Rx Coolant Makeup Sys.

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t TOPIC 11 INSTRUMENTATION i

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Nuclear Instrumentation i

In Core Instrumentation l

Reactor Coolant Instrum.

i Auxiliary Shutdown Panels Control Rod Drive Instrum.

Reactor Protective System I

j Engineered Safeguards System SSF-Fire Protection System l

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TOFIC 12 CONTROLLING PROCEDURES Operator Aid Computer Pressure Temperature Indicating Display Safety Parameter Display Sys.

TOPIC 13 TRANSIENTS AND ACCIDENTS Normal Transients Abnormal Transients Accident Mitigation - Core Cooling Mechanics Accident Mitigation - Gas / Steam Binding TOPIC 15 WASTE AND ENVIRONMENTAL l

Process Radiation Monitors A

TOPIC 16 Fuel Handling System Fuel Handling Bridges Fuel Handling Auxiliaries Oconee Simulator Initial Condition List and Malfunction List F

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ATTACHMENT 2 ONS ABNORMAL PROCEDURES / EMERGENCY PROCEDURES UNIT #1 AP/1/A/1700/01 Load Rejection AP/1/A/1700/02 Excessive RCS Leakage AP/1/A/1700/03 Boron Dilution AP/1/A/1700/04 condenser Circulating Water System Failure AP/1/A/1700/05 Earthquake AP/1/A/1700/06 Natural Disaster AP/1/A/1700/07 Loss of Low Pressure Injection System AP/1/A/1700/08 Loss of Control Room AP/1/A/1700/09 Spent Fuel Damage AP/1/A/1700/10 Uncontrollable Flooding of Turbine Building AP/1/A/1700/11 Loss of Power i

AP/1/A/1700/12 Loose Parts in Reactor Coolant System AP/1/A/1700/13 Loss of Condenser circulating Water Intake Canal / Dam Failure AP/1/A/1700/14 Lcss of Normal Makeup or Letdown AP/1/A/1700/15 Inoperable Control Rods AP/1/A/1700/16 Loss of Flux Indication AP/1/A/1700/17 Loss of Containment Integrity AP/1/A/1700/18 Abnormal Release of Radioactivity AP/1/A/1700/19 Loss of 4160V Power and the BWST AP/1/A/1700/20 Loss of Component Cooling AP/1/A/1700/21 High Activity in RC System AP/1/A/1700/22 Loss of Instrument Air AP/1/A/1700/23 Loss of 1KI i

EP/1/A/1800/01 Emergency Operating Procedure

ATTACHMENT 3 OPERATING PROCEDURE INDEX (NRC COPY)

OP/1/A/1102/01 Controlling Procedure for Unit Startup OP/2/A/1102/01 OP/3/A/1102/01 OP/1/A/1102/02 Reactor Trip Recovery OP/2/A/1102/02 OP/3/A/1102/02 OP/1/A/1102/04 Operation at Power OP/2/A/1102/04 OP/3/A/1102/04 OP/0/A/1102/06 Removal & Restoration of Station Equipment OP/1/A/1102/10 Unit Shutdown OP/2/A/1102/10 OP/3/A/1102/10 OP/1/A/1103/04 Soluble Poison Concentration Control OP/2/A/1103/04 OP/3/A/1103/04 OP/0/A/1103/05 Pressurizer Operations OP/1/A/1103/06 Reactor Coolant Pump Operation OP/2/A/1103/06 OP/3/A/1103/06 PT/1/A/1103/15 Reactivity Balance Procedure PT/2/A/1103/15 PT/3/A/1103/15 OP/1/A/1104/02 High Pressure Injection System OP/2/A/1104/02 OP/3/A/1104/02 OP/1/A/1104/04 Low Pressure Injection System OP/2/A/1104/04 OP/3/A/1104/04 OP/0/A/1104/05 RB Spray OP/1&2/A/1104/10 Low Pressure Service Water OP/3/A/1104/10 i

OP/1/A/1104/12 Condenser Circulating Water System OP/2/A/1104/12 OP/3/A/1104/12

OPERATING PROCEDURE INDEX (NRC) COPY cont'd OP/1/A/1104/15 Reactor Building Cooling System OP/2/A/1104/15 OP/3/A/1104/15 OP/1&2/A/1104/18 Gaseous Waste Disposal System OP/3/A/1104/18 OP/0/A/1105/09 Control Rod Drive System OP/1/A/1106/01 Turbine Generator t

OP/2/A/1106/01 OP/3/A/1106/01 OP/1/A/1106/06 Emergency Feed System OP/2/A/1106/06 OP/3/A/1106/06 OP/0/A/1106/19 Keowee Hydro at Oconee l

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ATTACHMENT 4 CONTROLLED DOCUMENTS / TEXT BOOKS 1 Volume Technical Specifications 1 Volume Health Physics Manual 3 Volumes Emergency Plan

'i Volume Operations Manual 1 Book Fundamentals of Nuclear Reactivity Engineering 1 Book Thermodynamics 1 Set Selected Station Directives

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ATTACHMENT 5 ALARM RESPONSE PROCEDURES AND P&ID DRAWINGS 1 Set Alarm Response Procedures P&ID DRAWINGS HPI:

OFD-101A-3.1 3.2 3.3 3.4 3.5 LPI:

OFD-102A-3.1 3.2 3.3 RBS:

OFD-103A-3.1 RBC:

OFD-116E-3.1 l

CONDENSATE:

OFD-121A-3.4 3.5 3.6 3.7 3.8 4~

3.9 3.10 FEEEWATER:

OFD-121B-3.1 3.2 3.3 EFW:

OFD-121D-3.1 MS:

OFD-122A-3.1 3.2 l

3.3 3.4 LPSW:

OFD-124A-3.1 3.2 1

OFD-124B-3.1 3.6 CCW:

OFD-133A-3.1 l

3.2 3.3