NUCLEAR TRAININGgonuke.org/wp-content/toolkits/Radiation Protection/ch… · Web viewThis course will be taught using Radiological Protection Technician Training lesson plans and

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Boiling Water Reactor Systems

HPT001.014C Revision 2Page 1 of 89

NUCLEAR TRAININGTRAINING MATERIALS COVERSHEET

RADIOLOGICAL PROTECTION TECHNICIAN INITIAL TRAINING PROGRAM SYSTEMS TRAINING HPT001COURSE

COURSE NO.

BOILING WATER REACTOR SYSTEMS HPT001.014CLESSON TITLE LESSON PLAN NO.

INPO ACCREDITED YES X NO

MULTIPLE SITES AFFECTED YES X NO

PREPARED BY Brian K. Fike

Original Signed Signature / Date

PROCESS REVIEWDavid L. Stewart


LEAD INSTRUCTOR/PROGRAM MGR. REVIEWRob L. Coleman


PLANT CONCURRENCE ______________________________________ Signature / Date

TVAN CONCURRENCE (If applicable) ______________________________________ Signature / DateBFN SQN WBN CORP_____________________________________

Receipt Inspection and Distribution: Training Materials Coordinator /Date

Standardized Training Material Copies to: SQN Technical Training Manager, STC 2T-SQN

WBN Technical Training Manager, WTC 1D-WBNBFN Technical Training Manager, BFT 2A-BFN

TVA 40385 [NP 6-2003] Page 1 of 2


NUCLEAR TRAINING

REVISION/USAGE LOG

REVISION

NUMBER

DESCRIPTIONOF CHANGES

DATE PAGESAFFECTED

REVIEWED BY

0 Initial Issue. ALL

1 Program was inactive. Reviewed and revised to reactivate.

3/23/90 ALL Woodrow R. Burbage

2 General revision during program reactivation to enable lesson

TBD ALL Brian K. Fike

plan to be used in conjunction with material maintained current by Operations Training.

TVA 40385 [NP 6-2003] Page 2 of 2


I. PROGRAM : Radiological Protection Technician Initial Training

II. COURSE: Systems Training

III. LESSON TITLE: Boiling Water Reactor Systems

IV. LENGTH OF LESSON/COURSE: 80 Hours

V. TRAINING OBJECTIVES:

A. Terminal Objective:

Upon completion of the Nuclear Plant Systems Orientation for BWRs course , the student will demonstrate knowledge of Browns Ferry plant systems, by scoring >80% on the course written examinations.

B. Enabling Objectives:

Included in HO-3 is a list of enabling objectives that apply to the Boiling Water Reactor Systems course (HPT001.014C) for Radiological Protection Technicians. This course will be taught using Radiological Protection Technician Training lesson plans and Operations Hot License Training lesson plans.

VI. Training Aids

A. Whiteboard

B. Markers

VII. Training Materials

A. Appendices

1. Handouts

a. HO-1, List of Abbreviations and Acronyms

b. HO-2, Course Curriculum

c. HO-3, Enabling Objectives (Student’s Copy)


2. Transparencies

None

3. Appendix A, Enabling Objectives (Instructor’s Copy)

B. Attachments

Lesson plans listed in HO-2, Course Curriculum

VIII. References

INPO ACAD 93-008, Guidelines for Training and Qualifications of Radiological Protection Technicians, August 1993.


IX. Introduction

A. This lesson provides an overview of the course including the course administration, criteria for passing, objectives, curriculum, and method

of presentation.

B. Method of Presentation

1. Lecture and discussion with frequent questioning by instructor.

2. Reference for each lecture is the corresponding lesson plan listed on curriculum handouts.

3. Operations Training lesson plans used to ensure accuracy since most recent license exam.

4. Students are responsible for learning objectives listed in Enabling Objectives handout (Student’s Copy).

C. Instructional Methodology

The following guidelines are to be utilized by the instructor to ensure consistency.

1. For HPT001.XXX lesson plans, instructor will present material as directed by the lesson plan. For HPT001.014E Radiological Hazards Associated with Boiling Water Reactors, this lesson will be integrated with the course curriculum such that radiological hazards associated with each system (where applicable) are presented immediately after the Operations lesson plan has been presented.

2. For Operations lesson plans, the instructor will present the material as follows:

a. Introduce the particular lesson in a manner which will motivate the students and provide a reason for study by RadCon personnel.

b. Emphasize Error Prevention Tools as appropriate in each lesson.

c. Periodically ask questions appropriately to ensure comprehension.

d. Summarize the lesson by reviewing the enabling objectives in HO-3 Students should be encouraged to write answers to each objective.


e. Standardized answers to objectives are provided in Appendix A.

NOTE: The page numbers referenced in the objective answers may have shifted. Since Appendix A is an instructor tool only, the instructor will verify page numbers as part of their class preparation. The intent of this section is to provide the instructor with a tool to ensure continuity and consistency. This document should NOT be provided to the students.

HPT001.014CRevision 2Page 7 of 89

X. Lesson Body

A. Present HPT001.014D Introduction to BWRs

B. Present OPL171.002 Reactor Pressure Vessel/Internals

C. Present OPL171.053 Fuel Handling Equipment and Interlocks

D. Present OPL171.006 Control Rod Blade/Drive Mech

E. Present OPL171.007 Recirculation System And Flow Control

F. Present OPL171.039 Standby Liquid Control

G. Present OPL171.019 Source Range Monitors

H. Present OPL171.020 Intermediate Range Monitors

I. Present OPL173.148 Power Range Neutron Monitor System

J. Present OPL171.023 Traversing Incore Probe System

K. Present OPL171.052 Fuel Pool Cooling And Cleanup

L. Present OPL171.209 Auxiliary Decay Heat Removal

M. Present OPL171.013 Reactor Water Cleanup

N. Present OPL171.047 Reactor Building Closed Cooling Water

O. Present OPL171.050 Condenser Cooling Water

P. Present OPL171.048 Raw Cooling Water

Q. Present OPL171.049 Raw Service Water/Fire Protection

R. Present OPL171.009 Main Steam

S. Present OPL171.011 Condensate System

T. Present OPL171.026 Reactor Feedwater System

U. Present OPL171.030 Off-Gas System

V. Present OPL171.220 H2 Water Chemistry


W. Present OPL171.040 Reactor Core Isolation Cooling System

X. Present OPL171.042 High Pressure Coolant Injection System

Y. Present OPL171.043 Automatic Depressurization System

Z. Present OPL171.051 Emergency Equipment Cooling Water System

AA. Present OPL171.046 Residual Heat Removal Service Water System

BB. Present OPL171.044 Residual Heat Removal System

CC. Present OPL171.045 Core Spray System

DD. Present OPL171.016 Primary And Secondary Containment

EE. Present OPL171.032 Containment Nitrogen Systems

FF. Present OPL171.018 Standby Gas Treatment System

GG. Present HPT177.019 Radwaste Systems

HH. Present HPT001.014E Radiological Hazards Associated with Boiling Water Reactors


XI. Summary

This lesson has presented an overview of the BWR Systems course. Students should now be aware of the course schedule, the examination process, and passing criteria in accordance with the course objectives.


LIST OF ABBREVIATIONS AND ACRONYMS

Abbreviation Description

P Delta-P, Differential PressureT Delta-T, Differential Temperature ADHR Auxiliary Decay Heat Removal ADS Automatic Depressurization SystemALARA As Low As Reasonably AchievableAPRM Average Power Range MonitorARM Area Radiation MonitorAUO Assistant Unit OperatorCCW Condenser Circulating WaterCIV Combined Intermediate ValveCRD Control Rod DriveCRW Clean RadwasteCSS Core Spray SystemCST Condensate Storage TankDBA Design Basis AccidentDCN Design Change NoticeD/P Differential PressureDRW Dirty RadwasteDW DrywellDWEDS Drywell Equipment Drain SumpDWFDS Drywell Floor Drain SumpECCS Emergency Core Cooling SystemEECW Emergency Equipment Cooling WaterEPRI Electrical Power Research InstituteEQ Environmental QualificationFCV Flow Control ValveFE Flow ElementFI Flow IndicatorFPCC Fuel Pool Cooling and CleanupFSAR Final Safety Analysis ReportFT Flow TransmitterHCU Hydraulic Control UnitHEPA High Efficiency Particulate Air (Filter)HPCI High Pressure Coolant InjectionHWC Hydrogen Water ChemistryHx Heat ExchangerINPO Institute of Nuclear Power OperationsIRM Intermediate Range Monitor

HO-1 List of Abbreviations and Acronyms, page 1 of 3


LIST OF ABBREVIATIONS AND ACRONYMS (continued)

LCV Level Control ValveLER Licensee Event ReportLOCA Loss of Coolant AccidentLPCI Low Pressure Coolant InjectionLPRM Local Power Range MonitorMOV Motor Operated ValveMS Main SteamMSIV Main Steam Isolation ValveMSL Main Steam LineMSV Main Stop ValveMWt Megawatts thermalNPSH Net Positive Suction HeadNRC Nuclear Regulatory CommissionOI Operating InstructionPWR Pressurized Water ReactorRBCCW Reactor Building Closed Cooling WaterRBEDS Reactor Building Equipment Drain SumpRBFDS Reactor Building Floor Drain SumpRCIC Reactor Core Isolation CoolingRCP Reactor Coolant PumpRCS Reactor Coolant SystemRCW Raw Cooling WaterREP Radiological Emergency PlanRFP Reactor Feedwater PumpRFPT Reactor Feedwater Pump TurbineRHR Residual Heat Removal SystemRHRSW Residual Heat Removal Service WaterRPV Reactor Pressure VesselRSW Raw Service WaterRWCU Reactor Water CleanupRx ReactorSCFM Standard Cubic Feet per MinuteSDC Shutdown CoolingSDV Scram Discharge VolumeSFSP Spent Fuel Storage PoolSGT Standby Gas TreatmentSI Surveillance InstructionSJAE Steam Jet Air EjectorSLC Standby Liquid ControlSOER Significant Operating Experience ReportSPE Steam Packing Exhauster



LIST OF ABBREVIATIONS AND ACRONYMS (continued)

SRM Source Range MonitorSRO Senior Reactor OperatorSRV Safety Relief ValveSTA Shift Technical AdvisorS/U StartupTCV Turbine Control ValveTMI Three Mile IslandTSV Turbine Stop Valve



COURSE CURRICULUM - WEEK ONE

TOPIC LESSON PLAN NUMBER MONDAY

INTRODUCTION TO BWRs HPT001.014D REACTOR PRESSURE VESSEL/INTERNALS OPL171.002 FUEL HANDLING EQUIPMENT AND INTERLOCKS OPL171.053

TUESDAY

CONTROL ROD BLADE/DRIVE MECH. OPL171.006 RECIRCULATION SYSTEM and FLOW CONTROL OPL171.007

WEDNESDAY

STANDBY LIQUID CONTROL OPL171.039 SOURCE RANGE MONITORS OPL171.019 INTERMEDIATE RANGE MONITORS OPL171.020 POWER RANGE NEUTRON MONITOR SYSTEM OPL173.148 TRAVERSING INCORE PROBE SYSTEM OPL171.023

THURSDAY

FUEL POOL COOLING AND CLEANUP OPL171.052 AUXILIARY DECAY HEAT REMOVAL OPL171.209 REACTOR WATER CLEANUP OPL171.013 REACTOR BUILDING CLOSED COOLING WATER OPL171.047________________________________________________________________________FRIDAY

CONDENSER COOLING WATER OPL171.050RAW COOLING WATER OPL171.048RAW SERVICE WATER/FIRE PROTECTION OPL171.049MAIN STEAM OPL171.009

HO-2 Course Curriculum, page 1 of 2


COURSE CURRICULUM - WEEK TWO

TOPIC LESSON PLAN NUMBER MONDAY

REVIEW N/A EXAM N/A CONDENSATE SYSTEM OPL171.011 TUESDAY

REACTOR FEEDWATER SYSTEM OPL171.026 OFF-GAS SYSTEM OPL171.030 H2 WATER CHEMISTRY OPL171.220 _ WEDNESDAY

REACTOR CORE ISOLATION COOLING SYSTEM OPL171.040 HIGH PRESSURE COOLANT INJECTION SYSTEM OPL171.042 AUTOMATIC DEPRESSURIZATION SYSTEM OPL171.043 EMERGENCY EQUIPMENT COOLING WATER SYSTEM OPL171.051 THURSDAY

RESIDUAL HEAT REMOVAL SERVICE WATER SYSTEM OPL171.046 RESIDUAL HEAT REMOVAL SYSTEM OPL171.044 CORE SPRAY SYSTEM OPL171.045 PRIMARY and SECONDARY CONTAINMENT OPL171.016 CONTAINMENT NITROGEN SYSTEMS OPL171.032 FRIDAY

STANDBY GAS TREATMENT SYSTEM OPL171.018 RADWASTE SYSTEMS HPT177.019

REVIEW N/A EXAM N/A

HO-2 Course Curriculum, page 2 of 2


BOILING WATER REACTOR SYSTEMS FOR RADIOLOGICAL PROTECTION TECHNICIANS

TERMINAL OBJECTIVE: Upon completion of the Nuclear Plant Systems Orientation for BWRs course , the student will demonstrate knowledge of Browns Ferry plant systems, by achieving a score of at least 80% on the course written examinations.

ENABLING OBJECTIVES:

On the following pages is a list of enabling objectives that apply to the Boiling Water Reactor Systems course (HPT001.014C) for Radiological Protection Technicians. This course will be taught using Radiological Protection Technician Training lesson plans and Operations Hot License Training lesson plans, supportive of these objectives.

The students will perform each enabling objective from memory, under the examination ground rules, utilizing information and materials provided by the instructor, and per any additional conditions stated in a particular objective.


OPL171 .002 Reactor Pressure Vessel and Internals

1. Describe the normal flow path of coolant through the Reactor Pressure Vessel (RPV).

2. Describe the injection paths of Emergency Core Cooling Systems (RHR, CSS, and HPCI) to the RPV.


3. Given a drawing of the Reactor Vessel label the following components and give their purpose:

a. Baffle Plate

b. Feedwater inlet nozzles and spargers

c. Main Steam outlet nozzles

d. Jet pump assembly

e. Main Steam separators and dryers

f. Core Plate

g. Top Guide

h. Core Shroud

i. Core Spray Sparger

j. Recirc suction and inlet

k. Vessel Support Skirt and Ring Girder

l. Control Rod Drive Housings/Support Network

m. Control Rod Guide Tube

n. Orificed Four-Lobed Fuel Support

4. Describe the jet pump design feature that ensures core flooding is possible following a DBA LOCA.


OPL171.053 Fuel Handling Equipment And Interlocks

1. Given a drawing, locate the following Refuel Floor Areas:

a. Reactor Cavities (all units)

b. Spent Fuel Pools (all units)

c. Equipment Pits (all units)

d. U1/2 Transfer Canal

e. New Fuel Inspection Stands

f. Containment Relief (Blow-out) Panels

2. Identify the purpose of the following tools/components:

a. Refueling Bridge/Platform

b. New Fuel Inspection Stand

c. Fuel Prep Machine

d. Defective Fuel Canisters

e. Blade Guides

f. Dunking Chambers (Fuel Loading Chambers - FLCs)

g. Control Rod Unlatching Tool

h. Control Rod Grapple

i. Control Rod Guide Tube Grapple

j. Fuel Support Grapple


OPL171.006 Control Rod Blade and Drive Mechanism

1. State the three purposes of the Control Rod Blade and Drive Mechanism.

2. State the neutron absorption material utilized by the control rods.

3. Describe the following components and give their purpose:

a. Control rod velocity limiter

b. Index tube

c. Indicator tube

d. Spud

4. Describe what is meant by the term "uncoupled" control rod.


OPL171.007 Recirculation System and Flow Control

1. State the purpose of the Recirculation System.

2. Describe the Recirculation System flow path/configuration under the following conditions:

a. Normal operation, 0% to 100% power.

b. DBA LOCA

3. Describe the Recirculation pumps and state their location/purpose.


OPL171.007 Recirculation System and Flow Control (cont'd)

4. Describe the interrelation of the following systems with the Recirculation System.

a. CRD Hydraulic System

b. RHR System

c. RWCU System

d. RBCCW System

e. RCW System

f. Coolant Sampling

5. Describe how an increase in Recirculation Pump speed causes an increase in reactor power.


OPL171.039 Standby Liquid Control System (SLC)

1. State the purpose of the SLC System.

2. Describe the SLC System flow path and major components, to include their location.

3. State the neutron absorber solution used by the SLC System.

4. State the purpose of the squib valve

5. State the conditions which require initiation of the Standby Liquid Control System


OPL171.019 Source Range Monitor System (SRM)

1. State the purpose of the SRM System.

2. Describe the purpose and operation of the following SRM components:

a. Fission Chambers

b. Pulse Height Discriminator

3. State the following concerning SRM detectors:

a. Number of detectors detectors

b. Ranges of Reactor operation in which SRMs are normally used to monitor power.


OPL171.020 Intermediate Range Monitoring System (IRM)

1. State the purpose of the IRM System.

2. State why the active coating of the IRM detector is only 1/5th of that found in the SRM detector.

3. State the following concerning IRM detectors:

a. Number of IRM detectors detectors

b. Ranges of Reactor operation in which IRMs are normally used to monitor power.


OPL171.148 Power Range Neutron Monitoring System (PRNM)

1. Describe the operation of an LPRM detector

2. State the total number of LPRM detectors. detectors

3. Describe the interrelationship of the LPRM detectors with the TIP system.


OPL171.023 Traversing Incore Probe System (TIPs)

1. State the purposes of the TIP System.

2. Identify the purpose and location of the following components of the TIP system:

a. Probe

b. Cabling

c. Drive mechanism

d. Guide tube

e. Shield chamber

f. Shear valve

g. Ball valve

h. Index mechanism

3. State the type of detector utilized by the TIP System.


OPL171.052 Fuel Pool Cooling and Cleanup System (FPCC)

1. State the purpose of the Fuel Pool Cooling and Cleanup System.

2. Describe the FPCC System flow path under normal conditions, to include major components and their location.

3. Describe the interrelation of the following systems with the FPCC System.

a. RBCCW

b. RHR

c. RWCU


OPL171 .209 Auxiliary Decay Heat Removal System

1. State the purpose of the Auxiliary Decay Heat Removal System.

2. Describe the function and flow path of the primary loop, to include major components and their location.

3. Describe the function and flow path of the secondary loop, to include major components and their location.


OPL171.013 Reactor Water Cleanup System (RWCU)

1. State the purposes of the Reactor Water Cleanup System.

2. Describe the Reactor Water Cleanup System flow path/configuration under the following conditions:

a. Normal operation

b. Plant heat-up and start-up

3. Describe the following components and give their purpose and location:

a. Regenerative heat exchanger

b. Non-regenerative heat exchanger

c. RWCU pumps

d. Filter/demineralizers


OPL171.013 Reactor Water Cleanup System (RWCU) (cont’d)

4. Describe the interrelation of the following systems with the Reactor Water Cleanup System:

a. RBCCW System

b. Control Rod Drive Hydraulic System

c. Standby Liquid Control System


OPL171.047 Reactor Building Closed Cooling Water System (RBCCW)

1. State the purpose of the RBCCW System.

2. Describe the RBCCW System flow path during normal system operation, to include major components and their location.

3. State the normal and backup sources of cooling water to the RBCCW heat exchangers.

4. Recognize typical heat loads cooled by the RBCCW System.


OPL171.050 Condenser Circulating Water System (CCW)

1. State the purpose of the Condenser Circulating Water System

2. List the two modes of operation of the Condenser Circulating Water System and describe the flow path through each, to include major components and their location.

.


OPL171.048 Raw Cooling Water System (RCW)

1. State the purpose of the RCW System and the following RCW System components, to include their location:

a. RCW pumps

b. RCW booster pumps

2. Describe the flow path through the RCW System.

3. State the interrelationship between RCW and the following:

a. Condenser Circulating Water

b. Raw Service Water

c. RBCCW

d. EECW


OPL171.049 Raw Service Water System

1. State the purpose of the Raw Service Water System.

2. State the purpose of the Raw Service Water tanks.


OPL171.009 Main Steam System

1. Describe the Main Steam System flow path/configuration under normal operating conditions.

2. Identify the purpose and location of the following components of the Main Steam system:

a. Steam lines

b. Flow Restrictors

c. Safety/Relief Valves

d. Main Steam Isolation Valves (MSIV)

e. Turbine By-passValve

f. Main Steam Stop Valve (MSSV)

g. Turbine Control Valve

h. High Pressure turbine

i. Moisture Separator

j. Combined Intercept Valve

k. Low Pressure Turbine

l. Reactor Head Vent

3. Recognize the relationship of the Main steam system with other systems/components to include:

a. HPCI

b. RCIC

c. ADS

d. Condensate

e. Feedwater

f. SJAE


OPL171.009 Main Steam System (cont’d)

4. Describe the position to which MSIVs fail on loss of air, including the purpose of the air accumulators.

5. List the balance of plant steam loads supplied from the Main Steam System


OPL171 .011 Condensate System

1. State the purpose of the Condensate System.

2. Describe the Condensate System flow path/configuration under the following conditions:

a. Normal operation at power

b. Startup or shutdown at less than 350 psig reactor pressure

c. Short cycle recirculation/cleanup

d. Makeup

e. Reject

3. Describe the purpose and operation of the following components, to include their location:

a. Main condenser hotwell

b. Condensate pumps

c. Condensate booster pumps

d. Low Pressure feedwater heaters

e. Filter/demineralizers


OPL171.026 Reactor Feedwater System

1. State the purpose of the reactor feedwater system.

2. Describe the purpose and operation of the following components, to include their location.

a. Reactor feedwater pumps

b. Startup by-pass valve

c. High pressure feedwater heaters

3. Describe the flow path/configuration of the reactor feedwater systems during the following plant conditions.

a. Startup below 350 psig reactor pressure.

b. 100% power normal operation.

c. Long cycle recirculation/cleanup


OPL171.026 Reactor Feedwater System (cont’d)

4. Describe the interrelationships of the following systems/components with the reactor feedwater system.

a. High Pressure Coolant Injection System

b. Reactor Core Isolation Cooling System

c. Reactor Water Cleanup System


OPL171.030 Off-Gas System

1. State the purposes of the Off-Gas system.

2. Describe the Off-Gas system flow path during normal operation.

3. State the purpose of the following Off-Gas system components, to include their location.

a. Steam jet air ejectors

b. Off-Gas pre-heaters

c. Catalytic recombiners

d. Off-Gas condenser

e. Six-hour holdup volume

f. Charcoal adsorber

g. Dilution chamber


OPL171.220 Hydrogen Water Chemistry

1. Describe the purpose of the Hydrogen Water Chemistry System.

2. Determine the location of the hydrogen and oxygen injection points.


OPL171.040 Reactor Core Isolation Cooling System (RCIC)

1. State the purpose of the RCIC system.

2. Describe the RCIC system flow path after automatic initiation.

3. Describe the RCIC pump and location.


OPL171.042 High Pressure Coolant Injection System (HPCI)

1. State the purpose of the HPCI System.

2. Describe the HPCI System flow path/configuration during accident conditions:

3. Describe the HPCI pump and location.


OPL171.043 Automatic Depressurization System (ADS)

1. State the purpose of the ADS System.

2. Describe the ADS system components and flow path to include their location.


OPL171.051 Emergency Equipment Cooling Water System (EECW)

1. State the purpose of the EECW System

2. Describe the interrelationship between EECW and the following:

a. Raw Cooling Water

b. Raw Service Water

c. Diesel Generators

d. Reactor Building Closed Cooling Water


OPL171.046 Residual Heat Removal Service Water System (RHRSW)

1. State the purpose of the RHR Service Water system.

2. Describe the flow path of the RHRSW system to include purpose and location of major components.

3. Explain the relationship between the RHRSW system and the EECW system.


OPL171.044 Residual Heat Removal System

1. State the purposes of the RHR system.

2. State the six modes of operation of the RHR System and describe the flow path for each.

3. State the number of RHR pumps, RHR drain pumps, and RHR heat exchangers, and the location of each.


OPL171.045 Core Spray System (CSS)

1. State the purpose of the Core Spray System

2. Describe the Core Spray System flow path after automatic initiation.

3. State the number of CSS pumps and the location of each.


OPL171.016 Primary and Secondary Containment Systems

1. State the purpose of the following containment systems:

a. Primary containment

b. Secondary containment

c. Containment Atmosphere Monitoring (CAM) System

2. List five ways that fission products are contained or releases are controlled.

3. State the purpose of the following components/subsystems:

a. Suppression Chamber-drywell vacuum breakers

b. Torus-reactor building vacuum breakers

c. Suppression pool

4. State the Primary Containment design pressure and temperature.

Design pressure psig Design temperature °F


OPL171.016 Primary and Secondary Containment Systems (cont’d)

5. Describe the containment response to a design basis loss of coolant accident (LOCA).

6. List two methods of hydrogen generation in primary containment upon a primary rupture.


OPL171.032 Containment Nitrogen Systems

1. State the purpose of the following Containment Systems.

a. Containment Atmospheric Dilution (CAD) System.

b. Nitrogen Inerting System.

c. Drywell Air Coolers.

d. Drywell D/P Compressor.

2. State the purpose of the hardened wet-well vent system and the flow path.


OPL171.018 Standby Gas Treatment System (SGT)

1. State two purposes of the Standby Gas Treatment System.

2. Describe the Standby Gas Treatment System flow path to include major components and their location.

3. State the conditions that will automatically initiate the Standby Gas Treatment System (set points not required).

HPT001.014CRevision 2Appendix APage 53 of 89

OPL171.002 Reactor Pressure Vessel and Internals

1. Describe the normal flow path of coolant through the Reactor Vessel. (Page 43, Figure 33))

Feedwater enters downcomer - Recirc System suction from downcomer - discharge to 10 inlet nozzles - 20 jet pumps - entrains water from downcomer - flows below core plate - thru core - steam separators - steam dryer - drains to downcomer - steam exits main steam lines.

2. Describe the injection paths of Emergency Core Cooling Systems.

RHR/LPCI - discharges into Recirc Inlets - thru jet pump risers, thru jet pump nozzles - below core plate.

CSS - 2 CSS lines to Core Spray Spargers inside shroud, discharges on top of fuel bundles (Page 18)

HPCI/RCIC - FW lines A/B (Page 47 &48)

3. Given a drawing of the Reactor Vessel label the following components and give their purpose:

a. Baffle Plate (Page 12) - mounting surface for jet pump diffuser

b. Feedwater inlet nozzles and spargers (Page 9) - FW System discharge to vessel

c. Main Steam outlet nozzles (Page 9) - Conduct dry steam out of reactor

d. Jet pump assembly (Page 13) - Provide forced flow of coolant-moderator through the reactor to yield higher reactor power than possible with naturalcirculation

e. Main Steam separators and dryers (Page 32 & 36) - remove moisture from steam flow prior to exiting the vessel

f. Core Plate (Page 19) - provide vertical and lateral support for peripheral fuel bundles, lateral support for control rod guide tubes and fuel bundles, forces flow through fuel bundles

g. Top Guide (Page 20) - provides lateral support for upper end of fuel bundles

h. Core Shroud (Page 17) - separates downcomer annulus area from core region, provides floodability of core after LOCA

i. Core Spray Sparger (Page 18) - distribute water from CSS to top of fuel bundles


j. Recirc suction and inlet (Page 10) - route water from/to recirc system

k. Vessel Support Skirt and Ring Girder (Page 11) -provide vertical support for reactor vessel and internals

l. Control Rod Drive Housings/Support Network (Page 39) - prevent rapid ejection of a control rod in the unlikely event of a control rod drive housing

failure with the reactor at pressure

m. Control Rod Guide Tube (Page 23) - lateral support for the control rod blade velocity limiter; vertical support for the fuel support piece/ four fuel

assemblies.

n. Orificed Four-Lobed Fuel Support (Page 24) - lateral alignment for bottom end of fuel assemblies; transmit weight of fuel to control rod guide tube and

down to the reactor bottom head.

4. Describe the jet pump design feature that ensures core flooding is possible following a DBA LOCA. (Page 43-46)

2/3 core coverage ensured by jet pump standpipe design


OPL171.053 Fuel Handling Equipment And Interlocks

1. Given a drawing, locate the following Refuel Floor Areas:

a. Reactor Cavities (all units)

b. Spent Fuel Pools (all units)

c. Equipment Pits (all units)

d. U1/2 Transfer Canal

e. New Fuel Inspection Stands

f. Containment Relief (Blow-out) Panels

2. Identify the purpose of the following tools/components:

a. Refueling Bridge/Platform - for use in handling of fuel bundles and other related core components over the reactor and SFSP.

b. New Fuel Inspection Stand - used during inspection of new fuel prior to loading. Actually a fork lift/platform attached to an I-beam vertically bolted to the floor. Can

be located between U1/2 SFSPs and between U2 equipment pit and U3 SFSP.

c. Fuel Prep Machine - (two each on SFSP wall opposite gates); used to remove and replace fuel channels.

d. Defective Fuel Canisters - used during out of core sipping to prevent escape of fission product gases.

e. Blade Guides - used to support control rod blades when no fuel is loaded in a cell.

f. Dunking Chambers (Fuel Loading Chambers - FLCs) - Used with SRM electronics; held in a modified single blade guide

g. Control Rod Unlatching Tool - used to unlatch a control rod blade from its drive mechanism from above the core. CRBs may also be unlatched from under vessel

using a special tool (NOT the preferred approach due to dose).

h. Control Rod Grapple - used to transport control rod blades or other items having a similar bail assembly; used to reinstall CRBs instead of the unlatching tool.

i. Control Rod Guide Tube Grapple - used to remove and replace control rod guide tubes.

j. Fuel Support Grapple - remove and install fuel support pieces in the control rod guide tube.


OPL171.006 Control Rod Blade and Drive Mechanism

1. State the three purposes of the Control Rod Blade and Drive Mechanism. (Page 7)

1) Control reactor power2) A means of shaping both axial and radial flux profiles to achieve optimum

core performance and fuel utilization3) Adequate excess negative reactivity to shutdown the reactor from any

normal operating or accident condition at the most reactive time in core life.

2. State the neutron absorption material utilized by the control rods. (Page 9)

Boron carbide (B4 C) granules; 5B10 isotope; Some of the new rods contain hafnium

3. Describe the following components and give their purpose:

a. Control rod velocity limiter (Page 10) A stainless steel casting below the absorber section of the blades. Purpose is to limit free fall rate of the blade to 3.11 ft/sec. Mitigates the consequences of a C.R.D.A.

b. Index tube (Page 13 & 14) a notched moveable tube. Drive piston screwed in place at bottom and coupling spud screwed to top.

c. Indicator tube (Page 16) welded to piston tube at bottom forms a dry housing for the rod position indication probe.

d. Spud - multi-fingered; couples drive to CRB

4. Describe what is meant by the term "uncoupled" control rod.

The CRD mechanism is not attached to the CRB.


OPL171.007 Recirculation System and Flow Control

1. State the purpose of the Recirculation System. (Page 13)

Provides variable forced circulation of water through the reactor core which allows higher specific power to be attained and control flow distribution to all channels. Provides a reasonably fast means of changing reactor power.

2. Describe the Recirculation System flow path/configuration under the following conditions:

a. Normal operation, (Page 14 & 15) 0% to 100% power. Reactor vessel downcomer area to 2 separate loops with suction valve, recirc pump, discharge valve, ring header, 5 risers to 10 jet pumps.

b. DBA LOCA (Page 27) - Lo Lo level trips recirc pumps, 230 psig isolates discharge valves, and LPCI mode of RHR injects into discharge piping.

3. Describe the Recirculation pumps and state their location/purpose:

Recirculation pumps (Page 24) two single stage centrifugal pumps located inside primary containment; pumps on 550’ el.; motors on 563’ el.

4. Describe the interrelation of the following systems with the Recirculation System.

a. CRD Hydraulic System (Page 57) - Provides seal purging water to the #1 seal cavity of the recirculation pumps.

b. RHR System (Page 56) - Loop "A" provides a suction path for the SDC mode of RHR and both loops provide a discharge path for SDC and LPCI modes of RHR. (A loop RHR Sys. II, B loop RHR Sys. I)

c. RWCU System (Page 57) - Takes suction from the RHR pipe emanating from "A" Recirculation loop and from the bottom head drain line.

d. RBCCW System (Page 57) - Cools recirculation pump seals and motor oil cooler

e. RCW System (Page 57) - Provides cooling to M-G set air coolers and lube oil coolers.

f. Coolant Sampling (Page 57) - Primary system can be sampled from the "A" recirculation loop.


5. Describe how an increase in Recirculation Pump speed causes an increase in reactor power. (Page 21)

Speed increases; flow thru the core increases; density of moderator increases; rate at which neutrons are thermalized increases; fission rate increases; power increases.


OPL171.039 Standby Liquid Control System (SLC)

1. State the purpose of the SLC System. (Page 7) A backup system designed to bring the reactor from full power to a cold, Xenon free condition assuming none of the withdrawn control rods can be inserted, by injecting a solution of diluted Boron 10 into the reactor coolant system as directed by the BFN Emergency Operating Instructions.

2. Describe the SLC System flow path and major components, to include their location. (Page 7)

Injection path is from the storage tank, through one 100% capacity pump through both 100% capacity explosive valves and into the reactor via the in vessel injection sparger. All major components located in Rx Bldg, 639’ el. north.

3. State the neutron absorber solution used by the SLC System. (Page 9)

sodium pentaborate

4. State the purpose of the squib valve. (Page 13) To provide a zero leakage seal between the boron solution and the reactor vessel.

5. State the conditions which require initiation of the Standby Liquid Control System. (Page 21)

Manually initiated from the main control room 9-5 panel as directed by the emergency operating instructions.


OPL171.019 Source Range Monitor System (SRM)

1. State the purpose of the SRM System. (Page 7)

Monitor core neutron flux levels during, shutdown, refueling, and startup until IRMs are on scale.

2. Describe the purpose and operation of the following SRM components:

a. Fission Chambers (Figure 3 & Page 8 & 9) - To generate an electrical signal proportional to the neutrons flux level in the core. When neutrons penetrate

U3O

8 coating they cause fission with U235 atoms, causing fission products to recoil into the argon gas filled chamber. This gas ionizes and is attracted to the inner and outer electrodes, causing a current pulse when they strike them.

b. Pulse Height Discriminator (Page 16) Eliminates the pulses from the detector which are carried by gamma events, which are smaller, while passing those pulses generated by neutron events.

4. State the following concerning SRM detectors:

a. Number of detectors 4 detectors

b. Ranges of Reactor operation in which SRMs are normally used to monitor power. 3 cps to 10-3% power


OPL171.020 Intermediate Range Monitoring System (IRM)

1. State the purpose of the IRM System. (Page 7)

To monitor and record core neutron flux levels between the startup range and power range during reactor startup and shutdown.

2. State why the active coating of the IRM detector in only 1/5th of that found in the SRM detector. (Page 9)

To keep the detector from burning up (due to heat generated from higher fission rate).

3. State the following concerning IRM detectors:

a. Number of IRM detectors 8 detectors

b. Ranges of Reactor operation in which IRMs are normally used to monitor power.

104 cps to 40% power


OPL171.148 Power Range Neutron Monitoring System (PRNM)

1. State the operation of an LPRM detector

neutrons enter detector and cause fission of U235 in the detector coating; FPs cause subsequent ionizations of argon gas; free electrons are collected at positively

charged inner electrode producing a pulse; gamma pulses much smaller than that caused by FPs, which are much more energetic; neutron pulses result in an average signal that is proportional to the neutron flux.

2. State the total number of LPRM detectors. 172 detectors(Page 10)

3. Describe the interrelationship of the LPRM detectors with the TIP system: (Page 18)

Used to calibrate the LPRM detector and uses the dry tube in the LPRM detector assembly when traversing the core.


OPL171.023 Traversing Incore Probe System (TIPs)

1. State the purposes of the TIP System. (Page 6)

5 probes used to

(1) measure and record the axial thermal neutron flux profiles at 43 radial locations.

(2) Calibrate the fixed in core detectors (LPRMs)

2. Identify the purpose and location of the following components of the TIP system:

a. Probe - High range gamma sensitive gas chamber provides smooth output;NOT Special Nuclear Material; 2.5 inches in length; filled with argon gas; stainless steel chamber with Titanium anode attached to TIP cable; traverses the entire active length of the core through a dry tube in the LPRM detector tube.

b. Cabling - co-axial cable about 0.25 inch diameter by 150 feet in length; approximately 144 inches is exposed to core with full traverse; helical wrap of carbon steel covers entire length of drive cable providing a low friction means of driving detector; cable is no longer coated with graphite.

c. Drive mechanism - located just outside TIP room shield wall; provides forward or reverse and high or low-speed detector cable drive and provides detector position indication signals.

d. Guide tube - houses TIP probe and cabling; runs from outside of drive mechanism (drive box) through shield pigs, shear/ball valve assemblies, indexers, LPRM instrument tube.

e. Shield chamber - located inside TIP room; provides personnel shielding from a recently withdrawn detector.

f. Shear valve - located inside TIP room; provides an emergency method of sealing the guide tube

g. Ball valve - located inside TIP room; provides the normal means of sealing guide tube; normally closed except during TIP operation.

h. Index mechanism - located inside drywell; permits one TIP detector to be directed (indexed) to any one of up to 10 LPRM assemblies.

3. State the type of detector utilized by the TIP System. (Page 6)

High range gamma sensitive gas chamber


OPL171.052 Fuel Pool Cooling and Cleanup System (FPCC)

1. State the purpose of the Fuel Pool Cooling and Cleanup System.(Page 7)

a. Remove decay heat released from spent fuel elementsb. Minimize the corrosion product buildup to keep radiation levels low on the

refuel floor and prevent release to the environment.c. Control water clarity for fuel handling.d. Monitor fuel pool temperature and water level.

2. Describe the FPCC System flow path under normal conditions, to include major components and their location.(Page 16)

Fuel pool (RB, 664’ el.) to skimmer surge tank (RB, 664’ el.) to pumps (RB, 621’ el.) to heat exchangers (RB, 621’ el.) to filter/demineralizers (Radwaste Bldg, 565’ el.)to diffusers (RB, 664’ el. inside SFSPs).

3. Describe the interrelation of the following systems with the FPCC System. (Page 25)

a. RBCCW - Supplies cooling water to the FPCC heat exchangers.

b. RHR - RHR pump supply heat removal capability above the maximum normal design limit.

c. RWCU - Provides an alternate means of rejecting water from the pools.


OPL171.209 Auxiliary Decay Heat Removal System

1. State the purpose of the Auxiliary Decay Heat Removal System.

To provide an alternate means to remove decay heat from the fuel pool and reactor cavity during the early stages of an outage and therefore reduce the impact on outage durations.

2. Describe the function and flow path of the primary loop to include major components and their location.

To transfer decay heat from the spent fuel pool to the secondary loop, the primary loop pumps take suction from the spent fuel pool, discharge through one backwash strainer, two ADHR heat exchangers, and return to the spent fuel pool in a closed loop configuration.

Primary loop equipment located on RFF.

3. Describe the function and flow path of the secondary loop.

To reject heat from the primary loop to the atmosphere. Flow path is from the ADHR cooling tower basins to the pumps, through the ADHR heat exchangers, and back to the cooling towers.

Secondary loop equipment located on the ground outside of Rx Bldg except ADHR heat exchangers.


OPL171.013 Reactor Water Cleanup System (RWCU)

1. State the purposes of the Reactor Water Cleanup System. (Page 7)

(1) Reduce impurities in the reactor water.(2) Remove excess water from the reactor to either the hotwell or radwaste

during reactor heat-up.(3) Alternate means of removing heat from the reactor.

2. Describe the Reactor Water Cleanup System flow path/configuration under the following conditions: (Figure 1, Pages 8, 26 & 27)

a. Normal operation - Suction recirc loop A and bottom head drain, containment isolation valves, regenerative heat exchangers. Non-regenerative heat exchangers, RWCU pumps filter/demineralizers, regenerative heat exchangers, feedwater lines (U1&2 "B," U3 "A & B").

b. Plant heat-up and startup - Same flow path but some flow diverted to the blowdown line to the main condenser to control level in the reactor, necessary as reactor water volume swells during heat-up.

3. Describe the following components and give their purpose and location:

a. Regenerative heat exchanger (Page 11) - 3 heat exchangers avoids excessive demands on the RBCCW system and minimizes the heat loss from the reactor. Located in the RWCU HX Room, RB 593’ el.

b. Non-regenerative heat exchanger (Page 12) - 2 heat exchangers, uses RBCCW cooling water to cool effluent to <130°F which is necessary to prevent resin damage in the filter/demineralizers. Located in the RWCU HX Room, RB 593’ el.

c. RWCU pumps (Pages 10) - 2 centrifugal pumps 120 gpm each provided to overcome the ΔP of the system and inject water into the feedwater system for return to the reactor. Located in the RWCU Pump Rooms ‘A’ and ‘B’, RB 593’ el.

d. Filter/demineralizers (Page 12) two 50% capacity units used to maintain water purity by mechanical and chemical filtration. Located on the RFF, RB 664’ el. under shield blocks.


OPL171.013 Reactor Water Cleanup System (RWCU) (cont'd)

4. Describe the interrelation of the following systems with the Reactor Water Cleanup System:

a. RBCCW System (Page 24) - Supplies cooling water to the non-regenerative HT exch. and RWCU pumps.

b. Control Rod Drive Hydraulic System (Page 25) - Supplies water to the RWCU pump seals.

c. Standby Liquid Control System - isolates RWCU when initiated.


OPL171.047 Reactor Building Closed Cooling Water System (RBCCW)

1. State the purpose of the RBCCW System. (Page 7)

To provide cooling water to reactor auxiliary equipment located in primary and secondary containment over the full range of reactor power operation. Acts as a buffer between potential sources of radioactive contamination and the raw cooling water system.

2. Describe the RBCCW System flow path during normal system operation, to include major components and their location. (Figure 1)

Two RBCCW pumps (RB 593’ el.); RBCCW supply header to essential and nonessential loads to RBCCW return header to RBCCW heat exchangers (RB 593’ el.) to RBCCW pumps.

3. State the normal and backup sources of cooling water to the RBCCW heat exchangers. (Page 15)

Normal - Raw Cooling WaterBackup - Emergency equipment cooling water

5. Recognize typical heat loads cooled by the RBCCW System. (Fig. 2 and Page 8)

Essential Loop Non-Essential LoopDrywell control air compressors Reactor building equipment drainDrywell atmospheric coolers sump heat exchangerReactor recirculation pump Reactor water cleanup pump sealmotor coolers water coolersReactor recirculation pump Non-regenerative heat exchangersseal coolers Fuel pool cooling heat exchangerDrywell equipment drain Reactor recirculation pump samplesump heat exch. cooler


OPL171.050 Condenser Circulating Water System (CCW)

1. State the purpose of the Condenser Circ Water System. (Page 7)

To provide a means of rejecting heat from the main condenser to the ambient surroundings.

To provide a flow of water for auxiliary services and to dilute low level radioactive waste discharges.

2. List the two modes of operation of the Condenser Circulating Water System and describe the flow path through each, to include major components and their location. (Page 7)

Open mode - The intake (180º S of plant) to main condenser (TB 557’ to 586 el.) to reservoir.

Helper mode - Intake (180º S of plant) to main condenser (TB 557’ to 586 el.) to cooling towers (330º NNW of plant) to reservoir.


OPL171.048 Raw Cooling Water System (RCW)

1. State the purpose of the RCW System and the following RCW System components, to include their location. (Page 6) To remove heat from the turbine associated equipment and auxiliaries located in the turbine building, RBCCW heat exchangers and other reactor associated equipment.

a. RCW pumps (Page 9) Total of 12 pumps provide sufficient head for all loads (in conjunction w/booster pumps when needed). (TB 565’ el. north) and (RB 593’ el. north)

b. RCW booster pumps (Page 10)1 pump per unit + one spare pump = 4 total (located RB 593’ el. north)Supply additional pressure for servicing the recirculation MG set coolers on the 639' elevation

2. Describe the flow path through the RCW System.

Suction from CCW inlet conduit to pumps to loads to discharge to CCW outlet conduit

3. State the interrelationship between RCW and the following:(Page 16 & 17)

a. Condenser Circulating Water - RCW takes suction from and discharges to CCW conduits.

b. Raw Service Water - RCW shares a suction path with RSW.

c. RBCCW - The normal source of cooling water to the RBCCW heat exchangers is the RCW system.

d. EECW - RCW is the source of charging water to EECW north header if EECW is not running.


OPL171.049 Raw Service Water System

1. State the purpose of the Raw Service Water System. (Page 6)

a. To supply river water for yard watering, cooling of plant equipment not conveniently serviced by the raw cooling water system, wash-down services.

b. To provide a means to pressurize the HP Fire Protection System.c. To supply charging water to EECW South Hdr and RHRSW Hdr.

2. State the purpose of the Raw Service Water tanks. (Page 7)

2 tanks supply a static water head to the fire protection system during normal operation and supplies water for extinguishing fires until the fire pumps start.


OPL171.009 Main Steam System

1. Describe the Main Steam System flow path/configuration under normal operating conditions: (Fig. 1, and page 7)

RPV Head to MSLs to MSRVs, MSL flow restrictors, I/B MSIVs, O/B MSIVs, Equalizing header, Turbine Control Valves, BOP steam supplies, by-pass valves.

2. Identify the purpose and location of the following components of the Main Steam system:

a. Steam lines - direct steam from the boiler (reactor) to the turbines at rated temperature and pressure

b. Flow Restrictors - Limits flow to <200% of rated, limits inventory loss, limits ΔP across flow internals, provides mechanism for measuring steam flow. (located upstream from I/B MSIVs inside the drywell)

c. Safety/Relief Valves - Prevent over pressurization of the nuclear steam supply system. 13 SRVs exhaust below the water level of the suppression pool. Six of the 13 SRVs serve ADS for emergency depressurization.

d. Main Steam Isolation Valves (MSIV) 2 valves (inboard and outboard) per MSL, air to open air and/or spring to close. Prevent exceeding radiation release rates of 10 CFR 100 guidelines and inventory loss during a MSL break outside of primary containment. (I/B inside drywell, 563’ el. north; O/B just outside primary containment in the RB steam tunnel, 565’ el. north)

e. Turbine By-pass Valve - To provide a by-pass, for steam not needed by the main turbine, around the turbine directly to the condenser during start-up, rolling the turbine, turbine trips, and reactor cool-down. Located in Moisture Separator Room, turbine building, elevation 601, south of moisture separators.

f. Main Steam Stop Valve (MSSV) - To protect turbine from over speed. Located in Moisture Separator Room, turbine building, elevation 601

g. Turbine Control Valve - To regulate the flow of steam to the turbine and in doing so, controls the turbine generator load. They also, in conjunction with the by-pass valves, function to maintain a constant reactor pressure for a specific reactor power. Located next to MSSVs in the Moisture Separator Room

h. High Pressure Turbine - To turn the generator to generate electricity. Located in the Turbine Building, 617’ el. south.

i. Moisture Separator - To remove about 90% of the moisture by passing the steam through a series of baffle plates. Located in the Moisture Separator Room, Turbine Building, 586’ el.



j. Combined Intercept Valve - protect the turbine from over speed which could occur due to flashing of moisture to steam in the moisture separators. Located to the LP Turbines on

the 617’ el. of the Turbine Building.

k. Low Pressure Turbine - in conjunction with the HP Turbine turn the generator to generate electricity. Located in the Turbine Building, 617’ el. north of the HP Turbine.

l. Reactor head vent (Page 9) - Vents non-condensables to the "C" MSL during power operation or to DWEDS when reactor is below 20 psig pressure.

3. Recognize the relationship of the Main steam system with other systems/components to include:

a. HPCI - During accident conditions, main steam from the reactor vessel sent here via a 10” line off “B” main steam line.

b. RCIC - During accident conditions main steam from the reactor vessel sent here via a 3” line off “C” main steam line.

c. ADS - Uses select main steam safety/relief valves to prevent over pressurization of the reactor vessel and to allow for emergency depressurization to permit actuation of ECCS systems (e.g. - RHR and Core Spray)

d. Condensate - Receives exhausted steam from Low Pressure Turbines and condenses it back into water.

e. Feedwater - Returns condensed steam from the main steam system back to the reactor vessel.

f. SJAE - Removes air and non-condensable gas from the main steam system back to the reactor vessel.

4. Describe the position to which MSIVs fail on loss of air, including the purpose of the air accumulators. (Page 18)

MSIVs fail closed on loss of air.

Accumulators provide supply air for one closing operation to ensure closing time limits are met on a loss of pneumatic supply



5. List the balance of plant steam loads supplied from the Main Steam System - (Page 8)

Off-gas - Steam Jet Air Ejectors Pre-heaters

RFPTsGland Sealing Steam


OPL171.011 Condensate System

1. State the purpose of the Condensate System. (Page 7) To supply reactor feedwater pumps with heated demineralized water at a rate and pressure sufficient to provide adequate NPSH.

2. Describe the Condensate System flow path/configuration under the following conditions:

a. Normal operation at power (Page 7 & 9) - Hotwell, condensate pumps, OG Loads, filter demineralizers, condensate booster pumps, low pressure feedwater heaters.

b. Startup or shutdown at less than 350 psig reactor pressure - Same flow path as normal with fewer pumps and demineralizers in service. Short cycle recirculation in service for cleanup and minimum flow for condensate & booster pumps and SJAE condenser.

c. Short cycle recirculation to main condenser (Page 9) - Allows cleanup of condenser water inventory before operating. Hotwell, condensate pumps, OG loads, F/D's, CBPs, hotwell.

d. Makeup (Page 12) - 4" Automatic level control air op valve (normal) and 10" (emergency) makeup MOV. CST to hotwell

e. Reject (Page 12) - 4" Automatic level control air op valve (normal) and 10" (emergency) reject MOV. CP discharge to CST

3. Describe the purpose and operation of the following components:

a. Main condenser hotwell (Page 9) - Collects and, retains condensate 2 min. to allow decay of N16 and provides NPSH for condensate pumps. (TB 557’ el.)

b. Condensate pumps (Page 13) Motive force for condensate flow, NPSH for condensate booster pumps. (TB 557’ el.)

c. Condensate booster pumps (Page 15) - Provide NPSH for reactor feedwater pumps. (TB 557’ el.)

d. Low Pressure feedwater heaters (Page 18) - Improves plant efficiency uses extraction steam to heat feedwater and remove LP turbine moisture. (TB 586’ el.; 4’s, 5’s, and drain cooler inside Main Condenser; 3’s in separate rooms in heater alley)

e. Filter/demineralizers (Page 15) - Maintains purity of the reactor feedwater by removing dissolved and suspended solids 9 units, 9 normally in service, one can be out for resin backwash/replacement. (TB 575’ el. under shield plugs)


OPL171.026 Reactor Feedwater System

1. State the purpose of the reactor feedwater system. (Page 8)

Provides adequate feedwater to the reactor vessel for full power operation.

2. Describe the purpose and operation of the following components, to include their location.

a. Reactor feedwater pumps (Page 8): Provides driving force for returning feedwater to the reactor. 3 pumps, 1/3 capacity, steam driven, variable speed, centrifugal pumps. (TB 617’ el. in separate rooms)

b. Startup by-pass valve (Page 32): During low power operation <350 psig, by-passes RFPTs and uses condensate pumps to maintain reactor water level. Operates in single-element automatic level control. (TB 617’ el. north)

c. High pressure feedwater heaters (Page 33): #1 and #2 heaters, three strings each, cascading drains improve overall plant efficiency. (TB 586’ el. in heater alley in separate rooms)

3. Describe the flow path/configuration of the reactor feedwater systems during the following plant conditions.

a. Startup < 350 psig reactor pressure (Page 32): S/U BPV used to by-pass RFPs. CP/CBP discharge, around RFP, thru #2 HPFW Htrs, #1 HPFW Htrs, 2 FW lines, 6 RPV inlet nozzles.

b. 100% power normal operation (Fig. 1): 3 RFPTs, 6 HPFW Htrs, 2 feedwater lines, 6 inlets to reactor annulus area.

c. Long cycle recirculation/cleanup(Page 34): Used during plant startup to recirculate and flush as much of the condensate and feedwater piping as possible. Located at outlet of H.P. feedwater heater, recirculates to condenser.

4. Describe the interrelationships of the following systems/components with the Reactor Feedwater System. Note: all interfaces are in the RB Steam Tunnel

a. High Pressure Coolant Injection System (Page 38) - HPCI injection flow path is through FW line A

b. Reactor Core Isolation Cooling System (Page 38) - RCIC injection flow path is through FW line B

c. Reactor Water Cleanup System (Page 38) - RWCU return to reactor is through FW line B (U1 & U2) and FW lines A & B (U3)


OPL171.030 Off-Gas System

1. State the purposes of the Off-Gas system. (Page 7)

a. Maintain condenser vacuum by removing non-condensable gases from the condenser.

b. Minimize and control the release of radioactive isotopes by:

(1) Holdup for decay into non-radioactive nuclides or into particulates which can be filtered.

(2) Adsorption of iodine and holdup of noble gases

c. H2 control and volume reduction.

2. Describe the Off-Gas system flow path during normal operation.(Page 7, 8 & Fig. 1)

Pre-cooler, steam jet air ejectors, pre-heater, catalytic recombiner, off-gas condenser, water separator, dehumidification coil, 6-hour holdup volume, cooler condenser, moisture separator, re-heater, pre-filter charcoal adsorber, after filter, stack.

3. State the purpose of the following Off-Gas system components, to include their location:

a. Steam jet air ejectors (Page 9) - Dilutes hydrogen to <4% and provides driving force for the system. (TB 586’ el. heater alley north in separate rooms)

b. Off-Gas pre-heaters (Page 17) - Preheats the steam gas mixture exiting the SJAE. Ensures absence of water which poisons the catalyst in the catalytic recombiners. (TB 586’ el. heater alley north in the recombiner room)

c. Catalytic recombiners (Page 17) - Reduces H2 content to less than 1%.(TB 586’ el. heater alley north in the recombiner room)

d. Off-Gas condenser (Page 18) Cools superheated steam and condenses water vapor. (TB 586’ el. heater alley north in the recombiner room)

e. Six-hour holdup volume (Page 21) - Provides holdup time for the decay of shorter lived radioactive isotopes to either non-radioactive isotopes or radioactive particulates.

f. Charcoal adsorber (Page 24) - Delays noble gases by filtration and removes iodine by adsorption. (Off-gas Treatment Building, el. 561’)

g. Dilution chamber (page 26) - Provides for dilution of residual hydrogen prior to release. (Inside the Stack, el. 580’)


OPL171.220 Hydrogen Water Chemistry

1. Describe the purpose of the Hydrogen Water Chemistry System.

To mitigate the chemical conditions in a BWR that allows Intergranular Stress Corrosion Cracking (IGSCC).

2. Determine the location of the hydrogen and oxygen injection points.

Hydrogen - suctions of the three Condensate Booster pumps

Oxygen - Suction of Condensate Pumps. - SJAE suction line


OPL171.040 Reactor Core Isolation Cooling System (RCIC)

1. State the purpose of the RCIC system. (Page 9) To provide a source of high-pressure coolant makeup to the reactor vessel in case of a loss of feedwater flow. Used to maintain reactor vessel level and for pressure control during MSIV isolation conditions.

2. Describe the RCIC system flow path after automatic initiation.(Figure 1)

(Water flow path) CST (can draw from Torus) to RCIC pump to feedwater line "B" to reactor

(Steam flow path) MSL "C" to isolation valve to RCIC turbine; exhausts to suppression pool

3. Describe the RCIC pump and location.

Turbine driven centrifugal pump located in the RB 519 el. NW quad


OPL171.042 High Pressure Coolant Injection System (HPCI)

1. State the Design Basis of the HPCI System. (Page 7)

To provide adequate core cooling for all break sizes which do not result is rapid depressurization of the reactor vessel. To function without off-site power or diesel generators.

2. Describe the HPCI System flow path/configuration during accident conditions: (Page 7 & Fig. 1)

a. Automatic initiation (steam path) "B" MSL to HPCI turbine; exhausts to suppression pool (water path) CST (will draw from Torus on low CST level or high Torus level) to HPCI pump to reactor via FW line "A".

3. Describe the HPCI pump and location.

Turbine driven centrifugal pump located in the RB 519 el. SW (U1) SE (U2 and U3)


OPL171.043 Automatic Depressurization System (ADS)

1. State the purpose of the ADS System. (Page 7) In the event of a small to intermediate break in the primary system, ADS automatically reduces reactor vessel pressure so that flow from the core spray system or LPCI mode of RHR can enter the reactor vessel in time to cool the core and limit fuel cladding temperature to protect the fuel barrier. For intermediate breaks ADS assists in reducing pressure if high pressure systems cannot maintain water level, for small breaks acts as a backup to the HPCI system.

2. Describe the ADS system components and flow path to include their location. (Page 7)

6 of the 13 SRVs vent steam from the MS Lines to the suppression pool. The lines and valves are all contained inside primary containment. The valves are located on the 584’ el. (Steam Deck)


OPL171.051 Emergency Equipment Cooling Water System (EECW)

1. State the purpose of the EECW System. (Page 7)

To supply cooling water to safety related components in the core spray, residual heat removal and diesel generator systems.

Can also supply cooling water to the SD Bd Room chillers, H2-O2 analyzers, control room air conditioning equipment, RBCCW heat exchangers and control air compressors.

2. Describe the inter-relationship between EECW and the following:

a. Raw Cooling Water (Page 20) - Supplies charging water to EECW north header and supplies RHR pumps and room coolers with cooling water when EECW is in standby.

b. Raw Service Water (Page 20) - Supplies charging water to EECW south header

c. Diesel Generators (Page 20) - EECW cools the engine via heat exchangers.

d. Reactor Building Closed Cooling Water (Page 20) EECW is the alternate cooling water supply to the RBCCW heat exchanger.


OPL171.046 Residual Heat Removal Service Water System (RHRSW)

1. State the purpose of the RHR Service Water system.

Remove heat from RHR systems via heat exchangers; provide standby core and containment Cooling, and supply water to EECW system.

2. Describe the normal flow path of the RHRSW system to include location of major components.

From CCW pump pit to RHRSW pump suction pit to RHRSW system headers to RHR HXs to Tennessee River. Pumps are located in the intake structure in respective pump rooms. RHR HXs are located in the RB 565’ el. SW (A & C) and SE (B & D) in separate rooms.

3. Explain the relationship between the RHRSW system and the EECW system.

4 of 12 pumps normally assigned to serve the EECW system.


OPL171.044 Residual Heat Removal System (RHR/LPCI)

1. State the purposes of the RHR system. (Page 9)

Restore and maintain the coolant inventory in the reactor vessel so that the core is adequately cooled after a LOCA.

Provides containment cooling so that condensation of steam resulting from the blowdown of the design basis LOCA is assured.

Remove decay heat and residual heat so that refueling and nuclear system servicing can be performed.

Supplement the FPCC system capacity when necessary to provide additional pool cooling capacity.

2. State the six modes of operation of the RHR System and describe the flow path for each. (Page 10, 11, 12)

(a) Low Pressure Coolant Inj - ECCS ring header to pumps, heat exchangers, injection valves, recirculation loops (Loop I injects into Recirc loop B; Loop II injects into Recirc loop A), reactor

(b) Containment Cooling - ECCS ring header, pumps, heat exchangers, drywell spray header or suppression pool spray header or Torus cooling test line.

(c) Shutdown Cooling - Recirc loop A, pumps, heat exchangers, recirc loop A & B

(d) Standby Coolant Supply - RHRSW pumps, RHR cross-tie, LPCI injection valves, recirc loops, reactor

(e) Supplemental fuel pool cooling - Skimmer surge tank, RHR pumps or RYR drain pumps, heat exchanger, fuel pool discharge valve

(f) RHR Cross-tie (Containment cooling, LPCI and Shutdown Cooling): ?Unit 1 loop 2 to/from Unit 2 loop 1 and Unit 2 Loop 2 to/from Unit 3 Loop 1

3. State the number of RHR pumps, RHR drain pumps, and RHR heat exchangers, and the location of each. (Page 14)

Number of RHR pumps 4 , location: A & C are RB 519’ el. SW quadB & D are RB 519’ el. SE quad

Number of RHR HXs 4 , location - A & C are RB 565’ el. SW B & D are RB 565’ el. SE

Number of RHR drain pumps 2 , location - RB 519’ el. South


OPL171.045 Core Spray System (CSS)

1. State the purpose of the Core Spray System. (Page 7)

Protects against over-heating the fuel in the event of a LOCA. Accomplished by spraying water directly on the fuel from spray spargers located within the shroud.

2. Describe the Core Spray System flow path after automatic initiation.(Page 7 and Fig. 1)

ECCS ring header, pumps, injection valves, 360° sparger inside core shroud.

3. State the number of CSS pumps, capacity and flow rate. (Page 8)

Number of CS pumps 4 , location - A & C are RB 519’ el. NW quadB & D are RB 519’ el. NE quad


OPL171.016 Primary and Secondary Containment Systems

1. State the purpose of the following containment systems:

a. Primary containment (Page 8) - Contain fission products in the event of failure of the primary system - utilizes pressure suppression system to store heat of the primary system following a loss of coolant accident.

b. Secondary containment (Page 8 & 9) - Controls fission products released from primary containment by releasing through elevated release point to minimize ground release. Negative pressure ensures in-leakage from environment.

c. Containment Atmosphere Monitoring (CAM) System (Page 31) - Measures hydrogen and oxygen concentration and radioactivity levels in primary containment.

2. List five ways that fission products are contained or releases are controlled. (Page 8)

(1) In the Fuel(2) In the Cladding(3) Reactor Vessel Primary System(4) Primary Containment(5) Secondary Containment

3. State the purpose of the following components/subsystems:

a. Suppression Chamber-drywell vacuum breakers (Page 18) - Prevents exceeding design external pressure of the drywell. Allows pressure to equalize between drywell and Torus during a (LOCA) as steam condenses in the drywell. (12 vacuum breakers)

b. Torus-reactor building vacuum breakers (Page 19) - Prevents exceeding the design external pressure of the suppression chamber by allowing RB atmosphere to enter the suppression chamber as steam condenses. (2 vacuum breakers)

d. Suppression pool (Page 20 & 22) - Large volume of water used to condense the steam during a LOCA. Used as a source of water for LPCI, HPCI and Core Spray.

4. State the Primary Containment design pressure and temperature. (Page 11)

Design pressure 56 psig Design temperature 281 °F -2 psig


OPL171.016 Primary and Secondary Containment Systems (cont'd)

5. Describe the containment response to a design basis loss of coolant accident (LOCA). (Page 20 & 22)

Steam from the reactor vessel is released in the drywell pressurizing the drywell to 50.6 psig. As the drywell is pressurized, steam is blown down into the suppression pool where it is condensed. Non-condensables are also blown into the suppression pool and increase the Torus pressure. The drywell pressure drops as steam condenses and the Torus to drywell vacuum breakers open when the drywell pressure is 0.5 psid less than the Torus pressure. The Torus heats up 50°F. Containment cooling controls pressure and temperature from decay heat.

6. List two methods of hydrogen generation in primary containment upon a primary rupture. (Page 26 & 27)

Zircaloy water reactionRadiolytic decomposition of water


OPL171.032 Containment Nitrogen Systems

1. State the purpose of the following containment systems.

a. Containment Atmospheric Dilution (CAD) system (Page 21)

Controls the combustible gases in primary containment following a loss of coolant accident (LOCA). 2 CAD systems shared by 3 units; uses N2 to

maintain H2 <4% and 02 <5%. It may be used as a supply to the Drywell

Control Air System.

b. Nitrogen Inerting System (Page 8)

Provides nitrogen for initial inerting of primary containment and normal makeup requirements.

c. Drywell Air Coolers (Page 14)

10 coolers use RBCCW and fans to maintain the temperature inside the drywell between 135°F and 150°F for drywell pressure control and to protect components from heat damage.

d. Drywell D/P compressor

Maintains a differential pressure between the drywell and the Torus in order to reduce the consequences of hydraulic loading during the vent clearing phenomena of a LOCA.

2. State the purpose of the hardened Wet-well Vent System and the flow path.

Provide manual overpressure relief through a scrubbed and elevated release point.

Flow path is from the suppression pool air space, and a straight path out the stack. Discharge point is prior to dilution fans.


OPL171.018 Standby Gas Treatment System (SGT)

1. State two purposes of the Standby Gas Treatment System. (Page 7)

a. To maintain a small negative pressure in the reactor building under isolation conditions to prevent ground level release of airborne activity.

b. To treat the effluent from the containment buildings before discharging it through the plant stack to minimize the release of radioactive material from containment to the environment.

2. Describe the Standby Gas Treatment System flow path to include major components and their location. (Figure 1 and Page 7)

HPCI, DW and Torus exhaust and RB Ventilation to SGT trains to Stack

SGT train flow and components Moisture separator, relative humidity heater, pre-filter, HEPA filter, carbon bed adsorber, HEPA after-filter, fan, and stack. SGT trains located in the SGT building el. 565’.

3. State the conditions that will automatically initiate the Standby Gas Treatment System (set points not required). (Page 17 & 18)

a. High drywell pressureb. Low reactor water levelc. High radiation reactor zoned. High radiation refuel zone

(Starts all 3 trains of SGT)

Documents

NUCLEAR TRAININGgonuke.org/wp-content/toolkits/Radiation Protection/ch… · Web viewThis course will be taught using Radiological Protection Technician Training lesson plans and