HPT001.014C
Revision 2
Page 6 of 89
NUCLEAR TRAINING
TRAINING MATERIALS COVERSHEET
RADIOLOGICAL PROTECTION TECHNICIAN INITIAL TRAININGPROGRAM
SYSTEMS TRAINING / HPT001
COURSE
/ COURSE NO.
Boiling water reactor systems / HPT001.014C
LESSON 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 REVIEW
David L. Stewart / Original Signed
Signature / Date
LEAD INSTRUCTOR/PROGRAM MGR. REVIEW
Rob L. Coleman / Original Signed
Signature / Date
PLANT CONCURRENCE / ______
Signature / Date
TVAN CONCURRENCE (If applicable) / ______
Signature / Date
BFN 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-WBN
BFN Technical Training Manager, BFT 2A-BFN
TVA 40385 [NP 6-2003] Page 1 of 2
REVISION/USAGE LOG
REVISION
NUMBER / DESCRIPTION
OF CHANGES / DATE / PAGES
AFFECTED / 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.
HPT001.014C
Revision 2
Page 12 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
DP Delta-P, Differential Pressure
DT Delta-T, Differential Temperature
ADHR Auxiliary Decay Heat Removal
ADS Automatic Depressurization System
ALARA As Low As Reasonably Achievable
APRM Average Power Range Monitor
ARM Area Radiation Monitor
AUO Assistant Unit Operator
CCW Condenser Circulating Water
CIV Combined Intermediate Valve
CRD Control Rod Drive
CRW Clean Radwaste
CSS Core Spray System
CST Condensate Storage Tank
DBA Design Basis Accident
DCN Design Change Notice
D/P Differential Pressure
DRW Dirty Radwaste
DW Drywell
DWEDS Drywell Equipment Drain Sump
DWFDS Drywell Floor Drain Sump
ECCS Emergency Core Cooling System
EECW Emergency Equipment Cooling Water
EPRI Electrical Power Research Institute
EQ Environmental Qualification
FCV Flow Control Valve
FE Flow Element
FI Flow Indicator
FPCC Fuel Pool Cooling and Cleanup
FSAR Final Safety Analysis Report
FT Flow Transmitter
HCU Hydraulic Control Unit
HEPA High Efficiency Particulate Air (Filter)
HPCI High Pressure Coolant Injection
HWC Hydrogen Water Chemistry
Hx Heat Exchanger
INPO Institute of Nuclear Power Operations
IRM Intermediate Range Monitor
HO-1 List of Abbreviations and Acronyms, page 1 of 3
LIST OF ABBREVIATIONS AND ACRONYMS (continued)
LCV Level Control Valve
LER Licensee Event Report
LOCA Loss of Coolant Accident
LPCI Low Pressure Coolant Injection
LPRM Local Power Range Monitor
MOV Motor Operated Valve
MS Main Steam
MSIV Main Steam Isolation Valve
MSL Main Steam Line
MSV Main Stop Valve
MWt Megawatts thermal
NPSH Net Positive Suction Head
NRC Nuclear Regulatory Commission
OI Operating Instruction
PWR Pressurized Water Reactor
RBCCW Reactor Building Closed Cooling Water
RBEDS Reactor Building Equipment Drain Sump
RBFDS Reactor Building Floor Drain Sump
RCIC Reactor Core Isolation Cooling
RCP Reactor Coolant Pump
RCS Reactor Coolant System
RCW Raw Cooling Water
REP Radiological Emergency Plan
RFP Reactor Feedwater Pump
RFPT Reactor Feedwater Pump Turbine
RHR Residual Heat Removal System
RHRSW Residual Heat Removal Service Water
RPV Reactor Pressure Vessel
RSW Raw Service Water
RWCU Reactor Water Cleanup
Rx Reactor
SCFM Standard Cubic Feet per Minute
SDC Shutdown Cooling
SDV Scram Discharge Volume
SFSP Spent Fuel Storage Pool
SGT Standby Gas Treatment
SI Surveillance Instruction
SJAE Steam Jet Air Ejector
SLC Standby Liquid Control
SOER Significant Operating Experience Report
SPE Steam Packing Exhauster
HO-1 List of Abbreviations and Acronyms, page 2 of 3
LIST OF ABBREVIATIONS AND ACRONYMS (continued)
SRM Source Range Monitor
SRO Senior Reactor Operator
SRV Safety Relief Valve
STA Shift Technical Advisor
S/U Startup
TCV Turbine Control Valve
TMI Three Mile Island
TSV Turbine Stop Valve
HO-1 List of Abbreviations and Acronyms, page 3 of 3
HPT001.014C
Revision 2
Page 14 of 89
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 OPL171.050
RAW COOLING WATER OPL171.048
RAW SERVICE WATER/FIRE PROTECTION OPL171.049
MAIN 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
HPT001.014C
Revision 2
Page 52 of 89
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.
HPT001.014C
Revision 2
Page 52 of 89
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