ML20065B539
| ML20065B539 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/21/1983 |
| From: | Baynard P FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.2.1, TASK-2.B.4, TASK-TM 3F-0283-19, 3F-283-19, NUDOCS 8302230208 | |
| Download: ML20065B539 (12) | |
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Power C O m P o a A T e 0 es Feoruary 21,1983 3F-0283-19 Director of Nuclear Reactor Reguhtion Attention: Mr. flohn F. Stolz, Chief Operating Rea'.cors Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 NUREG-0737, Items I.A.2.1.4 and II.R.4
Dear Sir:
In response to your December 27, 1982 letter, Florida Power Corporation (FPC) hereby responds to your request for additional information on " Upgrading of RO and SRO Training" (NUREG-0737 Item I.A.2.1.4) and " Training for Mitigating Core Damage" (NUREG-0737 Item II.B.4).
Question 1 Describe in detail how the material contained in Enclosure 2 of Denton's March 28, 1980 letter, is incorporated into the licensee's training and retraining programs.
l Response to Question 1 l
' of Mr. Denton's March 28, 1980 letter pertaining to training in heat transfer, fluid flow, and thermodynamics is incorporated into a forty-two (42) hour program. The Crystal River Unit 3 course is outlined in the table of contents of the program text. This table of contents, for the text titled " Heat Transfer, Thermodynamics and Fluid Flow for the Nuclear Power Plant Operator,"is enclosed as Attachment 1.
Question 2 a5
-g 39' Describe in detail how the material contained in Enclosure 3 of Denton's March 28, 1980
@8 letter is incorporated into the licensee's training and retraining programs.
.mm Response to Question 2 m
., concerning training criteria for mitigating core damage, is covered in FPC's n4 sixteen (16) hour program, " Operator Training - Degraded Core Recognition and N
Mitigation." The topics covered in this course are listed in Attachment 2.
5 EL General Office 3201 Thirty-soortn street south. P O. Box 14042. St. Petersburg Fiorda 33733 813-866-5151
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' Question 3' r
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4 The response.to Question 5 in your May 5,* 1982 correspondence, refers to an instructor j'
requalification program. If not the same as'the licensed operator requalification program,
- please describe this program in detail.-
jL Response to Ques' tion 3
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r, The instructor requalification program is the same as.the licensed operator requalification
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- Question 4
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The total training time (approximation) that INPO has recommended to be provided on p
heat transfer, fluid flow and thermodynamics and on training to recognize and mitigate the consequences of core damage is'222 hours0.00257 days <br />0.0617 hours <br />3.670635e-4 weeks <br />8.4471e-5 months <br /> (STG-01 and STG-02). The NRC (OLB) has taken the position that approximately 80 contact hours of. instruction are required to adequately cover this subject. matter to the depth of understanding desired.- FPC's training program provides only 56 total hours'for this subject matter. Please describe in detail how your program' covers-this information to the depth required within the time
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frame specified in your program.
Response to Question 4 l
This question was verbally answered in a telephone conference with Mr. Pierce Skinner of the NRC on January 31,1983.
Question 5
-Your response to Question 3 in your May 5,1982 correspondence states that training was -
provided to eleven different groups 'of personnel. The facility organ 17ation chart provided i
with Technical Specification Change Request Number 67, Rev.1, dated January 19,1982, I
identified various other personnel that would or could be involved in an accident. Please provide a detailed description of the training involved in an accident. Please provide a detailed description of the. training involving - mitigating core damage that is to be provided.to' personnel such as plant Health Physicist, Chemical and Waste Manager, Chemical and Waste Supervisor, Chemistry Technicians, and the Operations Engineer.
Response to Question 5 j
The training received by personnel such as the plant Hea'th Physicist, Chemical and Waste j
Manager, Chemical and Waste Supervisor, Chemistry Technicians, and Operations Engineers on mitigating core damage is the same instruction received by operators in training. The outline of the course, as stated in the Response to Question 2 above, is j
given in Attachment 2.
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Mr. John F. Stolz 3F-0283-19 Page 3
' Question 6 Please provide details of how increased ear.phasis on reactor transients has been implemented in the training program.
Response to Question 6 FPC has implemented _ a Transient Assessment Program (TAP) to emphasize. reactor transients. As part of the TAP, various transients.that have taken place at the Crystal River. Unit 3 or similar nuclear facilities are studied. - They are also modelled at the Babcock & 'Wilcox reactor simulator -in Lynchburg, Virginia to allow operators and operators-in-training an opportunity to respond to these transients.~.
. Sincerely, A&
fvAA*l Dr. Patsy Y. Ba nard Assistant to Vice President Nuclerr Operations Attachments i
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i HEATTRANSFER.
THERM 0 DYNAMICS AND FLUIDFL0.W F0R THE r
i NUCLEAR POWER PLANT OPERATOR-42 Hour Program l
By C. J. BOSTED I
Illustrated by Dolores F. Stark
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TABLE OF CONTENTS C
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Page CHAPTER 1 DIMENSIONS AND UNITS 1
l.0 Introduction 1
1.1 Definition of Dimensions and Units 1
1.2 Conversion of Units 2
1.3 Fundamental Dimensions and Units for Heat Transfer and Fluid Flow 3
1.4 Weight and Mass 6
il 1.5 Unit Analysis 6
Problems 8
j CHAPTER 2 PROPERTIES 10 2.0 Introduction 10 2.1 Density and Specific Yo!ume 10 2.2 Pressure 11 2.3 Temperature 14 2.4 Charles' and Boyles' Law 14 2.5 Absolute Temperature Scale 16 2.6 General Gas Law 17 Problems f;
19 CHAPTER 3 DEFINITIONS 21 3.0 Introduction 21 3.1 Thermodynamic System 21 3.2 Properties 22 3.3 State 23 3.4 Processs 24 3.5 Cycle 24 3.6 Phase 24 2
3.7 Working Fluids 25 3.8 Summary of State 25 Problems 26 l
CHAPTER 4 ENERGY 27 4.0 Introduction 27 4.1 Definition of Energy 27 4.2 Forms of Energy 27 4.3 Heat 28 4.4 Heat Measurement 29 4.5 Types of Heat Transfer 30 4.6 Work 31 4.7 Work and Heat 32 4.8 Power 33
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4.9 Internal Stored Energy 33 4.10 Specific 33 4.11 External Stored Energy 34 4.12 Flow Energy 35 Problems 38 ann,, ;.r 1.-
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TABLE OF CONTENTS
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(Page 2)
Page CHAPTER S FIRST LAW 0F THERMODYNAMICS 40 5.0 Introduction 40 5.1 First Law of Thermodynamics 40 5.2 General Energy Equation 40 5.3 Non-Flow System 42 5.4 Steady Flow Systems 44 5.5 Enthalpy 45 5.6 Use of General Enery Equations 45 5.7 Examples of Systems 46 5.8 Continuity Equation 49 5.9 Mass Flow and Volume Flow 51 5.10 Bernoulli's Equation 51 Problems 53 CHAPTER 6 THE RELATIONSilIP AND DETERMINATION OF PROPERTIES 57 6.0 Introduction 57 6.1 Forms of Matter 57 6.2 Conversion of Form 57 6.3 Critical Point 59 6.4 Liquid-Vapor Phase Change: Definitions 60 6.5 Determiation of Relationship of Properties 61 6.6 Saturated Vapor Tables 63 6.7 Compressed Liquid Tables 64 6.8 Techniques For Use of Tables 65 Problems 66 CHAPTER 7 HEAT ENGINES AND THE SECOND LAW 0F THERMODYNAMICS 68 7.0 Introduction 68 7.1 Heat Engines 68 7.2 Directional Laws and Reversibility 71 7.3 Second Law of Thermodynamics 74 7.4 Entropy 74 7.5 The Carnot Engine 80 Problems 83 CHAPTER 8 PROCESSES:
M0LLIER DIAGRAM 84 8.0 -
Introduction 84 8.1 Reversible and Non-Reversible Processes 84 8.2 Real Process 84 8.3 Mollier Diagaram 85 8.4 Isobaric Process 88 8.5 Isovolumic Process 89 8.6 Isothermal Process 89 8.7 Isentropic or Reversible Adiabatic Process 90 8.8 Isenthalpic Process 92 Problems 93 L
TABLE OF CONTElfTS
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CHAPTER 9 STEAM POWER CYCLES 94 9.0 Introduction.
94 9.1 The Ideal Rankine Cycle 94 9.2 The Real Rankine Cycle 99 9.3 Real Steam Generators 99 9.4 Real Turbines 100 9.5 Real Pumps 102 r
9.6 Real Rankine Cycle, Solved Problem 103 9.7 Improving Cycle Efficiency -
105 Problems
-106 CHAPTER 10 THERMODYNAMIC STUDY OF A POWER STEAM PLANT 107 10.1 Design Study 107 10.2 Additional Refinements for Power Plants 111 Problems 122 1
CHAPTER 11 CONDUCTION HEAT TRANSFER 123 11.1 Heat Transfer by Conduction 123
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11.2 Conduction Through a Plain Wall -
125 11.3 Conduction Through a Composite Wall 126 11.4 Resistance Concept 129 11.5 Heat Transfer in a Cylinder 129 11.6 Conduction in Multi Layered Cylinders 131 11.7 Heat Transmission in Plate Fuel Elements 132 11.8 Heat Transmission-in Clad-Plate Fuel Element 134 11.9 Heat Transmission in Clad Cylinder Fuel Pin 135 Problems 139 CHAPTER 12 FLUID FLOW 141 l
12.1 Viscous Flow 141 l
12.2 Viscosity 142 12.3 Shearing Stress and Velocity Profiles 12.4 The Reynold's Number 145 12.5
.aminer and Turbulent Flow 147 12.6 The Boundry layer Concept 1 51 l
Problems 153 l
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TABLE OF CONTENTS (Page4)
Pace CHAPTER.13 APPLICATINS OF HEAT TRTANSFER AND FLUID FLOW
~155-13.1 Heat Conduction Involving fluids 155 13.2 Heat Conduction in-the Case of Natural Circulation 155 13.3 Film Coefficient 155 13.4 Combined Conduction Through Solids and Fluid (Slabs) 156 13.5 Combined conduction Through Solids and Liquids (Cylinders) 159 13.6 Heat Transfer in Forced Convection 163 13.7 Application to Heat Exchangers 165 13.8 Boiling Water Heat Transfer 169 Problems 175 CHAPTER 14 BASIS FOR THERMAL LIMITATIONS 177 14.1 Operating Limits 177 14.2 Thermal Envelope 177 c.s 14.3 DNBR 180 Appendix 1 List of Symbols
'182 Appendix 2 Conversion Factors 'and Constants 185 Appendix 3 Pump Theory 186 l
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1-1 Lesson 2 - GAS / STEAM BINDING 2-1 Lesson 3 - BORCN PRECIPITATION CONCERNS FOLLOWING A LOCA 3-1 09 Lesson 4 - EQUIPMENT FAILURE SEQUENCES THAT COULD LEAD TO A DEGRADED CORE 4-1 Lesson 5 - AVOIDING DEGRADED CORE CONDITIONS 5-1
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OPERATOR TRAINING-DEGRADED CORE RECOGNITION AND MITIGATION
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h CONTENTS Page Lesson 6 - CONSEQUENCES OF INADEQUATE CORE COOLING AND LIKELY CORE DAMAGE EFFECTS.
6-1 Lesson 7 - USE OF SPNDs IN RECOGNITION OF DEGRADED CORE CONDITIONS 7-1 Lesson 8 - DETECTION AND TREATMENT'0F INADEQUATE CORE COOLING USING CORE EXIT THERMOCOUPLES...............
8-1 Lesson 9 - RELATIONSHIP OF OCD SOURCE RANGE DETECTORS TO DEGRADED CORE CONDITIONS 9-1 Lesson 10 - INCORE THERM 0 COUPLES AND CORE FLOW BLOCKAGE..
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Nd Lesson 11 - RELEASE OF FISSION PRODUCTS FROM DAMAGED FUEL..
11-1 Lesson 12 - FISSION PRODUCT TRANSPORT CHARACTERISTICS AND RELEASE PATHWAYS 12-1~
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Lesson 13 - RESPONSE OF GAMMA RADIATION MONITORS 13-1 Lesson 14 - CHEMICAL AND RADI0 CHEMICAL PROBLEMS.
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