ML20053C730
| ML20053C730 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/28/1982 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.2.1, TASK-2.B.4, TASK-TM NUDOCS 8206020511 | |
| Download: ML20053C730 (16) | |
Text
.
BALTIMORE GAS AND ELECTRIC CHARLES CENTER P.O. BOX 1475 BALTIMORE, MARYLAND 21203 ARTHUR E. LUNDVALL. JR.
vice pacs ocar May 28,1982 U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC 20555 ATTENTION:
Mr. Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2, Docket Nos. 50-317 & 50-318 NUREG-0737, items I.A.2.1 & II.B.4
REFERENCE:
(a)
NRC Letter to A. E. Lundvall, Jr., from R. A. Clark dated 4/26/82, Request ior Additional Information Gentlemen:
The additional information requested by reference (a) is enclosed. Should you have any questions regarding this matter, please contact us. Specific questions concerning the infor mation provided should be directed to Mr. S. E. Jones, Jr., at (301) 269-4798.
Very truly yours,,
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f Vice President Supply AEL/SE3/gla Enclosures cc:
- 3. A. Biddison, Esquire G. F. Trowbridge, Esquire D. H. Jaff e, NRC R. E. Architzel, NRC Dr. R. T. Liner, Science Applications, Inc.
Btbs 8206020511 820528 PDR ADOCK 05000317 fl P
ENCLOSURE (1)
Responses are numbered to coincide with questions asked in Enclosure (1) to Mr. R. A.
Clark's letter dated April 26,1982.
1.
Yes, our June 18,1980, response does apply to both Unit I and 2.
2.
Yes, our courses do involve 80-contact hours. In fact, the course for our license operator cardidates presently includes 288 contact hours, as detailed below, in June 1980 the courses involved 248-contact hours. However, in July 1981 the Heat Transfer and Thermodynamics section was expanded from 40 to 80-contact hours.
The previously licensed operators at Calvert Cliffs have also been given considerable training in this area. Their training presently totals 142 contact hours i
as detailed below:
1.icensed Operator Candidate Training Contact Hours Heat Transfer / Thermodynamics 80 Plant Chemistry 48 Radiation Protection 40 Transient Analysic 40 Procedures 24 Instrumentation 32 Degraded Core 24 TOTAL 288 Licensed Opertor Requalification Training Contact Hours 1981 Heat Transfer / Thermodynamics 20 Transient Analysis (Classroom) 12 Transient Analysis / Procedures (Simulator) 20 Mitigation of Core Damage 40 TOTAL 92 1982 Heat Transfer / Thermodynamics 14 Transient Analysis / Procedures (Simulator) 20 Pressurized Thermal Shock 8
Procedures for Accident Conditions 8
(Classroom)
TOTAL 50 3.
The lectures and associated quizzes on accident mitigation listed above and described later were administered to all NRC licensed individuals at the plant. This
I i
includes both alternates for the Plant Superintendent (Plant Manager), but not the Plant Superintendent himself. The Plant Superintendent particiapted in an 8-hour course on Core Damage Mitigation conducted by Combustion Engineering on November 11,1981. Additionally, the Plant Superintendent, who previously held an SRO license received training similar to that listed above as a part of his license training program and as an officer in the Navy's Nuclear Training Program.
The organization structure showing training status is as follows:
Plant Superintendent - 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> General Supervisor - 3perations (1)
Shif t Supervisor (1)
Senior Control Room Operator (1)(2)
Shif t Supervisors Assistant (1)(2)
Unit 1 Unit 2 Control Room Operators (1)
Control Room Operators (1)
NOTES (1)
Trained as per program listed in response to question 2.
(2)
Serves as STA-Transient Analysis.
4.
Yes, accelerated requalification is required for < 80% overall or < 70% in any category on the licensed operator requahfication examination.
5.
Yes, the control manipulations required as a part of licensed operator requalificaiton has been modified to conform with enclosure 4 of Mr. H. Denton's letter of March 28,1980.
i 6.
In July 1981 the Heat Transfer / Thermodynamics course was revised and expanded from 40 to 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. The emphasis is placed not only on basic theoretical concepts but also on their application to a nuclear power plant. Enclosure (2)is an outline of the course as it exists today.
7.
Mitigation of Core Damage Training at Calvert Cliffs no longer follows the exact outline listed in Mr. Denton's March 28, 1980, letter.
The course has bden rearranged for more effective presentation. Enclosure (3) is an outline of all mitigating core damage related training which was also asked for in Mr. Clark's letter of April 26,1982.
l l
ENCLOSURE (2)
TRAINING IN HEAT TRANSFER, FLUID FLOW, & THERMODYNAMICS 80 HOURS I.
STEAM POWER CYCLE A.
Basic Cycle 1.
Purpose & Principle Componer.ts of Steam Cycle 2.
System & Component Boundaries B.
Pressure, Temperature, & Volume 1.
Define Temperature & Pressure 2.
Temperature & Pressure Scales 3.
Specific Volume & Weight 4.
Gas Laws C.
Heat & Its Effects 1.
Heat, Specific Heat, BTU, Latent Heat of Vaporization, Latent Heat of Fusion, Sensible Heat, Change of Phase 2.
Effects of Pressure on Latent Heat & Boiling 3.
Problem Solving for Specific Heat & Latent Heat D.
Enthalpy & Entropy 1.
Work, Energy, Enthalpy, & Entropy 2.
Problem Solving involving Work & Enthalpy E.
Cycle Diagrams 1.
Plotting T-S Diagrams 2.
Explanation of Diagrams F.
Steam Tables 1.
Mollier Diagram 2.
Quality 3.
Sat. Pressure, Temperature, & Subcooling 4.
Superheat II.
THERMODYNAMICS A.
First Law 1.
Potential & Kinetic Energy 2.
Velocity 3.
B.
Heat at Work 1.
Internal Energy j
2.
Flow Work 3.
Mechanical Work j
4.
Heat 5.
Bet noulli's Equation C.
Energy Conversions 1.
Conversion Units 2.
Flow Processes 3.
Nozzles & Orifices D.
Second Law 1.
Second Law 2.
Efficiency III.
BASIC HEAT TRANSFER A.
Basic Heat Transfer Principles 1.
Conduction 2.
Convention 3.
Radiation B.
Physical Parameters of Basic Heat Transfer l
l.
Conduction Heat Transfer 2.
Effects of Flow on Heat Transfer C.
Boiling Heat Transfer r
l 1.
Critical Heat Flux, DNB 2.
Nucleate & Film Boiling 3.
Heat Transfer Curve D.
Physical Parameters of Boiling Heat Transfer 1.
Pressure 2.
Flow 3.
Temperature 4.
Boiling Heat Transfer E.
Steam Boiler Characteristics i
1.
Natural Circulation
(
2.
Moisture Separators 3.
Quality & Carryover l
4.
Shrink & Swell
IV.
TURBINE GENERATOR A.
Turbine Cycle 1.
Moisture Separator Reheaters 2.
Turbine Arrangement 3.
Turbine Efficiency B.
Energy Conversion 1.
Critical Pressure Ratio 2.
Flow Measurement 3.
Energy Conversion C.
Superheat & Reheat Cycles 1.
T-S Diagram 2.
Advantages & Disadvantages V.
CONDENSERS A.
Condenser Theory 1.
Condenser Operation 2.
T-S Diagram B.
Condenser & Cycle Efficiency C.
Turbine Extraction & Feedwater Heating 1.
Feedwater Heating & Heat Exchanger Operation 2.
Extraction Steam VI.
HYDR AULIC SYSTEMS A.
Hydraulic Systems 1.
Pump Head 2.
Laminar & Turbulant Flow 3.
T-S Diagram 4.
Pump Operation 5.
Head Loss & Flow 6.
Pressure vs. Flow Diagrams 7.
Density 8.
Viscosity 9.
Friction Losses B.
Positive Displacement Pumps 1.
Operation 2.
Pump Laws 3.
Pump Curves
C.
Eductors & 3et Pumps 1.
Pump Operation 2.
Nozzle & Fluid Movement D.
Centrifugal Pumps 1.
Pump Operation 2.
Series & Parallel Pump Operation 3.
Pump Curves E.
Net Positive Suction Head 1.
Define NPSH 2.
Cavitation Vll.
STEAM PLANT CALCULATIONS A.
Efficiency B.
Heat Balance 1.
Calorimetric 2.
Reactor & Electrical Power VIII.
REACTOR THERMAL & HYDRAULIC PERFORMANCE A.
Fuel & Clad Performance 1.
Clad Failure 2.
Fuel Failure 3.
Heat Transfer Across the Fuel Rod 4.
Atomic Action B.
Thermal Limits & Fuel Channel Flow 1.
Thermal Limits 2.
Coolant Flow & Instabilities 3.
Heat Transfer in Fuel Channel 4.
Factors Effecting Heat Transfer 5.
DNBR 5.
Steam & Non-condensible Gases 7.
Critical Power 8.
Hot Channel Factors, Axial & Radial Power Limits C.
Temperature & Pressure Limits 1.
Temperature Limits, Heat-up & Cooldown 2.
Brittle Fracture, NDTT 3.
Operators Curve
ENCLOSURE (3)
MITIGATING CORE DAMAGE 1.
NSFER, FLUID FLOW & THERMODYNAMICS - 80 Hours Enclosure (2) to this letter)
II.
. i., ANT CHEMISTRY - 40 Hours A.
Basic Concepts 0
1.
Chemical Reactions 2.
Solutions 3.
pH 4.
Conductivity B.
Corrosion of Plant Materials 1.
Effects of Corrosion 2.
Methods of Corrosion 3.
Carbon Steel 4.
Stainless Steel 5.
Nickle & Copper Based Alloys 6.
Zircalloy C.
Effects of Nuclear Operation 1.
Activation of Corrosion Products 2.
Crud 3.
Activation of Water and Water impurities 4.
Fission Products 5.
Tritium 6.
Radiolytic Decomposition D.
Chemistry Control Equipment 1.
Filters 2.
lon Exchangers 3.
Evaporators E.
Primary Chemistry 1.
Water Specifications F.
Secondary Water Chemistry 1.
Water Specifications 2.
Make-up Water
111.
RADIATION PROTECTION - 40 Hours A.
Theory of Radiation Exposure 1.
Type of Radiation 2.
Interaction with Matter 3.
Contamination B.
Exposure Limits 1.
Federal 2.
Administrative C.
ALARA Concepts 1.
Time, Distance, & Shielding 2.
Job Planning 3.
CCNPP Program D.
Radiation Work Practices 1.
Work Permits 2.
Contamination Control E.
Radiation Detection Equipment IV.
TRANSIENT ANALYSIS - 40 Hours A.
CEN-128," Transient and Accident Analysis" B.
FSAR Accident Analysis C.
Normal Plant Transients V.
PROCEDURES - 24 Hours A.
Operating Procedures B.
Abnormal Operating Procedures C.
Emergency Operating Procedures D.
Emergency Response Plan Implementing Procedures VI.
INSTRUMENTATION - 32 Hours A.
Reactor Coolant System Instrumentation 1.
Function & Control 2.
Power Supply 3.
Modes of Failure
B.
Reactor Protective System 1.
Function & Control 2.
Power Supply 3.
Modes of Failure C.
Nuclear Instrumentation 1.
Function & Control 2.
Power Supply 3.
Modes of Failure D.
Engineered Safety Features Actuation System Instrumentation 1.
Function & Control 2.
Power Supply 3.
Modes of Failure E.
Radiation Monitoring System 1.
Function & Control 2.
Power Supply 3.
Modes of Failure 4
F.
Reactor Regulating System 1.
Function & Control 2.
Power Supply 3.
Modes of Failure G.
Feedwater Control 1.
Function & Control 2.
Power Supply 3.
Modes of Failure Vll.
DEGRADED CORE TRAINING - 24 Hours A.
Incore Instrumentation 1.
Purpose of Incore & Thermocouples 2.
Location 3.
Principles of Operation - Normal Plant 4.
Principles of Operation - Accident Conditions a.
Self-Powered Neutron Detectors 1.
TMI Response 2.
Heating Effects 3.
Determination of Geometry Changes 4.
Determination of Core Damage
_r
t b.
Thermocouples 1.
Range 2.
How to Extend Range 3.
Effects of Overranging 4.
Direct Reading Techniques 5.
Plant Computer a.
Neutron Detectors 1.
INCA Programs 2.
Print Values 3.
Alarms 4.
Demand Log b.
Thermocouples 1.
Trend Blocks 2.
INCA Programs 3.
Print Value 4.
Expansion of Range 6.
Computer Failure a.
Reading Neutron Detector Voltages b.
Reading Thermocouple Voltages B.
Excore Nuclear Instrumentation (NIS) 1.
Purpose 2.
Location 3.
Principles of Operation a.
Proportional Counters b.
Fission Chambers 4.
Response
a.
TM1 1.
Void Effects on Readings 2.
Geometry Changes 3.
Reactor Water 1.evel Determination 4.
Extent of Core Damage 5.
Sources of Neutrons b.
CCNPP 1.
Location Differences from TMI 2.
Comparison to TMIInstruments 3.
Water Level Determination
5.
Comparison of INCORE, EXCORE, & Thermocouples a.
Response of Fission Chambers b.
Response of Proportional Coiinters c.
Response of Incores d.
Response of Thermocouples e.
Determinaton of Core Uncovery C.
Vital Instrumentation - 4 Hours 1.
Normal Operation a.
Pressure Instrument b.
Level Instruments c.
Flow Instruments 1.
A p
2.
Acoustic d.
Temperature 1.
RTD's 2.
Thermocouples 2.
Effects of Accident Environment on Transmitters a.
Temperature 1.
Transmitter Failures b.
Pressure 1.
Transmitter T ailures c.
Humidity l
1.
Transmitter Failures d.
Radiation 1.
Indications on High Range Monitors 3.
Accident Process a.
RCS - Actual vs. Indicated Parameters 1.
Temperature 2.
Pressure 3.
Pressurizer Level a.
Conversion tables in EOP's b.
Containment - Expected Response l
s i
1.
Pressure 2.
Temperature 4.
- Failure Mechanism a.
Level 1.
Dry Leg 2.
Wet Leg b.
Pressure c.
Temperature 1.
RTD l
2.
Thermocouples d.
Flow 5.
Alternate Methods of Determining Parameters a.
Pressure Level 1.
Reasons Why This is not Available b.
Letdown Flow 1.
Heat Balance c.
RCS 1.
Temperature - Loops RTD's i
a.
Thermocouples 2.
Flow t
- a. A T across Core i
3.
Pressure a.
Saturation Conditions for Large Break b.
Superheat Conditions for Small Break with Core Uncovery l
l D.
Primary Chemistry I
1.
Basic Chemistry (Review) a.
Polarity b.
Ionization i
c.
Electrolytes l
d.
pH
_. ~
~,..
.m.,__,_.,_.
e.
Conductivity f.
Oxidation 2.
Corrosion (Review) a.
Oxidation b.
Precore Hot Functional Testing c.
General Corrosion d.
Effects of:
1.
pH 2.
Oxygen e.
Control of General Corrosion f.
Localized Corrosion g.
Stress Corrosion h.
Corrosion Products 3.
Chemistry Control (Review) a.
Volital Control b.
Impurity Removal c.
Lithium d.
Boron e.
Ammonia f.
Hydrogen Overpresssure g.
Tritium Production 4.
Materials a.
ZirclV b.
Inconel c.
304 S.S.
5.
Concerns & Objectives a.
Prevention of Equipment Damage b.
Exposure Control c.
Waste Control 6.
Core a.
Fission Reactions i
b.
Fission Product Rgase c.
Dose Equivalent I d.
Technical Specification Limits e.
Clad Contamination f.
Fuel Defects
7.
Degraded Core Considerations a.
Fuel Swelling b.
Fuel Bursting c.
Clad Oxidation d.
Candling e.
Core Slump f.
Core Melt g.
Hydrogen Gas Generation h.
Radiolysis 1.
TMI j.
Hydrogen Combustion k.
Rod Burst - TMI 1.
Fission Gas Release m.
lodine Release n.
Fission Product Release o.
Sources of Oxygen in Containment E.
Radiation Monitoring 1.
Fission Fragment Release Characteristics a.
Fission Fragment Release Mechanisms 1.
Recoi!
2.
Knockout 3.
Thermally Activated Migration a.
Bubble Formation & Channels b.
Clad Failure 1.
Means of Detection - Normally Sample 2.
Causes of Failures - Zr Hydriding a.
Core Uncovery 3.
Thermal Cycling - Breathing 2.
Inventory of Fission Fragments a.
Gap Activity 1.
Clad Failure b.
RCS Activity i
1.
Equilibrium Activity 2.
Activated Corrosion c.
Fuel lnventory j
1.
Pellet Release
,,v
N 3.
RMS System a.
Pre-TMI Equipment 1.
Range of Detectors 2.
Effects of Accident b.
Post-TMI Equipment 1.
High Range RMS 2.
Use of Detector in Determining Core Damage c.
Hand Held Meters 1
1.
Expected Readings 2.
Determining Core Damage 3.
Determining Dose Rates Inside Containment
-l d.
ERPIP 1.
Determination of Core Damage j
d 4
l
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