ML19331B521

Control Operator Training Program, Revision 1

ML19331B521
Person / Time
Site:	Point Beach
Issue date:	07/30/1980
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML19331B519	List: ML19331B518 ML19331B520 ML19331B521
References
TASK-1.A.2.1, TASK-2.B.4, TASK-TM TAC-44188, TAC-44189, TAC-44538, TAC-44539, NUDOCS 8008120385
Download: ML19331B521 (71)

Text

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WISCONSIN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PIANT CDNTROL OPERA'IOR TRAINING PROGRAM i

' Revision 1 i

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s CONTROL OPEPATOR TPAINING PROGRAM .

1.0 PURPCSE -

To outline the formal and guided training program for the Control Operator Trainee. The following guidelines are not intended to be a rigid detailed list of all tr'11ning which need to be ec=pleted by the Control Operator Trainee and does not restrict the assigned superviser from making additions, deletions, and/or changes as dee=cd necessary to accomplish the goal of training competent control operators.

2.0 CBJECTIVES

( 2.1 To i=part to these personnel attending the course the technical infor=ation and experience required to operate the Point Beach Nuclear Plant units in a safe and efficient ma.nner.

2.2 To develop in the trainee an insight and understanding about the plant so that their knowledge is not based on rote memory.

- 2.3 'Ib insure that the trainee has sufficient knowledge to pass the NRC Licensing Examination. This objective will be met when the first two objectives are completed.

3.0 , PROGRAM L 3.1 The formalized training program will be Mminstered during the week of relief shift by a co=bination of classroom instruction and control board training watches with a NRC Licensed Cperator..

During the time on shift other than relief shift, the Control

- Operator Trainee will perform his normal Auxiliary operator duties.

At the discretion of t.he Shif t Supervisor, and as time permits, .-

the Control operator Tra,inee =ay have additional time on the main control boards or for self study during his shift cycle.

- The principle effort and burden of learning to become a Licensed

operator lies with the control operator Trainee and he is expected to study the material in the time span required to insure timely qualification.

L 3.2 On-the-job training will be conducted in acecrdance with Appendix "A".

3.3 Specific subjects and outlines for classroom training are listed

- in Appendices "B" "M" Sections may be deleted depending on the

. Control Operator Trainee previous training and experience.

4.0 EXAMINATICNS

4.1 Quizes will be given throughout the training program.

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e Control Operator Training Program - 2 4.2 Written examinations will be administered at the completion of each aajor section.

4.3 A final written and oral examination will be administered by the Training Supervisor, plus an additional oral examination -

by an independent licensed supervisor will determin*c final qualification before taking the NRC examinations.

5.0 RECORbS 5.1 The following records will be maintained by the Training Supervisor 5.1.1 subject covered in classroom training.

( 5.1.2 Hours spent in classroom training 5.1.2 Completed on-the-job training (Appendix "A") .

5.2 The following records will be maintained by the trainee.

5.2.1 Control operator Trainee on-the-job training goals.

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APPENDIX "A" CONTROL OPERATOR - TRAINING ON-Ti!E-JOB TRAINING PROGRA!!

1.0 PURPOSE To outline the formal and guided on-the-job training program for the Control Operator Trainee. The following guidelines are not intended to be a rigid detailed list of all operations which need to be completed by the COT, and does not restrict the assigned Supervisor from making additions, deletions and/or changes as deemed necessary to

. accomplish the goal of training competent Control operators.

2.0 DISCUSSICN The on-the-job training section of the overall COT program is very important in developing the required skills and self-confidence to oper-ate the plant in a safe and efficient manner and to pass the NRC oper-ational examination. In order to accomplish this, the COT must actually perform the evolution himself, under close supervision of a licensed

- operator, including the required initial preparations and signing off the procedure or checklist, if applicable.

Se training can be accomplished during training watches as assigned -

by the Training Supervisor and on shift under control of the Shift

- Supervisor. Since many of the evolutions listed in Attachment A only occur on backshifts, it is the responsibility of shift supervision to allot time to accomplish this training.

7. Some of the items in Attachment A require specific plant conditions (cold shutdown, unit shutdown, etc.) and can only be accomplished when the

opportunity arises. In such cases personnel schedule changes may be j- required to complete the training. Other items, as marked, may be done

! any time plant conditions allow solely for the purpose of training.

3.0 PROGRAM ,

3.1 Attachment A will be maintained in the traince's AO Practical Factor file in the control room and is to be kept up-to-date by the COT.

3.2 he trainee's Shift Supervisor should review Attachment A as l

necessary to determine which items can be completed on shift.

3.3 Review completed items with the Training Supervisor each relief shift training session.

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• ATTAt fA CONTROL OPERAMR-TRAINEE ONTHE-JOB TRAINING GOALS DATE COMPLETED ,

TRAINING EVOIAFTIGI .

i 1.O* Reactor Startup (OP-1B[ ,

l.l* ERP calculation (REI-4)

' l.2* ICRR calculatioh (REI-5) 1.2.1 Sourca range 1.2.2 Intermediate range 1.2.3 Without computer 1.2.4 With computer ,

1.3* Pre-critical check (CL-1A) .

1.48 Instrument check 1.4.1 . Source range (ICP 2.9) 1.4.2 Intermediate range (ICP 2.10) 2.0 Plant Startup to 20% Power (OP-IC) ,

2.1 Reactor control 2.2 Primary system control l 2.3 Steam generator level control

• 2.4 Turbine and generator control j 3.0 Power Operation (OP-2A) 3.1 Power increase of greater than 104 3.2 Power decrease of greater than 104 3.3 Xenon follow (greater than 40% power change) '~

3.4* lleat balance (REI-1) .

3.4.1 C'omputer 3.4.2 AT method '

3.4.3 Condenser pressure / load method , _

3.4.4 RCS heatup method ,

3.4.5 Secondary calorimetric ,

3.4.6 Power range calibration (2EI-2) 3.5* Leak rate determination (PDNP 4.11) 3.6* Reactor coolant system 3.6.l* Fill RCP standpipo 3.6.2* PRT makeup / drain 3.6.3* Equalize pressurizer boron concentration 9

Attichment A

• Page 2 -

DATE COMPLETED . , , .

TRAINING EVOLtFFION 3.7* CVCS operation 3.7.1* Shift chargf.ag pumps 3.7.2* Increase / decrease letdown flow 3.7.3 Establish excess letdown 3.7.4 operato deborating demineralizer 3.7.5* Bypass demineralizers 3.7.6* Vent volume control tank pressure 3.8 Miscellaneous 3.8.l* SIS accumulators makeup / drain .

3.8.2 Drain sump "A" I 3.8.3* Main generator voltage adjustment 3.8.4* Ice melt temperature adjustment 3.8.5 Establish or shift ice melt  !

3.8.6 Start and load Unit SG 3.8.7* Secure and start- PAB ventilation 3.8.8 Run flux mapping system 3.8.9 Operate unit during I & C analog tests g *

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4.0 Shuto"wn operation .

4.1 Start reactor coolant pumps 4.2 Establish RHR system operation .

4.3 Take the RCS solid

• 4.4 Draw a bubble in the pres'surizer 4.5 control steam generator level with auxiliary SGFP's.

5.0* Fill Out the Following Loq Sheets and Forms 5.1 Control room shift log & Attachment A 5.2 Safeguards shift log 5.3 Containment vent and purge record 5.4 racade sump drain log 5.5 Steam generator blowdown log -

s 5.6 Cold shutdown log 5.7 Power history chart 5.8 Ambient lake temperature log 5.9 RCS leakage determination chart 5.10 Circulating water data log 5.11 Ice melt data log 5.12 Shift operational data log 5.13 Log of jumpers, lifted wires and bypasses .

Main turbine thermal load cycles (CLelC) 5.14

1 Attnchment A -

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DRTE COMPLETED TRAINING EVOLUTION

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6.0* Computer Operatiort (Computer Operator's Manual) ,

6.1 Perform all functions in Appendix A

. 6.2 Perform all functions in Appendix B 6.3 Perform all functions in Appendix C 6.4 'ICRR program 6.5 Boron follow program

! 6.6 General purpose program 7.0 Perform the Following Tests and checklists , 7.1 High head safety injection system IT-01

7.2 Low head safety injection system IT-03 7.3 Spray system IT-05 7.4 Electric auxiliary feed pump IT-10 7.5 Turbine auxiliary feed pump IT-08 7.6 Emergency Diesel TS-Ol 7.7 Rod Exercise TS-05 j

7.8 Control room ventilation TS-09 g

7.9 Turbine trip test, TLSD, SD PC-ll Instrument air compressors PC-9 7.10 i'

7.11 Turbine lube oil system, chg., pump PC-23 7.12 Boron update - . PC-22 ~ ~ " ~ ~ ~

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7.13 Radio & communications check 8.0 Other (Write in items performed but not listed) ,

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APPENDIX "B" PRIMARY PLAIC SYSTEMS AND COMPONEICS I. OVERALL PLAIC A. Basic Cycles B. Valve Numberin6 ,

II. REACTOR COOLANT SYSTD1 A. . Piping, materials, basic system layout B. Pressure vessel and NDTT C. Pressure vessel internals D. Reactor coolant pu=ps E. Steam Oenerators

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F. Pressurizer (including relief tank)

_ III. PRIMARY PLANT VALVES A?D FILTERS IV. CHEMICAL AITD VOLUME CONTROL SYSTDI A. Chargin6 and letdovn .

B. Purification p e C. Seal vater and RCP seals D. Supply to boric acid evaps.

E. Evaporators F. Boric acid system

,. 'G . Makeup water system V. COMPONENT COOLING SYSTIM VI. RESIDUAL HEAT REMOVAL SYSTEM VII. SPENT FUEL PIT VIII. SPENT FUEL PIT COOLING PURIFICATION SYSTEM IX. SAFETY INJECTION SYSTEM .

A. Safety injection, pumps, accumulators & assoc. piping B. Containment spray system ,

C. RHR (as it applies to SIS)

I. SAMPLING SYSTEM XI. WASTE DISPOSAL SYSTEM ,

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A. Waste liquids ,

1. Evaporator B. Waste gas C. Clean gas ,

.. D. Drumming XII. REFUELING SYSTD S A. Refueling canal and transfer tube B. Refueling tools i XIII. OPERATING PROCEDURES

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. APPE!IDIX "C" SEC0!IDARY PLANT SYSTF113 & COMPO!TETS

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I. INSTRODUCTION A. Class of systems

1. Fundamental

2. Auxiliary ,

3. Service B. System Equipment C. System Instrumentation II. STEAM GENERATOR A. Components B. Connections C .. Design Conditions D. Operatins Conditions ,

III. TURBINE A. Components B. Auxiliaries C. Design

(. D. Operation .

E. Control ,

1. Start-up

2. Operation

3. Shutdovu IV. REHEATER A. Components B. Connections C. Design Conditions D. Operating Conditions F w-w -.

...'. o' Y. STEAM SYSTDIS A. ifain Steam

1. Measurement

2. Control

3. Protective release I .

Safety Valves

a. ,

. b. Steam dump

h. Blowdown B. Auxiliary stean

1. Auxiliary feed pump turbine

2. Reheaters

3. Air ejectors

a. Priming ejectors

b. 2-stage ejector

k. Gland seal steam C. Extraction steam ,

1. Theory ..

2. Components

3. Control TI. CONDENSATE AND FEEDWATER A. Surface condenser i 1. Components

2. Operation

3. Control y,., 4-w.--w

B. Condensate .

1. Components

2. Equip =ent C. Feedvater .

1. Components

2. Equipnent 3.' Control .

D. Auxiliary feedvater

1. Components

( 2. Equipment

3. Operation i

l. Contro1 E. Feedvnter heater vents and drains .

1. Components

2. Operation

3. Contro1 VII. PUMPHOUSE AND INTAKE FACILITY

( A. Intake structure .

B. Intake pipes .

l C. Fore bay

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1. Seal bay 1

2. Flow control I 3. Tee melt D. Pumphouse l 1. Level control i

2. Isolation f

E. Equipment ,

T TIII. WAT E SERVICES l

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- k-A. Circulating water

1. Components

2. Control

. a. Priming

b. Starting intervals .

,c. Seasonal operation B. Service water .

? 1. DesiEn

2. Centrol I,

s. Nomal operation

b. EnerSency operation

c. Isolation C. Fire protection .

1. Components

a. Pumps

b. Deluge system

c. Automatic sprinkler

d. Manual sprinkler .

2. Control

a. Fire detection

b. Periodic test II. AIR SYSTD'.S A. Control and service air

1. Components

2. Operation

3. Control 6

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B. Ventilation

1. Design

• 2 Control . .

X. OIL SYSTDs A. Lube 011 .

1. Components

2. Operation

3. Control B. Seal Oil

1. Services .

2. Control C. Fuel Oil J.. Services

a. Diesel generators

b. Heatin6 boilers

c. Fire pump

d. Gas turbine 2 . Operation

3. Control II. GAS SYSTDS A. Hydrogen

1. Components

2. Operation

3. Control B. Carbon Dioxide

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APPENDIX "D" CONTAINtENT AND AUXILIARY SYSTEMS AND C0; NENTS I. Water Treatment Plant .

. A. System Description B. Chemistry of Water Treatment

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II. Containment , Structure and Testing A. Foundation, Dome, Walls, Liner B. Testing and Design Criteria C. Drains III. Containment Equipment Support

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A. Reactor Vessel B. Reactor Coolant Pumps C. Tanks D. Crane E. Piping IV. Containment Mechanical Penetrations A. Equipment Hatch

. B. Personal Hatch C. Piping Penetration V. Containment Electrical Penetrations

( VI. Containment Heating and Ventilation A. System Description . .

B. Components 4

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APPENDIX "E"

. CAS TURBIF.E SYSTD'S AND COMPONENTS Ir REVIEW OF CAS TUP 3INE PRINCIPLES A. Co=pr.ssor

1. Construction

2. Operation 3 Fsr stability - Eleeds B. Combustion

1. Fuel injection .

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2. Cc=bustion cans C. Turbine

1. Materials - Creep

2. Influence of cooling ,

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1. Fuel .

2. Turbine inlet - te=p.

3. Coc: presser discharge pressure i

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k. Inlet air te=perature.

II. FUEL SYSTEM . .

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APPENDIX "F" PLANT ELECTRICAL SYSTEMS AND COMPOhTNTS I. ELECTRICAL THEORY A. Basic Theory and Definitions

• B. Motor, Generator and Transformer Theory C. Protecti,on Systems II. WMPCO-WEPCO TRANSMISSION AND DISTRIBUTION III. POWER SUPPLY OFFICE OPERATIONS A. Interconnections .

B. System Control IV. 345 KV SWITCHYARD V. 19 KV SYSTEM VI. GENERATOR VII. 13.8 KV SYSTEM .

VIII. 4160 VOLT SYSTEM X. EMERGENCY DIESEL GENERA'ICR

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XI. SAFEGUARD POWER SUPPLY XII. 120/208 VOLT AC AND 125 VOLT DC SYSTEMS XIII. ALARM SYSTEM

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APPENDIX "G" INSTRUMENTATION AND cot 3 TROL I. BASIC INSTRUMENTATION AND CONTROL A. Symbols and Terminology

1. Instrumentation and control terminology

2. Standard instrumentation symbols

3. Standard logic symbols

4. Block diagrams Elementary wiring diagrams 5.

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6.. Coincidence

7. Redundancy

8. Accuracy / reliability B. Tripping Logic and Relaying

1. Logic elements

2. Logic diagrams ,

C. Measurement

1. Pressure and differential pressure

(

a) Bourdonekements b) Helical elements c) Spiral elements d) Spring and bellows e) Manometers f) Pressure switches, g) Force balance type

1) Pressure

2) Differential pressure

3) Vacuum and absolute pressure

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. h) Remote indication

2. Temperature a) Thermocouples

1) Iron-constantan

2) Copper constantan

3) Chromel-alumel i b) Resistance temperature detectors

1) Platinum

2) Nickel

3) Copper

( c) Filled-system thermometers

1) Vapor-filled

2) Gas-filled

3) Mercury-filled d) Bimetal thermometers f'

e) , Thermistors f) Temperature switches

3. Flow

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a) Differential-pressure flow meters

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2) Flow no::1c

3) venturi tube b) Pitot tube .

5) centile flov tube

6) Elbow taps b) Variable-area flov =eters c) Positive-displace:e'nt flev =etc.s d) Magnetic flov meters e) Turbine flov =eters

( 5 Level a) Hydrostatic-head devices

1) Differential pressure =eter

2) Pressure gauge

3) Diaphrass box k) Mercu:7 =s.nc=eter ,-

5) Purge or tubbler b) Ball ficat c) Displace =e=t type

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d) Level switches ,

6. Radiation a) Gas ionizatica detectors - General

1) Detector circuit

2) Electric field

3) Collection of icus and pulse for=ation

%) Function of detector

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5) Gas amplification b) Pulse height vs. applied voltage curve .

. - 1) Recom,bination sub-r'gion e

2) Ionization chamber region

3) Proportional region .

h) Limited proportional region

5) Geiger-Mueller region

6) Continuous discharge region c) Gas ionization detectors - Specific

( 1) Ion chamber detectors

2) Proportional counters

3) Geiger-Mueller tube detectors d) Scintillation detectors .

1) General system

2) Advantages .

3) Operation e) Neutron detection methods

1) Neutron induced transmutations

2) Elastic scattering of neutrots

3) Neutron detection by induced activity f) Common neutron detectors 10

1) Boron

2) Fission chambers

3) Proton-recoil proportional counters l

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1 II. PRIW RY PLANT INSTRUMENTATION'& CONTROL A. Nuclear Infonration

1. Source range a) Proportional counter tube b) Cabling ,

c) Voltage supplies d) D3Acriminator, integrator and 3og amplifier e) level indicators f) Start-up rate indicators

(' g) Trips and alar =s

2. Int rmediate range a) Compensated ion cham M r b) Cabling c) Volta 6e supplies

.. d) Log amplifier ,

e) I4 vel indicators f) Start-up rate indicators _

g) Trips and alarms

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3. Power Range a) Uncompensated ion chamber .-

b) Cabling c) Voltage supply d) Summing circuits e) Level indicators f) Trips and alarns l

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B. Reacter Coolant Systes

. 1. Loop Instrumentatica a) Cold leg te=perature -

b) Tawg. - AT RTD's c) Head te=perature d) Vessel flange leak-off te=perature e) Coolant pressure f) Coolant flov

2. Pressurizer Instr.:=entation & centrol

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( a) Pressure

1) Heater centrol

2) Spray control

3) Power relief valves k) Trips, alar =s , and indication

5) Deadveight pressure tester

. b) Level

1) Level controller

2) Trips, alar s and indication

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3) Cold calibratica -

c) Temperature

1) Surge line -

2) liquid

3) Vapor

%) Safety valve cutlet

5) Relief valve line d) kastrumentatien*cubiele te=perature centrol

3. Pressurizer relief tank instrr.=entation e

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a) Pressure

. b) Level c) Temperature -

k. Reactor coolant pu=p instrumentation a) Standpipe level C. Reactor Control & Protection System

1. Separation of protection & control a) Protection racks b) Control racks

2. T . avg & 6T Measurement

(

a) RTD's and dual current source b) Channel def.ats c) Alarms d) Recorders and indicators

3. Overpower trip calculators a) Flux tilt circuit .

b) Equation

'/ c) Trips and rod stops

( '

d) Recorders and indicators

%. Over te=perature trip .

a) Equation b) Trips and rod stops e) Recorders and indicators 5 Rod insertion li=it calculators D

a) Equation

, b) Alarms

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6. T avg. Controller a) Reactor power vs. turbine power input

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. - b) Tref. calculator c) Rod speed and direction 7 Steam Dump Control a) Temperature control b) Pressure control c) Load change interlock

(' d) Valve sequence  ;

8. Power Supplies a) Rod supply and trir breakers ,

b) Instrument power supplies .

9 Reactor trip and rod stop logic a) Nuclear instrumentation trip signals .

b) Primary coolant system trip signals c) Pressurizer trip signals (r-d) Steam generator trip signals e) Safety injection trip signals, f) Turbine trip signal g) Permissives h) Rod stop signals D. Rod Instrumentation & Control

1. Mechanisms a) Full length rods ,

b) Part length rods k

E.

3. Digital Position indicators

k. Analog Position Indicaters a) Coils

• b) Calibration circuit c) Indicators ,

E. Containment 77strumentation

1. Temperature

2. Humidity

3. Pressure

( k. Ventilation 5 Penetrations F. Safeguards Instrumentation

1. Safety Injection a) Lo6 c 1 b) Pressure c) Flov d) Containment Sump level e) Refueling water storage tank level b

2. Accumulators --

a) Level '

se b) Pressure

3. Steamline isolation

4. Feedwater Isolation 5 Containment Spray

~a) Spray additive tank inlet flov b) Spray additive tank levels ge muy e ,e -

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6. Containment Isolation G. Digital computer system .

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1. Basic Operation

2. Inputs and outputs a) Analog inputs

. b) Digital inputs ,

c) A[talogoutputs d) Alarm typewriter e) Trend typewriter .

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3 Control panel operations H. In-core instrumentation

1. Thermocouples a) Installatior.

b) Indication

2. Flux-mapping system a) Thimbles b) Drive units

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c) Controls d) Indication III. PRIMARY PLAET AUXILIARY SYSTEMS INSTRUMENTATION A. Chemical and Volume Control

1. Boric acid tanks a) Levels l

b) Heaters c) Recirculation

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2. Batching Tank a) Level b) Temperature "

3. Blend Control i

k. Volume control tank level control ,

t Pressures 5

6. Temperatures 7 Flows B. Auxiliary Coolant System l' l. Spent Fuel Pit a) Temperature b) Level

2. Component Cooling a) Pressures b) Temperatures c) Flows d) Levels ,.

3. Residual Heat Removal

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a) Flov b) Temperature ,

k. Reactor coolant pump cooling a) Temperatures C. Sampling System D. Fuel Handling System l

E. Waste Disposal System i

l 1. Levels

2. Pressures

3. Flows ,

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h. Conduc'tivity 5 Temperatures IV. RADIATION MONITORING SYSTU4 A. Area System

1. Channels ,

2. Hardware B '. Operational System

1. Channels

2. Hardware

( V. SECONDARY PLANT INSTRUMEiTATION A. Steam and Feedvater System

1. Feedvater Control a) Level measurement b) Feedvater measurement c) Steam flow measurement d) Controllers e) Feedvater valves f) Trips and alarms

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2. Steam Generator Feed Pumps a) Lov flow recirculation I b) Seal water temperature and diff. pressure c) Heater bypass l d) Motor driven auxiliary pumps e) Turbine driven auxiliary pumps

3. Feedvater Heater Controls i

a) Level control b) Bleeder trip valve control O

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Is . Reheater-Moisture Separator Controls a) Level control .~

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5 Miscellee.cous Controls & Instru=entatica a) ! in Steam Isolation valves b) Atmospheric relief valves c) Cohdensate recirculation d) Eea.er drain tank e) Auxiliary steam B. Steam Turbine Instru=entation & Centrols

1. Supervisory Instru=entatica a) Rotor eccentricity b) Rotor vibration .

c) Roter position d) Casing expansion .

c e) Differential easing and rotor expansion

- f) Speed and governor valve position

( g) Metal te=perature .

2. Electro-hydraulic governor systes a) Control panels b) Speed and load centrol c) Valve actuators 3 Miscellanecus Turbine Instru=entation a) Hood sprays b) Seal steam pressure c) Te=perature and pressure measure =ent g , ,-- - - - - -, - - - - - - -

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4. Turbine trip logic a) Auto-stop oil trip b) Trip from generator logic .

c) Steam generator feed pump trip signal d) Trip from reactor logic i e) Low condenser vacuum trip signal f) ww bearing oil pressure trip signal-g) Thrust bearing failure trip signal h) Overspeed trip signal

1) Main steam stop closed C. Generator Instrumentation

1. Temperature

2. Hydrogen cooling .

a) Hydrogen temperature control b) Hydrogen purity D. Condenser Instrumentation and Control .

1. Level control

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2. Pressure measurement

3. Temperature neasurement Air ejectors ..

4.

I VI. MIS &T.T ANEOUS INSTRUMENTATION AND CONTROL i

! A. Pump House Instrumentation l

B. Emergency Diesel Instrumentation C. Gas Turbine Instrumentation D. Fire Protection and Alarm E. Communications Equipment l

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APPENDIX "H" CHEMISTRY I. FUNDA!ENTALS AND BASIC CONCEPTS .

A. Matter

1. Properties of matter

2. Changes in matter

. 3. Elements

h. Compounds B. Structure of Matter

1. Atoms

i. /

2. Subatomic particles

3. Molecules C. Atomic Structure -

1. Nucleus -

2. Electron structure D. Classification of the Elements

1. Inert gases

2. Transition elements

( '

3 Representative elements E. Periodic System

1. Properties of elements l a) Metals b) Non-metals c) Amphoteric elements F. Chemical Symbols and Formulas

1. Symbols for elements l

2. Formulas for compounds

1. --' - " - - - -- -- - - - , _.,f,y _,,- _ , ,,. , _ _ ,,_,. _ _,__, _ _ _ _ _

2 C. Chenical Equations

1. Balancing equations

2. Writing of equations 3 Meaning of chemical equations i

4. Calculations H .' Solutions., Ions, and Radicals

1. . Definitions st) Solubility b) Saturation c) Ion d) Radical

2. Ionization of ecmpounds in solution a) Salts f

b) Strong and-veak acids c) Strong and weak bases d) pH II. EXTEPliAL WATER TREATMENT

(

Water and Sources of Impurities A.

B. Reason for Treating Water &.

C. Deleterious Substances and Reason for Removal

1. Silica

2. Calcium and magnesium

3. Iron and manganese

k. Carbon dioxide 5 Chlorides

6. Sulfates

- - - - , --,-w, , ee,w--- , ,- ,-, ~ -- ~-- -- --

~

7 Dissolved oxygen

8. Suspended solids

~~

9 Organico

10. Other miscellaneous inpuiities D. Clarifier-softener Operation and Purpose

1. Coagulation process

2. Sorten'ing process .

a) Reactions b) Carbonate.resoval .

(

E. Filtration F. Cation Exchange and Anion Exchange

1. Reactions

2. Regeneration .

G. Deaeration H. Mixed-Bed Exchange .

I. Levels of Impurities after each Step III. CORROSION AND WEAR A. Reasons.for Corrosion Control B. Types of Corrosion ,

1. General

2. Local

! a) Stress corrosion b) Caustic corrosion and hydrogen embrittlement c) Galvanic corrosion d) Crevice corrosion

1) Ion concentration cell  !

l

2) Oxygen concetration cell l

. 1 l

l

, ,-r -

, , , --- -- ,---m , , a-. , - - - -,m, - ,,--

- .h.

e) Pitting f) Miscellaneous types IV. CORROSION CONTROL AND INTERNAL WATER TREATMENT A. Feedvater Treatment

1. Use Sf hydrazine +

2. Use of morpholine

3. Auto =. tic control a) pH b) Hydrazine-oxygen

k. Instrumentation used B. Steam Generator Water Treatment

1. Use of phosphates

2. Disadvanta6es of phosphates .

3. Blovdown

4. Zero solids treatment 5 Disadvantages of zero solids V. RADI0 ACTIVITY

, A. Brief history -

B. Review of Atomic Structure

1. Isotopes , ,

2. Symbols and designation C. Types of Radiation and decay, Nuclear Stability

1. Alpha

2. Beta

3. Gamma and X-rays

4. Positron 5 Electron capture .

6. Other -

_ __ - , . - ~ - - - - - - --

1 D. Bate of Decay -

VI. PRIMARY CHEMISTRY AND RADIOCHE!ISTRY

, .- A. Methods of Radioactivity Production by Activation

1. Neutron-gacna -

2. Neutron-proton s

3. Neutron-alpha -

k. Proton:-neutron .

5 Other B. Sources of Radioactivity in Reactor Coolant

1. Activation of corrosion products a) Transport of crud b) In situ activation of crud

2. Induced activity of coolant and inpurities

~

a) N-16, N-17 production b) F-18, Na-24, A-41

3. Interaction of neutrons with additives a) Tritium frem Li-6 b) Tritium from.B-10 i

c) B-10 ( ) Li-T reaction

~

4. Fission products a) Tritium from ternary fission .

b) Fuel defects and escape mechanis=s c) Tramp uranium d) Diffusion through claddins 5 Radiation-induced chemical reactions a) Radiolysis of water b) Use of hydrogen

. 3- . __ 3.- ---__ .-__

.f c) Use of hydrazine

1) Decomposition ,

.. 2) When in use  :

d) Am=onia ,

1) Synthesis in reactor

2) Decomposition

. ' 3 ). Am=onia-oxycen reaction h) Nitric acid synthesis C. Chemistry of Boric Acid Solutions f-

1. pH of solutions

(

2. Partially neutralized solutions

3. Ionization of boric acid D. Adjusted pH Operation

~

1. Use of lithium or a==onia

2. Advantages

3. Disadvantages E. pH of Coolant at Reactor Temperature vs. Room Te=perature VII. PRIMARY SYSTEMS CHEMISTRY

( .

A. Vaste Disposal System

1. Waste gas .

2. Solids disposal

3. Vaste evaporator chemistry B. Boron Recovery System

1. . Ion exchangers

2. Filtration

3. Boric acid evaporation s

-~ ___. _ _ _ _ _

.l l

. o, i l

7

_ C. Main Coolant System

1. Chemistry specs. -

2. Shutdown specs. .

D. Spent Fuel Pit E. Component Cooling

"..VIII. POINT BEACH CONTRUCTION MATERIALS A". Alloys Used B. Composition C. Reasons for Use

< IX. SAMPLING SYSTEM AND LABORATORY

./

A. Location of Samples B. Reasons for each sample C. Frequency of Sa=pling D. Instrumentation used E. Analysis Required

1. pH methods

2. Conductivity

, 3. Titrimetric procedures

4. Gas analysis 5 Counting procedure's 4

9 4

6

. .. . . . . . . * - .* .-- * * * = = * *=====*- -* * * * * * - * * - * * ' 9-

APPENDIX "I" HEALTN PHYSICS .

I. RADIATION TYPES AND CHARACTERISTICS .

A. Alpha particles B. Beta particles C. Gamma radiation D. Neutrons .

E. Protons F. Interaction with matter G. Radioactive decay II. DOSE UNITS AND BIOLOGICAL EFFECTS s'

A. Development t B. Curie .

C. Rocntgen D. RAD, REP, REM

- E. RBE factors F. Dose Rate Calculations

( .,

G. BioloSi cal effects of ionizing radiation III. MAXIMUM PEPMISSABLE EXPOSURES AND CONCEICRATIONS A. Normal exposure sources B. Acute exposures C. Chronic exposures D. Internal and external exposures E. Partial and whole body exposures F. Maximum permissable exposures G. Maximum permissable concentrations

~

,. r', ' -

2 IV. PRI!!CIPLES OF RADIATION PROTECT 10!!

A. Time (vork time calculation)

B. Distance (inverse square'lav) .

C. Shielding (shielding calculation)

V. RADIATION DETECTION INSTRUMENTS i

A. Basic principles of detection instrument.s B. Gas ionization instruments (theory a operation)

1. Ionization chamber region

2. Proportional region

3. Geiger-Mueller region C. Scintillation detectors D. Neutron detectors ,

E. Laboratory instrumentation '

F. Portable instruments G. Calibration VI. RADIATION MONITORING SYSTEM A. Types of detectors .

B. Location of detector.s C. Instrument sensitivity D. Alarm setpoints E. MPC considerations F. Action following alarms VII. PERSONNEL MON TCRIllG-- one hour A. Purpose B. Individual responsibilities ,

C. Supervisors responsibilities D. Film badges

1. Limitations

2. Energy dependence

3. Types of films 14 . Special badges E. Dosimeters and pocket chambers ,

1. Beta-gam =a

2. Neutrca (thermal) .

F. Special monitoring devices

1. Threshold detectors

(~ G. Exposure records VIII. CONTAMINATION AND C0!;TAMINATION C0!! TROL A. Sources of contamination ,

B. Fixed and removable contaminaticn .

C. Control areas D. Contamination limits E. Radiation vork permits F. Radiation varning signs e

(- G. Access control points H. Transport of radioactive materials and equipment I. Svipe surveys J. Protective clothing K. Respiratory equipment , ,

L. Area preparation IX. PLANT SHIELDING A. Radiation from Reactor Operations

1. Gamma photons t

I l

(

c. -

. k ,

2. Fast neutrons

3. Thermal neutrons B. Gamma Sources ,

1. Operating core sources .

a) Fission prompts b) Fission products

. c) Capture gn=na .

2. Secondary ga==a (outside core)

3. Coolant activation gam =a a) 016 (nip) NIG .

h. Shut down core fission products 5 Residual coolant activities a) Corrosion products b) Leaked fission products

6. Activation ga=ma sources - structural T. Accident case gn=ma fission product sources C. Fast Neutron Sources

1. Fission ,

2. Photo neutron

3. Delayed group

4. 01I (ny p) -N1 + 0" D. Shield Design and Function .

1. Primary Shield a) Operating function b) Shutdown function

2. Biological Shield a) Operating function

'* O *

%'F . O .

6 5 98' e

" ~" ~ " ~ ~ ' '

• J b) Accident function E. Plant Shielding Arrangement ,

.1. Primary shield ,

2. Secondary shie.1d

3. Fuel handling shield

h. Auxiliary shieldic.

X. PIGULATIONS, RECORDS & REPORTS A. Code of Federal Regulations,(10CFR 20, etc.)

B. Records, reports 6 notifications XI. RADI0 ACTIVE WASTE MANAGSENT A. Types of Waste (liquid, solid, gasbous)

B. Liquid vaste processing C. . Solid vaste processing .

D. Gaseous vaste processing E. Release limits (liquid & gaseous)

F. Solid vaste packaging limitations G. Waste. disposal , records & reports. - .

XII. ENVIRONMENTAL MONITORING PROGRAM A. Development B. Purpose C. Sample types & locations D. Sample analysis E. Reporting procedures XIII. N GEUCY PROCEDURES - one hour ,

A. Review & analysis of Ibergency Plan .

- . . .y. _-_ , , , -

= l g

s B. Emergency monitoring C. L3 cation of emergency equipment XIV. SURVEY TECHNIQUES - PORTABLE SURVEY EQUIPMENT A. Portable Instruments (operation & practical use of)

1. Beta-gamma (G.M. tube)

2. Gamma (ion chamber)

3. Neutr'ons - fast & thermal .

k. Alpha meter B. Calibration sources C. Calibration procedures (work inverse square calculation)

XV. LABORATORY INSTRUMENTATION A. Scaler operation .

1. Operating voltage ,

2. G.M. tube ple.teau 3 Operating checks B. Counting techniques .

1. Efficiency determinations

2. Statistics of counting 3 Activity calculations XVI. AIR ACTIVITY DETERMINATIONS A. Natural background activity B. Inversion activity C. Air sampling equipment

1. Line operated samplers

2. Battery operated samplers D. Air activity calculations E. Plot sample decay

~ - - - -_

1 XVII. C0!iTAMI!!ATION SURVL"I TECHNIQUES -

A. Arca swipe survey procedures ,

l B. Equipment svipe surveys C. Sample countin6 & activity determinations D. Decontsminations techniques XVIII. RESPIRATORY PROTECTIVE EQUIP!G.iT A. Types & Li'mitations of each

1. Half face respirator

2. Full face respirstor .

( 3. Air line respirator

4. Self-contained breathing apparatus B. Operation of self-contained breathing. apparatus O

G S

...o o P'

APPENDIX."J" REACTOR ENGINEEitING I. MATl!

A. Units, Conversion Fac' tors, Symbols and Definitions .

1. Units a) Dese$iption of various systems b) Systems used in the course

1) Ccs. for nuclear work

2) Engineer.ing for most other aspects

2. Conversion Factors a) Hand-out list and tables b) How they are used ,

1) Units must cancel out p::cperly

2) Must be compatibic vith ' unit system used

,' 3. Symbols a) Describe and name Greek letters

1) Hand-out list

2) Upper case

3) Lower case b) Co= mon usage of English letters as symbols c) Subscripts and superscripts

'1) Mathematicai applications

2) Nucicar and other applications d) Some of the mathematical "shorthands" .

1) Function notation ,

2) Use of brackets

3) Summation symbol and notation 9

..o s' ' ' ,

h. . Definitions ,

I a) }!and-out of prepared " dictionary"

1) Explanation of terms that are defined' differently for different uses. ,

B. Alcebra

1. Algebraic equations a) Definition b) Sum *and product equations ,

c) Equation development

1) Understanding others equations .

2) Developing our own equations

2. Symbolic manipulation a) Equation r.anipulation 3 Powers and exponents .

h. Real number system

. a) Zero b) Infinity ,

c) Negative numbers d) Usin6 and understanding the real number system-l 1) Addition, subtraction, multiplication, division

2) Multiplication of two ne,gative numbers i

3) Multiplication and division by zero h) Multiplication and division by infinity

5) Large and small numbers ,

6) Scientific notation ,

5 Significant Figures, errors, and standard deviation a) Definition .

b) Use of

. C. Geometry

1. Definition of frequently used terms (band-out) 9

~ . , .. . _ . - - - - . . - - . -

., o. e . ,' '

~

2. Trigonometric functions a) Sine b) Cocinc .

c) Tangent ,

D. Graphs

1. Parts of a graph and definitions a) Ordinate b) Absisca c) Cootdinate

2. Types and use a) Linear

' b) Semi-log -

c) Log-log d) Special types and hand-outs E. Mathematical terms commonly used with nuclear reactors

1. Definition of terms and examples a) Slope b) Derivative (differential) ~

c) Inte6ral (integration) d) Differential equations ..

2. Exponential growth and decay a) Examples b) Origin of .

F. Logarithms

1. Definition .

2. Base 10 .

a) Use of logarithms

1) Characteristic

2) Mantissa b) Anti-loss

3. Other bases 1

/

a) Natural logarithms .

G. Calculations .

1. How to use the various functions II. ATOMIC PHYSICS A. ,

Atomic Stracture

1. History and development

2. Parts of the atom a) Electron b) Proton .

c) Neutron 3 Energy levels a) Atoms exist at discrete energy states b) Chances of state .

1) Ionization

2) X-rays B. Nuclear structure

1. Atomic number Z

2. Atomic mass A

( 3 Neutron nu=ber N = A-Z

k. Elements and Symbols ,

Isotopes, isobars, and isotones

~

5 C. Atoms and molecules l .

1. Molecules . ,

a) Structure

. b) Valance and bonds

2. Molecular properties vs. atomic properties a) Atomic veight

~b) Atomic mass unit .

c) Molecular weight d) Avogodro's number D. Periodic Chart

~

1. Hand-out and description III. NUCLE /Jt PHYSICS A. Nuclear Stability

. 1. Nuclear,Porces a) Short range b) Common to all nucleons c) Density of nucleus

( 2. Neutron-proton ' ratio a) Relative size of forces b) Curve .

c) Liquid drop model

3. Binding energy

• a) Mass-energy relationship (E = mc ) .

b) Mass defect c) Binding energy

6) Binding energy per nucleon

1) Curve

' 2) Fission

3) Fusion .

B. Radioactivity

1. Particle and ray emission .

a) Alpha particle (a) b) Beta particle (S) c) Gamma ray d) Combination

2. Stability curve and radioactive decay

^ ~ ' ~ ~'

' * -^ A

': .? ^*

]

l a) Chart of the nuclides b) Neutron heavy nuclides

. 1

1) Type of deeny c) Neutron light nuclides

1) Type of decay C. Radioactive Decay

, 1. Equation

2. Decay constant

3. Radioactive decay lav

h. Half life 5 Decay chains .

D. Interaction of radiation with matter

1. Ionization and ion pairs

2. Specific ionization .

a) Alpha (a) .

b) Beta (S)

. 3. Gamma ray (y) interaction a) Photoelectric effect b) Compton scattering c) Pair production

(

s h. Attenuation -

a) Concept and equation (I = I ,e.~"*)

b) Linear absorption coefficient j

c) Half thickness d) Mass absorption coefficient e) Application to shielding ,

E. Neutron Interactions

1. Scattering 1

a) Elastic b) Inelastic

2. Capture reaction

3. Capture with particle ejection

( h. Nuclear fission l

~ '

5. . Activation reaction in the coolant F. Neutron cross-sections

1. The cross-section concept

~

2. Microscopic (c) a) Measure of the probability of interaction b) Barn unit c) A function of three factors d) Magnitudes e) Barn book

3. Microccopic cross section (E)

h. Types a) Scattering

1) Elastic scattering

2) Inelastic scattering b) Capture c) Fission .

d) Absorption

~

e) Total 5 Energy dependence a) 1/v relationship .

b) Resonance region c) Threshold effects G. Neutron flux

1. Physical definitions , , .

a) Spherical surface b) %=nv . ,'

c) Surface of 1 en d) Co111 mated beam

2. Neutron density

3. Energy levels a) Thermal flux

. . ~

1) Equilibrium with surroundings

2) Statictical distribution b) Epithermal flux c) Fast flux H. Heutron Current e I. Reaction Rate

" 1. Equation

2. Types J. Heutron slowing down and diffusion

1. As related to a thermal reactor a) Neutron energy level resultin6 from fission

2. Energy losses a) Elastic or billiard ball collision b) Inelastic collicion c) As a function of target mass 3 Slowing down - Fermi age

4. Diffusion Length 5 Migration area

6. Diffusion coefficient IV. REACTOR PHYSICS A. Fission ,

1. Liquid drop model

2. Critical energy .

3. Spontaneous fission ,

h. Fertile and fissile materials a) Even-odd nuclides 5

Fission products

~ a) Fission fragments

1) Neutron-proton ratio

2) Distribution

.pg e - e

e c) In terms of power 7 Fast fission

- 8. Thernal. fission 9 Moderation B. Chain rea: tion i

1. Critical mass .

C. Multiplication factor or reproduction factor

1. Defiraition a) da b) K c) !(ff

2. Subc;itical

3. Critical -

k. Supercritical D. Four factor formula

1. K= " UEPf for infinite reactor a) n(eta) = neutron production factor b) c (epsilon) = fast fission factor c) p = resonance escape probability d) f = thermal utilization factor

( 2. Neutron generation problem .

E. Leaka6e

1. Leakage in a finite sized reactor ,

2. The neutron Icakage factors a) Fast leakage factor , '

b) Thermal leakage factor

3. Critical equation for bare homogeneous finite reactor F. Reflector and reflector savin 68 C. Buckling e

. .,6' Definition 1.

2. Geometric

~

3 Material .

. H. Relation between neutron flux 1cyc1 and power

1. Equation

2. Pover level changes a) Period

- b) Equation I. Reactivity (p)

1. Definition

2. Reactivity value for suberitical, critical, and supercritical .

reactor J. Sources

1. Primary .

2. Secondary

3. Purpose K. Suberitical =ultiplication

1. Equation - multiplication (M) .

2. Inverse countrate ratio (1/M) 3 Mathe=atical model breaks down near criticality L. Reactor Loadings

1. Inverse countrate ratios (ICRR) - .

a) Implies 1/M b) Loading to criticality c) Loading suberitical reactor .

d) Sample problem .

2. Geometric effects a) Source too close to detector b) Changing geometry V. REACTOR KLVETICS A. Theory Review

1. Neutron balance and K,ff

2. Reactivity

") Ecx b) Ak c) p * '

3. Exponential behavior and period

k. Prompt neutrons .

a) Neutron lifetime 5 Delayed. neutrons a) Delayed neutron fraction B. Delayed neutrons and reactor control

1. Delayed neutron groups a) Bi - six groupings b) E - one group treatment

2. Neutron kinetics and the multiplicdtion factor a) Mathematical model of reactor kinetics b) In-hour equation

3. Transient effects in a reactor a) Prompt jump b) Delayed neucron effect

'.. k. Units of reactivity a) ak/k b) I ak/k ,

c) pcm d) {and) .

e) In-hours , ,

5 Plot of in-hour equation C. Reactivity Calculations

1. Tir.e behavior based on one group model

2. Negative reactivities and period a) Longest delayed group b) 80 sec., period

3. One group model equatiore a) For p6 c) For pnB .

d) For p S

h. Sampic Calculations 5 Variations of reactivity and period for various 8 fractions D. ,

Effective delayed neutron fraction Seff n IS E. Description .r power level change rates

1. Period

2. Doubling time

(~

Startup rate (decade time)

~

3. .

h. Mathematical relations F. Prompt critical J VI. REACTOR AND REACTIVITY CONTROL A. Reserve or Exces d activity requirements

/

1. What is EOL

2. U loading for energy burnup

3. U required for criticality at EOL -

B. Fuel depletion C. Fission product poisoning E-

1. Xe and Sm

2. Fission products D. Methods of reactor control . ,

1. Rods ,

2. Boron

3. Boron burnable rods E. Control rod material and lifetime F. Functions of Control Rods egens =

• e se en e eup e 4 + ese - = s e & e ce 9

• WD e 6 m meme .g e

=

a) Shutdown b) Startup

- c) Power control G. Chem Shim H. Inherent reactivity effects in a PWR reo-tcr

1. Temp. feedback

2. Doppler feedback I. Shutdown reactivity require =ents

1. Shutdown margin 2.. Stuck rod J. Flux distribution in a reactor ,

K. Power distribution in a reactor L. Rising Neutron Flux

1. K,ff greater than 1

2. Reactor startup rate ,

3. Reactor period

" M. Decreasing Ft. tron Flux

(,/ 1. How initiated

2. Delayed neutron effect

3. Source level

( ,

N. General Reactor Control a) Startup b) Operating

• c) Shutdovu VII. REACTOR CHARACTERISTICS A. Core Mechanical Design

1. Reactor vessel and internals a) Core b) Baffle t

i

' ~ ' ~ '

~

c) Support plate d) RCC, guide tubes, and mechanism

2. Uranium fuel

, a) Fuel assemblics .

1) Dimension and Mass

2) Fuel cladding

3) Pellet design b) Flow control devices 1)' Flow mixers

2) Grids c) Sources and boron class rods

3. Rod control clusters (RCC) a) Types

1) Full length

2) Partial length b) Physical structure c) Material d) Number in core and location e) Rod grouping -

k. Reactor coolant a) Description l

b) Moderator B. Reactor Thermal and Hydraulic Parameters

1. Thermal power level

2. Programmed T AVE

3. Loop temperatures and core bypass

h. Fuel temperatures 5 Reactor coolant a) Flow b) Chemistry C. Control Rods a

1. Types and functions

a) Shutdown b) Control

. c) Partini len6th

2. Control rod worths  ;

a) Shutdown b) Control'

3. Control rod reactivity worth curves

. a) Differential ,

b) Integral c) Use ,

D. Reactivity Coefficients

1. Reactor moderator coefficients a) Pressure coefficient b) Temperature coefficient

1) Boron and temperature effects

2. Boron coefficient (vorth)

• 3 Power coefficient

4. Ph reactivity effect 5 Xenon reactivity vorth E. Hot channel factors

1. Types ,

a) Engineering b) Nuclear

2. Enthalpy Hot Channel Factor a) Definition .

b) How used - .

3 Axial hot channel factor a) Definition '

b) How used

%. Heat flux bot channel factor m) Definition l

b) How used l

I

0 0 l

)

5 Other hot channel factors that are used and their relationship to those given above .

a) Radial peaking factor b) Local peaking factor F. Departure froct Nucleate Boiling

1. Definition ,

2. How used VIII. CORE STATIC' AND DYNMfIC BEHAVIOR A. Initial Core Loading

1. Fuel movement

2. Loading sequence 3 Core monitorire B. Initial Criticality

1. Plant Conditions .

a) Primary b) Secondary

2. Instrumentation and monitoring ,

a) Nuclear .

b) Primary c) Reactor Coolant Chemistry

3. Initial Critical Approach a) Method used

1) Rod withdrawal

2) Boron dilution .

b) Monitoring the critical approach

1) Count xate multiplication

2) Startup rate

3) Inverse count rate plotting

c) Geometric effects

1) Source and detector location effects

2) Relecting and shadowins of neutron from

~

detectors by fuel add control rods d) Indication of criticality

1) Startup rate

2) Flux level indication C. Subsequent Critical Approaches 9

1. Monitoring required

2. Estimating just critical conditions D. Physic Testing Programs

1. Zero power

2. Power escalation

3. Recurrent test series .

E. Reactor at Power ,

1. Thermal Power vs Electrical Power a) Plant efficienty .

b) Calorimetrics c) As a function of load and back pressure

2. Transient plant behavior for load changes a) In automatic control

.1) Step load changes

2) Ramp load chan6es

3) Reactor trips b) Manual control .

1) Inherent power stabilization

3. Long-term behavior for load chan6es a) Xenon transient b) Samarium c) Boron w - r-- - - , --, _ y-- v -.-- -. - - - .- - --, y

7. Reactor Shutdown From Power

1. Reactivity Requirements a) Temperaturc b) Doppler c) Mar 6in d) Xenon

2. Programed Shutdown a) In automatic control b) Manhal 3 Reactor Trip shutdown a) Cauces b) Plant behavior

k. Core decay heat a) Function cf previous power history b) Magnitude G. Core Renetivity Folica

- 1. Definition

2. Purposes a) EOL prediction ~~

b) Detection of unexplained reactivity chan6es 3 Reference conditions

b. Corrections to reference conditions a) Power level b) Rod position c) Boron concentration -

d) Temperature ,

5 Typical curves H. Core Stretch-Out

1. Definition

2. Reactivity gains resulting from new operating conditions a) Reduced power level b) Reduced TAVE

3. Stretch-out economics I. Reactor Accident Analysis J. Refueling

1. Monitoring

2. Fuel movements 9

e S

S e

(

%m e

e 6

e

- APPENDIX K

, TITERMODYNAMICS AND HEAT TRAIISFER

\

i A. Terminology and Definiticno

's v,. J

1. Pressure a) Absolute b) Gauge c) Atmospheric

2. Enthalpy

3. Entropy Is . Specifib volume 5.' Specific gravity.

6. Temperature - heat 7 Energy

( ,

8. Work 9 Power B. Thermodynamics .

1. Energy

,,;h :

,,;./ a) External forms

1) Potential energy

2) Kinetic energy b) Internal form

1) Chemical

2) Molecular ,

3) Nuclear ,

. 2., Thermodynamic System .

a) Boundary b) Closed and open ,

. c) Reversible Processes

3. Phases .

a) Solid b) Liquid c) Gaseous

~ d) Triple Point

. e) Saturated Liquid and Saturated Vapor f) Subcooled liquid

== .m.mm.m .- ... . . ... . . . . .

-= +, ---w,

• = = - --e. -

C. Fluid Flov ,

7. .

i uj 1. Mass flow rate

2. Laminar flov 3.' Turbulent flov .

h. Reynolds nu=ber 5 Bounda:7 layer

6. Free convection 7 Forced convection

8. Two phase flow D. Ther=odynamic Cycles

1. Used in power plants E. Heat Transfer

( 1. Temperature a) Balk te=perature b) Surface or claddin6 te.perature

.3 c) Te=perature gradient

.@ 2. Heat .

~

a) Heat flux b) Yolu=etric ther=al source strength, q" (pover density)

(function of flux) ..

c) Specific power and linear power

( 3. Ther=al conductivity a) Equation

h. Convective heat transfer a) Newton's law of cooling b) Heat transfer coefficient ,

c) Prandtl number d) Nusslet number e) Heat transfer correlations F. Boiling heat transfer .

l. Nucleate boiling d 2. Flin boiling

3. Departure from nucleate boiling (Dh'3) e s e . .my %w , my - -,7 r.;,,,- c ;a4 .. er .. A w. .. :n-- 1.:.r.c. - - r - ' - - -

, ~_ -

1 , .

i .

, , C. Coolants -

i,-J 1. Types

' .. s

2. Desirable properties -

) <

3. Water .

I a). Advantages l 1

b) Disadvantages i 4

H. Temperature variations in a reactor l

1. In a coolant channel

2. At fuel' assembly outlets

)

j 1 .

(

s 4

d

.e

'^

lI>l}

i t .

( -

l i

u d

1

~ -.

_.-__:=,.,_-._:-._-,.-=.__:n__---.____..__..,__..,_-_-_._ ___ _ __- , _ ~ _ _ ~ . ~ _ , ~ . _ . _ . _ _ . . . ~ _ ~ . _ _. _ .

-- i

• e e

. o, t

so. '

. l APPCt1 DIX L

' E N/

FICULATING DOCUtD1TS T,ND MISCELLANEOUS PAPERWORK I. Technical Specifications A. Definitions B. Safety Limits C. Lindting Conditions for Operation D. Surveillance Requirements E. Design Featurcs F. Administrative Controls G. Non-Radiological Technical Specifications II. QA Manual A. Sections 3.1 .

3.4 .

. * )}g 3.18

'%sI 3.19 3.24

[ ,

. 3.29 4.0 9.3

,P III. Reportable Occurrences and Significant Operating Events

- IV. Standing Orders and Special Orders .

V. Operating Instructions VI. Operating Procedures VII. Refueling Procedures VIII. Emergency Procedures .

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APPENDI'X M 1

PLANT TRANSIENTS / ACCIDENT ANALYSIS AND MITICATION OF CORE DAMAGE ,

I. PLANT TRANSIENT ANATYSIS -*

7 A. Uncontrolled Dilution B. Startup of Idle Reactor Coolant Pump C. Opening of Feedwater Heater Bypass Valve D. 10% Load Increase /

II. PLANT ACCIDENT ANALYSIS A. . Loss of Flow

1. Two pumps

2. One pump

3. Locked rotor B. Loss of Load C. Loss of Feedwater D. Loss of AC Power E. Steam Generator Tube Rupture F. Steam Line Rupture

1. Inside containment

2. Outside containment G. Feed Line Break H. Loss of Coolant Accident

1. Large

2. Small

a. Liquid space

b. Steam space (TMI accident)

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' Appendix M Page 2

3. voids

a. Formation, indica' tion, prevention III. TRANSIENTS ON CONTROL SYSTEMS

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A. I & C Review of Control Systems

1. Rod control

-2

2. Steam dump j

3. Pressure control

4. Level control S. Steam generator level control B. Control Systems Responses

1. los step increase

2. 10% step decrease

3. 100% trip IV. ACTUAL PBNP TRANSIEN'IS A. Reactor Coolant System Flow Coastdown B. Loss of one Reactor Coolant Pump C. Start of Inactive Loop D. Turbine Trip from 70%

E. Turbine Trip from 40% ,

F. Rod Drop G. 50% Runback H. los Step Increase I. 10% Step Decrease

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• Appendix M Page 3 J. St/ Minute Ramp Increase K. St/ Minute Ramp Decrease L. PBNP Pecorder Traces M. Flux Map Traces V. MITIGATION OF COPE DAMAGE A. Use of Incore Instrumentation

1. Fixed incoro detectors

2. Movable incore detectors

3. Incore thermocouples

, a. Methods of range extension

b. Methods of direct reading

4. Use of P-250 computer B. Excore Instrumentation (Nuclear)

1. Determination of void formation

2. Determination of void location C. Vital Instrumentation

1. Instrumentation response in accident environment

2. Instrumentation failure sequence

3. Indication reliability

4. Alternative methods of measurement

a. Flow

b. Pressurizer level

c. ' Temperature

d. Pressure

-- , - + - v - - - -

+ e  %

' Appendix M Page 4 D. Primary Chemistry

1. Expected results with severe core damage

2. Radiological hazards

3. Expected isotopic breakdown

a. Fuel damage

b. Clad damage /

4. Corrosion effects E. Radiation Monitoring -

1. Detector response

, a. Saturation

b. Diret.t measurement

c. Accuracy

2. Use of detectors to determine core damage

3. Dose rate determinations

a. Measurements inside containment

b. Measurements outside containment t

F. Gas Generation

1. Methods of hydrogen generat<ct

2. Other gas sources (Xe, Kr3

3. Disposal of noncondensibles j 4. Hydrogen flamability and explosive limits

5. Sources o" oxygen inside containment l

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. . _ _ , . . [ ....us. . . .a . .u . 3m. ,e- . ... - .. .. . --- . . .

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Name ON-SHIFT TRAINING AND REVIEW FOR CONTROL OPERATOR TRAINEES Instructions

1. This training can be accomplished on shift when the COT is assigned to the turbine hall watches. Some amount of time should be spent on training during each turbine hall watch, dependent, of course, upon plant status, on backshifts and weekends.

2. Any licensed operator can conduct the training, but the signoff is the responsibility of the Shift or Operating Supervisor.

3. Sign off the attached sheets when completed.

4. Document time spent on training on the OJT form.

5. Knowledge of the following areas should be demonstrated before signing off a system:

a. Normal operation and parameters.

b. Remote controls and indications.

c. Auto control (basic knowledge).

d. Int ('/ ? aces with other systems.

e. Interactions with other systems.

f. Basic understanding of associated operating procedures, emergency operating procedures, and operating instructions.

g. Ability to make a basic diagram, including main flow path, remote-operated valves, crossconnects, etc., i.e., NRC-type drawings.

6. The following areas should be covered on procedures:

a. General knowledge of operating procedures including the reasons for the precautions and limitations.

b. Detailed knowledge of symptoms and bunediate actions for the emergency optrating procedures. General knowledge of subsequent actions.

c. General knowledge of the operating instructions which pertain to control room operations.

TR-12 Page 1 of 3 (12-79)

, e COT SYSTEMS REVIEW Name Complete by Supvr.

Init. Date PRIMARY SYSTEM

1. Reactor coolant system *

a. Pressurizer level control

b. Pressurizer pressure control

c. Rod control system

2. CVCS*

a. VCT level control

3. Safety injection system *

4. Containment spray system *

5. Residual heat removal

• 6 .- Spent fuel pit cooling

7. Component cooling *

8. Fuel handling system

9. Containment ventilation * & PACVS (M-224)

10. Containment structure

11. Sampling system

12. Waste disposal system liquid **

13. Waste disposal system gaseous **

• NRC-required drawings from memory

• • Block diagram from memory Page 2 of 3 TR-12

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. Supvr.

SECONDARY SYSTEMS Init. Date

1. Main & reheat steam (M-201)

a. Steam dump control

2. Condensate & feedwater (M-202)

a. Steam generator level control 3 .' Extraction steam (M-203)

4. Feedwater heater vents & drains (M-204, 205)

5. Gland steam & drains (M-206)

6. Service water (M-207)*

7. Fire water (M-208)*

8. Instrument air (M-209)

9. Heating & ventilation (M-215, 144)

10. Circulating water (M-212)

11. Lube oil system

a. Turbine lube oil

b. EH oil

12. Auxiliary feedwater (M-217)*

13. Fuel oil (M-219)

14. Electrical systems

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TR-12 Page 3 of 3

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. POINT BEACH NUCLEAR PLANT ON-SHIFT DISCUSSTION TECHNICAL SPECIFICATION NAME INSTRUCTIONS

1. This checklist is to be completed by

2. Non-shift personnel may complete these items on an individual basis.

3. The basis for each specification is required for Senior operators License.

TITLE L L L COM L TED C01 TED 15.1 15.4.10

~~

15.2.1 15.4.11

~~

15.2.2 15.4.12

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15.2.3 15.4.13 15.3.1(I) 15.4.14 15.3.1(II) 15.4.15

~~

15.3.2 15.5.1

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15.3.3 15.5.2

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15.3.4 15.5.3

~~

15.3.5 15.5.4 15.3.6 15.6.1

~~

15.3.7 15.6.2

~~~

15.3.8 15.6.3

~~

15 ,3.9 15.6.4

~~

15.3.10 15.6.5

~~

15.3.11 15.6.6 15.3.12 15.6.7 ,

15.3.13 . 15.6.8

~~~

15.3.14 15.6.9 15.4.1 15.6.10 15.4.2 15.6.11 15.4.3 15.6.12 15.4.4 16.1 15.4.5 16.2 15.4.6 16.-3 15.4.7 16.4 15.4.8 16.5

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15.4.9 16.6 TR-06 (01-80)

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e,, r POINT BEACH NUCLEAR PLANT l

\

ON-SHIFT DISCUSSION OPERATING PROCEDURES NAME INSTRUCTIONS

1. This checklist is to be completed by

2. Non-shift. personnel may complete these items on an individual basis.

TITLE COM L TED COM TED OP-6A OP-1A OP-1B OP-7'A OP-lc OP-7B OP-1D OP-8A OP-2A OP-9A OP-3A OP-9B OP-3B OP-9C OP-3C OP-9D' OP,4A OP-11A OP-4B OP-13A OP-4C OP-14A OP-4D OP-16A OP-5A special

__ orders OP-5B

__ Standing OP-5C orders OP-5D M

i TR-07 (01-80)

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w-ww- -**-,r- .----we---- --ci-e ---- -r- w- - - '=w-'----* - -

m w,--- - - --r -,-,-r -ree- i--.,,,,,,-w *w-r- r-e---=-y w r -we--w ,m-,se-=--ewe --w g

_ . - _ . ~ . . __. ..__.-_ _. . . _ _ .i

~ .. .- .

l POINT BEACH NUCLEAR PLANT t

, EMERGENCY AND HISCELLANEOUS PROCEDURES NAME INSTRUCTIONS

1. This checklist is to be completed by .

2. Non-shif t personnel may complete these items on an individual basis.

TITLE '

COM L TED COM TED EOF-1A E0P-11A e

E0P-2A E0P-11B E0P-3A E0P-12A -

E0P-4A E0P-13A E0P-5A , RP-1A E0P-5B -

RP-1B E0P-6A RP-1C E0P-6B RP-1D E0P-6C RP-2A EOP'-6D RP-2B E0P-7A RP-2C E0P-8A RP-3A E0P-8B RP-3B E0P-8C RP-4A E0P-8D RP-4B E0P-9A RP-5A E0P-9B QA Manual (SRO Only)

E0P-9C Emergency

-- Plan Manual E0P-9D

- HP Manual E0P-10A~

D a

TR-08 (01-80)

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