ML17334A383

to Operator Replacement Training Program

ML17334A383
Person / Time
Site:	Cook
Issue date:	02/03/1980
From:	Lange D, Lease R, David Nelson INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17334A381	List: ML17334A380 ML17334A383
References
RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8205040789
Download: ML17334A383 (13)

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OPERATOR REPLACEMENT TRAINING PROGRAM The Operator Replacement Training Program supplies selected oper-

-ating personnel with the background and experience necessary for safe and 4

reliable operation of the plant controls and prepares them for the NRC Reactor Operator 1 icensing examinations.

Prior to selection to the program, the license candidates shall have been working in the control room under the direction of qualified licensed operators.'ll control room instruction, including control manipulations, shall be documented on form OHI-2070 Attachment 5 (attached} until the trainee is licensed by the NRC.

Formal classroom instruction will be given in the areas and subjects listed in the Non-licensed Operator Training Program as necessary to ensure thorough trainee comprehension. In addition, formal classroom instruction will be given in the following subjects:

A. Neutron Behavior

1. Nicroscopic Cross Section.

2. Neutron Energy vs. Cross Section.

3. Doppler Broadening.,

4. tlacroscopic Cross Section.

5. Neutron Density.

6. Neutron Flux.

Page 1 of 11 Rev 1 2/3/80

. 7. Reaction Rate Calculations;-- .

8. Energy Dependence 'of Reaction Rate.

9. Neutron Reactions.

a. Control Materials.

b. Water.

c. Density Effects.

d. Structural Materials.

10. Power and Power Density.

11. Neutron Scattering.

12. Moderator Properties.

a. Slowing Down Power.

b. Moderating Ratio.

c. Non-Nuclear Factors.

13. Neutron Densi.ty Energy Spectrum.

14. Neutron Flux Energy Spectrum.

15. Neutron Diffusion.

16. Neutron Reflection.

I. Neutron Balance Equations.

2. Multiplication Factors.

3. The Neutron Cycle.

4. Fast Neutrons.

5. Epi thermal Neutrons.

6. Neutron Leakage.

Page 2 of 11 Rev 1 2/3/80

Thermal Absorption - Fuel.

8. Fast Fission.

9. Epithermal Resonance Capture.

10. Thermal Absorption - Not Fuel.

ll. Neutron Cycle Calculations.

12. Calculating the Reproduction Factor.

13. The Fast Fission Factor.

14. The Resonance Escape Probability.

15. Calculating the Thermal Utilization Factor.

16. The Four Factor Formula - The Infinite Multiplication Factor.

17. Enrichment Effects on the Four Factors.

18. Poison Effects on the Four Factors.

19. Moderator-to-Fuel Ratio Effects on the Four Factors.

20. Core Life Effects on the Four Factors.

21. Thermal Neutron Leakage Calculations.

22. Fast Neutron Leakage Calculations.

23. Hoderator-to-Fuel Ratio Effects on Leakage.

24. Enr ichment Effects on Leakage.

25. Poison Effects on Leakage.

26. Core Life Effects on Leakage.

27. The Six Factor Formula - The Effective Multiplication Factor.

28. Neutron Flux Oistribution.

29. Neutron Reflection.

30. Core Zoning.

31. . Power-Flux Relationship.

Page 3 of ll Rev > 2/3/80

32. Power Distribution.

33. .Peaking Factors.

34. Radial Nuclear Factor.

35. Axial Nuclear Factor.

36. Local Nuclear Factor.

37. Total Nuclear Factor.

38. Neutron Production.

39. Prompt Neutrons.

40. Delayed Neutrons.

41. Delayed Neutron Emissions.

42. The Delayed Neutron Fraction.

43. The Delayed Neutron Fraction Change Over Core Life.

44. The Effective Delayed Neutron Fraction.

45. Neutron Lifetime and Generation Time.

46. Delayed Neutron Effects.

47. Reactivity.

48. Reactor Period.

49. The Power Law.

50. Startup Rate.

51. Doubling Time.

52. The Inhour Equation.

53. Reactor Control System Effects.

a. Short-Term.

b. Intermediate-Term.

c. Long-Term.

Page 4 of ll Rev 1 2/3/00

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54. Typical Absorber Hater ial s.- -

55. Effect of Control Poisons on the Effective Hultiplication Factor.

56. Control Poison Forms.

57. Black and Gray Poisons.

58. Effects of Control Systems on Flux Shape.

a.. Control Rods.

b. Soluble Poison.

c. Burnable Poisons.

59. Differential.Rod North.

60. Integral Rod !lorth.

61. Differential Boron Worth.

62. The Doppler Coefficient.

63. The Hoderator Temperature Corefficient.

64. Undermoderation...

65. Overmoderation.

66. The Pressure Coefficient.

67. The Void Coefficient.

68. The Isothermal Hoderator Temperature Coefficient.

69. The Power Coefficient.

70. Calculations of Reactivity Changes.

'71. Variations in the Doppler Coefficient.

72. Variations in the Hoderator Temperatur Coefficient

a. Effect of Fuel Temperature Changes.

b. Effect of Changes in Hoderator Density.

c. Effect of Poison Density.

d. Effect of Core Age.

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73. Reactivity Defects.

74. The Power. Defect.

75. Neutron Competition and Shadowing.

76. Conditions Affecting Control Rod Morth.

77.. Coefficients and Control in a Pressurized Mater Reactor.

78. Fission Product Formation.

79. 'Xenon Production and Removal.

80. Equilibrium Xenon..

81. Startup Xenon Transients.

82. Shutdown Xenon Transients.

83. Restart Xenon Transients.

84. Power Change Xenon Transients.

85. Xenon Oscillations.

86. Equilibrium Samarium.

87. Samarium Transients.

88. Core Reactivity Requirements - Excess Reactivity.

89. Core Nuclear Reactions.

90. Fuel Depletion Effects on Reactivity.

a. U-235 Burnout.

b. Fission Product Poison Buildup.

c. Pu-239 Buildup.

d. Burnable Poisons Depletion.

e. Total Core Life Effect.

f. Refueling.

91. Other Fuel Depletion Effects.

Page 6 of 11 Rev 1 2/3/80

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a ~ Effects on Flux.

b. Effects on the Six Factors.

c. Effects on the Effective Oelayed Neutron Fraction.

d. Effects on the Reactivity Coefficients.

92. Neutron Sources.

94. 1/H Plots.

95. Fuel Loading.

96. The Approach to the Critical Condition.

97. Predictions of Criticality.

98. Physics Testing.

a. Rod >lorth Measurement.

b. Coefficient Horth Measurement.

c. Reactivity Follow.

99. Power Changes.

100. End of Core Life.

101. Reactor Coastdown.

102. Turbine Runback.

103. Planned Shutdown.

104. Reactor Trip.

105. Shutdown Cooling Requirements.

106. Fuel Management.

107. Pefueling.

To enhance the theory phase of instruction, the trainees will participate in a training program at a research reactor. Ouring this Page 7 of 11 Rev 1 2/3/80

program they will perform experiments to exhibit and measure reactivity effects. The trainees will gain hands-on experience by performing startups arid shutdowns of the reactor.

Plant systems will be taught in depth through formal classroom instruction and in-plant study. Normal, Abnormal, and Emergency Operating Procedures will be emphasized. Controls, instrumentation, setpoints, auto-matic actions, differences between the units, system interfaces, and Technical Specifications limitations will be stressed. The systems covered are:

1.'eactor Core.

2. Reactor Coolant System.

3. Pressurizer and Pressure Relief System.

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4. Rod Control System.

5.'hemical and Volume Control System.

6. Residual Heat Removal System.

7~ Excore Nuclear Instrumentation System.

8. Incore Huclear Instrumentation System.

9. Reactor Protection System.

10. Emergency Core Cooling System.

ll. Containment System.

12. Ice Condenser System.

13. Containment Spray and Hydrogen Recombiner System.

14. Fuel Handling System.

15. Primary Sampling System.

16. Component Cooling Water System.

ll. Essential Service Mater System.

Page 8 of 11 Rev > 2/3/80

18. t(on-Essential Service Mater System.

19. Demineralized Mater System.

20. Spent Fuel Pit Systems.

21. Maste Disposal Vent and Drain System.

22. Liquid Maste Disposal System. ~ /

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23. Gaseous Maste Disposal System.

24. Solid Maste Disposal System.

25. Containment Ventilation System.

26. Auxiliary Building Ventilation System.

27. Control Room Ventilation System.

28. Emergency Diesel Generator Systems.

29. Auxiliary Feedwater System.

30. Compressed Air System.

31. Lube Oil Cleanup System.

32. Secondary Sampling System.

33. Secondary Chemical Feed Systems.

34. Primary Mater System.

35. Primary Gas System.

36. Mater Fire Protection System.

37. Carbon Dioxide and Halon Fire Protection System.

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38. Hiscellaneous Fire Protection Systems.

39. Plant Computer.

40. Radiation thoni toring System.

41. Portable Radiation Instruments.

42. Steam Generator and Steam Generator Slowdown System.

43. Main Steam System.

Paqe 9 of 11 Rev ~ 2/3/80

45. Auxiliary Steam System..

46. Plant Heating Boiler .

47. Main Turbine and Control System.

48. Steam Seal Supply and Exhaust System.

49. Main Turbine Lube Oil System.

50. Bleed Steam System.

51. Moisture Separator/Reheater and Feedwater Heater Drains.

52. Circulating Water System.

53. Chlorination System.

54. Miscellaneous Sealing and Cooling Water System.

55. Vacuum Priming System.

56. Condensate System.

57. Feedwater System.

58. Steam Generator Level Control System.

59. Steam Dump System.

60. Main Generator and Auxiliary Systems.

61. 4160 KY Electrical Distribution.

62. 600Y AC Electrical Distribution.

63. 120Y AC Electrical Distribution.

64. 250V DC Electrical Distribution.

The trainees vIill be instructed in the Plant Technical Specif-cations Safety Limits, Limiting Safety System Settings, Limiting Conditions for Operation and Bases for these limits. They will be held responsible for knowing all Action Statements of one hour or less.

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Further intensive training in Instrumentation and Control systems C

and in Radiation Control and Protection will be given.

Periodic written and oral examinations will be given throughout the program to evaluate trainee performance and to prepare them for taking the NRC written and oral examinations.

Plant operating characteristics and responses to transients will be taught. Accident diagnosis and corrective actions will be emphasized.

The trainees will attend a simulator training program where they will perform plant evolutions and casualties. An NRC approved simulator certification program will be utilized for the demonstration portion of the Reactor Operator licensing examination at this time.

Simulated NRC written and oral examinations will'e administered to the license candidates to audit their preparation for the NRC Reactor 0)er ator licensing examinations. This audit will be an input in determining which candidates will be recommended for the NRC examination and will be used to identify weak areas needing further study.

After the audit examination, a'minimum two week review series, will be conducted in final preparation for the NRC examination. Meak areas and overall plant operation will be stressed, Page ll of 11 Rey I 2/3/80

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~ ~ r-2070 Attachment  ;-5 No. of Hours to the nearest l/10 hour Date Shift REACTI~I iT. 'lAHLPULATIGH Control Board Time To be comoleted by Hot License candidates (Replacement Reac.or Operator Students}

working under instruction in the Control Roam, or by any individual Auxiliary equipment operator that is working under instruction in the Control Room.

Name - Prin. Signature Control lhnipulations, Oral "-xams (Mai kthrough}, etc.

Be Spe"ific:

~Iame - Print (RG,SRO) Slgnatul e

'"-r~ard im. diately to the Training Depar =..ent acn and every ime a student wor4s in he Control Room.

page l of l Rev 1 2/3/80

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