ML20030A535
| ML20030A535 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 07/26/1976 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20030A534 | List: |
| References | |
| NUDOCS 8101090961 | |
| Download: ML20030A535 (12) | |
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LIG ROCK POIRT PLUTT LICEI; SED OFER*. TOR REQUALIFICATIO:1 PROGRU4
-Objective To escut e a continuing high degree of knowledge and pro-ficiency is naintained by AEC licensed operators at the Big Rock-Point Plant.
' Applicability
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Applies to plant personnel that are licensed. operators (RO) or senior operators (SRO) that are required to routinely supervise plant evolutions or perfom control manipulations as well as those RO or SRO that perfom such duties on an infrequent basis.
Baeh r.round_
'The Big Rock Point Plant has been in operation for approxi-
,mrit'cly eleven years. Training and retraining efforts have been con-ducted in the past on an infomal and irregular basis.
Because of the variety of tines of original operator license examinations and the in-f-
form l training program, Consumers Powcr Co=pany personnel evaluated the 1cvel of knowledge and proficiency of Big Rock Point Plant licensed operators prior to fomulating the retraining pro:gren described herein.
As a result of these evaluations, the retraining program vill be conducted during the first two-year cycle placing expanded emphasis on areas requiring theoretical knowledge.
Program During the first two-year retraining cycle, the classroom portion of the procron vill be extended in length in order to concen-
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trate on basic fundementals and application of theory.
The first cycle vill consist of seven weeks of classroom work, utilizing selected units from a co=mercial video tape program with a full-tice instructor. An
. outline of the material to be covered is tabulated in Appendix A of this cub.'11ttal and in general covers the subjects listed in Paragraph 2C of Appendix A to 10 CFR 55 The classroem work vill consist of a reading nusignment, video tape viewing, a quiz and a discussion period.
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i This applies to each session listed in the outline. An instructor will continually be present during video tape viewing and discussion periods.
Topical excms vill be administered throughout the classroom portions of the program. A minimum grade of 80% vill be required for all part~cipants in these examinations.
Annual examinations patterned after the AEC license exa=ina-tion vill be cdainistered to determine effectiveness of training efforts and to define creas which require emphasis during lecture progra=s. An overall grade of 70% on the annual exam must be attained to qualify for performing licensed duties. A person receiving a grade belov 705 vill enter an accelerated training progrcs within 10 days of grade determina-1 tion to upgrade his knowledge to an acceptable level.
The scope and dur-ation of the accelerated training program vill be determined from analysis of results of the individual exa=s.
Persons receiving a grade of greater than 80% in a particular category in the annual exam vill not be required to attend the lectures on that material.
The classrocm work vill be coupled as closely as practical with k
a three-day course at a BWR simulator. The simulator vill be used to demonstrate the principles covered in the classroom sessions.
In addition, the simulator vill aug=ent en-the-job experinece, permitting manipulation of controls in many modes of operation.
It is not intended that the sicu-lator be used for evaluatien of performance during abnormal or e=ergency conditions as required in Paragraph hC of Appendix A to 10 CFR 55. The General Electric Boiling Uater Peactor Training Center (GE EWETC) simula-tor vill be used during the first two-year cycle and the results evaluated to determine the advisability of further sbnulator sessions. An outline of the three-day simulator course is attached to this submittal as Appen-dix B.
Credit toward relicensing for reactor startups or critical approaches and Rx shutdowns may be gained at the GE BWRTC simulator.
Classroom sessions to review facility changes, procedure changes, operating incidents, Technical Specifications changes, license changes, other commitments and discuss systems vill be conducted weekly when possible.
Classes will not be conducted during refueling outages, high vacation 2
periods or when full-time classroom work is in progress. A minimum of six such lectures per calendar year shall be conducted. Examinations vill be
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administered at these sessions to evaluate understanding of material presente' W
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Individuals must attend a minimum of 75% of the systems, etc lectures during a two-year cycle to qualify for renewal of their licenses.
Credit for attendance vill be given if a grade of 80% or greater is ob-tsined on an examination covering the material. Persons whose regular duties include reviewing and/or approving facility changes, procedure 3
changes, license changes, etc vill not be required to attend lectures or to take the quizzes on such material.
Evaluation of perfor=ance in routine and abnor=al operations vill be conducted on shift as well as in sLsulated abnor=al conditions.
Evaluation will normally be perfonned by the person's immediate super-visor. However, a minimum of five exercises, during a given two-year renewal period, vill be evaluated by someone other than the person's immediate supervisor. In addition to evaluation of performance in these operations, a scheduled review of emergency procedures by each licensed operator ensures familiarity with the " symptoms" and "immediate action" portions of these procedures. This review vill be routinely administered and documented for record purposes.
t The "10 reactivity control manipulations" (required by 10 CFR Part
- 55) may be accomplished by each person at an approved BWR simulator, or in h
performance of his regular duties, or a combination of both. Plant control manipulations which demonstrate skill and/or familiarity with reactivity control systems for the Big Rock Point Plant are described below:
1.
Critical approach from a suberitical condition and increasing power to the point of adding heat.
2.
Change of reactor power of 25% of full pover or greater either by controlled rod movement or reactor recircula-tion flov adjustment.
3.
Performing suberiticality and/or shutdown margin checks during fuel handling operations.
k.
Performing control rod drive tests required prior to a reactor start-up after an extended shutdown.
An effort vill be made to give each man a variety of manipula-tion experience. If the simulator is not used, a person must perform three of the listed manipulations at least once.
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The classroom phase for the second and succeeding cycles vill be three weeks instead of seven weeks. The emphasis vill be reduced in the areas of basic fundanentals and application of theory as compared to the first cycle.
All licensed operators vill reviei procedure changes, facility changes, abnormal occurrence reports, Technical Specifications changes, license changes, and other cocmitments and sign off that they have seen this material. These items vill be discussed during the classroom ses-sions, as noted above, as appropriate.
Records shall be maintained in an individual file for each licensed operator. All exams, evaluation reports, and other pertinent documentation vill be maintained in this file. Exams and exas ansvers will be maintained by the training coordinator.
Schedule The first retraining cycle was considered to have started in July 1973 (for record purposed, July 1) with the administration of an evaluation examination. Each cycle vill be two years in length.
General The program described above vill be implemented by the plant superintendent. Execution, coordination, record keeping, etc, vill be the responsibility of the training coordinater.
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APPENDIX A
' Big Rock Point Retraining Pr'. ram The first cycle of classroom work in basic fundamentals vill follow the schedule tabulated below. Classroom session vill consist of reading assignments, daily quiz, video tape and discussion. The instructor will lead discussions, answer questions and give specific plant application of the general material on the tape where appro-priate.
Day 1 MS Slide Rule Use M6 Log Base Day 2 M8 Algebra Applications M9 Algebra Day 3 Mll General Science M12 General Science Day h M13 General Science BNP10 Radioactive Decay Day 5 BNP13 Cross sections BNP1h Reaction Rates
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TEST - 1/2 Day Day 6 BNP15 Neutron Spectrum and Energy Effects BNP16 Neutron Slowing Down Day 7 R04 4-Factor Formula R05 h-Factor Formula Day 8 R06 Buckling and Leakage R08 Reactor Control Day 9 R09 Reactivity C~-fficients R010 Reactor Kinetics Day 10 R011 Time Dependence and Fission TEST Day ~11 R012 Core Depletion R013 Start-Up and Shutdown Day 12 CP2 Thermodynamics Properties CP3 Thermodynamics Day 13 CPh Thermodynamics and Heat Balance CP8 Heat Transfer Day 1h CP9 Boiling Heat Transfer CP10 Core Thermal Performance
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Day 15 CP11 Core Thermal Performance CP12 Performance and Control TEST Day 16 RP2 Interaction of Radiation RP3 Biological Effects Day 17 RPh Units RP5 Protection Against Radiation Day 18 RP6 Protection Against Contamination RP8 Detection of Radiation Day 19 RPQ Miscellaneous Detectors, Personnel Monitoring PC3 Coolant Parameters Day 20 PCh Chemical Processes TEST Day 21 PC5 Corrosion - Types PC7 Chemistry Control Equipment Day 22 PC8 Radiation Effects - I PC9 Radiation Effects - II Day 23 PC10 Reactor Water Chemistry (BWR)
PC11 Condensate and Feedvater
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Day 2h PC13 Radvaste Handling PC1h Radvaste Discharge Day 25 IC1 Basic Electricity IC2 Basic Electrical Circuits Day 26 IC3 Measurement Methods ICh Process Instrumentation Day 27 ICS Basic Control Systems IC6 Neutron Detection Day 28 Reactor Protection System - BRP OOC Instrumentation Day 29 Incore Instrumentation Feed-Water Controt Day 30 IPR Control BPV Control TEST Day 31 Technical Specifications Review Technical Specifications Review Day 32 Operating Incident. Review Operating Incident Review Day 33 Site Emergency Plan Site Energency Itan
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Day 314
' FINAL EXAM FINAL EXAM Day 35 Simulator Layout Review Simulator Layout Review e
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APPENDIX B
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Big Rock Point 3-Day Simulator Training Program Day 1 A.
Introduction to BWRTC Control Room 1.
Brief system descriptions.
2.
Brief component description.
3 Annunciator system.
B.
Review Start-Up Checks as a Group C.
First Operator Pull Critical From. Mode 2 (144 F, Suberitical) 1._
Students observe response and discuss the following:
a.
Suberitical multiplication.
b.
Administrative requirements for start-up.
c.
Limitations on rate of power increase.
d.
Decay heat production.
2.
Temperature vill be maintained with the shutdown cooling system.
3.
Instructor introduce uncoupled control rod.
Stall computer and
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discuss problem.
4.
Establish heating power and increase moderator temperature to 165*F.
Students observe response and discuss the following:
System heat losses vs heating power.
a.
b.
Overlap of nuclear instruments.
c.
Temperature coefficient.
d.
Pressurization limits.
5 Maneuver through the IRMs until strongly suberitical.
D.
Second Operator Pull Critical From Previous Conditions (l' ode 2) 1.
Students observe response and discuss:
a.
Technical Specifications concerning deviation from predicted critical conditions.
b.
Reactor period. Each student calculate reactor period.
2.
Establish heating power and increase moderator temperature to 165*F. All students plot temperature increase.
Discuss the following:
a.
Minimum temperature for pressurization.
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Minimum operable nuclear instrumentation channels for start-up.
c.
Minimum source range count rate required for start-up.
3 Instructor introduce SRM stuck detector.
h.
Maneuver through IRMs until strongly suberitical.
E.
Third Operator Till Critical From Previous Conditions (Mode 2) 1.
Establish }2ating power and increase moderator temperature to 165*F.
2.
Instructor introduce failure of an IBM channel (fail high).
Discuss effects on continued operation, operator response.
3 Instructor introduce failure of control rod drive hydraulic pump. Discuss effects on continued operation, operator response.
h.
Maneuver through the IRMs until strongly suberitical.
F.
Fourth Optrator Pull Critical From Previous Conditions (Mode 2) and Proceed To 2% crease Temperature to 165*F.
G.
After Attaining Approximately 165*F, the Instructor Shall Re-
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initialize Into Mode 6 (550#, Heating Up) and Have t'he Operator Continue en With System Heatup and Pre'ssurization 1.
Instructor introduce a failure of all bypass valves.(fail valves open). Students monitor system response, using stall function.
Review abnormal procedure and discuss operator response.
H.
Return Simulator to Mode 6 and Have First Operator Continue With Heatup and Pressurization.
1.
After an appropriate delay, introduce the failure of the bypass valves again. Students take corrective action previously I
discussed.
2.
Review the operator's response.
I.
Reinitialize Into Mode 8 (20% Power, Turbine at 1800 r/ min, Not Synchronized).
1.
Instructor review synchronization procedure.
2.
Each student synchronize the generator and pick up initial load.
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D4Y 2 A.
Initialize in Mode 11 (100% Power, Steady-State Xenon) 1.
Instructor introduce loss of one rectreulating pump using stall function. Discuss:
a.
Reactor response.
b.
Power / flow relationship.
c.
Operator response.
2.
Repeat Step A.1 in real time.
B.
Reinitialize Into Mode 11 1.
Instructor introduce a turbine trip using stall function. Discuss:
a.
Reactor response.
b.
Operator response.
2.
Repeat Step B.1 in real time. Operators take appropriate actions.
3.
Instructor review and critique operators' actions.
C.
Initialize Into Mode 9 (45% Power) 1.
Instructor order plant power dropped to below the 45% scram l,
bypass point.
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2.
Instructor initiate turbine trip using stall function. Discuss:
a.
Reactor response, b.
Effect of cold water addition.
c.
Operator response.
3 Repeat Steps C.1 and C.2 in real time.
D.
Initialize Into Mode 11 1
1.
Instructor order a power reduction to 700 MWe.
Each operator to participate in the reduction by inserting in sequence control rods. Discuss:
a.
MCHFR (Minimum Critical Heat Flux Ratio).
b.
Peaking factors.
c.
Control rod worth at power.
2.
Instructor introduce the following conditions and discuss each individually:
a.
Control rod drift-in.
b.
c.
Accumulator failure.
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Feed-water level controller failure.
e.
Total loss of feed pumps.
E.
As Time Permits, the Following Items May Be Covered:
1.
Demonstration of load following with flow control.
2.
Feed-water heater tube leak.
3 Recirculating pump seal failure.
34. Turbine trip without bypass valves.
5 Feed-water regulating valve lockup.
M A.
Initialize Into Mode 15 (Hot Scram Recovery, Suberitical, Xenon Peaking) 1.
One operator to pull critical. All students observe and discuss:
a.
Effects of xenon poisoning on reactor start-ups.
b.
Reactivity balances, changes in critical position.
2.
Each operator pull critical from Mode 15 (Reinitialize after each critical.)
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B.
Initialize Into Mode 17 (Scram Recovery, Critical 8 95% Power, Xenon Burning Out) 1.
Operator ordered to maintain 775 MWe, All' students observe and discuss effects on reactor operations and power production as xenon burns out.
2.
Instructor introduce high-high off-gas activity (in real time).
a.
Operators attempt to recover.
b.
Carry out scram procedure if vacuum is lost.
3 After immediate action portion of scram procedure is completed, the instructor shall stall the computer and critique the high-high off-gas activity drill.
C.
Reinitialize in Mode 11 1.
Instructor introduce a Group I isolation using stall function.
Students observe and discuss:
a.
Reactor response.
b.
Operator response.
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2.
Repeat Step C.'1 in real time. Students gain control of pressure 1
with isolation (emergency) condenser and commence a controlled 1
cooldown.
D.
Reinitialize Into Mode 11, 1.
Instructor introduce rupture in the dry well using stall function.
Discuss:
Integrated response of the emergency core cooling systems, a.
b.
Operator response.
2.
Repeat Step D.1 in real time.
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