ML20030A417
| ML20030A417 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 12/17/1973 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20030A416 | List: |
| References | |
| NUDOCS 8101090459 | |
| Download: ML20030A417 (11) | |
Text
5 BIG ROCK POINT PLANT LICENSED OPERATOR REQUALIFICATION PROGRAM Objective To assure a continuing high degree of knowledge and proficiency is maintained in AEC licensed operators at the Big Rock Point Plant.
Applicability Applies to plant personnel that are licensed operators (RO) or senior operators (SRO) that are required to routinely supervise plant evolutions or perform control manipulations as well as those RO or SRO that perform such duties on an infrequent basis.
Background
The Big Rock Point Plant has been in operation for approxi-mately eleven years. Training and retraining efforts have been con-ducted in the past on an infonnal and irregular basis. Because of the variety of times of original operator license examinations and the informal training program, Consumers Power Company personnel evaluated the level of knowledge and proficiency of Big Rock Point Plant licensed operators prior to formulating the retraining program described herein.
As a result of these evaluatio'ns, the retraining program will be conducted during the first cycle that places an expanded emphasis on areas requiring theoretical knowledge.
Program During the first retraining cycle, the classroom portion of the program will be extended in length in order to concentrate on basic fun-dmnentals and application of theory. The first cycle will consist of seven weeks of classroom work, utilizing selected units from a commercial video tape program with a full-time instructor. An outline of the mate-rial to be covered is tabulated in Appendix A.
The classroom work will consist of a reading assignment, video tape viewing, a quiz and a dis-cussion period. This applies to each session listed in the outline.
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2 The classroom work will be coupled as closely as practical with a three-day course at a BWR simulator. The simulator will be used to demonstrate the principles covered in the classroom sessions.
In addition, the simulator will augment on-the-job experience, permitting manipulation of. controls in many modes of operation. 'The General Electric Boiling Water Reactor Training Center (GE BWRTC) simulator "will be used during the first two-year cycle and the results evaluated to determine the advisability of further simulator sessions. An out-line of the three-day simulator course is attached as Appendix B.
Weekly classroom sessions vill be conducted when full-time classroom work is not in progress to review facility changes, procedure changes, operating incidents, Technical Specifications changes, license changes, other commitments and discussion on systems. This vill result in a given shift having one day of classroom work each five weeks plus the full-time classroom session of seven weeks for the first cycle.
Examinations will be administered at these weekly sessions to evaluate understanding of the material presented.
Evaluation of performance in routine and abnormal operations will be conducted on shift as well as in simulated abnormal conditions.
Evaluation will be performed by supervisory personnel.
Annual examinations will be utilized to determine the effective-ness of the program and to determine areas to receive concentration of effort. Should a person appear marginal or significantly below the ex-pected level of competence at any of the evaluation checkpoints, in-cluding the annual examination, he vill be given appropriate accelerated training to upgrade his performance to an acceptable level.
Participation in the lecture series on fundamentals and weekly classroom sessions will be in accordance with the following guidelines:
1.
An examination vill be available, on request, covering specific topics and material.
If a person takes this examination and receives a grade of 80% or greater, he need not participate in the lectures on that particular topic.
3 Participants in the lecture series must receive a minimum grade of 70% for Ros and 75% for SR0s for satisfactory completion of the material.
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3 3.
Individuals must attend a minimum of 75% of the weekly lectures during a two-year. cycle to qualify for renewal of their licenses.
-Credit for attendance will be given if a satisfactory grade is obtained -
on an examination covering the material.
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The disparity between the satisfactory grade for participating
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- students and the bypass grade is to ensure individuals bypassing ses-j_
sions bave a high leve3 of knowledge.
Plant control manipula'. ions 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.
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2.
Change of reactor power of 25% of full power or greater ei-ther by controlled rod movement or reactor recirculation flow adjustment.
- 3.. Performing suberiticality and/or shutdown margin checks
.during fuel handling operations.
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Performing control rod drive tests required prior to a j
reactor start-up after an extended shutdown.
The classroom phase for the second and succeeding cycles vill be three weeks instead of seven weeks. The emphasis will be reduced in the' areas of basic fundamentals and application of theory as compared to the first cycle.
i Schedule l
The first retraining cycle was considered to have started in July 1973 (for record purposes, July 1) with the administration of an evaluation examination. Each cycle-vill be two years in length.
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6 APPENDIY A Big Rock Point Retraining. Program t-The first : cycle of classroom work in basic fundamentals.will J.
- follow the schedule tabulated below. Classroom session will 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.
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Day 1 M5 Slide Rule Use M6 Log Base Day 2 M8:
Algebra Applications l
M9
. Algebra Day 3 Mll General Science M12 General Science Day 4 M13 General Science
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BNP10 Radioactive Decay I
Day 5 BNP13 Cross Sections BNPlh Reaction Rates i
TEST - 1/2 Day I
Day 6 BNP15 Neutron Spectrum and Energy Effects BNP16 Neutron Slowing Down i
R' h h-Factor Formula Day 7 O
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R05 4-Factor Formula "
Day 8 R06 Buckling and Leakage j
E08 Reactor Control
-L Day 9 R09 Reactivity Coefficients RO10 Reactor Kinetics Day 10 R0ll Time Dependence and Fission TEST Day-ll 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 14 CP9 Boiling Heat Transfer CP10 Core Thermal Performance I
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Day-15 CP11 Core Thermal Performance CP12 P _*formance 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 Contanination RP8 Detection of Radiation a
Day 19 RP9 Miscellaneous Detectors,' Personnel Monitoring PC3 Coolant Parameters Day 20 PCh Chemical Processes TEST Day 21 PC5 Corrosion - Types PCT Chemistry Control Equipment Day 22 PC8 Radiation Effects - I PC9 Radiat'.on Effects - Il Day 23 PC10 Reactor Water Chemistry (BWR)
PC11 Condensate and Feedwater Day 2h PCl3 'Radwaste Handling PC1h Radwaste Discharge Day 25 ICI Basic Electricity IC2 Basic Electrical Circuits Day 26 IC3 Measurement Methods ICh Process Instrumentaticn Day 27 ICS Basic Control Systems IC6 Neutron Detection Day 28 Reactor Protection System - BRP f
OOC Instrumentation Day 29 Incore Instrumentation Feed-Water Control Day 30 IPR Control BPV Control TEST I
Day 31 Technical Specifications Review Technical Specifications Review i
Day 32 Operating Incident Review Operating Incident Review Day 33 Site Emergency Plan Site Emergency Plan
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Day 314 FINAL EXAM FINAL EXAM Day 35 Simulator Layout Review Simulator Layout Review
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APPENDIX B Big Rock Point 3-Day Simulator Training Program Day 1-A.
Introduction to BWRTC Control Room
~1.
Brief systen descriptions.
2.
Brief component description.
3 Annunciator system.
B.
Review Start-Up Checks as a Group C.
First Operator Pr.11 Critical From Mode 2 (lh'4 F,Suberitical) 1.
Students observe response and discuss the following:
a.
Suberitical multiplication, b.
Administrative requiremente for start-up.
c.
LLaitations on rate of power increase.
d.
Decay heat production.
2.
Temperature will be maintained with the shutdown cooling system.
3.
Instructor introduce uncoupled control rod. Stall computer and discuss problem.
4.
Establish heating power and increase moderator temperature to 165 F.
Students observe response and discuss the following:
a.
System heat losses vs heating power.
b.
Ov rlap of nuclear instrument's.
c.
Temperature coefficient.
d.
Pressurization limits.
3 Maneuver through the IRMs until strongly suberitica3.
D.
Second Operator Pull Critical From Previous Conditions (Mode 2) 1.
Students observe response and discuss:
a.
Techrical 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.
Mintmwn temperature for pressurization.
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b.
Minimum operable nuclear instrumentation channels for start-up.
c.
Minimum source range count rate required for start-up.
- 3. -Instructor introduce SEM stuck detector.
h.
Maneuver through IRMs until stron6ly suberitical.
E, Third Operator Pull Critical From Previous Conditions (Mode 2) 1.
Establish heating power and increase moderator temperature to
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165 F.
2.
Instructor introduce failure of an IRM 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 Operator J Critical From Previous Conditions (Mode 2) and Proceed To Increa; emperature to 165 F.
G.
After Attaining Approximately 165 F, the Instructor Shall Re-initialize Into Mode 6 (550#, Heating Up) and Have the Operator Continue on With System Hee. tup and Pressurization 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 t.n appropriate delay, introduce the failure of the bypass valves again. Students take corrective action praviously discussed.
2.
Review the operator's response.
I.
Reinitialize Into Fade 8 (20% Power, Turbine at 1800 r/ min, Nos Synchronized).
I 1.
Instructor review synchronization procedure.
2.
Each student synchronize the generator t i pick up initial load.
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t Day 2
-A.
Initialize'in Mode 11-(100% Power, Steady-State Xenon) 1.
Instructor introduce loss of one recirculating 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 bypass point.
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 l.
Instructor order a power reduction to 700 MWe.
Each operator to participate in the reduction by inserting in sequence control rois. r'.ccuss:
MCH/R (Minimum Critical Heat Flux Ratio).
a.
b.
Peaking factors.
i a.
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 Penmits, the Following Items May Be Covered:
1.
Demonstration of load following with flow control.
Feed-water h'ater-tube leak.
2.
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- 3. -Recirculating pump seal failure.
4.
Turbine trip without bypass valves.
5 Feed-water regulating valve lockup.
Day 3 A.
Initialize Into Mode 15 (Hot Scram Recovery, Subcritical,- 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 it. critical position.
2.
Each operator pull critical from Made 15 (Reinitialize after each critical.)
B.
Initialize Into Mode 17 (Scram Recovery, Critical @ 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 immedia. e 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 with isolation (emergency) condenser and commence a controlled cooldown.
i 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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AEC D7 ?.IP.UTION FOR PART 50 DOCTET MJ NIAL (TE!!PORARY FOPJf)
CONTROL NO: 9114 FILE:
FROM:
!!D 0 RPT OTIER Consumers Pcwer Company J ckson, Michigan 49201 12-17-73 12-21-73 X
R. B. Sewell TO:
D. J. Skovholt 1 sighed SENT LOCAL PDR X
CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NG:
XXX 40 50-155 DESCRIPTION:
ENCLOSURES:
Ltr trans the following:
Requalification Program
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PLANT NAME: Big Rock Point
( 1 Orig 6 39 cys rec'c: )
FOR ACTICN/INF070GTION 12-26-73 GC LUTLER(L)
SCir4ENCER(L)
/IDIANN(L)
REGAN(E)
W/ Copics W/ Copics W/ 5 Copies (info)
W/ Copics CLARK (L)
STOLZ(L)
DICIER (E) vP. COLLINS W/ Copies W/ Copies W/ Copies W/ 2 Copies COLLER(L)
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SCHEMEL(L)
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W/ Copies W/ Copies W/ Copics W/ Copies INTER"AL DISTRIEUTION
/IG FILE TECH REVIEW DENTON A/T IND M EC PDR HENDRIE GRIMES LIC ASST BRAI'D1AN OGC, ROOM P-506A SCHROEDER CAMM1LL dIGGS (L)
SALTZMAN r.
HURT MUNTZING/ STAFF ltACCARY KASTNER GEARIN (L)
CASE KNIGHT BALLARD GOULBOURNE (L) pgg GIAMEUSSO PAULICKI SPAl:GLER LEE (L) 1 CDC iALD BOYD SHA0 MAICRET (L)
DUBE M60RE (L)(EN'R)
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/ EG OPR TEDESCO REGAN WILLIAMS (E)
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(1)(2)(10)-NATIONAL LAB'S 1-PDR-SAN /LA/NY 4 - NSIC(EUCF'. NAN) 1-ASLUP(E/W Bld;.Rm 529) 1-GERALD LELLCUCHE 1 - ASLB(YORE /SAYRE/
1-W. PENNINGTON, Rm E-201 GT BRC0KHAVEN NAT. LAB
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12-26-73 DIGGS 1-GERALD ULRIKSON...ORNL l-RD.. MULLER..F-309
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