ML20030A475
| ML20030A475 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 07/19/1974 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20030A474 | List: |
| References | |
| NUDOCS 8101090620 | |
| Download: ML20030A475 (13) | |
Text
.
l BIG ROCK POINT PLANT LICENSED OPERATOR REQUALIFICATION PROGRAM Objective To assure a continuing high degree of knowledge and pro-ficiency is maintained by AEC licensed operators at the Big Mack 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 perfonn 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 informal and irregular basis. Because of the vsriety of tLaes of original operator license examinations and the in-formal 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 evaluations, the retraining program will 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 program will be extended in length in order to concen-trate on basic fundamentals 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 material to be covered is tabulated in Appendix A of this submittal and in general covers the subjects listed in Paragraph 2C of Appendix A to 10 CFR 55 The classroom work will consist of a reading assignment, video tape viewing, a quiz and a discussion period.
Mk
1 l
2 This applies to each session listed in the outline. An instructor will continually be present during video tape viewing and discussion periods.
Annual ' examinations patterned after the AEC license examina-tion will be administered to determine effectiveness of training efforts and to define areas which require emphasis during lecture programs. An overall grade of 70% on the annual exam must be attained to qualify for performing licensed duties. A person receiving a grade below 70% will be relieved and enter an accelerated training program to upgrade his knowledge to an acceptable level. The scope and duration of the ac-celereted training program will be determined from analysis of results of the individual exams. Persons receiving a grade of greater than 805 in a particular category in the annual exam will not be required to attend the lectures on that material.
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 addi-tion, the simulator will augment on-the-job experience, permitting manipulation of controls in many modes of operation.
It is not intended that the simulator be used for evaluation of performance during abnormal or emergency conditions as re quired in Paragraph hC of Appendix A to 10 CFR 55 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 outline of the three-day simulator course is attached to
'this submittal as Appendix B.
Weekly classroom sessions will 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 discuss systems. This will 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. Examina-tions will be administered at these weekly sessions to evaluate under-standing of the material presented.
(
3 Topical exams will be administered throughout the classroom portions of the program. A minimum grade of 80% will be required for all participants in these examinations.
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 grade of 80% or greater is obtained on
-an examination covering the material.
Evaluation of performance in routine and abnormal operations will be conducted on shift as well as in simulated abnormal conditions.
Evaluation will normally be performed by the person's immediate super-visor. However, a minimum of five exercises, during a given two-year renewal period, will 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 will be routinely administered and documented for record purposes.
Plant control manipulations which demonstrate skill and/or fsniliarity 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 power or greater either by controlled rod movement or reactor recircula-tion flow adjustment.
3 Performing suberiticality and/or shutdown margin checks during fuel handling operations.
4.
Performing control rod drive tests required prior to a reactor start-up after an extended shutdown.
An effort will 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.
The classroom phase for the second and succeeding cycles will 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.
1
(
4 All licensed operators will review procedure changes, facility changes, abnormal occurrence reports. Technical Specifications changes, license changes, and other commitments and sign off that they have seen this material. These items will be discussed during the weekly class-room sessions, 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 will be maintained in this file. Exams and exam answers will be maintained by the training coordinator.
Schedule 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 will be two years in length.
General The program described above will be implemented by the plant superintendent. Execution, coordination, record keeping, etc, will be the responsibility of the training coordinator.
t i
i i
s APPENDIX A Big Rock Point Retraining Program The first cycle of classroom work in basic fundamentals will 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.
Day 1 MS Slide Rule Use M6 Log Base Day 2 MS 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 BNP14 Reaction Rates 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 Coefficients 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 l
i
/
v i
2 l
l 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 RP9 Miscellaneous Detectors, Personnel Monitoring PC3 Coolant Parametera Day 20 PCh Chemical Processes TEST Day 21 PC5 Corrosion - Types PCT Chemistry Control Equipment Day 22 PCB Radiation Effects - I PC9 Radiation Effects - II Day 23 PC10 Reactor Water Chemistry (BWR)
PC11 Condensate and Feedvater Dgr 24 PCl3 Radvaste Handling PC1h Radwaste Discharge Day 25 IC1 Basic Electricity IC2 Ecsic 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 000 Instrumentation Day 29 Incore Instrumcatation Feed-Water Control 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 Emergency Plan
j i
3 Day 3h FINAL EXAM FINAL EXAM Day 35 Simulator Layout Review Simulator Layout Review e-
1..
APPENDIX B Big Rock Point 3-Day Simulator Training Program DRY l
' A.
Introduction to BWRTC Control Room 1.
Brief system descriptions.
2.
Brt:f component description.
3 Annunciator system.
B.
Review Start-Up Checks as a Group C.
First Operator Pull Critical From N de 2 (144*F, Suberitical) 1.
Students observe response and discuss the following:
a.
Suberitica1. s altiplication.
b.
Administrative requirements for start-up.
c.
Limitations on rate of power increase.
d.
Decay heat production.
2.
Temperature will be mcintained 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 1656F.
Students observe responso and discuss the following:
a.
System heat losses vs heating power.
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 (Mode 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.
t
+
2 b.
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 Pull Critical From Previous Conditions (Mode 2) 1.
Establish heating power and increase moderator temperature to 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.
14. Maneuver through the IRMs until strongly suberitical.
F.
Fourth Operstor Pull Critical From Previous Conditions (Mode 2) tad Proceed To Increase Temperature 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 Heatup 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 an appropriate delay, introduce the failure of the bypass valves again. Students take corrective action previously discussed.
2.
Review the operator's response.
I.
Reinitialize Into Mode 8 (20% Power, Turbine at 1800 r/ min, Not Synchronized).
1.
Instructor review synchronizatiota procedure.
2.
Each student synchronize the generator and pick up initial load.
i i
5 i
.r 3
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.
Reac+7r 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 Ell functica. Discuss:
a.
Reactor response.
b.
Operator response.
2.
Repeat Step B.1 in real time. Operators tai sppropriate actions.
3 Instruccor review and critique operators' act.
1s.
C.
Initialize Into Mode 9 (45% Power) 1.
Instructor order plant power dropped to below th 45% scram bypcss point.
2.
Iastructor initiate turbine trip using stall funct_.n.
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.
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 individ.ually:
a.
Control rod drift-in.
b.
c.
Accumulator failure.
(
h d.
Feed-water level controller failure, e.
Total loss of feed pumps.
E.
As Time Pennits, 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.
4.
Turbine trip without bypass valves.
5 Feed-water regulating valve lockup.
Day 3 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 critier.1 position.
2.
Each operator pull critical from Mode 15 (Reinitialize after each critical. )
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.
1 5
2.
Repeat Step C.1 in real time. Students gain control of pressure with isolation (emergency) condenser and cossnence a ec.,,, trolled 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.
2 6
o AEC DISTR
. rTC;LPOR P!.RT 50 DOCKET MATERI,.
6757 (TEriPCRARY FOPJ:)
C0ilTROL N0:_
FILE:
FROM:
DATE OF DCC DATE REC'D LTR TWX RPT OTHER Consumers Power Company Jcckson, Michigan 49201 R21ph B. Sewell 7-19-74 7-24-74 X
TO3
SENT LOCAL PDR X
M.
colline 1 efecea CLASS UNCLASS PROP INFO INPUT NO CiS REC'D DOCKET NO:
XXXXX 1
50-155 DESCRIPTION:
ENCLOSURES:
Ltr trans the following:
Big Rock Point Plant Licensed Operator Requalification Program.
p,,,,,, -. m r ~~ ~ -
( 40 cys rec'd)
- r. v d - '-
^ - * - "
D6 Not Rmre PLANT NAME:
Big Rock Point Plant FOR ACTION /INFOPl!ATION 7-24-74 A'
BUTLER (L)
SCIMENCER(L)
/IDIANN(L)
REGAN(E)
W/ 5 opies W/ Copics W/ Copies W/ Copies C
CLARK (L)
STOLZ(L)
DICKER (E) p P. COLLINS
- /.~..;.f a n W/ Copies W/ Copies W/2 Cop'es PAKK(LJ VAb b ALW(L')
MiU ttWN (5')
W/ Copies W/ Co,4es W/ Copies W/ Copies KNIEL(L)
PURPLE (L7 YOUNGBLOOD(E)
W/ Copies W/ Copics W/ Copies W/ Copics N
INTERNAL LTSTRIEUTICN G FILp TECH REVIEW DENTON LIC ASST A/T IND A t;u rv4 HENDRIE GRIMES BRAITMAN
' OGC, ROOM P-506A SCHROEDER GAMMILL A IGGS (L)
SALTZMA'i MUNTZING/ STAFF MACCARY KASTNER GEARIN (L)
B. HURT CASE KNIGHT BALLARD GOULROURNE (L) pggg GIAMBUSSO PAWLICKI SPANGLER KREUTZER (E)
MCDONALD BOYD SHA0 LEE (L)
CHAPMAM MOORE (L)(IGR)
STELLO ENVIRO MAIGRET (L)
DEYOUNG(L)(FWR)
HOUSTON MULLER REED (E)
OU SKOVHOLT (L)
NOVAK DICKER SERVICE (L)
AGLLER(L)(Ltr)
ROSS KNIGH'"0N SHEPPARD (L)
D. THOMPSON (2)
Ps COLLINS IPPOLITO YOUNGBLOOD SLATER (E)
KLECKER DENISE TEDESCO REGAN SMITH (L)
EISENHUT FAG OPR LONG PROJECT LDR TEETS (L)
LAINAS WILLIAMS (
/1LE& REGION (3) h h h
@III @ItIN ;1I MORRIS BENAROYA HARLESS WILSON (L) lM [g H H fl I
E SIZELE VOLU!ER
" " " ' " ' s W I 15.
~ ' - -
EXTERNAL DIST'M2UHON A - LOCAL FDR Charlevoix, Mich.
- TIC (ABERNATHY)
(1)(2)(10)-NATIONAL LAB'S 1-PDR-SAN /LA/NY 1 - USIC(3UCHANAN) 1-ASLBP(E/W FIdg,Rm 529) 1-LIBRARIAN 1 - ASLB 1-W. PENNINGTON, Rm E-201 GT BROOKMVEN NAT. LW I - P. R. DAVIS (AEROJET NUCLEAR) 1-CONSULT'.NT'S 1-AC'iED(Ruth Gurse d
- CYS ACRS E:nmF:cg SENT TO LIC /SST.
NEW iARK/ LLlliE/.iGBABI AN Rt-F-12 7. GT.
R. DIGGS FOR D ST 1-GERALD ULRIKSON.. 0mit 1-RD.. MULLER..r '309 Gi 1-B & M SWINEBRCAD, Rm E-201 GT pl'
._