ML18047A324

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Requalification Program - Reactor Operator & Senior Reactor Operator.
ML18047A324
Person / Time
Site: Palisades, Big Rock Point, 05000000
Issue date: 05/03/1982
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18047A321 List:
References
1302, NUDOCS 8205170393
Download: ML18047A324 (17)
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Text

NOTD A200*06*26*

NUCLEAR OPERATIONS TRAINING DEPT PROC NO. 1302 MASTER PROCEDURES/PROGRAMS MANUAL PAGE 1 OF l'7 REVISION o TITLE: *Requalification Program - Reactor Operator consumers POwer & Senior Reactor Operator DATE 05/03/82 I. PURPOSE The purpose of this program is to establish an effective requalification program for Reactor Operators and Senior Reactor Operators.

II. SCOPE This program applies to all Nuclear Regulatory Commission (NRC) licensed operators at Consumers Power Company (CPCo) nuclear facilities who perform licensed activities. The program is also applicable to instructors who teach integrated nuclear plant operation.

III. PR~REQUISITES Licensed Reactor Operators/Senior Reactor Operators of CPCo nuclear facilities who are assigned shift functions as Reactor Operators or Senior Reactor Operators shall participate in this program. Persons who maintain Reactor Operator or Senior Reactor Operator licens_e*s to provide backup capability to the operating staff shall participate in the requalification program except to the extent their normal duties preclude the need for training in specific areas.

IV. REFERENCES ANS 3.1 Rev. 1981 - Selection and Training of Nuclear Power Plant Personnel ANS 3.4/ANSI N546 1976 - Medical Certification and Monitoring of Personnel Requiring Operator Licenses at Nuclear Power Plants 10 CF,R 55 Appendix A - Operator Licenses INPO Guideline GPG-02-10 Guidelines for Qualification Programs for Nuclear Power Plant Licensed Operators NODS-A02 - Training for Nuclear Operations Department Personnel NODS~Al2 - Personnel Selection, Qualification and Certification V. PROGRAM - REQUALIFICATION (RO) - (SRO)

This program is established to review areas of knowledge necessary for safe plant operation and to cover recent operating experiences and operational changes. This program shall be conducted on a cyclic basis not to exceed two years. Successive requalification programs shall be conducted on a schedule so that a continuing program exists. The program shall be reviewed, evaluated, and updated on a two-year basis. Lessons learned from plant or industry experience shall be factored into the requalification program. Fixed performance standards and remedial training requirements, in the event of training deficiencies, shall be established. The requalification training program schedules may be adjusted to cover speciai nuclear plant operating conditions or significant nuclear industry operating experiences. The requalification program contains four segments. These segments are A) Pre-planned Lecture Series, B) Skills Training and Evaluation, C) Operational Review Program, and D) Annual Examination and Evaluation. Each segment is described separately. Approved~{i)\\.,:t: ,,1(~

82 0 5 17 0 J~~ Director NOTD Date

NOTD A200*06*26*

NUCLEAR OPERATIONS TRAINING DEPT PROC NO. 1302 MASTER PROCEDURES/PROGRAMS MANUAL PAGE 2 OF 17 REVISION o TITLE:* Requalification Program - Reactor DATE 05/03/82 consumers POwer Operator and Senior Reactor Onerator

v. PROGRAM - REQUALIFICATION (RO) - (SRO)

A, Preplanned Lecture Series The pre-planned lecture series shall include training sessions conducted on a regular and continuing basis. A minimum of twelve (12) lectures shail be scheduled and attended every two years.

Topics presented in the lecture series are selected on an as-needed basis reflecting the general results of the annual examinations, input from the Operations Department supervisory personnel and available operational experience information. Examination shall be administered after each lecture with a performance standard of 80% expected. Students who do not meet the performance standard shall complete remedial training within six weeks.

Such training content will be determined by the Training Department and Operations Department at the nuclear plant.

Topics to be addressed on an as-needed basis are:

1. Theory and Principles of Reactor Operation 2.* Heat Transfer, Fluid Flow and Thermodynamics
3. Features of Facility Design including Plant Systems
4. General and Specific Plant Operating Characteristics including Expected Response to Equipment Failure
5. Plant Instrumentation and Cqntrol Systems
6. Plant Protection Systems
7. Epgineered Safety Systems
8. Radiation Control and Safety
9. P).ant Chemistry

~O. Applicable Portions of Title 10 Code of F~deral Regulations

11. Fuel Handling and Core Parameters
12. Normal, Abnormal and Emergency Operating Procedure
13. Technical Specifications
14. Administrative Procedures, Conditions, and Limitations
15. Major Operational Evolutions
16. Facility Design and License Changes
17. Procedure Changes
18. Operating History and Problems
19. Related.Nuclear Industry Operating Experience B. Skills Training and Evaluation Each NRC licensed individual shall demonstrate proficiency in Plant Manipulations and Evolutions, Nuclear Plant Simulator Exercises and Plant Performance Evaluations. Reactor Operators shall manipulate controls while Senior Reactor Operators may either manipulate or actively supervise manipulation of the nuclear plant controls. The nuclear plant control room or a suitable simulator will be used for this training. Individual and tea.~ efforts shall be emphasized. Lecture sessions conducted in conjunction with a simulator training praRram. covering Approved: =il.i~~l'D
  • 9 NOTO A200*06*26*

.@ NUCLEAR OPERATIONS TRAINING DEPT PROC NO. 1302 MASTER PROCEDURES/PROGRAMS MANUAL PAGE 3 OF '.1-7

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W1 REVISION o TITLE:* Requalification Program - Reactor consumers Power Operator and Senior Reactor Operator DATE 05/03/82 topics designated in the Lecture series may be credited toward fulfilling the requirements of Section V. A.

1. A minimum of ten.(10) reactivity changes per two year period shall be obtained either on the individuals assigned nuclear plant or an approved simulator. No more than six (6) shall be the same manipulation. At least three (3) different manipulations must be undertaken by each individual. The Control Manipulations creditable for reactivity changes for both BWR and PWR are listed in Attachments A and B.
2. On an annual basis, each licensed individual shall participate in the .plant evolutions as listed in Attachment C.

These plant evolutions will be performed at the assigned nuclear plant or at an approved_ plant simulator.

3. On an annual basis, each licensed individual shall participate in training exercises covering the plant abnormal/emergency conditions as applicable to plant design, either at an approved nuclear plant simulator or during plant drill programs.

Tb,ese exercises are listed in Attachment D.

4. On a two-year basis, each licensed individual shall participate in training exercises covering off normal/emergency procedures for the nuclear plant either at an approved nuclear plant simulator or during the plant drill program. These exercises are listed in Attachment -E_--
5. On a biennial basis, each NRC licensed individual shall participate in walk-through plant drills in off normal/emergency procedures which are not specifically addressed or conducted at an approved nuclear plant simulator. Credit shall be given for documented satisfactory participation in an actual off-normal or emergency condition.. Team effort should be emphasized. All drills, either simulated or actual, shall emphasize Plant Technical Specifications and Procedures.
6. All plant drills shall include as a minimum the following items:
a. Reviewing plant procedure steps
b. Identifying actions to establish stable plant conditions
c. Identifying equipment control locations and functions
d. Identifying expected plant instrun~entation and alarm response
e. Reviewing communications needed to gather information or coordinate team actions
f. Identifying supplementary actions ,aimed at mitigating results or causes of plant abnormal/emergency conditions A.

~

Approved~ G..V Director NO'l'D

-~

NOTO A200*06*26*

NUCLEAR OPERATIONS TRAINING DEPT PROC NO. 1302 MASTER PROCEDURES/PROGRAMS MANUAL PAGE 4 OF 17 REVISION o TITLE:* Requalification Program - Reactor consumers Power Operator and Senior Reactor Ouerator DATE 05/03/82 Plant drill scenarios shall be carefully planned and monitored in order to evaluate individual or team response to the drill conditions.

7. Skills evaluation Each licensed individual's performance shall be evaluated during 1) nuclear plant simulator exercises and 2) plant drills. Evaluations shall be either "satisfactory" or "unsatisfactory". If unsatisfactory, the training supervisor and the licensed individualB supervisor shall make the recommendations to upgrade the individuals performance to a satisfactory level. The training supervisor shall notify the plant manager, individuats supervisor, and the Director-Nuclear Operations Training Department, of individuals who are delinquent in skills training as listed in this section.

Recommendations shall be made at this time regarding the licensed individual~ removal from licensed activities.

C. Operational Review Program

    • @ - This portion of the Requalification Program provides for on-shift review of operational experiences at CPCo nuclear plants fi.s well as throughout the industr~, plant modifications, ~rocedure changes and plant license changes. It is a means of disseminating new or changing information on a short-term basis. Care shall be exercised that only pertinent information is used in this required review program.
1. Modification Review A continuing on-shift review shall be maintained so that licensed operators (RO and SRO) review plant design changes, equipment modifications, procedure changes, and technical specification changes. These changes shall be reviewed pertinent to the basis for changes and their effect on plant operation. This information shall be routed on a formal license review form which require9 acknowledgement and understanding of the material by signature and date. Changes to emergency procedures, technical specifications pertinent to plant operations, and plant modifications shall be reviewed prior to the licensee assuming shift operation responsibilities.

The on-shift supervisor (SRO) shall provide guidance to the licensed operators in reviewing the changes and modifications.*

Expanded review of the changes and modifications shall be conducteq during the operational Proficiency Lecture Series.

A v

Approved :~Ql\lr Director NOTD Date

NOTD A200*06*26*

NUCLEAR OPERATIONS TRAINING DEPT PROC NO. 1302 MASTER PROCEDURES/PROGRAMS MANUAL PAGE 5 OF17 REVISION o TITLE: Requalification Program - Reactor consumers Power Operator and Senior Reactor Operator DATE 05/03/82

2. Operating Experience Review Program A continuing system shall be utilized so that each licensed individual reviews operating experience from his/her nuclear plant as well as operating experiences from applicable segments in the nuclear industry. Selection of the information shall be by the'Shift Technical Advisors/Shift Engineers, Operation Superintendent, and Training Supervisor. Sources for such information are Licensee Event Reports, Audits, Evaluations, inspection reports, NSAC/INPO Significant Event Reports and publications and ~eriodicals covering nuclear industry information. This information shall be routed on a formal licensee review form which requires acknowledgement and understanding of the material by signature and date.

Expanded review of the operating experiences shall be conducted during the Operational Proficiency Lecture Series.

D:~ Annual Requalification Examinations An annual written and oral examination shall be administered A to all licensed individuals. These examinations shall be used w to assist in determining an individual's current knowledge of his licensed activities, knowledge of information covered in previous requalification lectures, and proyi.de a basis for future requalification lectures and training.

1. The written exam shall contain questions on topics listed in Attachment F-. The written examinations should be structured to the level of questions consistent with the individual license activities (RO or SRO). Questions and answers shall be reviewed by the Training Supervisor and the Operations Su:perintlendent prior to use. Licensed personnel who compose the annual examination and answer keys are not required to write an annual examination unless directed by the licensed individual's supervisor. If required to write the annual exam the individual shall take a written examination of similar depth composed by the Plant Training Supervisor or a Senior Staff Supervisor.

A different written exam and answer key shall be used each year. The Training Supervisor or his/her delegate shall grade and review the ex;amination with each licensee. A licensed individual who receives less than 70% in any category on the written exam or an overall grade less than 80%, shall be placed in an accelerated t.raining program Within fi Ve days Of_determinatinn R,nd rP.ViF.!i.r ()f thP. .Q"rades tn 6!!A upgrade his knowldege~ The licensed individual shall then w be issued another written exam covering the categories of less than 70%, or a complete examination, whichever is determined appropriate by the Operatio~uer*~tendent and Approved:-f~-=-=--~~~~~.><.::::;-----.~~~

NOTD A200*06*26*

.@ NUCLEAR OPERATIONS TRAINING DEPT PROC NO. 1302 MASTER PROCEDURES/PROGRAMS MANUAL PAGE 6 OF 17 REVISION o TITLE:* Requalification Program - Reactor consumers Power Operator and Senior Reactor Operator DATE ,05/03/82 the Training Supervisor. During the accelerated training review, the licensed individual shall be removed from his work activities until he/she has requalified to a satisfactory level.

2. An annual oral exam shall be administered to each licensed individual. It shall contain questions on topics listed in Attachment "G". The Training Supervisor and Operations Superintendent shall establish the oral examination so that all oral exams are conducted in a timely fashion. The oral examinations may be conducted by individuals or an oral board composed of several individuals. Persons who conduct oral examinations shall hold NRC-SRO licenses, or shall have successfully completed education and training ~rograms required for a senior operators license. However, individual portions of the Oral Examinations may be conducted by persons not meeting the above qualifications if the examination and results are thoroughly reviewed by the Training Supervisor at the nuclear plant. Each oral examination shall be structured for a time of no less than two hours: The oral examination shall include the activities of the licensed person in the control room and plant areas where operators carry out actions directed by the licensed operator. Failure of an oral examination will require an accelerated training program in the areas of .deficienci~s a.rid re-examination in these areas within two weeks.of the determination of deficiencies. The Training Supervisor shall keep the Plant Manager/Superintendent informed of examination results and deficiencies.

E', Special Req_ualification Programs

1. The accelerated Requalification Program is directed to licensed individuals who have shown deficiencies in the four categories of requalification training described in VA, B, C, D of this program. The content of the accelerated program shall be specifically structured to upgrade the knowledge and skills identified as deficient. The Training Supervisor shall be responsible for the development and a~proval of the accelerated requalification program. The performance standard shall be at least 80% in each written category and a satisfactory result in each oral category.
2. If a licensed individual has not fulfilled his licensed activities for a period in excess of four months, he shall enter an accelerated training program,. des"igned under the auspices of the Training Supervisor, prior to assuming his/

her licensed activities. Oral and written exams shall be administered with a satisfactory passi~e; grade prior to

. .~pproved~(i),\b,t i!~:- ;

  • Director NOTD 1

NOTD A200.*06*26*

A

.@) NUCLEAR OPERATIONS TRAINING DEPT MASTER PROCEDURES/PROGRAMS MANUAL PAGE 1 OF 11 TITLE: *Requalification Program - Reactor PROC NO. 1302 REVISION O consumers Power Operator and Senior Reactor Operator DATE D'5/03/82 assuming licensed activities. Performance requirements are identical to the annual examination requirements.

3. Newly licensed individuals shall enter the requalification program upon receipt of their.licenses. Any individual newly licensed(within six months of the annual requalification written and oral exams) may be excused from the examination "

for that year.

F. Requalification Program Evaluation The requalification program shall be reviewed and evaluated on a biennial basis by the Training Supervisor and the Operations *superindendent. Changes to the program shall be formalized and implemented at this time. Input into the

_ requalification program review shall be from annual examinations, candidate and instructor interviews, interviews -~ith-plant management, and audits conducted by regulatory agencies-and Consumers Power Company audit personnel.

G, Requalification Program Records Records of licensed individuars performance shall be maintained under the direction*of t~e Plant Training Supervisor. They shall be maintained in an auditable fashion. Such records are as follows:

1. Oral and written examination results
2. Written examinations and answer keys
3. Lecture Series attendance records
4. Lecture Series lesson plans
5. Plant drill participation records
6. Reactivity manipulation and plant.evolution records
7. Simulator training records
8. Operational review series participation records
9. Special programs pertaining to licensee activities Records shall be maintained for a minimum of the five most recent years for each licensed individual at a nuclear plant.

Approved:~{)..:>\\,;t=- ~l~{fL

birector NOTD Date

I NOTO A200*06*26*

NUCLEAR OPERATIONS TRAINING DEPT PROC NO. 1302 MASTER PROCEDURES/PROGRAMS MANUAL PAGE 8 OF 17 REVISION o TITLE: *Requalification Program - Reactor consumers Power Operator and Senior Reactor Operator DATE 05/03/82 ATTACHMENT A Reactivity Manipulation Exnerience - BWR

a. Critical approach from a sub-critical condition and increasing power to the point of adding heat
b. Critical approach from a sub-critical condition and increasing power but not to exceed .1 : MWt (head-off refueling exercise) , .
c. Changes of reactor power of 10% of full power or greater, either by control rod movements or reactor recirculation flow changes
d. Performing sub-criticality and/or shutdown margin checks during fuel-handling operations or after 35,000 MWd total exposure on the core

~ e. Performing control rod drive tests* required prior to a

~ startup a~er an extended shutdown

f. Performing control rod dr-~ve tests required semi-annually, annually or at each major refueling operation Approve~{l_"}\\i.j"- ~hfri, Director NOTD Date

NOTO A200*06*26*

.(@ NUCLEAR. OPERATiONS TRAINING DEPT MASTER PROCEDURES/PROGRAMS MANUAL PAGE g OF 17 TITLE:*Requalification Program - Reactor PROC NO. 1302 REVISION o consumers Power Operator and Senior Reactor Qperator DATE 05/03/82 ATTACHMENT

  • B*

Reactivity Manipulation Experience - PWR

a. Manual control of the reactor during dilution or boration maintaining reactor power. Reactivity change required will be a minimum of o.01%r'
b. Manual control of the reactor maintaining stable reacto~

power during a xenon transient for one hour or more.

Manipulation must be performed in the first 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> of a transient following a power change of 25% or greater.

c. Change in core reactivity by the operator of 0.1%,,.0 in less than one ho~r for any reason utilizing either control rods or boric acid control.
d. Change of reactor power greater than 10% of full power in one hour or less.

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~ e. Attendance at plant controls during and immediately following a plant trip from power level greater than 10%.

f. Operation of the plant controls during any major step in startup or shutdown, for example:
1. Startup from cold shutdown to hot standby
2. Critical approach from hot standby
3. Turbine generator startup from hot standby
4. Plant loading from synchronization
5. Plant shutdown from power to hot standby
6. Plant cooldown from hot standby
g. Control of steam generator levels from synchronization to 15% power including transfer to automatic.
h. Manual reactor control from synchronization to 15% power, including transfer to automatic.

~

Vil Approved~~~

Director NOTD Date

NOTO A200*06*26*

.@ NUCLEAR OPERATIONS TRAINING DEPT MASTER PROCEDURES/PROGRAMS MANUAL PAGEio OF 17 TITLE:Req_ualification Program - Reactor Operator PROC NO. 1302 REVISION o consumers PDwer & Senior Reactor Operator DATE 05/03/82 ATTACHMENT C Nuclear Plant Evolutions - Annual

l. Reactor plant startup to the point of reactivity feedback from nuclear heat addition, and until a heatup rate is established
2. Plant shutdown
3. Manual control of steam-generator water level (PWR)
4. Manual control of feedwater flow during plant startup and/or shutdown (PWR-BWR)
5. Boration and/or dilution during power operation (PWR)
6. Reactor power changes of 10% or greater where control rod control is in manual or where recirculation flow is controlled manually
7. Operation of turbine controls in manual during turbine startup
8. Decay heat removal system operation
9. Incore monitoring system operation Approvea~\,.J-fuCtOrNOTD

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NOTO A200*06*26*

.@ NUCLEAR OPERATIONS TRAINING DEPT MASTER PROCEDURES/PROGRAMS MANUAL PAGE nOF 17 TITLE:*Requalification Program - Reactor PROC NO. 1302 REVISION o consumers PDwer Operator and Senior Reactor Onerator DATE 05/03/82 ATTACHMENT D Abnormal/Emergency Plant Evolutions - Annual

1. Reactor Trip (PWR/BWR)
2. Turbine and/or Generator Trip (PWR/BWR)
3. Loss of Coolant Accidents
a. Significant steam generator leaks (PWR)
b. Significant pressurizer leaks (PWR)

. c. Large primary system leak inside containment(PWR/BWR)

d. Large high energy line leak outside containment(PWR/BWR)
e. Small primary system leak inside containment including leak rate determination (PWR/BWR)
f. Small leak in high energy piping outside containment including leak rate determination(PWR/BWR) 1.

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k.

Saturated Primary System"Res~onse (PWR)

Loss of coolant flow/natural circulation (PWR/BWR)

Loss of all feedwater (PWR/BWR)

Control room inaccessibility(PWR/BWR)

Loss of shutdown cooling (head on - head off) (PWR/BWR) t

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Approved~jl'oJ- _th/tt.

Director NOTD Date

NOTD A200*06*26*

NUCLEAR OPERATIONS TRAINING DEPT PROC NO. 1302 MASTER PROCEDURES/PROGRAMS MANUAL PAGE1l2 OF 17 REVIS I ON o TITLE:* Requalification Program - Reactor consumers Power Operator and Senior Reactor Operator DATE 05/03/82*

ATTACHMENT E' Off Normal/Emergency Plant Evolutions - Two-Year Cycle

1. Loss of out-of-core instrumentation - Startup Intermediate Power
2. Loss of in-core instrumentation - Startup Intermediate Power. Range
3. Loss of Reactor Protection System (one and both)
4. Mispositioned control rods
5. Inability to insert control rods
6. Conditions requiring use of emergency boration or standby liquid control system

.7. Fuel cladding failure with high coolant activity and/or high off gas activity

8. Loss of integrated control system (PWR)
9. kiss of init*ial Pressure Regulator

+o. Loss of or failure of by-pass pressure control system

- 11. . Loss of volume control system (~WR)

12. Loss of Instrument Air System
13. Loss of electrical power to plant
14. Degraded AC power to plant
15. Loss of condenser vacuum
16. Loss of service water
17. Loss of component cooling system; or cooling to an individual component (Reactor Cooling Water System)
18. Loss of feedwater pump(s) or feedwater valve failures
19. Main steam line break inside and outside containment.

Approvod~lo,;t--

D{;ector NOTD

!:f,1/lz, ate J

NOTO A200*06*26*

NUCLEAR OPERATIONS TRAINING DEPT PROC NO. 1302 MASTER PROCEDURES/PROGRAMS MANUAL PAGE 13OF17 REVISION o TITLE: *Requalification Program - Reactor consumers Power Operator and Senior Reactor Operator DATE 05/03/82 ATTACHMENT F".

Suggested Annual Written Exam Content Topics listed below shall be covered as necessary in the annual written examination to aid in establishing the knowledge level of each licensed individual (RO AND SRO).

1. Theory and Princi~les of Reactor Operation 2.. Heat Transfer, Fluid Flow. and Thermodynamics
3. Features of Facility Design
4. General and Specific Plant Operating Characteristics
5. Plant Instrumentation and Control Systems
6. Plant Protection Systems

~

7. Engineered Safeguards Systems w
8. Radiation Control and Safety
9. Applicable Portions of Title 10, Cnapter 1, Code of Federal Regulations
10. Fuel Handling and Core Parameters
11. Normal, Abnormal and Emergency Procedures
12. Techro.ical Specifications
13. Administrative Procedures, Conditions and Limitations
14. Nuclear Industry Operating Experience Approved ~wi\oJ- ~~M~

Director NOTD Date

9*

NOTO A200*06*26*

(@ NUCLEAR OPERATIONS TRAINING DEPT ~ROC NO. 1302 MASTER PROCEDURES/PROGRAMS MANUAL PAGE14 OF 17 REVISION .0 TITLE: ORAL REQUALIFICATION EXAMINATION EVALUATION consumers *power SUGGESTED TOPICS AND FORMAT DATE 05/03/82 I

Licensee Date APPENDIX G I EVALUATION For each "U" (unsatisfactory), list the page number (s)' of the oral PAGE ft exam form on which the "U"s are explained. SRO RO for "U"

1.0 FACILITY EQUIPMENT

a. Major
b. Auxiliary c:. Engineered Safeguards
d. Plant Response 2.0 INSTRUMENTATION
a. Nuclear I
b. Process 3.0 REACTOR PROTECTION 4.0 PROCEDURES
a. Normal
b. Off Normal
c. Emergency 5.0 REACTIVITY EFFECTS 6.0 ADMINISTRATIVE REQUIREMENTS 7.0 EMERGENCY PLAN
8.0 RADIATION PROTECTION 9.0 RESPONSIBILITIES OVERALL EVALUATION Signature of Examiner Date

NOTD A200*06*26*

NUCLEAR OPERATIONS TRAINING DEPT PROC NO. 1302 MASTER PROCEDURES/PROGRAMS MANUAL PAGE15 OF 17 REVISION o TltLE: ORAL REQUALIFICATION EXAMINATION EVALUATION consumers Pawer SUGGESTED TOPICS AND FORMAT DATE 05/03/82 CO~TROL ROQ:.r AfID PLANT (M.1jor, Auxiliary and Engineered Safeguards systems')

a. Pu..-ryose
b. Flow Path
c. normal Para.-:ieters
d. Syste~ Response
2. 0 msTRID-!E?i""T.ATION
a. Detector

.~. Control Room Indication

c. Malfunction 3.0. REACTOR PRO'nCTION
a. Alarms Setpoints
b. Safety System Input
c. Interlocks 4.0 PROCEDURES

!1* Normal Procedures

b. Abnormal Procedures
c. Emergency Procedures 5.0 REACTIVITY EFFECTS
6. 0 ADMINISTRA..TIVE REQUIBEMENTS
a. Technical Specifications
b. Plant COM~£NTS: (Required for "U 11 )

l NOTO A200*06*26*

NUCLEAR OPERATIONS TRAINING DEPT PROC NO. 1302 MASTER PROCEDURES/PROGRAMS MANUAL PAGE 16 OF 17 REVISION o TITLE: *ORAL R:EQUALIFICATION EXAMINATION EVALUATION consumers Pawer SUGGESTED TOPICS AND FORMAT DATE 05/03/82 ccmTROL ROOM (Mucl~ar & Radiation Instruments) 2.-0 INSTRID.SNTS

a. Detectors
b. Malfu!lctions
c. Control Room Indications
d. Comne!'lsation
e. Immt to Safety Svstem i,*."':~ .

~ :-:.-;.o::.::~ ~ '

3. 0 REACTOR ~a:I'ECTIOU

- - SYSTEM

a. Ala ms - Setpoints I
b. Special Features
c. Power Supply
4. 0 PROCEDUP-SS '
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. : . . -.:,..:_;:::~~ ~ *::=t:-:~~~~,~-¥~.... :

a. ?formal
b. Off Uornal C*. Emergency 6.0 ADMINISTRATIVE REQUIREMENTS 11 COM-@..Ts (Required for U")

_..* ..... { .*......

NOTD A200*06*26*

(@ NUCLEAR OPERATIONS TRAINING DEPT MASTER PROCEDURES/PROGRAMS MANUAL PAG.El7 OF 17 TITLE: ORAL REQUALIF.ICATION EXAMINATION EVALUATION PROC NO. 1302 REVISION 0 consumers Power SUGGESTED TOPICS AND FORMAT DATE 05/.03/82 GENERAL DIScussror:s

.5. 0 REACTIVITY EFFECTS

a. Coefficient Effects
b. Tr,ansient Effects 6.o ADMINISTRATIVE REQUIREMENTS
a. Tech~ical Specifications
b. Plan~ Requirements 7.0 EMERGENCY P'"J.*AN B.o RADIATION PROTECTION 9.0 RESPO~SIBILITIES r.o~~~'i'S: (Reauired 'for "U")

I

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