ML19327A526

Training Instruction TI-200 Brunswick Plant Operator Retraining Program, Vol I,Revision 5

ML19327A526
Person / Time
Site:	Brunswick
Issue date:	07/25/1980
From:	Jonathan Brown, Michael Jones, Tollison A CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML19327A523	List: ML19327A522 ML19327A526 ML19327A529 ML19327A531
References
TI-200, NUDOCS 8008060326
Download: ML19327A526 (13)

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CAROLINA POWER & LIGHT COMPANY  !

BRUNSWICK STEAM ELECTRIC PLANT TRAINING INSTRUCTION TI-200 ,

BRUNSWICK PLANT OPERATOR RETRAINING PROGRAM Revision 5 4

i Recomended By: NM ~1ng Supervisor Date: 7 /23 /fC Tr Recomended By: M Date: 7 27/ #O perations Manager /

Approved By: h b General Manager Date: hEh

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LIST OF EFFECTIVE PAGES TI-200 i

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SSEP/Vol. I, Book 3/TI-200 Rev. 5 i

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1.0 Purpose  !

To establish the requirements for a retraining program for all NRC licensed personnel at the Brunswick Plant. This program is intended to

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meet or exceed the requirements of 10 CFR 55, Appendix A, for operator i retraining. j 2.0 Procedure 2.1 The Brunswick Plant Operator Retraining Program will be conducted in 2 accordance with Appendix A to this procedure.

2.2 All licensed operators will participate in the retraining program.

New licensees will be integrated immediately into the on-shift training portion and will participate in the next annual evaluation examination.

2.3 No change will be made to the Brunswick Plant Operator Retraining Program that diminishes the scope, time, or frequency of conduct of the various portions of the program unless authorized by the NRC.

3.0 Responsibility 3.1 The Manager - Operations will be responsible for the administration and reporting of the on-shift portion of the Operator Retraining -

Program.

3.2 Training Supervisor The Training Supervisor is responsible to the Director - Nuclear Safety & QA for the following: i

a. The execution and overall conduct of Operator Retraining ,

Program.

b. The ndministration and documentation of the retraining program,

c. Timely initiation of license renewal applications to the NRC.

d. The proper maintenance of all records pertaining to the Operator Retraining Program.

4.0 Documentation 4.1 The Training Supervisor will maintain forms and training reports to be used for training documentation.

4.2 On-shift training should be documented using a form such as the ene

in Attachment A.

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BRUNSWICK STEAM ELECTRIC PIANT UNITS 1 & 2 d

OPERATOR RETRAIN 7.NG PROGRAM 1

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BSEP/Vol. I, Book 3/TI-200 Rev. 5

LICENSEE ON-SHIFT TRAINING REPORT QUARTER: 1 2 3 4 HOURS ON(1)

WATCH STATION REQUIRING A NAME (PRINT) LICENSE REMARKS (2) SIGNATURE (4) 1.

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The individual (s) listed above has/have satisfactorily completed for this ,

quarter the following additional instructional sessions such as on-shift 1 seminars, special training. etc.

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I Shif t Foreman (5) Date  ;

i I have observed the performance and competency of personnel listed above during ,

normal and/or emergene o in " REMARKS" section.( ) perations and found them adequate unless otherwise noted l Shif t Foreman (5) Date BSEP/Vol. I, Book 3/TI-200 A-1 Rev. 5 i

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LICENSEE ON-SHIFT TRAINING REPORT (CONT'D)

(1) Shift. personnel whose normal duties are as Control Operator, Senior Control Operator, or Shift Operating Supervisor may indicate hours on watch station with a (/). Nonshift personnel must indicate number of hours as CO, SCO, refueling SRO, SF, or SOS.

(2) Indicate areas of weakness which require retraining. Indicate "not observed" for personnel whose performance was not evaluated.

(3) Nonshift personnel should arrange with the Shift Foreman or Shift Operating Supervisor for this evaluation during their proficiency watches.

(4) Signature acknowledges completion of (a) watch standing hours as indicated, (b) completion of required reading, and (c) completion of Operating Manual review as listed in Appendix A, Phase 1, Section 2.

(5) May also be signed by the Shif t Operating Supervisor or Training Supervisor. i i

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I BSEP/Vol. I, Book 3/TI-200 A-2 Rev. 5

3.

1 BRUNSWICK STEAM ELECTRIC PLANT OPERATOR RETRAINING PROGRAM The Operator Retraining Program is designed to ensure that all licensed Reactor Operators and Senior Reactor Operators will maintain proficiency in their assigned plant operating tasks. Further, it is expected that partici-pation in this program will allow all licensed personnel to meet or exceed the requirements set forth by the USNRC. ,

The following is a detailed summary of the Operator Retraining Program which will be conducted to fulfill the requirements of 10CFR55. It is the intention of CP&L to have a continuing training program between the time each annual examination is given. This consists of classroom training and on-shift training.

This will normally exclude the period that units are down for maintenance and refueling.

I The entire Operator Retraining Program will be conducted in two phases: (1) retraining on site, and (2) operator evaluation. The Training Supervisor will be responsible for the scheduling and supervision of this training except for some on-shift training.

I PHASE I - RETRAINING ON SITE The on-site portion of the retraining program will normally consist of approxi-mately 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> of instruction. This instruction will be given in two parts:

(1) classroom training as required in 10CFR55, Appendix A, " Lectures," and (2) on-shift training. The scheduling on site will be such that licensed operators s~11 have the opportunity to attend all lectures. The following is an outline '

of what subjects may be covered in each of these parts, but not necessarily in the order stated.

1. Classroom Training I. Theory and Principles of Operations  ;

A. Atomic and nuclear physics i B. Suberitical multiplication C. Xenon and samarium effects D. Rod worth E. Reactivity coefficients

1. Moderator temperature

2. Fuel temperature

3. Voida

4. Pressure

5. Power BSEP/Vol. I, Book 3/TI-200 A-3 Rev. 5

l PHASE I - RETRAINING.ON SITE (Cont'd)

II. General and Specific Plant Operating Characteristics A. Normal operating transients

1. Control rod manipulations

2. Xenon transients

3. Recirculation flow control

4. Automatic load following B. Safety analysis ,

1. Review of abnormal operational transients

2. Review of design basis accidents III. Plant Instrumentation and Control Synta=s A. Nuclear instrumentaton B. Reactor manual control C. Rod position indication i D. Electrohydraulic control systa=

E. Recirculation pump speed contrcl F. Vessel level control G. Reactor protection system H. Rod worth minimicer I. Rod sequence control systam J. Primary containment isolation K. ECCS initiation and control logic IV. Operating Procedures and Emergency Instructions A. Engineered safety features B. Site emergency plan and procedures C. Overall plant operating procedures V. Radiation Control and Safety A. Nuclear radiation B. Biological effects of radiation C. 10CFR20 D. Radiation protection manual E. Radiation monitoring systams F. Radiation procedures VI. Technical Specifications ,

A. Safety limits 1 B. Limiting conditions for operations C. Major design features  ;

D. Discharge limits VII. Chemistry A. Chemistry control B. Radiation chamistry l C. Specifications and criteria VIII. Quality Assurance Responsibilities BSEP/Vol. I, Book 3/TI-200 A-4 Rev. 5

PHASE'I'-' RETRAINING ON SITE (cont'd)

IX. Heat Transfer, Fluid Flow, and Thermodynamics A. Basic properties of fluids and matter B. Fluid statics C. Fluid dynamics D. Heat transfer by conduction, convection, and radiation E. C1.ange of phase - boiling F. Burnout and flow instability G. Reactor heat transfer limits.,

X. Mitigating Core Damage A. Incore instrumentation B. Excore nuclear instrumentation C. Vital instrumentatien D. Primary chemistry E. Radiation monitoring F. Gas generation Instructors who teach systems, integrated responses, transient and simulator courses, are required to hold a valid SRO license or to pass the NRC SRO exam and participate in SRO retraining. Annually, a comprehensive examination will be given to each licensed operator. From the results of this exam, an annual schedule will be formulated using the above topics as a guide. If any licensed operator shows he is deficient in any of the categories on the exam, he will be removed from licensed duties and placed in an accelerated requalification pro-gram using the following criteria:

1. If he scores less than 70% on any category, he will raceive accelerated requalification in that category.

2. If he scores less than 80% overall, he will receive accelerated requalifi- 1 cations in all categories on which he scored less than 80%. 1 The accelerated program will continue until the licensee demonstrates that he is again proficient in the subject categories. This will be determined by a l written and/or oral avamination.

Any operator who clearly shows he would have passed an NRC exam on a particular section (with an 80% or greater on that section) will be axempt from the lecture series on that section. If he scores less than 80% on a particular section, he will be required to attend a lecture series on that particular section. Upon completion of the classroom lectures, a topical examination on that section will be given requiring a passing grade of >80%.

BSEP/Vol. I, Book 3/TI-200 A-5 Rev. 5

PliASE I - RETRAINING ON SITE (C ont'd)

Certain licensed personnel, in the performance of their normal duties, may be very much involved with one or more of the areas covered in classroom lectures. These individuals would not be required to attend the applicable classroom lectures. In some cases, these individuals may be called upon to conduct lectures in their areas of expertise; e.g., Environmental and Radiation Control Supervisor for Radiation Control and Safety lectures.

2. On-Shift Training It is essencial to individual and crew readiness that emphasis periodi-cally be given to vital information on alarm settings, safety limits, abnormal condition symptoms, limiting conditions for operation, operating sequences, and emergency immediate-action steps.

Individual reviews, instructional sessions, and where applicable, walk-through discussions of controls and instruments will be conducted with

.such duration and frequency that the information contained in the following volumes is covered once each quarter, with the exception of the two to four months during each operating cycle when a unit 1s being refueled:

a. Volume I - Administrative Procedures (Section 4)

b. Volume VI - Emergency Instructions

c. Volume VIII - Radiation Control and Protection Manual

d. Volume XIII - Energency Plan and Procedures

e. Volume XVI - Annunciator Procedures (to be covered annually and when a proced'ure is revised)

Every quarter (with the exception of the. quarter in which the unit is being refueled), the Shift Foreman will submit to the Training Supervisor a report of the instructional sessions conducted during that quarter. The report will list the topics covered for each member of the shift operating crew and will contain the Shif t Foreman's judgment of each operator's familiarity with the information contained in the above volumes, as well as each operator's ability to take the required action.

The Training Supervisor will maintain a file of the reports filled out by the Shift Foreman. They will be used in compiling qualification information for NRC Reactor Operator license renewal applications.

It will be the responsibility of supervisors of nonshift licensees to assure that operations readiness training is conducted for nonshift licensed personnel j and that this training is adequately documented.

I To ensure that each licensed operator is cognizant of facility design changes, procedure changes, and facility license changes, significant safety-related modifications or changes to procedures and license will be reviewed. This 1 may be accomplished by group or individual review and documented in the I training files. The staff personnel holding an NRC operator license will stand an average of four (4) hours watch in the Control Room per month.

l BSEP/Vol. I, Book 3/TI-200 A-6 Rev. 5

PHASE I - RETRAINING ON SITE (Cont'd) l If he is regularly participating in a simulator training program, 75%

of this tima caa be satisfied on the simulator. During these four (4) hours he will carry out those duties normally conducted on a watch station requiring an RO or SRO license.

During plant operation, a record will be kept of the major reactivity changes a licensed operator performs. The following control manipulations and plant evolutions are acceptable for meeting the reactivity control manipulations requirements of Appendix A, Paragraph 3.a of 10CFR55. The starred items shall be performed on an annual basis; all other items shall be performed on a two-year cycle. Each individual shall perform or parti-cipate in a combination of reactivity control manipulations based on the

-availability of plant equipment and systems. Personnel with senior operator licenses are credited with these manipulations if they direct or evaluate control manipulations as they are performed. Normal control manipulations, such as plant or reactor startups must be performed. Control manipulations for abnormal or emergency operations may be walked through with, j and evaluated by, a member of the training staff at a minimum. An <

appropriate simulator may be used to satisfy the requiremants for control '

manipulations during normal or abnormal and emergancy conditions. The use of the Technical Specifications should be maximized during the simulator control manipulations. ,

• 1. Plant or reactor startups to include a range that reactivity feedback from nuclear heat addition is noticeable and heatup rate is established

2. Plant shutdown

• 3. Manual control of feedwater during startup and shutdown

4. Boration or dilution during power operation

• 5. Any significant (>10%) power changes in manual rod control or recirculation flow

, *6. Large and small loss of coolant including leak-rate determination

7. Loss of instrument air

8. Loss of electrical power (and/cr degraded power sources)

• 9. Loss of core coolant flow / natural circulation

10. Loss of condenser vacuum l i

i 11 Loss of service water

12. Loss of shutdown cooling BSEP/Vol. I, Book 3/TI-200 A-7 Rev. 5

PHASE I - RETRAINING ON SITE (Cont'd)

13. Loss of component cooling system or cooling to an individual component

14. Loss of normal feedwater or normal feedwater system failure

• 15. Loss of all feedwater (normal and emergency)

16. Loss of protective system channel-

17. Mispositioned control rod (s) (or rod dropped)

18. Inability to drive control rods

19. Conditions requiring use of emergency boration or standby liquid control system

20. Fuel cladding failure or high activity in reactor coolant or off gas

21. Generator or turbine trip ,

22. Malfunction of automatic control system (s) which affect reactivity

23. Malfunction of reactor coolant pressure / volume control system

24. Reactor trip

25. Main steam line break (inside or outside containment)

26. Nuclear instrumentation failure (s)

PHASE II - OPERATOR EVALUATION Annually, each licensed operator will take a USNRC-type comprehensive written examination. Periodically, oral examinations will be conducted, or a simulator will be used to evaluate the licensee's ability to perform abnormal or emergency conditions.

The following is a list of records to be kept on file on each licensed operator:

1. Startup, shutdown, and reactivity changes

2. Classroom training attendance

3. On-shift training

4. Grade sheet for examinations

5. Evaluation sheets for written comprehensive examinations

6. Evaluation sheets for oral eynMnations

7. Additional training conducted BSEP/Vol. I, Book 3/TI-200 A-8 Rev. 5

PHASE II - OPERATOR EVALUATION (Cont 'd)

Copies of periodic examinations and a copy of comprehensive examinations will be kept on file.

Any licensed operator absent from the site for a period of four months or longer will require an accelerated training program and notification to NRC per 10CFR55 prior to returning him to his normal duties.

NOTE: The term " licensed operator" means any person holding an NRC license to operate a nuclear power plant, whether it be Senior Reactor Operator or Reactor Operator.

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