ML20041B064

To CT Yankee Reactor Operator Requalification

ML20041B064
Person / Time
Site:	05000000, Haddam Neck
Issue date:	07/23/1980
From:	Ferguson J CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20041B057	List: ML20041B060 ML20041B062 ML20041B064 ML20041B066 ML20041B069 ML20041B070
References
TASK-1.A.2.1, TASK-2.B.4, TASK-TM OP-REQ-R01, OP-REQ-R1, TAC-44175, TAC-44525, NUDOCS 8202230226
Download: ML20041B064 (7)

Text

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1 CONNECTICUT YANKEE Rrogram 1.D.:

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\\wl R=4 TRAINING ABSTRACT

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Date:

7 0 %.iU TITLE Connecticut Yankee Reactor Operator Requalification l

DEVELOPED FOR Licensed Reactor Operators

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l OBJECTIVE Assure continued. competence of Reactor Operators i

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LENGTH Two (2) years SCHEDULE Continuous TYPE Lecture, On-the-Job EVALUATION written, orills, Observation CONTENT 1.0 Lectures 2.0 On-the-Job Training l

3.0 Simulator l

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8202230226 800815 PDR ADOCK 05000213 i

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I DOCKET NO. 50-213 HADDAM NECK PLANT OPERATOR REQUALIFICATION PROGRAM r

JULY, 1980

i' CONNECTICUT YANKEE Progrem 1.o., on-aro nev. 1 TRAINING PROGRAM

^veroved'%y4**Pm-f V'] 4th fi Date:

i TITLE Connecticut Yankee Reactor Operator Requalification OBJECTIVE Assure continued competence of Reactor Operators EVALUATION See Content, Section 4.0 CONTENT 1.0 LECTURES A lecture series, consisting of at least six lectures per year addressing the following topics, l

will be attended by all licensed personnel.

1.1 Reactor Theory 1

1.2 Operating Characteristics 1

1.3 Instrumentation and Control System l

1.4 Prptection and Safety Systems 1.5 Normal and Emergency Procedures 1.6 Radiation Control and Safety l

1.7 Fluid Flow and Pump Theory 1

1.8 Thermodynamics 1.9 Operation with a Damaged Core l

l Technical Specifications will be included where applicable.

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l Video tapes or other com=ercially available I

training programs will be limited to less than l

25 percent of the total lecture series.

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f 2.0 On-Tl!L-JOL TRAINING On-the-job training consists of the following three categories.

2.1 Review of Changes f

All Licensed Reactor Operators will review pertinent changes to the following:

2.1.1 Operating License 2.1.2 Normal Operating Procedures 2.1.3 Emergency Procedures -

2.1.4 Surveillance Procedures' 2.1.5 Technical Specifications-2.1.6 Plant Design,,

Review requirements will be established by the Plant Operations Review Committee.

2.2 Review of Emergency Procedures All Emergency Procedures will be scheduled for annual review.

i 2.3 Reactor Control Manipulations Reactor Control Manipulations, that demonstrate satisfactory understanding of reactor operation and provide for at least ten significant reactivity changes, must be experienced during each requalification per_iod.

An effort will be made to insure a variety of reactivity changes will be experienced.

A power transient is any power change other than adjustments for burnup.

This portion of On the Job Training may be satisfied by an approved simulator program.

Significant reactivity changes are identified as:

• 2.3.1 Reactor critical approach during which neutron level is brought to the point of adding heat.

• 2.3.2 Orderly reactor shutdown.

• 2.3.3 Dilution during power transient.

• 2.3.4 Boration during power transient.

• 2.3.5 Manual rod control during power transient.

• 2.3.6 Turbine control during phasing.

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• 2.3.7 Manuti ferdwater control during startup or shutdown.

• 2.3.8 Loss of coolant including

• 1.

significant PWR steam generator leaks 2.

inside and outside primary containment 3.

large and small, including leak-rate determination 4.

saturated Reactor Coolant response (PWR)

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

• 2.3.10 Loss of Reactor coolant flow / natural circulation.

2.3.11 Loss of condenser vacuum.

2.3.12 Loss of service water if required for safety.

2.3.13 Loss of shutdown cooling.

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

2.3.15 Loss of normal feedwater or normal feedwater system failure.

2.3.16 Loss of all feedwater (normal and emergency).

2.3.17 Loss of protective system channel.

2.3.18 Mispositioned ccstrol rod or rods (or rod drops).

2.3.19 Inability to drive control rods.

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2.3.20 Conditions requiring use of emergency boration.

2.3.21 Fuel cladding failure or high activity in reactor coolant.

2.3.22 Turbine trip.

2.3.23 Malfunction of reactor coolant pressure / volume control system.

2.2.24 Reactor Trip.

2.3.25 Main steam line break (inside or outside containment).-

2.3.26 Nuclear instrumentation failure (s).

• Indicates items that shall be experienced annually.

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3.0 Simulator A simulator program, of at least three days duration, may be used to meet Section 2.3 of on the Job Training.

The simulator must meet the following criteria:

1 3.1 Nuclear Regulatory Commission' approved.

i 3.2 Simulates Connecticut Yankee Operating Characteristics.

i 3.3 Provide the control manipulations required.

4.0 Evaluation 4.1 Exams A written exam, similar to the Nuclear Regulatory Commission License Exam, will be administered annually.

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Exams will be evaluated to identify deficiencies which will be factored,into future retraining lectures.

An overall score of less than 80 percent or less than 70 percent in each category on the annual j

exam will result in the individual being relieved i

of licensed duties and provided with acceleration training in the deficient areas.

4.2 Quizzes Quizzes will be' administered to evaluate student progress in lecture material.

I A score of less than 80 percent will be evaluated and specific training administered

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to upgrade the individual.

The lecture will t

be rescheduled if more than 50 percent of the L

attendees scored less than 80 percent.

4.3 Drills Drills will be conducted.at least annually to provide a systematic review of the operator's ability to respond to emergency conditions.

l 4.4 Exemptions l

Instructors will be exempt from evaluation based I

on their participation in the preparation and I

administration of the evaluations.

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1 5.0 Accelerated Programs Accelerated programs will be developed for individuals failing to meet the. requirements of Section 4.0.

4 6.0 Records t

6.1 Records will be maintained that document attendance and satisfactory performance of all phases of this program.

6.2 Masters and keys of all exams and quizzes will be maintained on file.

6.3 Copies of each operators response to exam and quiz questions will be maintained on file.

6.4 Drill evaluations will be maintained on file.

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