ML19322B686

Requalification Program for NRC Licensed Personnel. Revised Version of 750221 Rept

ML19322B686
Person / Time
Site:	Oconee
Issue date:	02/21/1975
From:	DUKE POWER CO.
To:
Shared Package
ML19322B685	List: ML19322B684 ML19322B686
References
NUDOCS 7912040702
Download: ML19322B686 (9)

Text

. . -

,

. . .

7.... .. -

.g-Al-75

.

DUKE POWER (X)MPANT OCONEE NUCLEAR STATION REQUALIFICATION PROGRAM FOR NRC LICENSED PERSONIEL DECEMBER 11, 1973

.

Revised

,

July 3, 1974 7 I January 7, 1975 February 21, 1975 7912040gC l l

i l

I

-

._-

.

.-

. . .

.l Table of Contents Section h 1.0 Introduction 1 2.0 Definitions 1 2.1 Reactivity Change 1 2.2 Licensed Operator 2

.

2.3 Backup Licensee 2 2.4 Training Supervisor 2 3.0 Examinations / Lectures 3 4.0 On-The-Job Training 4 5.0 Evaluations 6 6.0 Records 7

.

.

7/3/74

-- , ,. --. - -, - - ,

. _ _

-

.

• ~

. ,

.

DUKE POWER COMPANY OCONEE NUCLEAR STATION REQUALIFICATION PROGRAM FOR . NRC LICENSED PERSONNEL l 1.0 Introduction Recent changes to 10 CFR 55 requires all licensed operators to participate in an approved requalification program. The re ,

qualification program for the Oconee Nuclear Station is designed to maintain and demonstrate the continued competence of all licensed operators and senior operators. This progre:s will be conducted on an annual basis and will include a comprehensive exam, formal requalification lectures, on-the-job training and simulator operation. The program will be implemented so as to minielze scheduling difficulties that will be incurred by site management.

2.0 Definitions 2.1 Reactivity Change A licensed Reactor Operator that performs, or a licensed Senior Reactor Operator that performs or directs, ten (10) reactivity changes from those listedbelow, in accordance with Section 4.0, On-The-Job Trai gn Subsection 4.2, meets the requirements. of 10 CFR 55, Appendix A Section 3(a).

2/21/75

. _ _ - _ _ .-. - -

-

,.

' '

. .

'-

.

)

1

-

!

a) Critical approach from suberitical on source range instrumentation  ;

to critical at the point of adding heat on the intermediate range

!

instrumentation. l I

b) Any power level change (increase or decrease) of 10% of rated )

l power or greater with control rods in manual. I I

c) Reactor shutdown from critical at 15% of rated power to subcritical, '

l shutdown on source range instrumentation, l 1

d) Boration or deboration during critical operation. - '

e) Operation of refueling bridge to change core geometry during refueling.

.

2.2 Licensed Operator Individuals who maintain Operator or Senior Operator licenses and who are i actively and extensively engaged in the day-to-day operation of the plant.

l l

Any licensed operator who has not been actively performing the functions of an operator or senior operator for a period of four months or longer, shall, prior to resuming licensed activities, participate in an appropriate requalifiestion program pursuant to 10CFR 55.31(e).

2.3 Backup Licensee l

Individuals who maintain Operator or Senior Operator licenses for the purpose of providing backup capability to the Operating Staff.

2.4 Training Supervisor

.

A supervisor normally assigned no other duties except instructing, coordinating, and record keeping for pre-license operator training programs and licensed operator requalification program.

l l

i l

l 1/7/75  !

,

- .

,-

• ~

.

'

'

3.0 Fxaminations/ Lectures Annually, all SRO and RO licensed personnel will take a written exami-nation which closely parallels the hE written exanination. The exami- l nation will be given in three segments approximately three months apart following the lecture series for that segment.

Any operator who scores less than 70 percent overall on the Annual Re-qualification exam shall be removed from licensed duties and placed in an accelerated requalification program. The individual will be reevaluated by a comprehensive written exam paralleling the annual exam in format and by an oral interview with the Training Supervisor to detetmine his knowledge level. The results of the oral and written exam will be forwarded to the Operating Superintendent for determination of return to licensed duties.

Requalification lectures are intended to be given on an annual basis for all licensed operators in three segments of approximately 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> duration each, corresponding to the segments of the annual exam. The lecture schedule prior to each annual evamination segment will be determined based on weak areas shown from preceding annual exam.

Following the completion 'of all the annual exam segments, requalification lectures will be determined by the results of the annual exam (i.e.,

categories in which individuals received less than 80 percent). Attendance for all SRO and RO licensed personnel at these lectures will be based on the results of the annual requalification exam (i.e., less than 80 percent on a category requires mandatory attendance at lectures on topics of that category).

2/21/75

_ _.

-

- -

. .

_4 Following the completion of each segment of the annual exam, a special individualized study program will be instituted for anyone scoring less I

than 70 percent on a category to enable the individual to increase his knowledge level for that category in a timely fashion. This program will be in addition to the lectures following completion of all segments of the annual examination but will occur immediately following completion of the segment for which a grade of less than 70 percent was attained.

The individualized study program would be no more. than five (5) weeks induration and an examination to evaluate the retrainin;g would occur at

.

the completion of the individualized study program.

Any individual f ailing a re-examination of a segment of the annual examination following an individualized study program will be evaluated by the Superintendent of Operations to determine the course of action.

This action will be documented in the individual's training record.

Periodic written or oral quizzes will be administered throughout the lecture program with a required passing grade of 80%. Lecture attendance

.

will be based on 80% categorical grades from the annual requalification exam.

" Quality Assurance for Operation" is now a topic covered as part of the pre-license training and as such would be considered as a topic for requalification lectures.

l contingency meetings are an integral part of nuclear plant operation and l are normally scheduled as the need arises by plant management.

2/21/75

, e - - - - - - - - - . . - ,

. .

"

. .

.

. .

4.0 On-The-Job Trainina 4.1 In order to insure the continued proficiency of licensed operators in meeting all operating situations, on-the-job training will play a major role in the Oconee requalification program. Technical Specifications, Operating Procedures and Emergency Procedures will be reviewed on shif t according to a formal schedule. Short oral and/or written quizzes will be used tc demonstrate the effectiveness of this review with a passing grade of 80% required. All changes to Operating Procedures, f acility design changes and revisions to Technical Specifications will be reviewed on shif t also. Documentation of the specified reviews is filed in the individual's trainine records as per Section 6.0, Records. .

~4.2 All licensed Operators will participate, to the marium extent possible, in plant evolutions involving reactivity changes. These will include those items defined as reactivity changes in Section 2.0, Definitions. During the two-year license term, a minimum of ten such evolutions shall be conducted by each licensed Operator and either conducted or directed by each licensed Senior Operator with no more than three (3) such evolutions being any combination of Items 2.l(d) and 2.l(e) of Section 2.0, Definitions, Subsection 2.1, Reactivity Change.

.

4.3 All licensed personnel will partica . ate in a one-week (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />) simulator training course, consisting of 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> classroom and 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> simulator, at an approved facility such as the B&W simulator, Lynchburg, Virginia, during the two-year license term.

! The B&W simulator is considered the only existing simulator ap-propriate for use by Oconee personnel in meeting the requirements of Appendix A to 10 CFR Part 55. However, we retain the option to use other simulators that become available in the future and are l

rpproved by the NRC for use by Oconee personnel.

l 4

This training will include operation.during emergency or abnormal

.

conditions including the following:

a) Reactor Startup l b) 15-100% PWR Meneuver

!

I 2/21/75 l

'. - _ - . . - - , - _. -- ,- _ -..---__ - .- :

.- -. . _

...

'. .

- .

a .

I l

,

c) 100%-15% PWR Maneuver i d) Power Operations (Manual and Auto) e) Plant Shutdown /Cooldown j f) Reactor Trip g) Turbine Trip h) Steam Line Rupture

1) RC System Leaka ,

4.4 Control manipulations at the simulator will be credited the same as manipulations on the Oconee units.

4.5 Fackup licensees will acquire 4 hrs./ month on shift assigned the

(.uties of Assistant Shift Supervisor or Assistant Control operator, which are positions requiring a Senior Operator's and Operator's license respectively, at this f acility. The assignment to Assistant Shift Supervisor or Assistant Control Operator will be consistent with the license held by the backup licenses.

5.0 Evaluations 5.1 The performance and competency of Operators and Senior operators will be evaluated by the annual written exam as well as with personal evaluations from supervisors and training staff personnel. ,

i 5.2 Semi-annually each Shift Supervisor will submit a report to the Operating Superintendent, evaluating the performance of each man under his supervision during normal and abnormal operating conditions.

I I

l I

i t 1/7/75 i

_- _ _ _ _ _

- . _ . _ _ . . _ . _ _ _ __

- - - - _ _ _ _ _ _ _ _ _ __ __

,.

oso

.

5.3 The performance of Operators and Senior Operators will be evaluated by the simulator training staff follbwing simulator training. Evaluations of personnel will be made by several sources as noted above. The ultimate evaluation will be based on operators performance of his licensed duties at the Oconee Nuclear Station.

5.4 The Operating Superintendent will review these reports semiannually.

On the basis of the evaluations, the Operating Superintendent can j I

l recommend special traising classes and removal from shift duties if necessary. Prior to the license renewal date, the Operating Superintendent will review each Operator's training record. Based on this evaluation he will make recommendations for license renewal or specialized training prior to license renewal.

6.0 Records 6.1 Training records for each Operator and Senior Operator will be maintained and shall contain the followingt a) Copies of the graded annual exam.

b) Re-examinations given s'.ter regna14fication lectures.

c) Evaluations made by Supervisors.

d) Evaluations made by simulator personnel.

e) Documentation of all trainlag participation.

f) Any miscellaneous quizzes given by the training staff. l

.

g) Records of the number and type of reactivity changes.

l 6.2 Training records will be retained for a minimum of six (6) years.

1/7/75

.

_ . _ - _

,. <