ML20148F995

Operator Training Program, Revision 4

ML20148F995
Person / Time
Site:	Yankee Rowe
Issue date:	01/26/1978
From:	YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML20148F986	List: ML20148F982 ML20148F990 ML20148F995
References
AP-0500, AP-500, NUDOCS 8011070082
Download: ML20148F995 (8)

Text

o h a dupt./ /c leview lute ,

l. Mgr. of Ops.7 K , J.

q*;,

.YANTEE RONE' OPERATOR TRAINING PROGlW!

SCOPE ,

a To establish-a program through which holders and prospective holders of Nuclear Regulatory Commission Reactor Operator and Senior' Operator .mL licensos will be. trained for initial and renewal licensing.  :

.. ,x L ENCLOSURES-AP-0500 - Pgs. 1 Rev. 4 .

. Attachment A_- Pg. 1 - Rev. 4 >

REFERENCES

- 3

.1.  ! -:

ANSI N18.1 - 1971,:Scicction and Training of Nuclear Power Plant c Personnel. *'

l

2. Titic 10, Code of Federal Regulations Part 55 and Part 55 Appendix A.  ! ,

3. Technical Specifications, Section 6.4.1 l -

DISCUSSION

._. M .

.The training program is divided into two separate phases. The first ki of these is the initial operator licensing program. This phase will .

be designed to give unlicensed personnel the kncwledge and experience  !

necessary to moet the requirements of the rederal Regulations. for '

license application.

The second phase of the training program will bc licensed operator and senior operator retraining. The program will be ccnducted to i+

maintain licensed operators and senior operators at their highest pvt 1cyc1 of competence and proficiency. The pfogram is designated to M* :g'@

meet.or exceed the requirements set forth by the Nuclear Regulatory Commission in the Code of Federal Regulation, portaining to operator I=

retraining and license renewal. - The program will consist of a combination

of the .following: ,

J  %

1. Evaluation Exams. -

M

2. On site lecture series supplemented at times by videotapes and other effective training aids. {Iyi Jg I'

3.. ' Implementation and documentation of a review program in which all licensed personnel are kept aware of: kM bN

-a.- ~\ Operating and eniergency procedurcs.

,s(4 e: -

b.-. TApplicable' administrative procedures.:  ; m,v

~

j' c.)fPlantdesignichanges.- 4 5 '

I l '.. d. 2 AbnonnalLplanticvents, their. cause and correction.

jQgQhD h

• 1% g- , ,

e:

M f F .

Nss' e L

'f M 25% M M M M AEfMIN M 8Q5E N OE5 N $N N !

l'i . m , . -

4. Actual control ma. ,>ulation, or direct suparvisici hereof, for at least 10 reactor startups, shutdowns, or significant reactivity changes which demonstrate familiarity with the reactor '

control systems.

The following subject areas will be covered during the evaluation und lecture series of both phases of the progranu , . - , .

1. Reactor Theory and Principles of Operation. '

h

2. General and Specific Plant Operating Characteristics.

3. Plant Instrumentation and Control System.

4. Plant Protection Systems.

~5. Engineered Safety Systems.

6. Radiation Control and Safety. -

M#

7. Technical Specifications. k$ ..

8. Standard and Emergency Operating Procedures.

9. Applicabic portions of Titic 10, Code of Federal Regulations.

U .

Ibcumentation of the initial training and retraining programs will be maintained by the Training Coordinator.

'Ihc training coordinator has the responsibility of implementing all training. He will also be responsible for maintaining adequate records P n;3Q of the training effort.

I PROCEDURE I. Initial License Program.

A. As the need arises for additional N.R.C. licenses at ' akee Rowe, a training program will be instituted to ensure each ipt p' e candidate will receive sufficient training and experience for 4h-license application submittal. This program will consist of the following: 6 g,

1. Classroom lectures in the following subject material: kN n"$$

a. Reactor Theory rig

[.g.m,6

b. System and Components

c. Instrumentation and Controls ]jy:qy 4y',

N d.

c.

Transient Analysis- hhn s

Design Features s

(.4 y

\

r %?). .(

Q%.

p ..

t 1 e s O

h%G%f u  ;;.;J * ~. s-.o ..x

$$ $ h 5b"f$Q*h2tb % h I5jb $ 5 ? ^ <;$ &~ k&f~M&. / W ;.4vRO %W F ~*g

• !$3y&y

%OFe;m y! k? ? US WIs0'. f .Y

. Rev. 4 lica...h Physics f.

g. Technical Specifications

h. Operating and Emergency Prc cdures

,2 . Classroom lecture attendance and evaluation examination results will b1 maintained by the trainin ,+ ;

These records will be maintained only for'g thecoordinator, purpose It of license application. The applicati6n will become r. ,

a part of the individual's training file.

3. Actual manipulation of the reactor controls by the individual to demonstrate his ability to operate the plant in a safe and competent manner.

4. Upon completion of the ab.<c, each applicant will be fS%

required to pass a company examination similar in scope and depth to an N.R.C. cxamination. h*-

B. hhen an individual receives an N.R.C. license, a copy of the license will be filed in the training record. The licensec will then be enrolled in the retraining program.

II. Licensed Operator Retraining L__

A. Evaluation Examination .hk

1. Examinations will be administered to each licensed i operator and senior operator at least annually.

2. Reactor cocrator examination categories will consist of the 10110 wing topics:

a. Princip1cs of Reactor Operation {~, g

. b. Features of Facility Ibsign '^*#"

c. General Operating Characteristics h '#c -

d. Instrumentation and Control Systems M y.M .,

c. Safety and Emergency Systems "' W

. f. Standard and Emergency Operating Procedures n.94.,

g. P.adiation Control and Safety +y.M.t

3.

• Senior operator examination categories will consist -

, of the following topics: g, S,Nw .

/

s.

s

[h Q~t e

• h.

1 1

A s & $ ,5 * # '

j. p

~ .

4.- AP-0500' E .

, 'Roy. 4 .

p ..- .. ,

k. 'T, f ,

' a .o Reac orLTheory

• L .

b.- Radioactive Material Handling, Disposal and Hazards ,

( .

c. Specific _Op' crating Charactcristics *

d.  : Fuel Handling and Core Parameters . m

' ~

. e. Administrative Procedures, Conditions and Limitations

.f c T

'4. If aLlicensed operator or. senior operator fails to

~ achieve an overall examination grade of .70%, on either the annual examination or the walk through evaluations, ,

he willtbe required to participate in an accelerated requalification program prior to resuming licensed  ;

activities. ' A judgement will be made by the training i q,7 ,

coordinator at the time of'the failure as to how f#rt the accelerated program may best be administered. j($

1

5. The following infomation pertaining to evaluation

examinations will become a part of the license holders training file:

y

a. A copy of the licensecs' answers..

7

-b. ~

Tho' grade the licensec achieved for each section and his overall percentage grade.

g

, ugh.

y

. 6.. :A copy of all examination questions will be maintained by the training coordinator. '.

7. .The requalification records shall be maintained for a I period of two years per Reference 2. j &

B. On-Site Lecture Series 74

• L.

'lhe on-site lecture series will. consist of preplanned lectures c -"

to be given on a regular and continuing basis which will be M;m

' interrupted by heavy plant workloads or outages and the Qg e traditional vacation periods of June, July and August. p,. e a , r 1- '

hhore applicabic, up to 500 of the lecture series may bc WD' supplemented'by the use.of films, video tapes, and/or ,

.cindividual study. e  :

u 1  :

1. The following general sections.will. comprise the lecture  !

series: b W a.- . Theory and Principles of: Operation OV s' b.

~

General and Specific Plant Operating Characteristics b4 e:

4 - 3l L& ' s c.

g ' . Plant Instrumentation'and. Controls

~

(*h[i:

c"

, \ ,E m d.1 1 Plant Protection Systems *

-m n, . %. . 4,

'm .

2 g< i NQSN ie.(mvEngineeredSafetyJSystems s ,,

, .,u . .

. i 0& J .

,f . ,. ,31 . + u *;,

l Q

y,.

i

' '.a

['d [ -

as a . ..

3 [

7/

, ;x. *

,. y

. . a.

4 c.Q f;g y;

\_

qf9 ;a ,, , j i- ,5

~wwccm,% menn,mw mmrc m:m mar ~a~ w .-- , a+g[ V ]

.- _ . , , ,. .. _ . , . . _ . - _ _ _ . _ . . _ . . _ . - _ _ , . _ . _ . _ _ ~ _ . _ _ _ _ _ . - . . _ . . _

1

Revi 4 3 ,- ,

~*

f. .Noi...al, Abnomal and Emergency Ope 1 Ding Procedures N '

'.x

g. Radiation Control and Safety

h. ' Technical-Specifications

, i. Applicabic portions of Titic 10, 01 apter I, Code of Federal Regulations' +

2. " Each licensco who fails to achicyc a grade of 80% in a gg grado ~section or sections shall- be Inquired to attend

. Icetures given portaining to the subject material in which .

he has shown the deficiency.

3. The nomal' lecture series will be scheduled so that each , ,

t .

-licensec will have the opportunity to attend each lecture t. %

in the normal course of his work schedule., N _,

' s i 4. ~ An examination will be administered at the completion of the C. '

lecture period. Any individual failing to achieve a grado of 80% will be given individual instruction on the material to be able to achieve a satisfactory grade. j, q

(.

5. The training coordinator shall maintain the following records [

for the lecture series: G;

~

a.. Attendance Record k

b. Results of Examinations Administered -

c. Schedule and Curriculum Record ,

-C. Operator Review Program 1.. All licensed operators and senior operators will review .m' facility design changes, applicabic procedure changes and facility license changes.

f

%f%

2. The training coordinator will insure all licensed operators W6 and senior operators review all abnormal and emergency  ;

procedures, at least annually. The completed forms will be returned to the training coordinator for file in the g *'

individual's file.

E .

! ..6

3. .The performanc6 of all licensed individuals will be evaluated o .,'w . .

during actual or simulated abnormal and amergency plant .  ;',

, conditions. This will be done to meet the requirement '

~ -

for systematic observation and evaluation which appears N

.in Paragraph 4c'of Appendix A of 10 CFR Part 55. This will be accomplished b oral examination in the case of N simulated emergencies. ~These evaluations will be docu- ~

[" '%g pf.

r s

N,.j.mented'andplacedin!theindividual's1

, . . . m file.

n ,,. -

{Y . '

> ~

~

o

.. ~ , .

, .% i .

NS p

• t t,

i *

.7, 6 (b ,

f' . .

!a4 ~

. 't E

A s

4 p

,, a vA ,

• % *  ;  % t -

IS

, , , . _.g. ~ _

...m. ... -...._m_.. .. m ;_ -.m... -

a' ,

+ -

6 -

AP-0500 ' ' ..!;

- Rev. 4 3 D.:  : Reactivity Control Manipulations <

-F 1. Each 15consed operator:and senior operator is required to  ;

d ;porform or direct at least ten significant- reactivity changes, which demonstrate familiarity with the-control systems, b, ._ - .9 during the two year duration of his license. Refer to

' Appendix A of this procedure for a listing of reactivity N$

"" b '

changes for which_ Yankee Rowc'will take credit.

, :2. Reactivity manipulations will be documented by the training

• coordinator. This information will be incorporated into

-the individual's' training records. '

E

3..

Each operator should makc~ an effort to perform a variety yq

}l of reactivity changes. in lieu of the same reactivity change , f ten times.. ..

'?

E. l Operating Experience- -i ,

1. 110 CFR 55.31 requires satisfactory demonstration of knowledge and anderstanding of plant operation for any persons who have

[

- not actively perfonged operator or se:3ior operator dutics for [TN<

a period of four months or longer.

gp

2. Any individual absent from operating duties for a period of-  ;

four months or longer will be given a written and/or an oral  ;

examination to determine any areas in which the individual ..'

. needs accelerated training before resuming his normal _dutics, t

3. - The training coordinator shall ensure the individual who has '

been absent for four months or longer is made aware of d.A :

.. procedure, design and licenso change; which have taken place

'in his absence.- rr W

?N#^

Simulator Training F. "

i 1.

In tho future, if plant operating history indicates a need N4 for training under emergency or abnormal conditions a reactor Mh!

simulator may be utilized. ,

@% 4 .4 se

. 2.. -This training, .if used, will be used at least biennial +

4!

for all licensed operators when the need for such training *

[;

tis indicated. .

s" My.

x g DAM

-*; . t

.s.

g y

& s mi " -

, v. ,, ,

5

• 0 }

, 4?

1

[,

m .M 1 o,

f 7k((,

'(

m.- l' 1 JMp t

',f:f, ,

• g{

m.. ,

3. The training' .aordinator will be responsibic ~/r documentation of any individual's participation in simulator training.

~ '

G. Special Training Assignments

1. The training coordinator shall document special training assignments executed by licensed operators or :,enior operators, m.

l such as: * (94 s~, ,

a. In-plant assignment to another department. ,

b. Off-site seminars or classes.

I

f. -

g.wg P

,4

,i

[__.__ .

l -

i

h. .

• nWjg e W5

~

f 0

,.v I -

e% "

n.

m. .

g[<

6- f(

• f,- t, e,< .:

\ d' g p,

\

u JR ' s

~ , ;, .

, , 3 ~* .~ i a

e *4 .g

.+* ek sw e M of e #. ,% 3

i. 3

.. . a. -

1 -

F-0500 .

/. 4

, App. "A" 1

YANKEE RONE OPERATOR TR\lNING PROQ.O!

APPENDIX "A" $U k',

C/gr SIGNIFICANT REACTIVITY CL\NGES t

1. Reactor startup to the pcint of adding heat.

21 Controlled reactor shutdown.

3. Manual control of steam generator levels during startups and '

O '%# '

shutdowns when power is less than 15%. t.s

w. p

4. Operation of the turbine governor controls in manual during startups and for power changes equal to or greater than 10%.

5. Boration or dilution which changes boron concentration by at l 1 cast 10 ppm. t

6. I Operation of the manipulator crane in the core during re-fueling.

}

7. Any power changes of 10% or more in manual rod control.  ;

8. Manual rod control prior to and during generator synchronization.

(m : -

. . c h 20*%fW 6,q%.. u r '} il

%y;qt f I'it

- $:p'%

v e a

N, r

-* ( *<f

v. L..

.s

) .y-

\

(.

Q e

6e i .-.

g* .umem-*

1. , Y Y s5f f h ? ?*N.sY M N. 'Qfh*.* < p*' *r* , [*~ w

, ,e _ e ; rs. + ,av,y g a ~e,

, y p a.

'