ML20126M323

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Forwards Draft Proposed Rule 10CFR50 & 55 Re Reactor Operator Qualifications.Operators Should Be Required to Have Bachelor of Science or Bachelor of Engineering Degree
ML20126M323
Person / Time
Issue date: 06/09/1981
From: Ahearne J
NRC COMMISSION (OCM)
To: Bradford P, Gilinsky V, Hendrie J
NRC COMMISSION (OCM)
References
RULE-PR-50, RULE-PR-55 NUDOCS 8106170041
Download: ML20126M323 (49)


Text

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C4 UNITED ST ATES i

E NUCLEAR REGULATORY COMMISSION e

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WAS HIN GTON, D.C. 20555

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June g, 1981 7

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. OFFICE OF THE I

COMMISSIONER 5,

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l AEMORAi1DUM FOR:

Chairman Hendrie 2

Commissioner Gil'nsky '

N t

4 Conmissioner Br dfo FROM:

John Ahearne i

~

SUBJECT:

OPERATOR QU FICATIONS AND LICENSING PROPOSED RULE (SECY-8T-84 l

I continue to believe that the overall qualifications of reactor operators can be improved in a significant and important way by requiring operators to have a Bachelor of Science (BS) or Bachelor of Engineering (BE) degree.

A BS;or BE degree is a strong indicator of the technical knowledge, general aptitude, sense of responsibility and commitment that I believe I

is important for-reactor operators to have, particularly during an t

unanticipated emergency situation when written procedures may not apply.

As a point of comparison, 97 percent of all _1980 new pilot hires of major airlines had 4-year degrees.

A 4-year degree is required or preferred by S6 percent of the major airline carriers and an additional l

34 percent. require or prefer 2 years or more of college (source:

Future Aviation Professionals of America).

I also support in concept the plan presented by Commissioner Gilinsky for accommocating the Reactor Operators (R0s), Senior Reactor Operators -

(SR0s), and Shift Supervisors (SSs), currently in the system.

This plan i

provides a reasonable approach to upgrade the technical expertise of 1

nondegreed operator personnel while minimizing career impact on the i

indi vidual.

I' propose that Commissioner Gilinsky's approach be combined with a phased degree requirement in the following way:

l 1.

Licensees would be required on a phased basis to eventually hire or

-. reassign-degreed personnel to fill at least 50 percent of new R0 positions.

To provide for transition, at least 25 percent of new R0s would have to be decreed during tne tnirc year af ter the effective cate of the rule.

Startina with year 4, at least 50 percent of new R0s would have to be degreed.

2.

New nondegreed R0s, SR0s, and 55s would have to meet the requirements specified in Commissioner Gilinsky's proposal.

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2 3.

There.would be no specific percentage requirement for the total number. or. number. per shift of R0s, SR0s, and SSs with degrees.

Once the basic new hire and reassignment criteria are met, normal

. licensee selection procedures would determine who would be promoted to SRO, SS, or other Kanagement positions.

4.

Licensees would be encouraged to rotate engineers from support and maintenance staffs through operator positions as a method of meeting the degreed requirement for~new operators and also for broadening the experience base of key engineering and management staff.

5.

The long term objective would be to require all new reactor operators to' hold a BS or BE degree.

Prior to implementing this requirement, however, and at the end of a five year period after publication of c

the rule, NRC would assess the effectiveness and benefits of the c

revised criteria to determine if all new reactor operators should hold a BS or BE degree.

Assuming an average of approximately 50 reactor operator personnel per unit and 20 percent turnover per year, the net effect of my proposal would be that each unit would have to hire initially three and eventually five degreed operators per year.

I think this is clearly achieveable with the proper commitment by licensees.

Sufficient pay and advancement incentives can outweigh the disadvantage of shiftwork.

I suggest my proposal be incorporated into the rule as an alternative on which public comment be asked.

Attached is such a version.

Attachment:

As stated r-ace:

EDO

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to that of verif. vine. that the operator can c.oerate the a

contrcis, er supervise the operatic. Of the centrols in the case of a senior operator, in a ccmpetent and safe manner The annual examination will incluce an cral and simulator

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ecliece level course requirements, at the rate of 6 semester h o u..e oe-v_ea c'

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I 16 fe: which the sh;f: s u p e rv:. s c r 1 cense

_s scught.

Th :. s las requ:.: ement ceuld be-waived, wi:P ca s e-by-ca s e substituted requi*:emer.:s, fer plants that have ve: ic be crerated.

The Corr.irsion seeks comments on what substitutions may be appropriate.

These prepcsed amend.ments and add:.::.cns c 10 CTF. Par:

55 contain requirements for training and fer ecliege level courses which are specified independent cf each Other.

f the required training prograr. is suf f :.ciently ::. : c r e u s, and especially if accredited by a recogn:.::ed +5ucaricnal body, the Conr.issien may allow substitutier cf elements of the training program. for the proposed ec11ege level ecurs.e

.r e qu ir eme n t s.

Eowever.,.._the _ Corr.i s s ier ha.s nc : ye develeped standards for such substitution and s eeks publi; cer. men: en th:_s peint.

In addition to the above, the Comission seeks public comment on an alternative which would require college degrees for some operators.

dk A Bachelor of Science (BS) or Bachelor of Engineering (BE) degree that includes

}i&%

at least 60 semester hours of specific technical subjects would be proposed as l

the education requirement for at least 50 percent of new reactor operators.

Thit I

woald be implemented in a phased approach to allow reasonable time for comoliancd.

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4 17 I

l 1

l 1

A BS or BE oeoree serves as a measure of the individual's initiative to complete a comprehensive training program and is a general indicator of knowledge of the physical sciences, mental aptitude and sense of responsi-bility.

Such qualities are consistent with the strengthening of the cadre of highly trained and highly dedicated professional reactor operations personnel.

Related to the requirement for 50 percent of the new reactor operators to have BS or BE decrees is the expectation that utility management will look for indiviauals with degrees and experience as reactor coeraters as candidates for more senior positions in the nuclear lJk i

portion of the company.

Such opportunities for advan:ement for indivicuals

'h3d,ds l

with degrees should serve as enticement to serve on shift work.

A corollary to this principle is the option of rotating engineers in technical support and maintenance staffs into reactor operator positions.

Such reassigns would credit toward the percentage goal for degreed new reactor operators and at the same time would broaden the experience and perspective of these support functions.

l This alternative does not envision that specific requirements will be set for the percentage of degreed reactor operations staff in total or on a given shift.

Once the basic new hire or reass4crent goals ere met, I

normal personnel selection procedures would detemrine wht wculd be pro-moted to SRO, SS, or other management or staff oositions.

l 18 The long term objective under this alternative would be to have 100 percent of all new reactor operators possess a BS or BE degree.

Prior to implementing

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this requirement however, and at the end of a five-year oeriod after publication of this rule, NRC would assess tne effectiveness, benefits k'M and problems of the revised criteria.

Based on this evaluation, a determination would be made r_egarding the desirability of all or part of the reactor operators having Bachelor of Science degrees.

Guidance on the type of instruction which is acceptable te the Cers.ission staff fe: meeting the recuirements cf "ccilege level education" has been included i. Preposed revision 2 to P.egulatory Guide 1.8.

The type of s.mulater recuired c be used := cc5duc.

trainine would also be specified.

Provisions h2ve been i'6c16fe'd~ii Mhe crepesed amendments for'the Cerr.ission to approve alternative types of simula:crs, potentially for cider ene-cf-a-kind plants where procurement cf a simula:cr in accordance with the similarity recuirements cf the proposed

~

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rule may be impractical.

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wculd be developed case-by-case; cc..d...c;;de add.:;ena.

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the Inere..v Recre.a..ication Act cf Ic74, a s

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5 2.,.

c.e ~..;., e o-o. th e L,.:. e.:.....e.a.e.,

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- z e _is hereby civen that adoption of the followine a:neni.ents c 10 C.. s e ?.

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as an co.erater er a senior operator are cesse.nec to tes: :ne applicant's understandine. ef-the facili:V desie.n, the theer.v.

of co.eration,' and famiiiaritv with the centrcis and coeratinc.

,_. o e.e t. e.=. o' *he c.4'.4 v.

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Section 55.21 is e. mended to reaf as fc11ows:

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Sec.

--.e.

Cc.e.

ope a.n

-=

The operator wrinen....exa: ination, c the ex.en applicable 4. c.' u d e c u e.e

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.4.

(a)

Princioles of Reacter Plant o.c e r a t i on.

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.,eco:.msn.ddi.'on 10 of SECY-7 c-310I.

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s A

co.-.-

od e.'.# e...e., ' a n d c *.d *..' c a- ' i '..v 4._~4.'. a ' o.. s.

(2)

Sin le calculations showine. understandinc. of the principle invcived in this area.

(3)

Reactivity anf uhe effects Of poisons.

(c)

Features of Facility Design.

(2)

General c.esign.,eatures c, :ne core, incaucing

.e.,e. e. e.. e,. e.

..,. 3 o : e., anc coc a.

cc.e e.......e,

.e ma c k..

. (2)

Mechanical._.. design of features Of the reae:cr

.. a..v o w a' a...

e. v.e. e.. a n d a ' y...'.' a.v

.e v.e. e...e

... + -. - -.

.e

.m u.

M g

6

(I}

Shieldin; cesign.

(4)

Overall desigr pers:ective

' systems im::r.an; :: safey (5)

Electric power distritu-icr in:1utin; n:rmal, a', ternate, and emergen:y power, supplies for plant use.

(6)

Design limits (e.g., me.ximur flow, minimum vacuum, maximum 1

i pressure, allowable load) or fixed numerical values fer fabrication (e'.g.,

enrichment, dimensions).

(7)

Design features for normal ant'oe:ay heat removal.

(d)

General Operating Characteristics.

(1)

Causes and effects of temperature, pressure, flow, and reactivity changes.

(2)

E f f e c t s.o..f...g.a d. c h..a n. c e s.

lo (3)

Secondary system transients that indu::

reactor tran.sients.

(4)

Operating limitations and reasons.

(5)

Primary coolant sub:ocling, b:ilin; and su:erhea; ce e:-ion.

(e)

Instruments and Controls.

(1)

Design, cohponents, and function of rea::ivity and tre:ess

ct,aci..c.e:hanists and interlocks.

4

  • e 8

g

~

. ( 2 ',

Nu: lear En: process ins: u eristier (3:

In:cre instre:.enta:i.cr s es ter.

('

Purpose, principles, an: 'a iure c::e! :' con:rci rect instrumen:E icn, alares,' and annun:iators.

(E)

A ident m:niterin; ins rumen.ation.

(6)

Fundamentais of eie: ri:ity as. it per.ains to instrumer-tation and controls..

1

-(f)

Safety and Emergency Systems.

(1)

Design, components, and' function of systems designed.to prevent or mitigate accidents, includin; instrumentation, interlocks, and automatic and manual control features.

(2)

Setpoints for automatic features.

(3)

Components, capacity, and fun:tions cf reserve and emer-o.eney s.vstems.

(4)

Isolatipn. ap?. :entainme.n des.is.n f eatures.

_. (5)._ Locations and controis Of emergency shetcown paneis.

(E)

Use of 'all available stru:tures, systems, and compenen s that can centrei er mitigate degraded : re a::icents.

(g)

Standard and Emergency Operating Procedures.

(1)

Immeciate actions fer ene gency precedures.

"#~

-~ ~~~ ~'

(2)

Major steps of stan: arc ro:ecures.

(h)

Eaciatien "en:rci and Sa'ety.

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intiuding alarm and survey eceipment.

(2)

Radicio;i:El safety pr4.:i;ies and : ::edures.

(2)

Raciciogicai limits.

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.....1

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

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(4)

Types cf radiation r.:, s,

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!55.22 Centent of s,3nier operater wri :e.. exar.inatier.

Tne senior operator written exarination,.:. e exten a::li:a ie to the f a:ility, will in:lude cuestions en the : ;ics listed in pa a-graphs (a) through (h) of 555.21 (Relevant examples are also incluoed), and the following:s,$

(a)

Theory of Reactor Plant Operation.

(1)

Hydraulics and fluid flow theory.

.(2)

Heat transfer theory.

(.~: )

hermoc.ynamics.

t (4)

Calculational problems showing understanding in this area.

(b)

Reactor Theory.

(1)

Theory of fission process, neutror, m.itiplicati:n, s:urce

... effects, ccntrol rod effects, and criticality indicatiens.

e (2)

Ca.iculations showing understanding in this area.

(c)

Radica:tive Material Handlin;, Cisposai, an: Ha: arcs.

(1)

Radiation hazards that may arise curing the performan:e of experiments, shieldin; alterations,.aintenan:e a:.i. i;ies, and varicus contamination conditions.

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'See page 21.

S'See page 22.

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(2)

Snitiding effe:.! tr radiatier a.:

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t.,

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.s (1)

Cocient chemistry.

(2)

Rea::ivity cal cia-ions fer : '.i:a'ity and char.;'n; power.

(3)

Specific operatin; characteristics Of rea: or and auxiliary i

systems.

(ei Fuel handiin.o and core parameters.

1 (1)

Procedures and limitations involved in initial core load-ing, alterations in cre configuration, contrei - : programmin;, and deter-

~'~

mination of various internal and external effe :s c; cere,rea:tivity.

(2)

Procedures and ecuipment used in fusi handling.

(2)

Fuel element characteristics an:' limitations.

(f)

Administrative Protecures, Conditions and Limit.ations (1)

Conditions and limitatiens in the fa:ility license.

..(2)

Design and operating limitations in the technitai spe:i-fications for the facility and their basis.

(3)

Facility licensee peccecures require: :: cbtain at h:rity for design and operatin; changes in the f acility.

(4)

Facility ' ensee : ::ece es for.ne e'.iev En: approval cf ex:eriments an tests.

(5)

Emer;en:y procedu es inciu:in; site an: :ffsi.e n :ifi:2:icns.

J.

The first paragraph cf f55.22 is amenced to rea: Es feiio.s:

!55.23 Scope of operator and senior operator operating tests.

Tne operatin; tests a ministered :: a:;ii:ar..s 'c Operater a.:

senior operai.c'r licenses are genera,ily sim iar in s::pe.

.er the

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plants snall De a:~inistered us'n; tne same ;yre :f simat:- es requi e:

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.c tes, to the ex.ent applicable 10 the f a:il'y,

epuires.he aficant.:

oemenstrate an un erstanding ef:

n s

s 11 Paragraph 55.21(e) is amended te read as fellows:

g55.31 Conditions of licenses.

n s

n r.

s (e)(1)

If a licensee has not been actively per. forming the functions of an operator or senior operator for a period of four months or longer, the operator or senior operator shall, prior to resuming activities licensed pursuant to this part, cemonstrate to the Commission that the knowledge and. understanding of f acility opera. ion and administration are satisfactory.

For nuclear power plant licensees, this cemenstration shali in:iude re ertification on a simulator of tne same type as rec.: ired by Appendix E t: this part.11 (2)

The Commission may accept as evioence, a certification by an authorized representative of the f acility licensee by which the licensee

-nas Deef. emp 1 oVEC.

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see Encicsure "E", iter 2, Recommendati0n l'. Of SE?-79-310E.

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prior to returning to licensed cuties 1 lio.cin; a period of 4 m:nths of licensed duty ina:tivity.

Aisc see En:lesu e "E", i.er 2, Ee:ctmenda-tien 7 of SECY-79-220E.

g 9

w v

36 p.'-Para;ach55.31(f)is'renutoee: 55.31(g) l-6 para;rapr.

55.31(f) is adce: te read as fe'ioss:

s55.31 Conditiens of licenses.

r r

i.

.ne operator sha.l participate ;r a recua.ification pregrar:

i s.

(f) pursuant

Ac?endix A to inis part and sna satisf a:teriiy :::;1ete

.a annual examinations as, require,d by Appenc..;x A te thu. Part. "

13.

Paracraph 55.22 is a:nended :c read as follows:

Section 55.32 Expiration.

Each operator, senior operator and shift supervisor license shall expire twc years after the date cf issuance.

M.

Paragraph 55.33 (a) (4 ) is a:nended, c read as f cilows :

Ser. 55.33 Renewal cf licenses.

(a)

(4)

A statement that, during the effective te r c' the cur-ent license; the~-opera.6F bTiiidMr 5pertter ap;M: ant has satisf actorily

~

.c.ompl.e'.e.d.-the. -rec.ualification proc. ram f or the f acility f or which operater or senior operator license renewai is sought.

If an applicant has not satisf ac.crily ecmpieted all ef' the recualification ;r gram, the appii-cant must specify in the application for renewal (i) the area (s) in which program participation was incomplete, (ii) wher the prc;rac will be coc-pleted, and (iii) the special f actors, er Other,iusti'itation, bearing on

~

the renewai wnien the applicant wishes tne

m-ssic: :: :cnsi;er ir l

relation.: the in:cmplete reocalificati:r :r ;ra M

K F

7

-'hequires participation in a recualificatier ;

rar as a cen
ition of i

license.

.Ai:so see Enciosure "B",

iter 4, F.ecommen::atien 9 cf SECY-79-330E.

ug33ew3 fey cises in which a renewal applicant has not fully comcleted 5

a recualification program.

Also receires infermatien te be in:iuded to allow the Commission to determine additienti raining neecer pursuant euwsutamu3 -

t

, o 4

5.

ara: apn ::. :d, ) is amence:.: rea: as,.: r o.es :

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y (b)

In any case in wtich a' licensee n:t less than thirty days Orior tcth[ex:irationt'hisexistinglicense.hasfile: Er ao:li:stier in 1

proper ferc for' rene.<ai or for a nee'.i:ense an:.ne 'icenset has sa*.is-factorily conipleted at least one annual examir.ation under a recualifica-tion program pursuant t$ Appendix A te :nis' part, the existin; license

[,1

?

shall net expire until the application.for renewal or for a new license has been finally determined by the Com.ission.

W S

44 v t

16. Paracraph-55.33(c)(2) is amended tc read es follows:

g55.33 Renewal of licenses.

(s) a m

x

( ; ', ' i ;

The licensee has b+e.-

a :::.v ely and ex tens;.ve2 -

3 engaged as an operatort er as a senior operater er as a shif:

- -. n.u.z. e.. es.~..-

+

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be exa e..a...

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sibilities cer.petently and safely, and is capable of cen-inuine to do sC.

(ii)

The licensee has completed a recuali'fication procrat

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10 satisf ac.crily ::m;lete at:iti:.nal trz#rin; er exa-ina ions, or :

.n. 3 x

x x

    • An applican wn: does not mee. the re:.;iremer.ts f er li:ense rene. cal mEy be repujre.d,.tc take additional trair.in; er exacinaticr.s r b th :: ensure

(

. he is. propenly re. rained for the license.

Aisc see Enciosure "E", item 4.

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4

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u.

A new paragrap:. n. n.:. u

_s a::e: :: :ea:

as cc..cws:

_ce:

.senewal c*

censes.

M; pe r -n di e a r-pe w e r -pi & F. s -sp e r a s e r -ii e e n e e -r e d e ws i e ppi e e s s s e r.e - r e c e s v e d-a s s e r - B e e enie r - G i-- hi f i-- e e.d.;~ ; r non-decreed nuclear power plant senior operator license and shif: superviser a

license renewal applications received after anuary 1, 1985, se e enie r-6 & r-i966 7 the applicant for the license meets the.

se minimum education _a_l rec.uirements in Ac.cendi9. "E" to this par t. - ~

M.

A new paragraph 55.40(c) is added te read as follows:

555.40 Modification an.' revocation of licenses.

n n

n n

v (c)

Any license may be revoked or suspended for f ailure to satis-f actorily complete annual examinations as requirec by Appe.ndix A te this part.18 -

7--.,.=_..

c._....

. APP.ENDIX A - Requalification Procrams For Licensed Operators of Production and Utilication Facilities l

19.

Appendix A to 10 CFR Part 55 is amenced by celetin; the fourth l

paragraph of the " Introduction".

l

....._ 2 c.. Paragraph 2 of Appendix A tc 10 CF?. Part 55 is amence: as 1:11o.s:

1 Requalificatien Prograc F.ecuiremen e 7

R v

7

_he requah.,ication Oro; a: sha...'i incluc.e cre:.,anned 2.

Lectures.

i j

iectures on a, regular and continuin; basis :nreughout the iicense period s

1

    • Specifies ef f ective dates of ecucation requirements for nuclear power plant license renewal applicants.

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te be upc.raded.

0 her.rainin;.e:hnicues includin; f#its, v deotapes an:

.her i

effect've trainin; aids may aise ce uset.

Individual stud..v on the part of each operator shall be en:ouraged.

However, a re9ualification Procrat based solei.v c:en the use cf films.

videotapes or indivicual study, or all three, is not an accep. table si;b-stitute for a lecture series.

g.

Paragraph 3.a of Appendix A to 10 CFE :ar 55 is amen:ec.to read as follows:

Recualification Procram Requirements n

n s

r 3'

On-the-j ob-t ratniTig.

The recualif.icatior program shall include

.cn 'he-job tr.aining so that:

Each licensed operator of a production or utilitation f acility a.

manipula*.es the plant controls and each licensed senior operat:r either i

manipulates the controis or directs the a:.ivities of incividuais durin; piant control manipulations curin; the tero of

.n.e'."

licenses, ror C.*.*,'

" o B C i ( *.

e'

c. s

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Tnese re:vire-enough te satisfy recualification ; o;rar re uiremen.s.

mer.ts f,ayp lbeen expanded by the May 2E, ISE" it;*.er f r:- the Dire: tor of the.0.f.fice of Nu: lear Reactor Ee;'.'.E; ion an: are expectet. : nan;e i

as additional recuirements in this area are oeveloped.

. - ~.

i

_ 3.; _

)

l g.

Pa-a;ra:r, 3.e.cf Appencix A t: '.' -:' 'ar; !! is ans.,:e: ::

read as fcilows:

1 Requal.ificati:n Prograr Re:;i ements r

r he r e c,u a i,. ;. ation sna i in:iuce on-4.

n-the.lo

.rainanc.

i e

the-job training so that:

e.

A simulator may be used in meetin; the requirements of para-graphs 3a and 3b if the simulator is of the' type specified in Appendix B te Part 55.

A simulator of the type specified in Appendix E to Part 55 shall be usec.tc concuct abnormai, inf recuent, En: eme rgency e'le..: ::ainin? ;

for nu: lear power plant operaters and senier coeraters."-

H.

Paragraph 4a of' Appendix A to 10 CFR Part 55 is amenced to read as follows:

~: :~ c - -

Requalificati..on Program Reevirements

..:

  • R R

R F

F 4.

Evaluation.

The recualification program shall in:1ude:

a.

Annual examinations to determine that cperaters and senior operators have sufficier)t knowledge and exoertise to continue licensed d ut..i.e s.-.

m.sh m

'1,

' ne C O=.:. s s i e r s t a f f : r ::= ; s s :. r a:Oreditef centra ::: staff V:ll ad.= n:. ster the e::Enna: 1:ns ur._ess :-

9 dire :s the facility licensee :: de s.

    • Re vires.tne use of a simulater in :ne re:;giification ;re:73,
33e stE !..n c. i C s.Us*e " E ", i tem 2, R e c omme n d a t i 0 r c f S E ; Y */ i-3 30[,

(

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l

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- written, oral, and pr.a::1cas (performe: er a simulator 'er nut rea :over Diant operaters and senior Opera.crs) examint.icn.20

24. Para:raph 4d of Appendix A tc 2C CFR Part 55 is amenced t:

4 read as follows:

Requalification Program Receirements R

R R

R R

4.

Evaluation.

The requalificatier pr:; ram shali inciuce:

d.

To meet the requirements of paragraph 40,-simuistion of emer-gency or abnormal conditions may De accomplished by using the con:rci anel of the f a:ilit.v involved or b.v usin; a simulater.

Wnere the e

contro. panel o,, the,.aci,nty is usec f or simulation,.ne actions taken i

or to be taken for the emergenc.v or abnormal enditier, shall be discussed-.

..___.l.... manipul _ation of the plant controls is not requ;. re.

.f a simu fator a:tua is used it shall be the same type as specified in Appendix 5 te Part 55.21

& A new Appendix B to 10 CFR Part 55 is aeded te read as fc11ows:::

i

--EeOui"es ne annuil eXa-inatiOr.s 1; i n:l u0e a W"i *.e *, C rai, a'.:

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s.

..s IEefers *.: AOpendiX 5 tC Part 55 Vnen Oes *Ti;in; :ne *.yDe f s im.'.a.Or o be used.

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One appalcant,.

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.as, earned to opera:j.

o, tne app 3.1 cant, anc evicence that the at. :., a can:

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the controls in a competent and safe ma..ner.

The mini. mum acceptaEe qual:.fications of nuclear power plant ap:licants are listec in this

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chtain a shift superviser license' are E semester hours after January 1, 1952, 12 semester hours after

" January 1, 1983, 18 semester hours af:e.: January 1, j9E4, and 24 semester hours after January 1, 1985.

..g g e.. 4.. ~...e y.e e7e.....

.ee.-. e.,, v.e.. q.

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

c license after January 1, 1985 is 24 senester' hours.

1 l

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befcre the eff ective date of the rule have unt:.1 the

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may obtain experience credit at the rate Of c

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hours per year as an NRC licensed opera:cr cr senior operator be!cre Januarv.

  • c

- &c ' ~. - "...

. c.... e
e. _._

-1. =achelor degre'e in encineerine will be t a P. e.-

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g con :6.3 room ex.cer ence as a 2 cense: senic: coerator.

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havin; a tinir.um Qf One year Of cor.: :' rc r experien:e as a senior operator on the unit at vhi:.* *.ne supervis0ry :sfigna-tion is mace.

Befere ir.itial f aci".ity Operation, *.ne %mmis-sien may waive this last reoviremen; an: substitute case-by-case requirements to accommodate the f act i. hat the f acility has not yet been in operation.

C.

TRAINING 3.

Individuais assigned tc *.ne positions sha}i hav.e:

.ense.....,.:... w.u u.

. een!-.

z

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o 1...e c p e

c...,.

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supervisory designation is made, b.

received instru: tier in the fellovin:. superviser.v skills:

.l.eadership, 7nte? personal communicat..ons, comman: respon-

---sibilities and lim.ts, motiva. ion cf personnel, proble s.

i analysis, and ac..ministrative recuirements,or the parti-cular supervisory position, and i

c.

received three months of shift trainin;, with ne other con:Urrent duties assigned on the uni *. fer which t*4 super-

~

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visCry designatio* i! ma*e.

hring *.'.i s traini n;

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Esfore ini*.*.ai faci ity C*,re*ati0n, int Com-ission may vaive th's ret.uirere n and substitu*.e

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12 semester hours after Januarv 1, 1984, anc-18 semester hours after Januarv 1,

1985, The minimum

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.r not yet been in c.oe. atien.

... C..

..TPAINING:.The ac.clicant must have:

r,e e e.ev e d. a.d..i.n e.

o.*. c 7 d...". e.

S.c v e d e n. ^, ^..e.

c-e # a'-.4.v.

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Cencurren duties a: :ne

,ac.... :. :V.cr wn1Cn :n.e 1.. Cense.

is sought.

During this training the applicant has, unde the obse.vation and control c' a licenseC senior opera:c>

S, e

N,.;.e,e;.

he

..c...;y-....c.in, C.<

ue

.z.

a.

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'n. g e. 1eyg.i c3 r

w Corporate managemen:

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43 2.

The certification must centain details en (these items may be i;corporated by reference to other corres-pondence):

The courses of instruction; a.

b.

The number of course hours; The number of hours of training; c.

d.

The nature of the training used to fulfi'll the requirements of paragraph III.C of this Appendixi and The differences between the simulator used to meet e.

the requirements of paragraph III.C.1 of this Appen-dix and the facility fcr which the applicant seeks a license, as well as the actions taken to help ensure that'shefe differences U ll not result in the applicant

.;y0

-.-misinterpreting plant response er taking incorrect action.

~

~

~~4 IV.

QUALIFICATION REQUI?2MENTS FOR APPLICA';TS FOR OPERATOR LICENSE A.

EDUCATION:

For initial applicatiens received after December 31,

'9cli the applicant must hcid a ig? sChoO1 dip 1C~a.

t

..)k, (The followine additional wordino is beino considere dd 'N In addit lon to the above, during the period January 1 to December 3 1984, at least 25 percent of new recipients of reactor coerator licen must oossess a Bacnelor of Science (BS) or Bachelor of Engineerin s

l li 0n 1

I u

cegree that includes at least 60 semester hours of specific technical i

I subj ec ts.

Durino the period January 1 to December 31, 1985, and each bh calendar year thereaf ter, at least 50 cercent of new recipients of reactor Ud&&

operator licensee must possess a BS or BE degree that includes at least 60 semester hours of specific technical subjects.

(

B.

EXPERIENCE:

The applicant must have a minimum of:

Three years of experience in the testing, operation, and main-tenance of power ceneratinc. elants 'nct necessarily nuclear).

Two years of this experience may be substituted by

^

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s i.e.

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experience must be at the facility for which a license :.s sought, including s i>: mon:hs of duties as a non-licensed operater.

Sefere initial facility

, e. a..'...,

'n e C o.....' s.e.'..

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ai e e e--M.w-~w**eeeTh've+-=-s-

i 45 C.

TFJ.:NING :

The applicant must have:

l

.g e g. n ec g.a...a.n e. c..

g..
g_~..~..e c..e. c..;,a

~.

a s... ; e.

f actorily operate a simu' a:cr whese reference. pl. ant, v;;r respect to the f acility for which a license is sough

"..' e s e e.h e w d s e a 7.-.". e.

.'.v

. e w-..... s s c...-

e 4

7 Is the same type of f acility (e.e.,

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a.

, b.

Eas the same type-cf cen rel rect (e.g.,

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