ML19308D030

Met Ed Operator Requalification Program

ML19308D030
Person / Time
Site:	Crane
Issue date:	04/07/1978
From:	Metropolitan Edison Co
To:
Shared Package
ML19308D031	List: ML19308D030 ML19308D033
References
TASK-TF, TASK-TMR PROC-780407-01, NUDOCS 8002180015
Download: ML19308D030 (21)

Text

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METROPOLITA'T EDISOII OPERATOR ?.IO.UA1IFICATIC: PROG?J.M 13.2.2 The Metrepelitan Edisen requalificatic progrc=, as set ferth in this docu=ent, applies to the Three Mile Island ITuclear Station.

All licensed personnel vill participate in the applicsble pertien of the requalif#ca icn pro-

. d.m.

The basis of the requalificatics propa= is the need te -a'-tain operator p a=.

co=petence and proficiency in the quest for centinued safe operation.

"he guidelines for the requalification progran are found in 10CFR55 Appendix A.

In addition, the i=ple=entation of this pr.:pa= cc=fo=s to 10CF 50.

I.

Progra= Schedule II.

Pre-pl ened Lectures III.

On-the-job training IV.

Annual Evaluation Exa-*-atica V.

Records

' VI.

Accelerated Requalification Progra VII.

Four Month Absence Progra:

VIII.

IIevly Licensed Operators IX.

Requalificat'icn Program A*-4nistration 13.2.2.1 Proeras Schedule The requalification progrs= ascribed herein vill be i=plemented at a specified date within 9' days after receipt of an operating license. March 1, and subsequent a-"itersaries of this date, v4'1 be considered to be the start-ing date of each annuall cycle of requalification progra= operation.

The Metropolitan Edison Requalification Progran consists of four inter-related seg=ents which run concurrently.

These segnents are:

w 1)

Operational Review Lecture Series (OR) 2)

Fundamentals and System Reviev Program (FSR) 3)

on-The-Job Training 4)

Annual Evaluation Exa=inaticus The OR Series is a classroc= lecture presentation which provides licensed personnel with the details of operational infor=ation related to the Three Mile Island Station. As part of the OR Series, selected FSR topics are presented.

FSR topics are selected in areas where a=ual operator and senior operator v-itten exa=inations indicate that e=phasis in scope and depth of coverage is needed.

OR lectures are scheduled for a =in4 um of 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per year for all single and dual license holders.

On-the-job training is designed to insure that m

licensed personnel operate reactor controls and participate in =ajor unit evolutions. Records of r_11 on-shift perfor-a ce are maintained and periodically reviewed by supervisory personnel.

The annual evaluation examinations si=ulate the written and' cral exa=inatiens administered by the Iinclear Regulatory Cc-

• ssion.

Perfor=ance en these annual evaluation examinations deter =ine the extent cf the FSR progrc= du-ing the fol-loving twelve =enth requalification period.

, Annual, as refer ed to in the Operator Requalification P og-s=, is 12

L*.

=onths, not to exceed 15 =onths, in order to acec==cdate unit cre atiens.

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13.2-6 A=

6k (h-7-73) il w,.

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.'E Each license holder vill complete all applicable CR and FSR require =en s s.,

.on an an"ual cycle.

The On-the-job training is conducted throughout the two year ter= of the individual's license.

All required on-the-job training -#_11 ed '

be completed prior to license renewal.

A statement of Requalification Progen participation v4'1 be submitted with each license renewal application.

The requalification program is designed with fixed perfor-aace standards and specified re=edial actions. The progr?s results and records are fully auditable.

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13.2-6a t. sh (E-7-73) l

13.2.2.2 pra-Pla--ed Lectures 13.2.2.2.1 Crerational Reviev (OR) Lecture Series During each year, personnel shall attend the Operatienal Reviev (CR)

-j Lectrae Series on the following basis:

(a) Licensed station ad=inistrative and technical personnel vill participate in the OR Lecture Series as either students or instructors, except to the extent that their nor-a duties preclu:le the need for specific re-training in particular areas.

(b) OR Lecture Series attendance is required of all licensed operators and senior operators who are nor-an y en shift assign =ents.

Thefollowingtopjesshallbecoveredasar*,1=u: during the OR Lecture Series each year:

(a) Reportable Occurrences (b) Unit Modifications (c) Operating History and Proble=s (d) Procedure Changes (e) Abnormal And Energency Procedure Review (f) Technical Specificaticas (g) Major Operational Evolutions (such as refueling)

(h) Applicable portions of Title 10, Chapter I, Code of Federal Regulations (i) FSR Progra: Material Additional topict which may be presented include:

(but are not limited to) t@-

(a) Operational Q/A Mf (b)

Standing Orders -

p, 0/or (c) Operating Experiences - Reactor Safety and other pertinent NRC publications.

Lectures shall be held en a continuing basis and consist of a mind-"- of 60 scheduled hours per requalification prog a= cycle.

Credit for the classrec=

portion of the simulator tra***v progra= relating to either TMI Unit 1 or II

=ay be credited toward the 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> of OR Lecture.

Attendance of all licensed personnel vill be recorded.

Absences vill be made up by reviewing lecture materials and/or discussions with on-shift supervisory personnel or the technical staff.

The program for each session Jill be deterdned by unit operatic =s or pro-jected operations.

Reccrds of the topics covered in each session w-ill be maintained by the Training Department.

periodic evaluation quizzes covering the content of the OR lecture series vill be ad-*

istered.

The qui :es may be ad *nistered in either the closed book or open bcok for=at, as classroc= or on-shift qui es.

If an unsatis-factory grade (less than 805) is received, -akeup sessions with assigned instructors vill be conducted.

The =2keup session vill conclude vnen an cral evaluation is satisfactorily ec=pleted.

The centsnt of the qui: vill be different for RO and SRO license holders and vill re' lect the tcpic areas and degrees of responsibility needed by the license holder.

Exa=ples of 2These lectures may be gi'nen en ift by Shift Fore =en er Shift Superrisors 13.2-7 A=.

ch (L-7-78)

the =aterials to be used during tha CR Icetura serica ara:

(a) Unit records and icts.

., ' (b) Pertinent ec==unicciens to an'd frc= the. NRC'

~

~~

(c) Unit precedures and changes (d) Test te:ults (e) Applicable training program sateria's 13 2.2.2.2 Fundanentals an-1 System Reviev (TSR) Pror as During each year, licensed personnel sh" participate in the Funda-antals and Syste=s Reviev (FSR) Progras based on their annual written ava-Ntion scores as identified in Section IV - Ivaluations.

The FSR Progras =27 consist of preplanned lectures, self-study assign =ents, possible tutorial sessicas with designated ted 'eal instructors, and evaluatica qui :es. The study assignr.ents and preplanned lectures vill be in keeping with the license level of the individual.~.icense holder.

Individual study assig==ents, fil=s, and video tapes vill consist of no more than 50% of the FSR Progra=.

Preplanned FSR lectures shall be scheduled in those areas where annual operator and senior operator written era

• nations indicate that e=phasis in scope and depth of coverage is needed.

Any or all of the following topics =ay be included in a particular year's FSR Pro 5 ras:

(a) Principles of Operation (b) Features of Facility Design (c) General Operating Characteristics 3

(d) Instru=entation. and Control 4

(e) Safety and Energency Systems including unit / station protection systems (f) Nor=al and E=ergency Operating Procedures (g) Radiation Centrol and Safety For Senior Operators the FSR Program vill also include:

(h) Reactor Theory (i) Radioactive Material Handling, Disposal, and Ea:ards (j) Specific Operating Characteristics (k) Fuel Handling and Core Para =eters (1) Ad *"istrative Procedures, Conditiens and Li=itations Perfor-aace of FSR assign =ents vill be deter =ined through written j

evaluation qui::es. These qui::es vill be specifically directed towarti 30 l

and SRO kncvledge requirements. The qui::es =27 be ad *nistered in either I

the closed book, or open book for=at, as classroom or en-shift quis es.

A satisfactory grade on the FSR evaluation quJ.: vill'be 80%.

If a grade belov 80% is achieved by a license holder, a deficiency is assigned and the li-cense holder vill be assigned an accelerated requalificatica prega=- as per Secticn VI.

l' 6

4 u.2-3 an.a 9-7-m j

43.2.2.3 On-The-Job Training During the two-year ter= of his license, each. licensed operator shall participate in on-tne-joo tra1+g vnich, has tb.e following geals:

~

(a) Each licensed reactor operator or senior cperator sha participate

<j in ' a =ini=u= of ].O reactivity -anipulatiens as daNad ' 'his sec-tion of the requalificatien progran. Reactor operators or senior operators licensed on both TMI Units can perfor= or sapervise these reactivity ->nipulations on either unit.

(b) Each licensed reactor operator or senior operator shall participate as appropriate, in applicable surveillance testing, syste= checkout and equipment operation based on license level and relevant to the area of license responsibility.

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j P-W (c) Each licensed reactor operator or senior operator shall review /*f hg n

p procedure changes, unit modifications, technical specification changes, reportable occurrences and incidents, either on-the-job or during sessions of the OR Lecture series.3 Each licensed reactor operator sha'1 =anipulate the unit controls to effect reasonable reactivity changes. Each licensed senior reactor operator shall either manitulate or d4*ect the manitulation or the unit controls to e'ffect reasonable reactivity changes. Reactor operaters or senior operators licensed on both TMI Units can perfo:= or supervise these manipulations of unit controls to effect reasonable reactivity changes on either unit.

Reactivity manipulations which demonstrate skil' and or fa=iliarit/

vith reactivity control systems and which are credited to meeting on-the-job

6 training ym include, but are not li=ited to

'N 1.

Power change of greater than 10% full power with the reactor control station in manual.

2.

Control rod manipulation from suberitical condition to point of adding nuclear heat.

3 Boration and deboration ~= euvers involving control rod manipulation.

h.

Turbine startup and shutdovn.

5 Reactor trips and subsequent actions.

g The participation of licensed persennel in the on-the-job program vill be reviewed quarterly by appropriate supervisors to insure that operators,

participate in a variety of evolutions. If diversity of operations is laching,

@p specific assignments may be made to ensure vide operator experience.

Included in the following ifst are exa=ples of additional operations which may be considered in this category.

These sa=ples are not to be considered for reactivity manipulation credit.

1.

Surveillance testing including

. a.

Contain=ent spray syste=

b.

Safety injection c.

E=ergency Diesel Generators d.

Che=ical additien system 2.

Makeup and Purification Syste: Operation i

.3 Decay Heat Re= oval Syste= cperation lY' i

h.

Feedvater Syste Operatic:

1 3caly those changes, incidents, etc., which are selected by the supervisor of i

Operatiens or Supervisor of Training as pertinent to unit operation.

13.2-9

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5 Reactor Coolant Syste=

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6.

Turbine Valve Testing 7

Pressuricer Operation s.

C.

Incore Monitoring Syste: Operatic:

9 Control Roc = Calculations including a.

Heat balance b.

Quadrent tilt /i= balance / Rod withdrawal index c.

Reactivity balance 10.

Portable HP Instru=ent use.

ffffT {G7CSCk M f 0p 4 Licensed personnel, whose job assign =ents are not directly related to unit operations vill actively participate in control room operation an average of k he'i-n ter -c-a - During this period these licensed perscnnel vill participate in whatever activities are in preg ess. Reactor operators or g

senior operatops licensed en both TMI Units vill actively participate in d

either unit's control room operation an average of E hours per = cath.

I A simulator =ay be used 4" meed r %

m"4-*ments of this section. The use or a sa.=u.Lator to meet the on-the-jcb training section of the program also has been previously reviewed by the NRC.

The following standards apply to the evaluation of en-the-job perfor-e ce.

l i

1.

Quarterly review of operator participation v4H be made by the i 7 g u d-appropriate supe:-visors. The reviev =ust indicate a diversity pe(

of experience.

If this is not de=custrated, the operator vill be ppe' scheduled for additional operating experience.

)

2.

Quarterly review of reactivity control =anipulations (RO) or direction (SRO) =ust shov satisfactor/ progress toward the ni"4-'~ of 10 oper-M ations as defined in this section.

If satisfactory progress is not

!.n%ated, an operator vill be assigned additional control roo

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operations or =ay acco=plish the recuired reactivit'/ changes on a s

simulator.

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3 Annual review of licensed personnel 'h.cse job assign =ents are not directly related to unit operations =ust show a "4"4 um of k8 hours of unit operation assien=ents per year.

If this is not co=plete, personnel vill be assigned to active control roca duty until the time is nade up.

A s4-n' ater =ay be used to ec=plete centrol roc =

time.

Reactor operaters or senior operators licensed en both THI Units 1 and 2 =ust shev a mininun of k8 hours of operations assis-ents per yez-between the two units.

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V1 A=. 62

( !.-T-TS )

13.2.2.h telual Eval-r4 -- Exa < atien Evaluations vill be conducted en an a--"='

bacis as follows:

( a)' An annual written evaluation ex* *.ation vill be given to all licensed operators and senior operators prior to the co=pletion of each annual cycle. 1 l

(b) An ann"a1 oral evaluation vill be a4 *"istered to all licensed operators and senior operators prior to completion of each annual cycle.1 l

The annual vritten evaluation exa-* nation vill be ad=inistered to a71 licensed personnel as set forth in the folleving guidelines:

1.

The exe* nation vill simulate the e-ra

• ation nor-ally administered by the. Nuclear Regulatory Co m# ssion.

2.

Reactor Operators will take Sections A through G of the examination while the Senior Reactor Operators vill take Sections H through L and answer selected questions in Sec-tions A through G.

3 The ereination, exa-* nation ansvers and a grading key v be prepared in advance.

h.

The exa=ination results vill be used to identify specific FSR lecture series topics to be covered by each licensed individual during the subsequent annual requalifications progra= cycle.

5 The exa=ination vill be ad=inistered and graded by a =e=ber of the station technical staff, station "anagement staff, tra4-4'ig

~g depar'_ ent supervisor, or consultant.

6, The persons responsible for the preparation of the exa=inations and ansvers vd7' be given credit for passing the exa-ination.

The annual oral evaluation exa=inatien, using a checklist, will be ad=inistered to all 11 censed-~personne17 tee oral exa=ination vill cover the following areas:

(a) action in event of abnor-a1 conditions (b) action in event of e=ergency conditions (c) response to unit transients (d) instrumentation signal interpretation (e) procedure modification (f) unit =odification

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(g) Technical Specifications (h) r=ergency plans

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• ti eact r verat rs or senio.r_ operators, licensed on both TMI Units vill be given a single ananal written and oral evaluation exa-ination which c,c,yprs..

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13.2-11 An. 6h (h_7_78)

- -The folloving standards apply to the annual evaluation exa=ination:

' l.

A license holder Wo scores higher than 805 in all-sections of the ar-nal l

' written evaluation vill not be required tv participate in the FSR prog #'

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2.

If a license holder scores less than 80, of any section of tha ---"al vritten eva-f nation, the license holder vill participate in the FSR pro-gram related to failed sections.

3 If a license holder scored below 805 en two or nore sections of the annual vr: ten eva dration, the license holder' vill be given an oral e75 dnation and evaluatio:;t b'y the Supervisor of Operations, Supervisor of Traf-ing, or l

i.d other suitably qualified persons designated by the Unit Sup'erintendent.

S IS This examiner vill, based on the results of his examination, nake a reco=-

mendation in writing to the Unii; Superintendent that the operator either (1) be relieved of his responsibilities and dnter an accelerated training pro-gram or (2) be pernitted to renais on shift while participating in the appropriate requalification FSR progran with suitable tutorial assistance.

h.

- An unsatisfactory evaluation on the annual oral evamf-ation vill require that discussicus of deficiencies take place betveen the license holder and either the Supervisor of Operations, Superviser of Training, er other l

suitably qualified person designated by the Unit Superintendent. A second oral evaluation ex= #~ation vill be aanfnistered.

If perfor=ance is ar*

gatisfacy f, % license holder vill be reldereCof r.nste: s#hilities and Vlaced into an accelerated "mm1 * 'ication progra=.

5 Tan individus1 recieves a grade of less than Tor, overall on the

""-"a1 eva

• nation it vill be mandatory that (1) he be relieved of his licensed duties and (2) enter an accelerated requalification progra=. Upon (1) successfully passing a second written and oral exa'ination and (2) certif-ication of' satisfactory rating being sent to the NRC, the individual v41' be returned to his licensed duties.

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'L 13. 2--11a

.An. 64

(' -T-73 )

13.2.2.5.

7 ecords.

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' Records of licensed persennel perfo"*-a on all vritten evaluatien

,g ena=inations and qui::es shall be available fer IIRC exa=inatien fer the previous two annual requalification cycles.

These records shall. include:

l 1.

Examination and quis questions 2.

Ansver sheets and grade keys 3

Scamination papers and work sheets Records of participation in all OR lectures and FSR progress vill be available for NRC review for the previous t.,*o amual requalification cycles. These records shall include:

1.

Attendance records 2.

OR lecture content 3

FSR assign =ent k.

Absences and makeup sessions 5

Assignment check off lists 6.

Document review lists.

Records of ar.nual oral evaluation exa=inations shall be -Me available for NRC review for the previous two annual requalification l

cycles.

Records of all on-the-job activities shall be available for NRC

/

review for the two years prior to license renewal application. These (y

records shall include:

1.

Reactivity control manipulation 2.

Equipment operation, 3

Si=ulator participation Requalification records covering the previous two annual cycles vill be renoved from the files following license renewal.

A summary record vill be maintained on each license holder for the duration of his enployment.

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13.2-12 An. G (E-T-75)

~. _ _ _. _

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13 2.2.6

. Accelerated Recualification P: cgran An operator who does not clear deficiencies assigned due to terfernance below standards ~ on either the annus1 written er oral evaluatica vill be relieved g@.

of responsibilities and enter a full time accelerated requalification progra=.

Ole progra= duration and content. vill be dictated by the nature of the i

deficiency.

Progra= duratien vill be deter =ined by individual uerfor=ance.

Fnen the license holder is (1) able to satisfactorily pass an equivalent

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written or oral eyn,htien and (2) certification of his satisfactory rating i

is sent to the NRC, he shall resu=e his on-shift

• responsibilities. Durirg the period of accelerated requalification, attendance at the OR lecture series is require 1..

If the license holder is off-shift for nore than b =enths, Section 13.2.2.7 dealing with lengthy absences applies.

13.2.2 7 Four Month Absence Progras If a licensed persen has not actively carried out the functions of his license for a period in excess of four =enths, he shall:

j (a) reviev a'i naterial presented or scheduled to have been presented in the OR lecture series for the period of inactivity (b) be given an oral exWnation on the applicable Section cf the OR lecture series and current unit status If perfor a-ce on the oral evaluation is unsatisfactory, the indiviaal g

vill be placed in an Accelerated Requalification Progras in accordance with y

Section 13.2.2.6.

Upon receipt of a satisfactory rating, the licensed person sh=M be certified by the Supervisor of Operations, Supevisor of T: aining or other euitably qualified person designated by the Unit Superintendent.

The certification of satisfactory rating vill be trans=itted to the l

1TRC and only after approval by the NRC shall the operator be returned to nor- +' '

licensed duties.

13.2.2.8 Newly Licensed Ocerators l

Newly licensed operators shall enter the progrs= and participate in the annual program cycle upon receipt of their license.

New operators receiving their URC license less than six =cnths prior to the annual evaluation examination vill be required to attend the appropriate OR and FSR Programs but vill be excused frc= taking the current annual evalua-tien enttination.

However, he vill be responsible for taking all other annual evaluati:n examinaticns.

J

13.2.2.9 Rec"=4 cntion tro.e-as AM '-ictratien Id/

The Supervisor of Training and his sta"" --- -asponsible for:

1.

Assigning instructors for the OR lecture series 2.

Deter =ining FSR assign =ents for individual operators 3

Maintaining and reviewing all records h.

Assigning deficiencies, deter =ining appropriate action to clear deficiencies and clearing deficiencies upon satisfactory com-pletion of assigned action 5.

Arranging accelerated requalification progra=s as may be necessary 6.

Defining oral evaluation procedures 7

Scheduling necessary simulator ti=e 8.

Prepare license applications forlicense renewal The Supervisor of Operations, Supervisor of Ormining, or other suitably qualifieti person designated by the Unit Superintendent is responsible for:

1.

Evaluation'of on-the. job perfor-ece of all license holders 2.

Meeting with license holders who recieve unsatisfactory annual evaluation en nination' grades 3.

Certifying operator qualification when returning fro = a four month absence frem operation 4.

Constructing annual written evaluation exa-f nation, ansvers and grade key

j

-5 Grading of the annual written eva # nation

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U 13.2-lh An. 6h (L-7-73)

+-

s 13.2 3 TLo1ACD!r!T PERSCmfEL TRAETI:IG

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During nor--1 operation o' ""---* '.!ile Island :Tuclear Station,

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engineering, operating and =sintenance perso.nel say be assigned to the scation j

specifica11, "or training purposes.

"hese personnel vill be drawn frc= other l

q Met-Ed facilities cr esployed directly into the organi:ation at the station.

Their training program vill cover the sa=e general =sterial and follow the fundamental progras or its equivalent outlined for training the initial staff and vill be presented by the station, staff with outside assistance as required.

Available Centrol Roos Operator positions vill be filled by experienced Auxiliary Operators. Prior to being reco== ended for RO License, a replace =ent control roon operator =ust successfully ec=plete e. nine-=onth for=al training pregra=.

This progra= includes nor-*1 and e=ergency operating procedures, systes operation, si=ulator training, and. classroes training en selected topics such as reactor thacry and health p5ysics. The progras's effectiveness is =easured by written and oral ex "* nations. The Supervisor of Training is responsible for the ad-sinistration of this program.

Supervisory positions requiring an SRO license vill be filled by experienced perscanel.

Some Unit I licensed personnel =ay also be required to be licensed en Unit II.

These individuals vill be required to cesplete a =ini=u= of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> of training on Unit II syste=s, technical specifications and procedures stressing the differences between Unit I and II.

These individuals vill also be required to take a Unit II vritten exa=ination at the appropriate licensing level which vill stress the systes differences. The exas vill be prepared and ad=inistered by the TMI Training Department. Documentation shcwing satis-factory ec=pletion of this progran and a copy of the written examination and grades vill be forwarded to the NRC for review in order that their licenses 3

=ay be amended to include Unit II.

Q 13.2.k RECORDS The Supervisor of Traini=g vil?. be responsible for both the ad=inistration and evaluation of the stations training programs.

The Supervisor of Training (or his designate) vill also =aintain records which indicate the training a=d re-training of each =e=ber of the station's staff.

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13.2

-TRAIliIUG PROGRAM 13.2.1 PROGRAM DESCRIPTION y

The training for the Unit 2 staff is running concurrent with the Unit.1 training, and Unit 2 pre-operational testing and initial operations. A program has been established which includes on-the-job training and formal training to =eet the needs of each man chosen for responsible positions, depending on his background, previous training, and job assignment.

It is intended to provide individual training, as necessary, to assure that all =en requiring NRC '. censes for TMI l

Unit 2 vill have the training and experience required to meet ANSI N18.1-1971.

The training has been scheduled so that those members of the initial operations staff who vill be " cold" license candidates vill take the NRC examinations approximately two months prior to fuel loading.

13.2.1.1 Program Content 13.2.1.1.1 Initi'al Supervisory Staff (SRO License)

Members of the Unit 2 initial Supervisory Staff (SRO license) vill hold a license on Unit 1 except as otherwise herein specified. Training programs are being and have been provided for Unit 2 SRO candidates (all Unit 2 SRO candidates participated or vill participate except as otherwise noted) which include (d) the following:

For certain initial SRO candidates instnuction was provided in the a.

following courses:

1.

The Nuclear Instrumentation and Control Course included a description of the system, detector theory, and preli=inary Q

operating procedures.

2.

The Control Rod Drive Mechanis=s Course included a physical and operational description of the control rod drive assemblies g

their mounting, and positions. Descriptions of the reactor vessel, head closure, and refueling equipment were covered.

3.

The Reactor Protection Syste= Course presented both general and l

specific safety aspects of reactors. The history of accidents that have occurred was presented. Special safety considerations of the reactor included the accident analysis and e=ergency procedures. Technical Specifications were examined. Organizational relationships and the functions of regulatory aspects were presented.

Emphasis was placed on developing safety attitudes.

b.

Operational Reviev Se=inars given by station personnel as part of the Unit 1 Shift Foreman / Supervisor training vere attended by certain SRO candidates. These seminars were approximately 2-1/2 hours in duration, one day a week. The seminars included review of TMI-1 nor=al and emergency operating procedures, radiation protection, nuclear instrument-l ation, nuclear theory, transient analysis, and Technical Specifications.

Participation in the Unit 1 operctor requalification and retraining c.

progra=. This program consists of approximately 200 hrs /yr formal I

classroo= training in such areas as abnormal occurrences, modifications, w

t 13.2-1 Am. 33 (10-8-75)

cajor ep:rttional evolutions, (=2rg:ncy proc:durca, radiation control and safety, and categories a. through 1. of the NRC senior / reactor operator license examinations. This program additionally includes 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> "E...,(every other year) simulator retraining on the. Babcock and WilcoxJsi=ulatbr

~ facility. Written exaninstions are used to measure

,j 'this pro 6ran.

the effectiveness of ~

......'T

~

j d.

A Unit Differences Training Program training program vill be conducted which stresses the differences between Unit 1 and Unit 2 NSSS, secondary, and balance of plant systems for the Unit 2 initial supervisory staff.

This program vill be conducted in conjunction with the TMI Unit 1 re-qualification program (see 13.2.1.1.1.c) conducted over a two year period, and it will be conducted by the TMI staff. The program vill have approximately 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> formal classroom instruction in Unit 2 systems.

It will include a comprehensive final exanination in the operation of Unit 2 systems, e.

Should a member of the Unit 2 Initial Supervisory Staff not hold a license on TMI Unit 1 but otherwise be eligible for a " cold" license on Unit 2 through past experience and training, he vill participate in for=al training equivalent in scope and subject matter to 13.2.1.1.1.c. relative to Unit 2; and he vill participate in formal Unit 2 syste=s training which includes but will be longer than the training described in 13.2.1.1.1.d above. The effectiveness of the training for such an individual, vill be measured using written tests.

13.2.1.1.2 Initial Non-Supervisory Staff (R0 License)

Rs:ctor Operator License candidates for Unit 2 vill be selected frem the senior qualified Auxiliary Operators. They have received a mini =us of 26 veeks for=al' training in funda= ental nuclear theory, health physics, and selected pri=ary 3

and secondary syste=s. These reactor operator license candidates vill ud5 p;rticipate in approxi=ately 200 hrs of the classroom phase of the Unit 1 opiratcr requalification and retraining program described in 13.2.1.1.lc.

These Br:ctor Operator license candidates have all operated at TMI Unit 1.as Auxiliary Op:rators in excess of one year.

In crder to be eligible for a Reactor Operator License prior to initial criticality of TMI Unit 2, these Reactor Operator license candidates vill participate in the following additional training programs:

Training Reactor Operation conducted at Penn State University. This one n.

week program vill include various core physics and detector experiments

~

and ten reactor startups for each candidate. This progra= will be con-ducted approximately 20 =onths prior to fuel loading.

b.

Practical Observation Experience. In that all Reactor Operator License candidates have operated TMI Unit 1 as Auxiliary Cperators, ne in-plant observation experience has been scheduled. However, one month of practical on shift observation experience in the centrol roc = of TMI Unit 1 has been scheduled for Reactor Operator License Candidates. This training vill be conducted approximately 19 months prior to fuel loading.

c.

Pb'R Si=ulator Training. The Babcock and Wilcox s1=ulator facility in Lynchburg, Va. vill be used to provide eight weeks of si=ulator instructica to esch Reactor Operator licence candidate. The eight weeks vill have the following approxi= ate breakdevn: simulator operation-100 hrs., classroca e

d 13.2-2 Am. 54 (3-30-77)

in"3truction-170 hrs., and si=ulated NRC examinatien-and review

. v~~

LO hrs.

'~

i.

This simulator training vill conclude approximately one year prior to fuel loading.

d.

Unit 2 NSSS, Secondar, and Salance of Plant Syste=s. A systems

/

course that addresses NSSS, secondary, and balance of plant systems started in 1975 The course consists of approximately 160 hrs. of classroom training in Unit 2 systems. This program will conclude approximately 21 months prior to fuel loading.

e.

Nuclear Theory Review. A 60 hour6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> nuclear theory review course was conducted for Reactor Operator license condidates approximately 23 months prior to fuel loading..It was conducted as a refresher course to supplement the initial 26 week training program previously mentione f.

Advanced Systems, Procedure, and Nuclear Theory Training.

From 12 months prior to fuel loading Reactor Operator License candidates will devote approximately one week out of every six weeks to formalized training. This training vill include such topics as:

1.

energency procedures 2.

abnormal procedures 3.

radiation control and safet/

k.

technical specifications 5

nuclear theory review 6.

administrative procedures 7

fuel loading procedures and precautioris j

8.

continued systems training.

The programs described in 13.2.1.1.2.b and 13.2.1.1.2.d.-f. vill be conducted by the TMI staff.

Written tests vill oe used to measure i

the effectiveness of the programs described in 13.2.1.1.2.d.-f.

I g.

A member of the Unit 2 Initial Non-Supervisor /' Staff may enter the training progra= after the original group of candidates and still be eligible for a " Cold" license on Unit 2 through past experience and training. If this occurs, he vill participate in formal training equiavalent in scope and subject matter to 13.2.1.1.2 a-f.

The only difference being:

(1) The time relative to fuel lead for each seg=ent of the training program vill d.iffer from that of the original group.

(2) The training described in 13.2.1.1.2.f. vill be acco=plished by a concentrated 80 hour9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> classroo= progra=.

13.2-3 A=. Sh (3-30-77)

13.2.1.1.3 Approxi=ately tvalve =caths prior to fuel loading, the initial supervisory and r.on-apervisor/- staff vill begin to participate in the integrated test progr= cc==encing vith initial fill of Unit 2.

They vill contir.ue with this on t' 4

training in addition to the training described in paragra:

~ ~ ~ ~4 13.2.1.1.1.c,13.2.1.1.1.d. and' 13.2.1.1.2.f to the point of initial fuel'hs

'~M loading.

9 13.2.1.2 Coordination with Pre-p 4 rational Test and Fuel Loading As stated in 13.2.1, all formaj.,d on-the-job training for the Unit 2 license candidates has been schedulid so that cold license exams can be taken approxi=ately two months prior to iaitial fuel loading. The training for personnel required for both units, i.e., maintenance, instrument and control, cud technical support, has been provided such that it coincided with Unit 1 pre-operational testing and initial duel loading.

For such personnel specific training indigenous to Unit 2 will bs provided on an as needed basis.

13.2.1.3 Practical Reactor Operations 13.2.1.3.1 Initial Supervisory Staff (SRO License)

The supervisory operational staff has been assigned to the station site and is involved in the on shift operation of Unit 1.

In this capacity, the supervisory staff is becoming thoroughly famf Har with operating a nuclear steam supply system hay 1=g only minor differences from Unit 2.

Certain members of the Unic 2 initial supervisory staff also participated in the pre-operational testing l

end startup of Unit-1.

The Unit 2 supervisory staff will participate in the training of Unit 2 non-supervisory personnel. As components and systems becoce available, the operating staff will participate in the conduct of the functional and operational tests to verify satisfactcry perfor:ance.

g 13.2.1.3.2 Initial Non-Supervisory Staf f (R0 License)

~

The non-supervisory operational staff for Unit 2 joined with the Unit 1 staff in the conduct of that unit's pre-operational test program in order to become f a=iliar with nuclear station design, operation, and maintenance.

These parsonnel will participate in the initial checkout, testing and startup of Unit.

13.2.1.h Previous Nuclear Training The Unit'2 training program has been constructed to enable the initial Unit 2 supervisory staff to obtain " cold" tTRC licenses on Unit 2 by first holding MEC licenses on Unit 1.

The init.al non-supervisory staff vill be eligible j

to cbtain " cold" Unit 2 licenses by participation in the training pregra= outlined in 13.2.1.1.2 vhich includes extensive simulator training for each license l

candidate.

Current intentions are to " cold" license both the initial supervisory and non-supervisory staffs by =eeting the eligibility require =ents in the =anner previcusly cutlined. Supervisory persennel who do not hold a licer.se en Unit 1 (see 13.2.1.1.1.e) =ay be eligible for a cold license en Unit 2 depending on past training and experience. Such training may include, but is not limited to:

a.

Military Experience b.

Previcus License at a ec==ercial nuclear facility I

c.

Irperience at other ncn-licensed nuclear facilities.

-Ab 13.2 h A=. 5L (3-30-77)

[

- 13.2.1.5 "rsinin: Fre=rs=s for Hen-Licensed Parsonnel dDWD The initial. training pro rans for the Three !!ile Island ncn-licensed personnel Cz.

e are. identified f.ith approximate duration shown where applicable) as follevs:

- a.

For=al 26 week (full-time) funda= ental nuclear theory and systems training o its equivalen in previous training or experience.

b.-

Vendor faciliarization training Scsic health physics course (one day) conducted'at the site c.

t 1

l

t 1

w i

s-4..

. l i

i 13.2 ha A=. 51 ( 3_30_77) g,d

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depgeee-.p w.e-m--

=m=34 me wwewse,eh e

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d.

Inte: :ediate health physics course (one veek) conducted at the site

~

Advanced health physics course (tvo veeks) coniucted at the site e.

if.

Rad Che: Tech training progrs= (ho hrs /yr) g.

Unit 1/2 operator requalification and retraining progre= (as ti=e permits)

I h.

Auxiliar/ Operator "A" post-classrec= in-plant training progra= (h00 hrs) or its equivalent in previous training or experience.

1.

General e=ployee training retraining (health physics, security, site e=ergency plans and procedures, quality assurance, industrial health and safety) (8 hrs /yr) j.

On-the-job =aintenance procedures and technique training k.

On-the-job training 1.

For=al 12 week training progra=

=. Unit differences training program.

The ncn-licensed personnel were/are assigned to these progra=s as follows:

PERSOTTEL PROGRA'4 Auxilia./ Operators "A" a,b e,g,h,1,k,=

Rad Che= Techs f,1,k 3

Maintenance (electrical, d'

=echanical and instru=entation) b,d,1,j,k Office Personnel e,1,k Auxiliary Operator "3" In addition to training received as Aux. Op. C, e Auxiliary Operator "C" c,1,k,1 Progrs=s a,c,d,e,f,g,h,1,j,k,1, and = are taught by the TMI staff. The effectiveness of progra=s a,c,d,e,f,g,h,1,1 and = vill be =easured using written and/or oral ex =inations or spot checks.

13.2.1.6 ceneral E=elovee Training

• All e=ployees assigned at Three Mile Island vill, as a =ini=.:=, have trsining in bcsic health physics, security, site e=ergency plans and procedures, quality assurance, and industrial health and safety.

13.2.1.7 Restensible Individual The Supervisor-Training is respensible for the conduct and M-inistration of the statien training pregrs=.

4<

13.2.1.5 Trainin Schdule

'"he Fisre 13.2-1 shows the anticipated schedule of that training described in w

13.2.1 which was not conducted prior to 1975

,j 13.2-5 A=.

h3 (11-15-76)

1 1

d.

Int'Irm2 dicta h:2 2.th physics coursa (one week) conducted at the site Advanced health physics course (tvo weeks) conducted at the site e.

}d f.

Rad Chem Tech training progras (h0 hrs /yr) g.

Unit 1/2 operator requalification and retraining program (as time permits)

}

P Auxiliary Operator "A" post-classroom in-plant training program (kOO hrs) or its equivalent in previous training or experience.

i. General e=ployee training retraining (health physics, security, site emergency plans and procedures, quality assurance, industrial health and safety) (8 hrs /yr) l j

j. On-the-job maintenance procedures and technique training k.

On-the-job training 7

1.

Fomal 12 week training program i

m.

Unit differences training progra=.

n The non-licensed personnel vere /are assigned to these programs as follows:

PERS0!MEL

@ GRAM Auxiliary Operators "A" a,b,e.g,h,1,k,m 4f Rad Chem Techs f 1,k

]

Maintenance (electrical, mechanical and instrumentation) b,d,1,1,k Office Personnel e,1,k Auxiliary Operator "B" In addition to training received

.as Aux. Op. C, e Auxiliary Operator "C" c.i,k,1 m

l Progra=s a,c,d,e,f,g,h,1,j,k,1, and m are taught by the TMI staff. The effectiveness of progra=s a,c,d,e,f,g,h,1,1 and m vill be measured using written and/or oral examinations or spot checks.

13.2.1.6 General E=uloyee Training i

1 All employees assigned at Three Mile Island vill, as a minimum, have training in j

basic nealth physics, security, site emergency pla.s and procedures, quality assurance, and industrial health and safety.

13.2.1.7 Responsible Individual The Supervisor-Training is responsible for the cenduct and administration of the station training program.

13.2.1.8 Training Schedule The Figure 13.2-1 shows the anticipated schedule of that training described in 4

13.2.1 which was not conducted prior to 1975 13.2-5 Am. 48 (11-15-76)

13.2.2 METROPOLITAN EDISCN OPERATOR REC.UALIFICATION PROGRAM The Metropolitan Edison requalification progren, as set forth in this I

docu=ent, applies to the Three !dle Island Nuclear Generating ~ Station.

All

~sd licInsed personnel vill participate in the applicable portion of the requal-ification program. The basis of the requalification program is the need to maintain operator competence and proficiency in the quest for continued safe op; ration.

The guidelines for the requalification program are found in 10CF355 App:ndix A, issued on Septe=ber 17, 1973. In addition, the imple=entatien of this progra= conforms to changes in 10CFR50 dated Septe=her 17, 1973 13.2.2.1 Procra= S'chedule The requalification progra= described herein vill be i=ple=ented at a specified date within 90 days after receipt of an operating license.

This dit2, and subsequent anniversaries of this date, vill be considered to be the ctsrting date of each annual cycle of requalification program operation.

Each license holder vill complete all applicable sections of the requali-fientien program on an annual cycle. The applicability of each section of the progra= vill be deter =ined by an annual evaluation examination administered to each license holder.

A state =ent of progran participation vill be submitted vita lictnse renewal applications every other year.

The Metropolitan Edison Requalification Progran censists of four irterrelated sag =ents which run concurrently. These seg=ents are:

1)

Operaticnal Review Lecture Series (OR) ggg.

2)

Funda=entals and System Review Progra= (FSR) 3)

On-the-job-training k)

Annual Evaluation Ext.minations.

L The OR Series is a clasr. room lecture presentation which provides the l

lic;nsed personnel with the details of operational information related to the

.Thrse Mile Island Station. In addition to operational infor:stion, key areas l

covered during the FSR program are reviewed during the class room period. OR lectures are held fer a =ini=um of 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per year. The FSR progra= is ad-ministered to the licensed operators in addition to the OR lectures. The topics l

covered are determined by individual perfor=ance on the annual written exa=inatien.

l Study assign =ents are reviewed by supervisory personnel to insure a high level of trainin effectivenese. The FSR assignments are =ade.during the OR Classroc=

hnse and review d in the.following OR sessions, l

e l

On-the-job-training is designed to insure that all licensed personnel optrate reactor controls and participate in =ajor unit evolutions. Records of all en-shift performance are maintained and periedically reviewed by supervisory persennel.

The annual evaluatien examinations si=ulate the written and oral exa=inations ad=inisterei by the Nuclear Regula: cry Cc==issien.

Perfor ance en these ant !al evaluaticns 1eter=ine the extent of the FSR pregram during the folleving tvel e 1

=enth requalificaticn period.

g 13.2-6 Am. 25 (2-28-75)