ML20126A037

Rev 1-00 to Administrative Manual 6212-ADM-2611.04, Fuel Handling Senior Reactor Operator Training Program,Unit 2

ML20126A037
Person / Time
Site:	Three Mile Island
Issue date:	05/29/1985
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20125E669	List: ML20125E667 ML20126A008 ML20126A021 ML20126A037
References
6212-ADM-2611.0, NUDOCS 8506130207
Download: ML20126A037 (69)

Text

C Nuclear TMI TRAINING DEPARTMENT ADMINISTRATIVE MANUAL 6212-ADM-2611.04 Title Revision No.

9 FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 Applicability / Scope Responsible Office FUEL HANDLING SR0 CANDIDATES, UNIT 2 TRAINING DEPT.

This documentis important to safety 0 Yes W No Effactive Date List of Effective Pages PAGE REVISION PAGE REVISION PAGE REVISION PAGE REVISION 1.0 1-00 21 . 0 1-00 41. 0 1-00 61 . 0 1-00

2. 0 1-00 22.0 1-00 42.0 1-00 62.0 1-00 3.0 1-00 23.0 1-00 43.0 1-00 s 1-00 4.0 1-00 24.0 1-00 44.0 1-00 1-00

5. 0 1-00 25.0 1-00 45.0 1-00 -00 6.0 1-00 26.0 1-00 46.0 1- 1-00 7.0 1-00 27.0 47.0 Ig P. 0 1-00 1-90-() 48.0 68,0 1-00 8.0 1-00 28.0 - -

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F TMI TRAINING DEPARTMENT Number Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 Title (16219) Revision No.

FUEL HANDLI,NG SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 1.0 PURPOSE The purpose of the Fuel Handling Senior Reactor Operator Training Program is to maximize plant operating efficiency during defueling -

operations and ensure the safety of the plant personnel and the general public by developing and maintaining a staff of in-plant oper t personnel with the theoretical and practical background enable them to:

1.1 Understand how and f .

. Ic tasks a h o -

(eque es of thet )$

1.2 Understand t Von defueling and overall plant o ions.

1.3 Respond correctly to situat ey may ter during normal, abnonnal, and docc itions.

2.0 SCOPE /APPLICAMLI w

^

g- \ /

This e . applies to all F - dling Senior Reactor Operator candida designated by the Manager, Plant Operations.

3.0 DEFINITIONS 3.1 Fuel Handling Senior Reactor Operator (FHSRO) - an individual licensed by the Nuclear Regulatory Commission to supervise fuel g handling and core alterations operations.

5 3.2 Task Examiner - an individual conducting a checkout on a specific 0

j OJT task and certifying by his/her signature on the OJT sheet that k

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I I

1

)

TMI TRAINING DEPARTMENT Number Nuclear AoMINISTRATIvE MANuAt 62ia-AoM-asii.04 Title (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 the task has been satisfactorily completed. The task examiners shall be designated as outlined in this program. (See Section 7.5.1 a/b.)

3.3 Extra Person - a candidate assigned to on-the-job train se presence is not required to perform specific, non- - ated tasks. Q 3.4 Instructor - -.n r certifie er of the Training Department or a est" in ru wiin e expertise in a specific subject area, e.g s er, has r in his assignment, app ng by t e aining Manager orManager,q Tr ning to . tal on that subject area h ception of guesti turers, senior licensed or cer ified instructors must teach systems, integrated responses and transient behavior to licens'ed operators.

4.0 RESPONSIBILITIES

~

g 4.1 The Supervisor, Licensed Operator Training, is responsible for the h following:

!: a. General supervision of the development and conduct of the g Fuel Handling SR0 Training Program.

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TMI TRAINING DEPARTMENT Number Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 Titw (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00

b. Approval of the development, coordination, scheduling and administration of the Fuel Handling SRO Training ~ Program, including course outlines, lesson plans, student handouts, simulator training and evaluation exams.

c. Scheduling classes, students, classroom and facil g necessary to conduct the training program.

d. Interfacing with ons Department ers impactingthfrii rograms.

e. Assurt \ program con ' dated and revised to meet cur 9requi d upervising revision of the program content i .s, lesso %a ns, and exams,

f. Evaluatio o nstructi n li e candidate pro ermine the ett ss of the training p d reporti uations to the Operator r

v ing Manager.

g haintaining the necessary records and reports of training.

1. Developing and conduct'ing oral exams.

j. Evaluation of candidate critiques of the training received.

4.2 The Operator Training Manager is responsible for the following:

g a. Assuring the quality of the Fuel Handling SRO Training I Program by written approval of material including course outline, lesson plans, student handouts, simulator training, g quizzes and exams and their compatability with the Fuel l Handling SRO Training Program.

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TMI TRAINING DEPARTMENT Number Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 Tide (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00

b. Certification of candidates in accordance with 4210-ADM-2610.01.

c. Approval of guest lecturers.

4.3 The Manager, Plant Training is responsible for the foi  :

a. To ensure that the training program is deve the requirements esta 1 s by the Direc rough the Manager, Pla r t '4hs, and t pe cords and docume rovided an n. ned,

b. Certific of can d i cordance with 4210-ADM-2610.0 -

O

c. Approval f- ec urers.

O 4.4 The MafGge 91 ant Operations i ponsible for the following:

1 s re that the 11 level of training of plant operators is satisfactory through the approval of program content, schedules, and administrative procedures.

b. Certification of candidates in accordance with 4210-ADM-2610.01.

c. 1)esignation of candidates to enter the Fuel Handling SRO g Program.

In 5

g 4.5 The Director - TMI 2 is responsible for the following:

j a. Final certification of candidates in accordance with 4210-ADM-2610.01, h

.i.

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eff TMI TRAINING DEPARTMENT Number Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04  ;

Tide (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00

5.0 REFERENCES

5.1 Code of Federal Regulations. Section 10CFR55 5.2 Administrative Procedure 4210-ADM-2610.01

5. 3 Code of Federal Regulations, Section 10CFR50 5.4 4210-ADM-2610.01 Requirements for Certification of Oper r for NRC Licenses O

6.0 ATTACHMENTS 6.1 Appendix A - ( -Jo hecklists b 6.2 Appendix B - Or xam Sunna et 6.3 Appendix C - Final V fic IFxaminer tion 6.4 Appendix D - Ad itie o Letter-6.5 Appendix E standing 6 7.0 FUEL MREPLACEMENTPROG 7.1 dq sites:

All candidates for Fuel Handling Senior Reactor Operator shall:

1. Have a high school diploma or equivalency.

2. Have three years experience in operations or support of

' operations at a nuclear power plant.

g 3. Have one year supervisory experience.

@ 4. Satisfactorily meet the minimum medical requirements for

. 5

= licensed personnel as specified in 10CFR55.

I a

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TMI TRAINING DEPARTMENT Number Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 Title (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 7.2 Content

1. The program consists of the following:

a. Classroom (Fundamentals, Defueling and Plant Systems)

b. DJT - Plant and Defueling Systems

c. Decision Analysis,

d. Supervisory Devel'opment

e. Simulation T ah - Research Reg r ockup

f. Audit E:t The rep gram conc 1 h i / he NRC examination.

7.3 Objectives 7.3.1 The obj progra p N de the Fuel Han h an a 1 n ge of the principles f ar power ons and in particular the lied knowledge ills of defueling operations including:

a. Fundamentals of Fluid Flow, Heat Transfer, and Thermodynamics to enable the candidate to evaluate fuel handling and support operations performance through available monitoring devices.

g b. Mechanical Equipment Construction / Operation involved h~ in the fuel handling and support operations.

2

c. Reactor Physics to provide an understanding of the g operation of a heat source and the effect of k-A00010501182

7. 0 1007D

TMI TRAINING DEPARTMENT Number Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 Title (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 operator actions on fuel perfonnance. This topic area is to concentrate on suberitical operations.

d. Criticality Safety to provide the candidate with an understanding of the concerns associated with handling fuel as it exists at TMI-2.

e. Radiation Protection to enable the c incorporate / consideratio t ations.

5

f. Plant F1 i ens interfg wi efueling A '

b

g. I s A mentatio Co 1 Systems to ensure the candida he contro 4ms under his ns for defueling

h. Distri S T stems to provi - andidate with an understandt a the power systems established for defueling and support operations.

1. Administrative', Operating, Abnormal and Emergency procedures relating to defueling to enable the candidate to perform in accordance with established.

approved methods of plant control and to respond to g a variety of potential plant situations.

J. Fire System Training to enable the candidate to

=

properly respond to fire emergencies, e

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TMI TRAINING DEPARTMENT Number Nuclear AosINISTRATIvE nANuAt sai2-Aon 2sii.04 Title (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00

k. Industrial Safety Training to enable the candidate to practice the principles of personnel safety.

1. Regulatory Guidelines Training to enable the candidate to understand the company - regulatory interface,

m. Control Room / Fuel Handling Area integ h ofng to enable g ator to promt eh er,$ e and effic p ons.

n. 1 5 ng SR0/Sup or r zations interface t faing to p of we and efficient operatt 7.3.2 Certify cy of app f# ants rect defueling a c ton ope i ns T safe and efficient e , y satisfa ter nt of specified learning objectives.

7. 4 Outline The Fuel Handling SRO Training Program is divided into four phases of training. These phases are:

1. Fundamentals Training g 2. On-The-Job Training

3. Defceling Systems Training

4. Simuistion Training 8

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Number TMI TRAINING DEPARTMENT Nuclear xoniNISTRATIvE nANuAt sai2-Aon-asii.04 Tide (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PR00 RAM UNIT 2 1-00 This training is sequenced to provide the candidate with two periods of classroom training, practical on-the-job training and simulations training. The topics to be addressed in each of these areas are outlined in this program description.

7.4.1 Fundamentals of Training The fundamentals g is to be co e beginning o This ph o program is to provid date with g 'ge necessary to effec operate t sy involved in fuel handling supp provide candidate with a knowledge rating f damen .

T to i address ur e fundamentals rakn are liste b i

1. r Plant n is The purpose of the training in power plant fundamentals is to provide the candidate with a knowledge of the operating principles of mechanical, electrical and chemical systems, and reactor core characteristics as they relate to defueling.

g Training on fundamentals for systems not installed at the time of the initial class is to be included in l the Fuel Hao qing Systems Training phase of the program. The scope of the power plant fundamentals f

a i

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• U- TMI TRAINING DEPARTMENT Number Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 Titi. (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 training is to be determined by the Supervisor, Licensed Operator Training and approved by the Operator Training Manager. The topics to be covered are listed below.

Reactor Physics - emphasize subcritical o ions Mechanical Fundamentals Electrica amentals Criti at Control - b Accountab 1

2. Power Plant [

The pu th Power P an ps training is to tWcandidate th ledge of the long m ystems iris a TMI-2 which may not be modified du ing systems installation.

Systems to be included in training are those which can affect the defueling operation. The scope of this training is detemined by the Supervisor, Licensed Operator Training and approved by the

. Operator Training Manager and Manager, Plant g Operations. The topics to be covered are listed

below

Core Construction Core Cooling Systems f

a 1

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TMI TRAINING DEPARTMENT Number Nuclear AoMINISTRATivE MANuAt sai2-AoM-2sii.04 Title (16219) Revision No. -

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 Electrical Distribution Systems for Defueling Ventilation Systems - Reactor and Fuel Handling Bldg Core Monitoring Systems - Nuclear and Non-Nuclear Fire Protection Systems Liquid hste Handling Systems Communications Systems Technica fications

3. Plant f trainin d lagt procedures is to pr the candi- wt knowledge of administra i ng and rency procedures whic 1 ble to t instajM defueling the time t . Additional training be requi d, o orate the scope of changes effected by tallation of the defueling systems. The scope of this traf'ning is detennined by the Supervisor,: Licensed Operator Traning and approved by the Operator Training Manager and Manager, Plant Operations. The topics to be covered

- should include:

g Emergency Procedures Radiological Controls Procedures A&ninistrative Procedures i

a.

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I TMI TRAINING DEPARTMENT Number n

m Nuclear i AoMINISTRATIvE m uAt sai2-AoM-2sii.04 Title (16219) Revision No.

7 FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 m

k g 4. General Categories

~

[ The purpose of this training is to provide the candidate with training in areas not addressed

% elsewhere. Training conducted in this area should be a

I developed from the following list of topics: 4 i Facility Incidents and Industrial E Code of Fe 1 Regulations 7.4.2 On-The-J4 ng The p of the on -jo - ining (0JT) program is to It provide the candi' i he prac knowledge necessary t icensed ties. t OJT program is

~

to i 1 t cal traf g edures as well as

. 'he OJT p ' for plant systems and procedures

<4 ailed in d . The scope of the OJT program is determined by the Supervisor, Licensed Operator Training and approved by the Operator Training Manager and

{ Manager, Plant Operations, f The OJT program is to be completed during periods while h assigned as an extra person and during scheduled practical training. In addition, hands-on availability of equipment y during vendor site visits and periods other than when assigned on shift may be used to complete OJT requirements.

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i TMI TRAINING DEPARTMENT Number l Nuclear AonINISTRATIvE nANuAt 62i2-Aon-26ii.04 Tiue .

(16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00

' 7.4.3 Defueling Systems Training The purpose of the Defueling Systems Training is to provide the candidate with a knowledge of the systems installed specifically to facilitate defueling operations. The scope of this training is to be determined by t'he Supervisor, Licensed Ope ng and approved by Terator Trainin r Manager, Plant Opera i . trainin to Tg de the follow .

c' reas as th(y la defueling operatta ,

Electrical Dit'ri n Defuel- y s l C

&un a ons Sys

$T chnical S l Administrat ures Abnormal, Normal and Emergency Operating Procedures 7.4.4 Simulation Training i 7. 4. 4.1 Simulations training sh:,uld be conducted to i

.. reinforce skills and knowledge requirements identified for FHSR0s. This training should r- emphasize the practical application of

}

$ equipment operations and provide demonstration "g of basic principles.

k, I

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TMI TRAINING DEPARTMENT Number t Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 Title (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 7.4.4.2 Where practical, the Defueling Test Assembly or similar training mockups should be used to provide simulation training on defueling equipment operation. This training may be used to satisfy requirements establis in the OJT program for both replac requa 1 ation programs.

7.4.4.3 -r s -feactor 1 training e should nduct training to emphasize t ore fundamentals and opera -i ha racteris 7.5 Administration O 7.5.1 Progr ton 7.5.1 . -T e-Job Tr

a. The on- aining program consists of preselected tasks which involve participation by the Fuel Handling Senior Reactor Operator (FH SRO) candidate in activities designed to train the candidate to perform assigned duties.

. b. Primary verification of OJT tasks shall be by a oral checkout of the FHSRO candidate on I

Q individual task items by a task examiner. The h task examiner shall be RO or SRO licensed or j subject matter experts as designated by the l Manager, Plant Operations.

e AOOO10501182 t 15.0 10070

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• D' TMI TRAINING DEPARTMENT Number Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 Titie (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00

c. Final verification of OJT tasks shall be by oral checkout of task sheet sections by a licensed SRO or subject matter experts as designated by the Manager, Plant Operations.

d. OJT tasks specifically related to defuel equipment may be provided in additi appendix s equipment is de - a training dev erim cha t JT program aplemen u in e Addition / Deletion tter forma D. Changes initiated using th b t hall rporated into the p ption d i nual program W ring the 03 t e candidates may be

~

assigne ri6us shifts. ,

2. Classroom Train ng

a. The classroom training is conducted with material presented by qualified instructors using approved lesson plans. All portions of classroom training

. requiring self-study shall be monitored by a g qualified instructor who shall be available for individual consultation.

5 1

6 h

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TMI TRAINING DEPARTMENT Number Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 Title (16219) Revision No. .

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00

b. The candidate will be responsible for objectives designated for FHSR0s on material presented. If a candidate misses more than one (1) consecutive week, the Supervisor, Licensed Operator Training will review the situation and determine he candidate will be able to catch up w class, ke a recomendat erator Tra g 43 r and t g ant ns regardi o ition in the program.

7.5.2 Evaluat on Crite 7.5.2 1. On-Thee 09 r4 eing ensive or 1 c shall be a inistered sk examiners for specific task si Md documented by the task examiner's signature.

b. The ultimate responsibility for determining adequate achievement by the student rests with the Final Verification Examiner who shall

. evaluate the performance of the FH SRO candidate g by final oral checkout and/or written questioning h of each OJT section, using the Oral Examination

!:! Sumary Sheet in Appendix B. This form shall be g retained in the candidate's permanent training file ,

.h.

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TMI TRAINING DEPARTMENT Number Nuclear AoM m STRATIvE nANUAt sai2-AoM-2sii.04 Title (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00

c. All tasks which cannot be performed are to be simulated. Performance or simulation of a task shall not alone constititue successful completion of the task. Discussion and oral questioning by the task examiners and final verificatio examiners should be utilized to su 'ti success pletion of the .

d. In iv d ling to i ve ass" grade on erificati ec shall be:

) Informe t r ak areas and given di he matert , that they should upgrad heir reance.

-examine thi- (2) weeks of the init al NO

• tails of weak areas should be fontarded to the Supervisor, e Licensed Operator Training.

If an individual fails the second final verification check-out the Manager, Plant

. Operations and the Operator Training g Manager shall review the FH SRO license candidate's overall progress and performance g

$ and determine the corrective action to be E

g taken.

k k

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TMI TRAINING DEPARTMENT Number Nuclear ADMINISTRATIVE MANuit sai2-ADM-2sii.04 Tiue (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OFERATOR TRAINING PROGRAM UNIT 2 1-00 7.5.2 2. Written Examinations Written examinations during classroom training shall be administered by the Operator Training Section on a weekly basis. Questions should cover the lesson objectives presented in the classroom traint session.

A passing gr of 80% is mandato - 1 ritten examin tions ade of les a will require ca unseling b e Actor responsible ted weak a . s) candidate's exam with suggested c tions th t9111 upgrade the indivi 'D ormance. A should be n te' within s. If an individual S the second Manager, Plant Operations and the Ope.a raTning Manager shall evaluate the FH SRO license candidate's performance and decide on the corrective . action to be taken.

7.5.2 3. Final Examination

a. A comprehensive written and oral examination shall be administered at the conclusion of the g training program.

~

b. An 80% overall average and a 70% on individual

- sections is required for the satisfactory completion of the written examination phase.

f a

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TMI TRAINING DEPARTMENT Number NUCI68r ADMINISTRATIVE MANUAL 6212-ADM-2611.04 Tiue (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00

c. The oral examination should consist of two phases; a " walk through" phase, administered by an individual designated by the Supervisor, Licensed Operator Training, and a " board" composed of instructors designated by t Supervisor Licensed Operator Traf he Manager, P1 nt Operations or i d re r e . A "p a required for o examinati tation shall be pleted us th Examination Summary Sheet i )y .

d. U c J on of th e e p the FH SRO Candida g files and Training partment ret dat ons shall be forwarded to the Dir MI-2 who may certify the candidate for NRC examination.

/

7.6 Changes and Lesson Plan Correction 7.6.1 The program shall be maintained to reflect the following:

, a. Changes in regulatory requirements g b. Changes in applicable codes, standards and guides

c. Significant experiences at the facility a

d. Significant experience throughout the industry j e. Remedial changes recommended by review / audit findings k-A00010501182 20.0 10070

+ [7 TMI TRAINING DEPARTMENT Number Nuclear m INIs m TIvE m um. 6u 2-a-26u .04 Tio. ()6219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00

f. Regularly scheduled participant critiques

g. Changes in position responsibilities Changes will be incorporated per the applicable Training Department Procedure 7.6.2 Changes in the program content may be necessi n individual basis o unplanned equi . 1 or problems, op r3 itments, a changes or deletto . d ate quaiff c nd professional know e .

b

7. 6. 2.1 The reque etion(s) Pany, requirements fr (h ram shal si ted by the rJv or, Lice s r r Training with acknowledge t. t e license candidate.

Approval quested deletions shall be made by the Opera or Training Manager and Manager, Plant Operations, and Manager, Plant Training.

When approved, the deletion letter shall be kept in the Training Department files.

, 7.6.2.2 Deletions due to equipment problems or plant g operational commitments shall only be approved for situations where plant conditions cannot be established within a reasonable amount of time f

before required certification. In no case should a

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TMI TRAINING DEPARTMENT Number Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 Title (16219) Revision No. ,

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 deletions be authorized during a qualification program when required conditions are expected prior to certification.

7.6.2.3 When deletions are requested due to prior candidate experience, an assessment of t candidate's knowledge and previous o t expertene nd qualifications, M e by the License t aining. By t delett he Supervisor,

( censed Ope Or D is verifying knowledge level an experte through oral or w tion and/ r y al review of c af s records L Any# deletion rogram shall be made by the use tion Letter format in Appendix "D".

7.6.3 Changes in the OJT Appendices to this program are authorized when changes in plant status or procedures

, mandate a change in the program. At the completion of g each class, the OJT program should be evaluated and j required program changes issued.

Interim changes may be a

issued with approval from the Manager, Plant Operations j and Manager, Plant Training using the format provided in k-A00010501182 22.0 1007D

TMI TRAINING DEPARTMENT Number Nuclear ADMINISTRATIVE M4NuAt 62i2-ADM-26ii.04 Title (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 Appendix D. Any interim changes issued shall be incorporated into the annual program description change.

7.7 Program Scheduling The program will be scheduled as required to support plan operations.

7.8 Records and Reports

1. A Trainin ,. nistrat V o 1 be completed and D

submitted Adminis ive ' on for each classroon lecture or lesson.

2 Current and pa A edule , lesson 1 n , Student handouts, complete. completed exams and T $ ts, e.

q bot- ritten an s well as any additional ent qualificat 6fds shall be maintained in accordance with Training Department procedures.

7.9 Evaluation

7. 9.1. At the conclusion of each phase of training, the license

. candidates will be asked to complete a training critique g form to assist in program evaluation. Guidelines provided in 6200-ADM-268L12 Course Evaluation Process, may be used h

i

!u .

in conducting course evaluations. The completed critiques j shall be reviewed by the Supervisor, Licensed Operator k

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TMI TRAINING DEPARTMZNT Number Nuclear AoMINISTRATIvE MANUAL sai2-AoM-2sii.04 Title (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 Training and forwarded, along with recommendations or corrective action taken to the Operator Training Manager.

7. 9. 2. At the completion of each training program, an internal team will be formed by the Supervisor, Licensed Operator Training to review the Fuel Handling SRO Training Program. The review team will consist of Ins c from the Operator Traint Section and perso e Operations De a he team i a t' e adequacy of the re r.

Meet b shed requ re ~t,a d responding to ident d Adequacy of @

Qua yfk1andp Ef it v s 942 In cond t review, the team may use any records main ined by the Training or Operations Departments.to assist them. These may include:

NRC Inspections QA Audits Other Audits g Regulatory Changes Industry Experience

@ Candidate Critiques 9

l 6

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Number TMI TRAINING DEPARTMENT Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 Title (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 7.9.2.2 The review team shall report the results to the Manager, Plant Training and the Manager, Plant Operations via the Supervisor, Licensed Operator Training and the Operator Training Manager.

7.9.2.3 Guidelines established in 6200-F N-2682 Technical Content Review and Ir.teri s should u ed in conducting

_eh eval ti O D 8.0 FUEL HANDLING SRO EQU 3FICATIONTRAI311N

</

8.1 Objectives O 8.1.1 The Le the re h1 program are to:

t n systems nally safe and reliable, b sure that personnel maintain the high level of skill and knowledge required to accomplish routine and emergency duties.

c. Establish a system for evaluating and documenting licensed personnel proficiency and competency.

g 8.2 Program Description 8.2.1 The operator requalification program shall include pre-planned training sessions conducted on a regular and

{

continuing basis, Skills Training and Evaluation and an f

l annual examination.

.i A000105011 82 25.0 1007D

0

(!

Tn! TRAINING DEPARTnENT Number o F"7 Nuclear AonINISTRATIvE n4NUAt 62i z-Aon-26ii .04 Title (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 8.2.2 Scheduling of the requalification program shall be determined by the Supervisor, Licensed Operator Training and approved by Operator Training Manager. The following areas as they relate to defueling operations, should be considered by the Supervisor Licensed Operator Tr ing:

1. Review of Defueling Systems

2. Initial traint on new defueling

3. Modificati y1talled ad ueling y

4. e vents Re e ts Ubstrial Experience Re ews S. OJT to h

t systems

6. N 1 Amal, 0 ating Procedures, and 6 sbcTa ed proce n s

%view of F t training

. Changes to jo 'a countabilities

9. Technical Specifications 8.3 Pre-Planned Lecture Series Schedule 8.3.1 ,

The pre-planned lecture series shall be scheduled on an g annual basis.

8. 3.1.1 Lectures may be deferred due t) unanticipated

, E events but should be conducted as soon as g practicable thereafter and within the annual 8 cycle.

i AOOO105011 82 26.0 1007D

TMI TRAINING DEPARTMENT Number Nuclear M M STRATIVE M UAL m 2- M -2 m .04 Tiue (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 '.

8. 3.1. 2 Topics for the FH SRO requalification program may, when practical, be integrated into the Licensed Operator Requalification Program.

8.3.2 Pre-Planned Lecture Series Topic The requalification program program shall inc1 preplanned training sessions conducted o 1 nd continuing basis aining sessi a 1-1 clude lecture damental r 86 d operational proff .

8. 3. 2.1 funda ~tal - ew lec series topics are selec on )as needed shall as a i1 hclude th :e o g ver the period of the icense: v a) The nciples of Fuel Criticality b) Heat Tra sfer, Fluid Flow, and Thermodynamics c) Defueling Instrumentation and Control Systems d) General and specific Defueling Systems operating characteristics e) Defueling Systems Protection Systems y f) Normal Abnormal, and Emergency Operating Procedures

}

, g) Radiation Control and Safety h) Plant Support Systems associated with l

defueling h

i A00010501102 27.0 1007D

TMI TRAINING DEPARTMENT Number Nuclear M INISTRATIVE MANUAL 6212-M-26H .04 Tita (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00

1) Applicable portions of Title 10, Chapter I, Code of Federal Regulations These topics presented should reflect the results of the annual examinations and performance of the FHSRO as evaluated by the Manager, Plant Operations and Site Operations Direc The topics shall be presented on p basis. tape of the ert s should be by the Supe sed Operator r%

a ning and a ro 'the Operator Training Manager.

8.3.2. T o a tonal fb ture series shall cover areas volve essential defueling operati B q nts. The topics for this series art-selected to ensure opera'tional changes and experiences are integrated into the training program schedule. The lecture topics should include the following as they relate to defueling operations:

g a) Normal, Abnormal and Emergency Operating Procedures.

, @ b) Technical Specifications g

c) Administrative Procedures, Conditions and

@ Limitations i

A000105011 82 28,0 1007D

TMI TRAINI O DEPARTMENT wmber Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 Title (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 d) Major operational evolutions e) Related Nuclear Industry Operating l Experiences f) Operating History and Problems The scope of the lecture series should be determined by the Supervisor, Licens r Trainin roved by the 0_e r 3ing Manage n tion on h y also be IF ther th c10 training such as ta f' iscussi se bepj?

8.3.3 Pre-Planned _Lekure des Attend

8. 3. 3.1 of all i e nnel shall be

3. ,,f Absences o ividual exceeding more than one week of-s heduled training for a qualification year shall be approved by the Manager, Plant Operations or the Site Operations Director. In any case the individual who misses the training shall be responsible for the g material presented in his absence and shall take the quiz that was given on the missed material, 8.3.3.3 Any mandatory attendance requirements shall be g determined by the Supervisor, Licensed Operator l

N A00010$01182 29.0 1007D

i TMI TRAINING DEPARTMENT Number Nuclear AoMIN!sTRAT!vE MANUAt s2iz- m -2sii.04 Tiu. (16219) Rev.Dion No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 Training and approvied by the Manager, Plant Operations and Operator Training Manager.

8.3.4 Pre-Planned Lecture Series Training

8. 3. 4.1 The pre-planned lecture series shall use ining sessions supported by lesson plans p et, nd approved ccordance wi',h Tr i nt proce 8.3.4.2 presentin O s shall be al f ed in r th Training Department procedur[ rectur ped not be qu b hall be a y the Operator Manager r ger, Plant Training, riting.

53. Pre-Planned Lecture' ries Evaluation The lecture series shall be evaluated by conducting evaluations of the trainees knowledge, effectiveness of the overall lecture series, and the effectiveness of the instructors.

S

8. 3. 5.1 After each week of lectures, all trainees shall take a written, closed book quiz covering the

{

lecture topic (s). This evaluation shall contain k-A00010501182 30.0 10070

,7 N' / TMI TRAINING DEPARTMENT Number w Nuclear m INISTRATIvE m um. su 2-a-uu.04 Titw (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 questions related to the lesson plan objectives covered during the lectures. Quizzes shall be evaluated and grade determined for each trainee.

A performance standard of 80% shall be established for the written quizzes. Trainees who do not meet these performance sta should complete a remedial revief s within eh eks consist. -  :

1) ge' review of( i ing session as rial asso i identified knowl c encies.

2) ew of a s(&fp ted reference -

1 ident d 't V Training Departme t-.

3) Adm Ita oNf a second quiz covering at

. leas t identified knowledge deficiencies.

If the second quiz is completed satisfactorily, the trainee should receive credit for completion of the required lecture. If the second quiz is unsatisfactory, the Supervisor, Licensed Operator g Training shall notify the Operator Training Manager of the results and the Operator Training Section shall provide a reconenendation regarding b

a A000105011 82 31.0 1007D

TMI TRAINI~3 DEPARTMENT Number Nuclear M INISTRATIVE M UAL 6212-ADM-2611.04 Title (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 -

the trainee's removal from Itcensed duties and entrance into an accelerated requalification program.

8.3.5.2 An overall evaluation of the annual lectu series should be conducted on an ann in accordance with Training Depar res 8.3.5.3 Instrue (alpations bd in th Trai i nt procedures.

D 8.3.6 Skills ining and4v tt In order p optabid f skills and familia sy d wi 1 stem, controls and o onaLprocedure / H8RG shall participate in q , hen 3 and vart in foolutions. Each FHSR0 shall V monstrate operational proficiency by participating in Reactivity Manipulations and Plant Evolutions.

To maintain these skills, licensed operators shall actually manipulate or actively supervise manipulation of the controls.

[ 8.3.6.1 Reactivity Manipulation and Plant Evolutions a During the two year tem of the NRC license each FHSR0 shall participate in a variety of f

a A00010$0 ll 82 32.0 1007D

TMI TRAINING DEPARTMENT Number Nuclear m INIsTRATIvE m uAt san- a -2su .04

~

Titie (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 reactivity control manipulations and plant evolutions. Due to the unique status of Three Mile Island Unit 2, in lieu of centrol manipulations prescribed by the March 29, 1980, NRC Directive as satisfying the requirements of 10CFR55 Appendtx A, the following Ifst appropriate manipulations shall be' g by the licon perators at .

es land Unit TC ipulati all) clude the g g over theOtod 6 the license:

Load ter with fuel / core 2 T for of ca 15 r Yeactor vessel to storage ou t vessel.

3. Transfe ster to storage racks in the

\ f fuel ing building. -

The manipulations are designed to emphasize the necessity for a focused awareness of the unique conditions and potential operations which are peculiar to the TMI-2 status.

g . A total of ten manipulations shall occur over the period of the license, with a minimum of one per

$ category per year. Documentation of these i 2 g . manipulations shall be completed using Appendix E.

I A000106011 02 33.0 10070

TMI TRAINI T; DEPARTMENT Number NucIear ADMINISTRAmE MANUAL 6212-ADM-2611.04 Revis;on No.

Titw (16219)

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 8.3.6.2 Abnormal / Emergency Defueling Evolutions On an annual basis each Itcensed individual shall participate in training exercises covering defueling abnormal / emergency conditions during a drill program which includes the following evolutions:

1) Fuel Transfer Abnormal Ope

2) Op'A nister it s Requir c r Building vacuatlo D 4 Radiolo dont Ind peratio performance du n abnornay raining exercises 1 be mon t anf,ddficiencies corrected so that sa ff) proficiency is demonstrated.

7articiphtion in a plant drill involves either responding to del 11 conditions or being assigned monttor for observing / evaluating response to a drill. Plant drills may be conducted wtth the approval of the Manager, Plant Operattons and g shall meet the requirements estabitshed in 6212-ADM-2611.02, Licensed Operator 2

Requalification Program Description. THI-2.

8 A00010501f.82 34.0 1007D

TMI TRAIN! D DEPARTMENT Number Nuclear AoMiNrSTRATrvE M4NuAt 62i2-AoM-26ii.04 Title (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 8.3.6.3 Skills Evaluation System Licensed personnel performance and competency related to performing Itcensed duties shall be periodically evaluated. Their performance evaluation established in procedure 6200-ADM-2682.10 " Trainee Evaluation Onc ck on The Job", may be used to evaluate 11 operato reence. Re te or other i r

~

c graded should be av ) by the Ma r lafft Operations and the

~ rator Traf ; &ber and appropriate train n O

Training,M e on 8.3,4;

/ D 1

a. In he &v M \ v. that skills training guidelines for\ t c pation in reactivity manf pulations (8.3.6.1) and Abnormal / Emergency Defueling Evolutions (8.3.6.2) are not met within the required time period, they should be scheduled and g

completed within fourteen (14) weeks of the

! required period.

E a

A0001060 Il 82 35.0 10070

,?!

ha# IM A iMAiNilR ULFAMIMLMI Number oU Nuclear M NISTRATIVE M UAL 6212-ADM-2611.04 "hEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGR 2 '# b

. b. In additicq to meeting the requirements for participation noted above, each licensed FHSRO shall actively participate in defueling operations a minimum of one shift per month. During this period, the Itcensed personnel shall actively perfo ed operator duties. Based on h s, satisfact p nce shall d as mee he quirements on a quarterly has t e to meet the proflCl rement shall result in the 11(e[% rator placed in an act e Statup t in Program.

c Do umentat - c standing shall be comple n Appendix E.

T O Skills Training Participation The operational review program is a system for on-shift review of selected operational experiences and changes to existing operating guidance or equipment. The operational

" review program enables continuous updating of on-shift E personnel and estabitshes a means of disseminating new or changing information on a short tens basis.

6 36,0 100fD

TML T N ARTMENT Number Nuclear ^oatatsmitvc amat sziz-Am-zsu.a MEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGR 2 b , ,

8. 3. 7.1 Modt flcation Review

a. A continuing system shall be established by the Manager, Piant Operations such that licensed individuals review documented defueling equipment changes, equipment modifications, procedure changes a techncial specification chang d ch d modificati analyzed 1 formation ri tfo-hebasisfor tM. changes 1 -(r e rational implica 1 beted.

b.

d nge rgency dures, technical t ations d safe lated systems r to the licensee

~

s all be .

assuming L peration responsibilities.

c. r. Plant Operations and the

% The Supervisor, Licensed Operator Training should specifty changes and modifications to be analyzed, with information for review transmitted in accordance with the urgency of the situation. The Manager, Plant g

! E Operations should ensure that all on-shif t licensed personnel review the selected

{)

Information in a timely manner.

l " " ' "

37.0 100$D

l TMI TRAINING DEPARTMLNT Number Nuclear ADMINISTRATIVE MANUAL 6212-ADN-2611.04 l NEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGR 2 00

, d. Expanded coverage of plant design changes, equipment modifications, procedure changes and technical specification changes in the Operation Proff elency Lecture Series should be considered by the Supervisor, Licensed Operator Training.

e. On-shif t supervisory (FHSRO O p 1 should proy to sh ft operator ting and iewing che se d difications. An on-shi Ion period to review changes

.a ions is d uraged.

f viewshalyb o nted with a real tr tta\ all licensed h ind 1 acknowledgement of revfew re 8.3.7.2 Operating xperience Revfew

a. A continuing system shall be established by the Manager Plant Operations such that

, Itcensed individuals review operating g

E expertence from TM! and applicable segments of the nuclear industry. Selected operational events and reportable a

A000104011.Il 38.0 1007D

F IMI TRAINING DEPARintnI Number Neler ADMINISTRATIVE MANUAL 6212-ADM-2611.04

" BEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGR T2 b occurrences at the factitty should be analyzed and infonnation pertinent to the event collected. Selected operational infonnation from the nuclear industry should be analyzed. The following sources of information should be considered:

1) Licensee Event Reports 2h , evaluation  : tion rts

) Publicath4 periodicals covering u ddstry infonnation.

4) P0 Sign t Event Reports b J4hnager, P 0 erg)Nns should ensure hat all o - ift4 Mensed personnel review th in a timely manner.

1 c. Su t coverage of operating experience in the Operation Proficiency Lecture Series should be considered by the Supervisor, Licensed Operator Training.

d. This information should be fonnelly transmitted to all Itcensed Individuals with E required acknowledgement of review.

9 5

i

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TMI TRA N ENT Numbw Nuclear = tarStaATivE a uAt su r-m-un.04 DEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGR 2 1 00 8.4 Annual Requaitfication Examination In order to determine each licensed individual's knowledge of topics covered in the requalification program and provide a basis for determining areas in which retraining is needed, an annual requalification examination shall be given. The annual examination shall be given to all Itcensed individuals to d

the completion of each annual requalification propr shall consist of an oral p ination and a w .1 e 16ation.

8.4.1 Annualdth amination g An a %ritten ex tiojn all be administered to all Itcensed indt id O written ination shall contain ex ht estiont, y hefollowing topt(s, relate t_ - f ory and P ing taso Fuel Crtticality HeatTransf!n 1 id Flow and Thermodynamics N)

3) Features of Defueling Factittles Design

4) Defueling Systems Operating Characteristics

5) Defuel.ing Systems Instrumentation and Control Systems

6) Defueling Protection Systems

7) Radiation Control and Safety E 8) Appitcable Portions of Title 10, Chapter I, Code of Federal Regulations

9) Normal / Abnormal and Emergency Operating Procedures i oiosoit si

,o ..

ha' lM1 IRAIN11Ha Ut,rAKIMt,NI MNISMWE MM nun 2-2-2611.04

" O' Nuclear

" BEL HANDLING SENIOR REACTOR OPERATOR TRAINING PRO U 2 l "80

10) Technical Specifications

11) Defueling Administrative Procedures, Conditions and Limitattons

12) Nuclear Industry Operating Experience l The topf cs should be grouped categories similar NRC licensing examination for evaluation pur

8. 4.1.1 WelliQ tion Adp ra g) ,v v CW Sten examin d be prepared Lnder Pstructur 11 onsistency of questioning and , ssible c ise of e s prior ni tion. The ation con ctf and security shall be in accordan t t Ing Department Procedures.

8. 4.1. 2 Written Examination Performance Standards A licensed' individual receiving a grade of less than 705 in any examination category and an overall grade of less than 805 shall be relieved of his Itcense duties and placed in an g

E accelerated qualification program.

9 5 Under special circumstances where a grade of less

. 7.

than 705 has been scored in a single section, the N

i

41. 0 100 7 ""'"

TMI TRAININ(i DEPARIMt.NI Number Nuslear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 MELHANDLINGSENIORREACTOROPERATORTRAININGPRO 2 l "80

~

Director, TMI-2 may document the special circumstances and authorize an oral and written reexamination of the failed section within one (1) week. If the oral exam is completed satisfactorily and a grade of 80% or greater is i scored on the written section, the indiv al may 1

l return to shift in a licensed sta approval the Director, TM .

8.4.2 AnnualA$r nation D

, An ann ral examin ins L administered to all 1

licensed individ O

8. 4. < aminatiorpGn

a. The ta n tion should contain qu covering the following areas as they relate to defueling:

1) Licensed duties and responsibilities of the operating position corresponding to the individual's license level.

2) Action's in the event of abnormal E

E conditions.

a

~

o Actions in the event of emergency l 3)

~

j conditions.

I E l e Aoooioso n-s2 l

TMI TRAINING DEPARTMENI Number Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 MELHANDLINGSENIORREACTOROPERATORTRAININGPRO b2 b s 4) Interpretation of instrumentation I responses.

l l 5) Defueling System transients and f

accident response.

} 6) Defueling System modifications.

7) Procedure changes.

8) Technical Specificatio 9 r ency Plan.

ling g ry and Gp problems b

11) clear industry defueling kDat ng exper [ s. a O

T aminati d tion 8.42 (

nation shall be conducted

~

a.

un e itructure enabling consistency of questioning and evaluation. The following I

guidelines should be considered.

1) A checklist identifying the areas to be covered shall be used.

g ~. 2) Overall evaluation shall be made on a e

E pass / fail basis.

3) Comments on individual strengths and weaknesses shall be made.

l 8 i

A000105011-82 l 43.0 1007D

IMI 1 RAINING Ut;FARIMt;MI Number  :

Nuslear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 (i62is) i "YUELHANDLINGSENIORREACTOROPERATORTRAININGPROGRAMUNIT2 b y

=

l

!. b. The Supervisor, Licensed Operator Training d l

and the Manager, Plant Operations shall 4 i establish the oral examination schedule. 4

c. Personnel assigned to conduct an oral evaluation shall be designated by the Supervisor, Licensed Operator Tra and approved by the Manager, P1 s.

Or kaminations shal d by a ic TerSenior Opt r r rsonnel -

} ignated b M -

Ma er, Plant Operations and th i ons Director.

8.4.2.3 min tion Performance _ Gndards g overa) o i ation grade shall requirey individual to be removed g from hi se duties and placed in an accelerated requalification program. -

8.5 Special Retraining Programs Specific retraining programs for licensed individuals may be l

y required to upgrade or refresh knowledge and skills related to "j e

E licensed duties. -

l 9 -

g

. E i

l  ! =

1  :

I AOOO105011 82 E 44.0 1007D i G

1 l

IRA IMAIN ANb Ut'.FAKIRt'.Mi Nuclear ^oatutsTRATIve aa" val "1172-Aon-2sii.04

" 'I "NELHANDLINGSENIORREACTOROPERATORTRAININGPRO 2 1 "00

,' 8.5.1 Accelerated Requalification Program The accelerated requalification program is for licensed individuals having identified deficiencies requiring assignment to a special retraining effort.

8. 5.1.1 Required Attendance Licensed individuals meeting one he follow iteria shall be i an ai requalifica pr a:

I ual requal t written examination perfo dY encies.

2) nu3 ificati al examination nce def encie

-plann erfes quiz performance de

4) Si nt licensed duty performance deficiencies identified by the Manager, l Plant' Operations and/or the Supervisor,  ;

Licensed Operator Training.

8. 5.1. 2 Program Content The accelerated requalification program content E . shall be specifically structured to upgrade I

2 o knowledge and skills identified as deficient.

. K i Examination categories and areas in which I

e i

45.0 1007

0 -

TMI TRAININE: DEPARTMLNI Number

- o[~.j I Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 "bELHANDLINGSENIORREACTOROPERATORTRAININGPROGR 2 b

. performance standards were not met shall be covered in the program. The Supervisor, Licensed Operator Training, shall be responsible for formulating individual accelerated requalification programs. They shall be approved by the Operator Training Manager, and . er, Plant Operations.

0

8. 5.1. 3 PedRag ._ stratio lerated on program may volve a va Y raining exercises including:

1) rA f-study.

1 terview d dis ton sessions.

re-plan _ ec .

4) Ski 1s .n exercises at the plant.

Program on should be dictated by the extent of training required and the trainee's performaned.

8. 5.1. 4 Performance Standards y

~

a. Successful completion of the accelerated e

E requalification program shall be determined n

5 by administering an examination. The examination shall cover all categories of a

A00010501182 46.0 1007D l

TMI TRAINING DEPARTMull Number Nuclear ADMINISTRATIVE MMUAL 6212-ADM-2611.04 "YUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PRO 2 Nb0 ,

, the requalification written examination and/or all areas of the requalification oral examination originally failed.

b. The examination format should be similar to the original examination, and the examination shall be conducted by individuals designated by t ,

L Operator Trai .

c r grjiiance stan or e accelerated qualificati shall be as follows:

1) t least 80% on each k 14! rated re ication written o xaminati a go 9

) A e tion on the accelerated tion oral examination.

d. In ent.that these standards are not met, the individual's suitability for resuming itcensed duties will be reviewed by the Supervisor, Licensed Operator Training.

He shall provide a recommendation to plant n

management and the Director TMI-2, via the e

E Operator Training Manager and Manager, Plant n

5 Training regarding the individual's

. i<

permanent removal from licensed duties or a

i i

A000105011 82 47.0 1007D l

TMI TRAINING DEPARTMENT Number Nushr ADMINISTRATIVE MANUAL 6212-ADM-2611.04 (3043W) Revision No.

TitYUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 ,

additional upgrading efforts to be considered. If appropriate, another accelerated requalification program siiall be structured to correct deficiencies.

8. 5. 2 Inactive Status Retraining

8. 5. 2.1 If a Itcensed individual has not ried out lic duties for a p ess of fo y s, a spe 9 et ing program dvaluation b -

d prior to resuming fcensed du s.

a. .

s can be A tained by nce of en d es and participa in equalification pro e- nce of licensed duties for a F4] volves the manipulation or supervision of the manipulation of controls I which 'may effect the reactivity of fuel at the facility, and for those individuals not normally assigned to an operating shift, completing the requirements for h participation in defueling operations, n

j b. In the event that a licensed individual does not maintain an active status, the I

e s

! AOOO105011-82 48.0 1007D

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

TMI TRAINING DEPARTMENT Number ENuclear ADMINISTRATIVE MANUAL U 6219) 6212-ADM-2611.04 Revision No.

Tit EL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00

. Supervisor, Licensed Operator Training shall designate, subject to approval of the Manager, Plant Operations and Operator Training Manager, a Licensed Senior Operator or subject matter expert to conduct an oral examination similar to scope and t to an annual oral examination ming 1

9 duties. In a i , > aluation of r nce in t re re-planned Octure Seri conducted. If perf e Pre-Planned Lecture te nsatisfa \ a written nation s r n pe and format to the annual t xamination shall be the licensed individual

~

a .

pri resuming licensed duties.

c. Consideration should be given by the Managbr, Plant Operations to assigning the licensed individual to a training status on a defueling shift prior to resuming licensed a  ! duties.

e E d. The performance standards applied to the 2

3 annual requalification examination shall be i .

used in evaluating the results of the oral I

t 49.0 10070

IMI 1RAININU ULPAKIMLMI

"" Mag y Nuclear ADMINISTRATIVE MANUAL "NELHANDLINGSENIORREACTOROPERATORTRAININGPROGR 2 "* NO

, and written examinations. If the performance standards are not met, the licensed individual shall complete an accelerated requalification program prior to resuming licensed duties.

e. In cases where the licensed oper s not performed licensed duties f f re g than four (4) ensed t ay be re on rtificatio y rector TMI-2, which must a. to the NRC.

8.5.3 Requalifica ning for41y,Lt Msed Individuals 8 5 '. y cens y shall enter the requali 1 at ram and participate in the annual cycle upon receipt of their license.

8.5.3.2 Newly licensed individuals successfully completing their NRC licensing examination less than three (3) months prior to an annual requalification examination may be excused from g

!9 taking the current annual written and oral 5 examinations.

5 8

5 a,

3 e

aoooioso ii-s2

IMI IRAINING DEPARIMLMI Number Nuslear ^oarNtstarttve aANuat 62iz-AoM-26ii.04 DEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGR 2 NO 8.6 On the Job Training 8.6.1 The OJT program shall consist of tasks selected by the Supervisor, Licensed Operator Training and approved by the Operator Training Manager and the Manager, Plant Operations. These tasks will be chosen to reinforce new systems training or any problem areas identifie - the Manager, Plant Operations.

O 8.6.2 The OJT pr e elbped as pa th qualification will to suppl $ task lists issued undert; eplaceae t r 8.6.3 Due to conditio f he nt it will be neesk elop new k1 M for the licensed pera rs. These 3 s nd the associated training pJugram coverage 111 developed in accordance with the Training Department Procedures.

8.6.4 During the annual r5 view of the training program the tasks identified for inclusion in the requalification shall be incorporated into the replacement program description.

5 E 8.6.5 Primary verification of OJT tasks shall be done in n

5 accordance with guidelines established in the initial 5

program.

k n

i e

Aoooioso i t-s2

9,*

,o

- 0/;/ IMI IRAINING DEPARIMLNI Numtser Nu21 ear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 "YUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGR 2 b 8.7 Licensed Operator Certification 8.7.1 Due to the sequencing of defueling operations the training program for fuel handing senior reactor operators will

~

require that some phases of defueling after the initial defueling be covered in the requalification program. As a result, the tasks for which the operators were ally trained will be supplemented in order to h. ach  !

operator is ade trained to ac ueling operations ter comp o initial repla am. g 8.7.2 The completion a .

ned OJT g rams and satisfacto on of ex 1natio Wncompassing identi s s will co tification of the to safel -

w . ntly perform defueling

\p rations.

8.8 .a fication Program Records u

Records of FH SRO's performance in the requalification program shall be maintained in an auditable manner. These records shall be maintained in accordance with Training Department procedures.

E 5

n 5

t E

.e Aooot oso i t.82

IMI 1 RAINING DLPARIMLMI "

Nuslear ADMINIS M TIVE MANUAL 62Y2-ADM-2611.04

" BEL HANDLING SENIOR REACTOR OPERATOR TRAINING PRO 2 lb ,

I APPENDIX A ON-THE-JOB TRAINING CHECKLIST On these sheets are lists of Adminis eEmergency,Ag , rational and Surveillance procedures whi t 7 read, dis a alked through.

b Approximately fifteen (15) ese pr e be addressed each week to maintain an adequate rate of progr ss gh all o e items listed.

O NOTE: Unit 2 procedures 4 g ing forma change. Procedures indicated differen c eck with Control Room if any probl ining a proce urs.

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"".2T2-ADN-2611.04 Nuclear ^DMINISmTIvE MANuAt "YUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PRO U 2 NX) l APPENDIX A (NAME) l DATE I TASK EXAMINER l l I i 1.0 For the following Administrative l l l Procedures each candidate should: l l l A. Read the procedure. l l l B. Be able to identify and implement l l l the procedure which best suits a l l l given situation. (i.e., use the l l l procedure to correctly respo to a l I situation posed by the e y l l C. Describe your responsi ,

I l pertaining to the pr e l l 1.01 4000-ADM-1000.01 a 1000.01 b l TMI-2 Organizatiori y l l

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1.02 4000-ADM-1000.02 Organ zationa l 4 l l Shutdown Responsibility a h l /t I i 1.03 4000-ADM-1218.01 an 01 1 Procedure Numberin tent '

l l Implementation a ce and l l Operating P e'd6 l l l 1.04 4000- 4

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l l l 1.05 400 -1 3 Procedure Chan d l l l Review .I l l l l l 1.06 4000-ADM-1218.04 TMI-2 Document Control l l l and Distribution l l l l l l 1.07 4000-ADM-1218.08 Procedure Periodic Rev'tew l l l l I 1 1.08 4000-ADM-3000.1 TMI-2 Unit Work l l l Instruction- '

l l l 5 I I I 5 1.09 4000-ADM-3020.04 & 4000-ADM-3020.05 l l l 5 Tagging l l l 5 I I I

, ; 1.10 4000-ADM-1100.01 Confined Spaces l l l Tl I I k 1.1'1 4000-ADM-3020.06 Unit Facilities f I l Status Tagging l I l E

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IMi IK iNiNG UI.VAKIMLMi Number Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 "YUELHANDLINGSENIORREACTOROPERATORTRAININGPROGR 2 Y2iG

' APPENDIX A (NAME) l DATE l TASK EXAMINER l l l l 1.12 4210-ADM-3020.03 & 4210-ADM-3020.04 Shift l l l Relief and Log Entries l l l 1.13 1033 Operating Memos and Standing Orders l l ,_d l I I i 1.14 4000-ADM-3061 Recovery Operations Plan l l l Surveillance Test Program l m L& l 1.15 9200-ADM-1201.02 Radiological s l l Reporting l n _ _

/ l V\M ~ l 1.16 4015 - Admin. and . osure and V l l Contamination Limif a l l

/ I i 1.17 4046 Radiological Re tw Proce l Al l l l l 1.18 4000-ADM-2600.01 Job Brie .it h

) ek l d l Up Training  !? . .A l 1.19 4000-ADM-1500.02 a{ Informat'o O

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1 TMI TRAINING DEPARTMENT Number Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 "YUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGR 2 "1-ii0

, APPENDIX A (NAME) 1 DATE l TASK EXAMINER l l l l Read and be familiar with the FHSR0's l l l Responsibilities of the following l l l Administrative Procedures: l l l 1.20 9200-ADM-4110.07 Radiography Operations l l _

l 1 .21 4210-ADM-3020.01 Conduct of Operations l lC l 1.22 4000-ADM-3030.02 & 4000-ADM-303 Good Housekeeping I

I dl (v) cr I l l

1.23 4200-ADM-7350.01 Modifico 1 is l l 1.24 T.S. 6.2.2. & 2202 Requirements nning f > l l

l l

/ I i 1.25 4150 Rad Material Transfer Accou l />l l 1.26 4140 Radioactive Liquid i Tt 1 3 l 1.27 RWP's 9200-ADM-4110 h l 1.28 4041 ALARA P l l 1.29 4000-ADM-1 0 fold Insp l l l l Section 1.0 Final Verification Examiner /Date 5

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2. 0 Under the direction of the Operator at the l l l Controls perform the following l l l l l l 2.01 Observe / qualify switching and tagging l l l operations per 4000-ADM-3020 and l l l 4000-ADM-3020.05 l ln l O

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TMI TRAINING DEPARTMENT Number Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 "hELHANDLINGSENIORREACTOROPERATORTRAININGPROGR 2 1 iX) ,

APPENDIX A (NAME) l DATE l TASK EXAMINER l l l l 3.0 For the areas listed below be able to l l l complete the objectives identified for -l l l each: l l l l l l A. Describe the various l l l types of fire detection systems, I l l state their setpoints & Specs. l B. Describe the effects o ic I

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actuation sequenc ng:l l

1. Deluge Syst j l tds. I l

2. Fire detect system in t re l l 3.01 Coordination Center (A & B) l l l 3.02 Reactor Building (A & ) Q l 3.03 Auxiliary & Fuel .

ut ding (A <8 l l l I Sections Final Verific t on 2.0pab\

Examiner /Date 5

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TMI TRAINING DEPARTMENT Number Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 (l0219) Revision No.

• PUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 APPENDIX A (NAME) l DATE I TASK EXAMINER l l l l 4.0 For the following System Operating l l l Procedures in sections 4.0 and 5.0 the l l l candidate should be able to: l l l A. Trace flow paths l l l B. Locate major components l l l C. Locate instrumentation and controls l l l D. Discuss the following

1. Limits and precaution l

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2. Automatic response /in 1 6 l setpoints l / l

3. Indications f i l operations l l l 1

4. 01 Reactor Building No Emergen  ! l l Ventilation and Coolih 2104-5. ' l /)l l 4.02 Fuel Handling Building H 904 2 l k l 4.03 R.B. Purge using the 2104-4.91 d rge Syst lgW h l I

\ I i 4.04 Temporary Con Service A 1 l l System 4370 _ K01 l l l

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TMI TRAINING DEPARTMENT Numbe Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04

• BEL HANDLING SENIOR REACTOR OPERATOR TRAINING PRO NN 2 "$0 1-APPENDIX A (NAME) l DATE I TASK EXAMINER l 1 1 I

5. 0 Reactor Coolant System l l l 1 l l

5. 01 Reactor Coolant System Operation with l l l core cooling via natural losses 2104-10.2 l l ,M l o .

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" h EL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGR 2 "1-00

,' APPENDIX A (NAME)

I DATE I TASK EXAMINER l l l 6.0 Core Construction i I A. View the Quick Look 1 & 2 video tapes l l l and the Core Topography Videotape l l l (Candidate signature only re l l l in the task examiner column) quired l l l 6.1 Internals indexing Fixture Le ntrol l and Cleanup l l A. Explain / discuss the ope the 1 i l Internal Indexing F l l Control and Clea l I I "

l l P l i I I I I I I O I q l 0 l l l

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l l l I I I I I I I I l 5 Sections 4.0, 5.0 and 6.0 5

Final Verification

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& Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 "YUELHANDLINGSENIORREACTOROPERATORTRAININGPROGR 2 1$0 APPENDIX A (NAME) l DATE l TASK EXAMINER l l l l 7.0 For the following Emergency & Abnormal l l l Procedures, the candidate should be able l l l to complete the following objectives as l l l they apply to defueling operation: l l l

1. Describe the conditions that require l l l entry into the procedures. l l l

2. State the procedure objective (s). l l l

3. Explain the bases for not d l l l precautions. l l

4. Explain the conseque o l l following the proce l 1 1

7. 01 Station Blackout A -13 .02

i' I I 7.02 Blackout & Loss of Diesel l 4210-EAP-1300.03 Wh M ll l 7.03 Fire 4210-EAP-3680.01 o P o et

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7.04 Unanticipated C 2202-1.2 borations l\lv l l

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TMI TRAINING DEPARTMENT Number Nuclear M INISTRATIVE MANUAL 6212-ADrt-2611.04 IUELHANDLINGSENIORREACTOROPERATORTRAIN1NGPROGR 2 1-00 APPENDIX A (NAME) l DATE I TASK EXAMINER l l l l 7.06 Loss of Source Range Instrumentation l l 4210-EAP-3623.01 l l l l l 7.07 Loss of RCS Level Indication l l l 4210-EAP-3220.04 l l _. _

l 7.08 Changes in RCS Water Level Beyond l l Normal Span 4210-EAP-3220.06 l

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• TMI TRAINING DEPARTMENT Number Nuclear AoMINISTRATIvE nANuAt 62i2-AoM-26ii.04 (16219) Revision No.

mIUELHANDLINGSENIORREACTOROPERATORTRAININGPROGRAMUNIT2 1-00 APPENDIX A (NAME) l DATE l TASK EXAMINER l l l 1 8.0 For the following Emergency & Abnormal l l l Procedures, the candidate should be able l l ll to complete the following objectives as l l ll they apply to defueling operations: l l

1. State the procedure objective (s). l l

2. Explain the bases for notes and l l precautions. l 1

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3. Explain the consequences following the procedure. 9 l l

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8.01 Hazardous Releases '} , l 8.02 High Reactor Buildin > ressure l l

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4211 -EAP-3240.01 , l l l l O

(Q) \D Section 7.0 and 8 Final Verifica feb

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TMI TRAINING DEPARTMENT Number Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 "YUELHANDLINGSENIORREACTOROPERATORTRAININGPROGR 2 "' N$0

' APPENDIX B ORAL EXAMINATION SUM ARY SHEET:

PURPOSE (CHECK ONE)

IXEDTUKTE T NAME

( ) OJT SECTION FINAL VERIFICATION EXAMINER ( ) FINAL EXAMINATION

( ) OTHER DATE SUMARY OF QUESTIONS ASKED GRADE,(PASS h h- 0 dW W 4W s

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WEAK AREAS OVERALL EVALUATION (PASS / FAIL)

FURTHER ACTIONS REQUIRED (IF NONE, SO STATE) k i

- SIGNATURE OF EXAMINER h SUPERVISOR, LIGEN5ED OPERATOR TRAINING g

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IMI IRAINING DtPARIMLMI Nuclear ^onINISrRATIvE nANuAt "" 26T 2-Aon-26ii.04 "YUELHANDLINGSENIORREACTOROPERATORTRAININGPROGR N 2 b APPENDIX C DESIGNATION OF AS FINAL OJT EXAnINER DATE:

TO:

You are hereby designated to serve as the final verification examine r the OJT Sections noted below:

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(LIS IONS) for Fuel Handling SRO's on Shi _\

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• O Nuclear ^oaINistaATIvE MANUAL ""W2-ADM-26ii .04 "YUELHANDLINGSENIORREACTOROPERATORTRAININGPRO N 2 180 APPENDIX D Addition / Deletion Letter to Fuel Handling Senior Reactor Operator Training Program DATE:

SUBJECT:

Addition / Deletion of Training Program Requirements for Fuel dling Senior Reactor Operator T0: Manager, Plant Operations Operator Training Manager Ref: (a) Applicable section of ng program In accordance with re ({a it is requ t. the following requirements be added/ del Han nior Reactor Operator Replacement Traning Progra roar'the Fuel,d

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• TMI TRAINING DEPARTMENT Number Nuclear ADMINISTMTIVE MANUAL 6212-ADM-2611.04 "YUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGR 2 * *Y00 .

When approved, the candidate shall mark each affected item "Added/ Deleted Per 6211-(Letter Number)." A copy of this letter shall be kept by the candidate and this letter filed in the candidates training record in the Training Department.

SUBMITTED:

CONCURRE .n //

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ROVED: d,

\W Distribution: Candidate Candidates Training- r Manager Plant 0 Operator Tral Supervisor Li rator Tr in e

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TMI TRAINING DEPARTMENT Number Nuclear ADMINISTRATIVE MANUAL 6212-ADM-2611.04 Tim (16219) Revision No.

FUEL HANDLING SENIOR REACTOR OPERATOR TRAINING PROGRAM UNIT 2 1-00 APPENDIX E FHSRO WATCHSTANDING/ EVOLUTION DOCUMENTATION This is to certify that stood watch and performed licensed duties as a FHSRO on on the (07-15) (15-23)

(23-07) shift.

The following evolutions were supervised: l Evolution Qty Loading of fuel canister ~

Transfer of canister from react to storage outside the vessel Transfer of canister t ac s.

Other M

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