ML20037B409

Proposed Revised Requalification Program for Licensed Reactor Operators,Senior Reactor Operators & Limited Senior Reactor Operators

ML20037B409
Person / Time
Site:	Dresden
Issue date:	07/31/1975
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20037B408	List: ML20037B407 ML20037B409
References
NUDOCS 8009250566
Download: ML20037B409 (11)

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culy 1975 TM Reanalification Program Changes Throughout the document, references made to licensed' Fuel Handling Foreman has been changed to read, limited Senior Reactor Operator license holder.

This change was made because-not all ISRO holders are Fuel Handling Foreman by specific job title.

The document has some reorganization chanEes which.in-clude.the second paragraph of the document being relocated-from Section VII and rearrangement of items addressed to fuel handling personn61rbeing moved or deleted where redundant.

Section I Lectures Wording chancca to denote clarification but do not

. chanEe intent, scope or time.

7-2A-7,7 Section II Simulator Training

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Deleted paracraph on fuel handling foreman as it is not applicabic.

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Section III On The Job Training O@

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A.

Deleted Attachment A as it is redundant in Attachment B & C (Paragraph 1).

(Paragraph 3) Deleted sentence requiring an individual holding a license for all three Dresden Units will perform at least three manipulations on D'-1 Unit.

This was deleted due to the steady load conditions on D-1 making the requirement inpracticable..The simulator produces general operating characteristics which we feel are adequate for requalification -

training.

B.

Reworded to give responsibility of procedure-review of abnormal and emergency procedures to senior licensed operators.

C.

No Chance.

D.

Deleted time allotment of three days per year to make outline'd reviews.

The review may take more or less time depending on document revisions.

Delcted second paragraph as it is redundant in Section VI.B.

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July 1975 t Added additional paragraph to exempt annual-examination re-quirements for persona deeply involvqa in adninistering the requalification program C.

. Word changes for clarity.

D.

Word changes for clarity..

x E.

No Change.

Section V A.

Word change for. clarity.

B.

Reworded to cover item B & C together.

• Deleted requirement of be$ ng assigned shift supervisory duties of eight houre/ year.

This is not required nor.is it significant.

Section VI Fuel Handling License Training A.

Items one thru eight - Wording changes for clarity.

B.

No change.

C.

Added compliance of IV C which wac overlooked in submittal.

Section VII Records Relocated lact paragraph to opening statement..

Section VIII Last Paragraph Omitted the word " consecutive" from. three' day requirement..

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duly 1975 R:-QUALIriCATION Pi10GiiAbi POR 1,ICI:!CIO l'.F: ACTO 4. OFE:' ATOM, nic.t m is.c m ni' ATai * / *!U IJMI Ti'h T'NIIIO! lini,CToii O!

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CWOIiWE:AT.TM EDICO!! CnMPAI!y J'l 42.Of The followinC requalification program is designed to

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assure staticn management that all licenced reactor operators, senior reactor operators and limited senior reactor licensees maintain a high level of competence.

The program consists of lectures, situlator training and on-the-job ~ training.- Records shall be maintained and evaluations made of each man's progress.

Extra licensed operators are provided at each of our stations; so that personnel can be made available for requalification training.

The Station Superintendent at each Ccmmonwealth Edison Company nuclear power station has delegated to the Training Supervisor responsibility for implementing and coordinating the requalification program for the station.

I.

Lectures Lectures will be given on the following subjects as required by Sectica IV of this document on Reactor Operator and Senior Reactor Operator level.

A.

Theory and Principles of Oneration Lectures will include review of terminoloEy, reactor kinetics, rod worths, reactivity coefficients, reactor transients, thermodynamic effects and reactor behavior curves.

B.

Radiation Protection. Waste Disposal & Regulation Ldetures will include review of federal and company radiation exposure limitations, control methods, mcnitoring equipment, waste disposal cystems and calculations for exposure dose and shiciding.

C.

'I!chdsl. Abnormal and Emergency Procedures Lectures will include review of plant operating cnd/

or fuel handling procedures, including normal, atnormal and emergency procedures.

D.

Administrative Series Ic::urer 'cill rcciec ::minir r;;icc pr:redures.

r,U Eli.". aECUrance Jr:cedurer, technizal pCrificE-icnr. I;c'lity liter.re and ::::icr en rcen:: plan.

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'E.

?lant Modificationc This sect 10n will provide up-to-date informatien-Ocncerning rystem de:1cn changes. instrument cet point chance:, wiring modifications and any other plant modifications implemented during the. test recent~requalification interval.

F.-

Onerating Characteristics and Experience Analysis of plant operating characteristics during normal and abnormal operating conditions, FSAR-related transients and a review of incidents or

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abnormal c:currences at Edison stations and other utilities will be covered in these lectures.

G.

Plant Systems Creration and Control This secti:n will have lectures on the operation and control of the Reactor Protection Systems, plant instrumentation, emergency core and containment cool-ing systems, engineered safeguards and other related plant systems.

H.

Coen Lectures This secticn is reserved for lectures which may per-tain to upccming events or outages.

I.

The minimum time requirement for review of Section A -

through H will be 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> over a period of two years.

II.

Simulator Training A.

A period of three (3) days per year will be spent at a simulator which has the characteristics of the plant for which the senior operator or reactor opera-tor is licensed.

Here, he will perform normal cperating functions and will be exposed to situlated

• inormal.and emergency operating conditions.

The simulatcr may also.be used to complete the required reactivity changes in Section III A below.

III.

On-the-Job Training A.

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July 1975 of reactor start-ups, reactor shutdownc, or~other control manipulations which demonstrate skill'and/or familiarity'with reactivity control systems.

These operations will not be limited to any one unit,-

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but will be representative of all units for_which.

the licensee is licensed.

A separate list of manipulaticns are included in Attachments A (BWR) and B (PWR).

It is also our intent that a start-up is to the point of adding heat and a shutdown means an orderly plant shutdown.

B.

Licensed senior operators will be respcnsible-for

. reviewing the contents'of all abnormal and emergency procedures with licens~ed operators.

C.

Each licensed operator and senior operator will review facility design changes, procedure revisions, and facility license changes.

D.

Holders of a limited SRO license will review fuel handling procedures, procedure revisions, facility license changes and design changes which affect fuel handling operations.-

IV.

Evaluation A.

Examinations will be given to determine each licensee's knowledge of subjects covered in the lectures.

A minimum grade of 80% shall be the criterion used to determine that an individual has learned the material presented in the lectures.

Achieving a grade of less than 80% will necessitate the individual repeat the caterial presented ~1n the lecture.

The testing program will_ emphasize topics related tc. the operating functions of the licensee.

B.

Annual written examinations, which determine areas in which retraining is needed, will be administered to licensed reactor operators, senior reactor operators and limited senior reactor operators.

This examina-tion may be administered on one or two days at.the' discretion of.the administrator.

The reservation for administering an annual examination

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July 1975 duties.

Our intent is to adminirter the examination-cn One day or two contmcutive (f ayr.

In the event of.

an examination on more than onc uay, the cections wculu be ceparated to pre 9ent the examinee frc=

sccing the content of the examinaticn beforehand.

The criteria to be uced for determination of the requirements for retraining are as follows:

An individual must achieve a grade of 80% in any category of the annual written examination to be exempt from mandatory attendance at a lecture in that subject.

An individual failing to achieve an cverall grade of at least 70% en the annual written examinations will be relieved of licensed duties until he demonstrates. competence to canagement by either an additicnal oral examinaticn or satisfactory ccepletion of an accelerated requalification program..

Any persons deeply involved in administering the.

requalification program or annual examinations shall be exempt from the requirements of lecture attendance and examinations as this is part of their normal' work function.

However, these persons shall be required tc participate in the annual three day simulator retraining program.

C.

An oral examination will be administered at least once during each two year licensed interval to each reactor cperator, senior reactor operator and limited senior reactor operator.

This may. include an cral examination of the operators to determine their know-ledge of normal and emergency operating equipment and precedures and/or fuel handling equipment and proced-ures.

This may also include an' oral review of a licensee's performance during a reactor start-up,

. shutdown, abnormal or emergency operating recovery.

D.

Evaluations will be made-by persennel on the training staff, cperating shift supervisors er other licensed supervicors involved in crerations or vendors per-scnnel during actual or simulated ncrmal, aonormal cr emergency ccnditions.

E.

An annual review will be tade by station management cf each licensee's performance in_Secticn A-thrcugh D above and a determination will be.made concerning the licensee'c qualification to centinue in his assigned dutics cnd the n=ca fer retraining or accelerated

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Licensed ' Percennel Not Actively Inr.nged in Licensed-l'ut$ on for Ferio.lc of Peur (h) i3cnth: or irnecr Abennee L.in to Illnot:

The licensec will be enrolled-in an accelerated retraining program and must satisfactorily cetplete a written or oral examination prior to assuming licenced duties.

5.

Absence Due to Assir.nments Other Than-Licensed Duties The licensee will maintain license eligibility by participation in and catisfactory completion cf the requalification program, or he shall be enrolled in an accelerated retraining program or must satisfac-tcrily complete 0.n examination prior to assuming licensed duties.

VI.-

Puel Handling licenne Training A.

Limited senior reactor operators will attend lectures as designated in Item I appropriate to fuel handling operations.

Lectures considered appropriate _ for_ fuel

• handlers in Item I are as fc110ws:

1.

Review of terminology, reactor theory, rod worth, core loading physics and calculations.

2.

Review of federal and company radiation exposure limitations, control methods, monitoring equip-ment, waste disposal systems when pertaining to the fuel pool systems, calculations for exposure dose and shielding.

3, Fuel handling procedures.

E.

The Generating Station Emergency Plan and all items directly related to fuel handling indicated in the documents listed in this series.

5 Plant modifications directly or indirectly related to the perforn.ance and maintenance of fuel handling operations or equip. tant.

6.

FSAR transients, operating experience, incident review related to fuel handling.

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. B.

-Special reviews of fuel handling procedures and equip-ment in preparation for duties such ac refueling or receipt or chipment of-Ibel or. shipping cachs will be conducted with fuel handli-ng personnel.

C.

Comply with Item III TD,. IV B. and IV C~.

VII.

Recorde A.

The Training Supervisor is responsible for maintain-ing records of the training progress for each man in the requalification program to include as a minimum:

1.

Written evaluation examination, answers-given by licensee, and grade for.each tan.

Resultsofe'caluahionsrequiredin-thisdocument 2.

Sections IV C, D, and E.

3 Records of procedure review, facility design changes, procedure changes and facility. license change review, and plant manipulations required, in Section III.

4.

A record of the date of start and end of each person's two-year requalification period.-

VIII.

Schedules The requalification program shall be conducted continuously for two years with the exception of the 3 month summer vacation period.

The lecture series shall be -conducted on a continous -basis during the periods when licensed personnel are relieved of shift. duties and are available for scheduled classes.

Each lecture shall be repeated as necessary to afford licensed _ personnel the opportunity to mee: 1ecture require-menta as determined by the written examination evaluation.

Lectures shall not normally be scheduled during the months of June, July, and August'due to the minimum availability of shift personnel during this prime vacation period.

Simulator refresher training shall be scheduled for three days each year for each licensed operator and senior oper-ator as dictated by the availability of the simulator.

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ATTACHMENT-A EWR Manipulations for Which Credit Will be Taken 4~

in It'em III A. of Recualification Prc, ram S

Plant startup - suberitical to the point of adding heat.=

1.

2.

Orderly plant shutdown'- power to suberitical.

3 Power chances which demonstrates skill and/or familiarity with reactivity control systems.

4.

Core physics tests as follows:

Shutdown Margin Tests Rod-Worth Test 1'oderator Confficient Test Power Coefficient Test i

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ATTACHMENT B PWR Manipulations for Which Credit Will be Taken in Item-III A. of Rec.unlificaticn Prof, ram 1.

Plant startup - suberitical to the peint of adding heat.

2.

Orderly plant shutdown - power to suberitical.

3 Power changes.which demonstrate skill and/or. familiarity with reactivity controls.

4.

Boration or dilution of greater than 50 ppm 1(approximately 0.5% ok/k) while critical.

5 Core physics test as follows:

Shutdown-Margin Test Rod Worth Test Temperature Coefficient Test Power Coefficient Test Boron Worth-Test 1

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NRC DISTRIBUTION FOR PART50 DOCKET AiATERIAL (TEMPORARY FORM)

CONTROL NO: 8059-FILE:

F RO.M: Co==onwealth Edison Co.

DATE OF DOC DATE REC'D LTR TWX RPT OTHER Chica Ill.

60690 7-22 7-29-75 XX TO:

ORIG CC OTHER SENTimC PDR-XX XX Mr. Paul F. Collins 1 signed 79 SENT LOCAL PDR CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:

@ 237/249/254/265/295 80 DESCRIPTION: Ltr re Commonwealth Edison Co.

ENCLOSURES: Requalification Program 304 ltr of 4-5-74....trans the following:

Changes.....

Proposed Rivised Program Reuqalification Program for Licensed Reactor Operators, Senior Reactor Operators & Limited Senior Reactor Operatars....

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PLANT NAME: Dresden, Quad-Cities & Zion Stat i.ons g(,3;','; $ 7'9 FOR, ACTION /INFORMATION DHL 7-30-75 BUTLER (L)

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