ML20148F990

Responds to NRC 771223 Request for Addl Info Re Operator Training Program

ML20148F990
Person / Time
Site:	Yankee Rowe
Issue date:	01/26/1978
From:	Groce R YANKEE ATOMIC ELECTRIC CO.
To:	Collins P Office of Nuclear Reactor Regulation
Shared Package
ML20148F986	List: ML20148F982 ML20148F990 ML20148F995
References
WYR-78-6, NUDOCS 8011070075
Download: ML20148F990 (4)

Text

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$ HKEE ATODIC ELECTRIC C0fAPAHY f.. '

-6 cl 0 20 Turnpiko Road Westborough, Massachusotts 01581 Y#mtus n sqh, January 26, 1978

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!. . United States Nuclear Regulatory Commission l 1 Washington,'D. C. 20555 L r m.

• Attentions Office of Nuclear' Reactor Regulation  :

Paul F. Collins, Chief Operator Licensing Branch '

Division of Project Management References (a) License No. DPR-3 (Docket No. 50-29) I. -

(b) Letter, D. E. Moody to USNRC, dated

-October 17, 1977, WYR 77-97

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(c) Letter, USNRC to D. E. Moody, dated

,Docomber 23, 1977. $#'

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Subject:

Yankee Ecwe Operator Training Program  !

In Reference (b) Yankee Atomic Electric Company submitted their .

Operator Training. Program for the Yankco Rowc plant. Additional info- *

~a mation needed for the review of that program was requested by the NRC hy [ Q in Reference (c) . Attached you will find, as Attachment A, the answers fpt,,,:f4 to the questions outlincd in Reference (c) . Alco attached is Revision.4 '

to Procedure AP-0500, Yankee Rowe Operator Training Program which has ..

been revised to includo the information which appears in Attachment A *C(4 %.- -

to this lotter.

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We trus't that you will find this information satisfactory; however, should you dcasire additional information please contact us. $

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Very truly yours, 1 h, ?.id .,

YANKEE, ATOMIC ELFCTRIC COMPANY f

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-MAMTA ADDITIONAL INFOPJ1ATION i, ! '

JQUESTIONII.A.'4.. -

The comments and cvaluations contained on the completed operator

Evaluation- Form plus the results of the Annual Evaluation Examina- ' '

tion shall'f:rm the basis.for'an accelerated requalification program

-.when needed.. .

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RESPONSE II.A.4.., Changed to Road rTm -

If a licensed' operator for senior operator fails to achieve an overall .. 1

cxamination grade of;70%,- on either.the annual examination or the -

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,>.-" l walk through evaluations, he will be required to participate in an accolorated requalification program prior. to resuming licensed - '! 4

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)QUESTIONII.C.1. "

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-Facility changesust mdesign be explicitly changes, indicated procedure as part changes, and facility of the required license review, (+p[kh RESPONSE 'II.C.1. Changed to Read -

.All licensed operators and senior operators will review facility 1

design phanges, applicabic procedure changes and facility license chang d.

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QUESTION II.C.2.. w.:,

i 'As.a minimum, all abnormal and emergency procedures shall be reviewed k

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RESPONSE [I'l .C. 2. Changed'to Road The Training Coordinator will insure all licensed operators and senior am

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. operators review all abnormal and emergency procedures at least ik!

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, annually.<;The completed forms will be roturned to the Training C .. i Coordinator.for. file'intthe individual's file. . ye

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. QUESTION I1.C.4.

l Provide the method by which non-shift licensed personnel and Shift Supervisors are evaluated during actual.or simulated abnormal and emergency plant conditions.

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' RESPONSE II.C.4. . Changed to II.C.3. To Read -

The performance of all-licensed individuals will be evaluated during .

actual or simulated ' abnormal and emergency plant conditions. This

-will-be donc to meet the requirements for systematic observation and

~ cvaluation which appears in Paragraph 4.c of Appendix A of 10 CFR 55.

This will be accomplished by oral examination in the case of simulated cmergencies. -These evaluations will be documented and placed in individual's file. @%"%

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QUESTION.II.D.1.

Appendix A of AP-0500 contains a listing of reactivity changes for '

i which Yankee Rowe will take credit. The staff position is that t ~

only.the following constitute acceptable reactivity changes.

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1. Reactor startup to the point of adding heat. h, .y . .

2.- Controlled reactor shutdown.

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3. h!anual control-of steam generator levels during startups and  ;

shutdowns when power is less than 15%.

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

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5. Boration or dilution which changes boron concentration by at Icast 10 ppm. , yh'y r

6. ' Operation of the manipulator crane in the core during refueling. Irw

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

h!anual' rod control. prior to and during generator synchronization.

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RESPONSE II.D.1. Appendix A Changed to Read

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1. Reactor startup to :the point..of adding heat.

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2. . Controlled reactor shutdown.. ' '

'3. 41anual control of steam generator' levels during startups and shutdowns when power,is less than 15%. I 4&.

4 '... LOperation ofLthe turbino governor controls:in manual during &

i startups' andhfor power changes equal to orJgreater than 10%. -

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5. Boration or dilution which changes boron concentration by at least 10 ppm.

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Operation of the manipulator crane in the core during refueling.

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

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

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