ML20148F990
| 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: |
| References | |
| WYR-78-6, NUDOCS 8011070075 | |
| Download: ML20148F990 (4) | |
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$ HKEE ATODIC ELECTRIC C0fAPAHY f..
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. United States Nuclear Regulatory Commission Washington,'D. C.
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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)
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(b)
Letter, D. E. Moody to USNRC, dated
-October 17, 1977, WYR 77-97 4;;,
(c)
Letter, USNRC to D. E. Moody, dated
,Docomber 23, 1977.
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Dear Sir:
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-mation needed for the review of that program was requested by the NRC hy [ Q
~a 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
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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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h, ?.id Very truly yours, 1
YANKEE, ATOMIC ELFCTRIC COMPANY f
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ADDITIONAL INFOPJ1ATION 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..
4 RESPONSE II.A.4.., Changed to Road i
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If a licensed' operator for senior operator fails to achieve an overall 1
- cxamination grade of;70%,- on either.the annual examination or the l walk through evaluations, he will be required to participate in an J
accolorated requalification program prior. to resuming licensed -
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)QUESTIONII.C.1.
.xw changes mdesign changes, procedure changes, and facility license
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-Facility ust be explicitly indicated as part of the required review, RESPONSE 'II.C.1.
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.All licensed operators and senior operators will review facility design phanges, applicabic procedure changes and facility license 1
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'As.a minimum, all abnormal and emergency procedures shall be reviewed on an annual basis.:
RESPONSE [I'l.C. 2.
Changed'to Road am The Training Coordinator will insure all licensed operators and senior ik!
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. operators review all abnormal and emergency procedures at least dl annually.<;The completed forms will be roturned to the Training C
i Coordinator.for. file'intthe individual's file.
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. QUESTION I1.C.4.
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
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which Yankee Rowe will take credit.
The staff position is that t
only.the following constitute acceptable reactivity changes.
[4 1.
Reactor startup to the point of adding heat.
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Controlled reactor shutdown.
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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 yh'y Icast 10 ppm.
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' Operation of the manipulator crane in the core during refueling.
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Any power changes of 10% or more in manual rod control.
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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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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 I
shutdowns when power,is less than 15%.
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4 '... LOperation ofLthe turbino governor controls:in manual during i startups' andhfor power changes equal to orJgreater than 10%.
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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.
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Any power changes of 10% or more in manual rod control.
6-8.
Manual rod control prior to and during generator synchronization.
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