ML20062B888
| ML20062B888 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 10/13/1978 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Stampley N MISSISSIPPI POWER & LIGHT CO. |
| References | |
| NUDOCS 7811020025 | |
| Download: ML20062B888 (9) | |
Text
NRC PDR
[ >= aso *o UNITED ST ATES 8
n NUCLEAR REGULATORY COMMisslON
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WASHINGTON O. C. 20555 c.
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OCT 131978 Docket Nos: 50-416 and 50-417 Mr. N. L. Stampley Vice President - Production Mississippi Power & Light Company P. O. Box 1640 Jackson, Mississippi 39205
Dear Mr. Stampley:
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION IN GRAND GULF NUCLEAR STATION UNIT NOS. 1 AND ? FSAR Based on our review of Sections 13.2 and 13.5 of the FSAR, we have developed the enclosed requests for additional information regarding operator licensing.
A meeting has been arranged on November 1,1978 at your facility with members of your staff and Mr. Bob Campbell of NRC to discuss these matters.
Following this meeting, please submit your responses by an amendment to the FSAR.
Sincerely, fL i
l Joan F. Stolz, Chief -
(
( Division of Project Management Lfght Water Reactors Branch No. 1
Enclosure:
Requests for Additional Information l
I cc:
See next page l
".D'.?'.C7: 0027 A
- i Mr. N. L. Stampley OCI'131978
- cc: _Mr. Robert B. McGehee, Attorney Wise, Carter, Child, Steen &
Caraway P. O. Box 651 Jackson, Mississippi 39205 Troy B. Conner, Jr., Esq.
Conner, Moore & Corber
.1747 Pennsylvania Avenue, N. W.
Washington, D. C.
20006
'Bechtel Power Corporation ATTN:
T. W..Habermas Project Engineer Grand Gulf Nuclear Station Gaithersburg, Maryland 20760 I
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ENCLOSURE REQUESTS FOR ADDITIONAL INFORMATION GRAflD GULF flVCLEAR STATION UNIT NOS.1 AND 2 DOCKET NOS. 50-416 AND 50-417 Requests by the following branches in flRC are included in this enclosure.
Requests and pages are numbered sequentially with respect to previously transmitted requests.
Branch Page No.
Operator Licensing Branch - Conduct of Operation 440-1
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440-1 440.0 OPERATOR LICENSING BRANCH Conduct of Operations 440.1 Provide the number of persons who will be traf*ned (NONE) for licensing pursuant to Section 55.25 of 10 CFR
, Part 55. The number of persons for whom training is planned in preparation for senior operator and operator examinations prior to criticality should be sufficient to assure that applicable technical specifications conditions with respect to the number of licensed operators on shift crews can be met from the time of initial fuel loading. Due allowance should be made for examination contingencies and 3
the need to avoid planned overtime for supervisory
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personnel during the startup phase.
440.2 Provide contingency plans for additional training (NONE) for individuals to be licensed prior to criticality in the event fuel loading is subsequently delayed following completion of the formal training portions of the program.
441.1 Provide a detailed description of the fire protection (13.2) training and retraining for the initial plant staff and replacement personnel so that the findings addressed S
in Paragraphs TI.6.A-E of Section 13.2 of NUREG-75/087 (Rev.1), " Standard Review Plan..."
can be made.
441.2 Figure 13.2-1 indicates that, at this point in time, (13.2.1).
, essentially all of the training schedule has been completed. The descriptive material, however, implies that only the Basic Nuclear Course has been completed.-
s Specifically identify which counes have been conducted to date and correct Figure 13.2-1, if needed.
441.3 What is the duration of the GGNS Technology Course and-(13.2.2) what organization is ' responsible for teaching it?
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441.4 What facility or facilities will be used for the BWR (13.2.2)
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Observation Training described in Paragraph 13.2.2.1.5?
i Describe the supervision-that the trainees will receive during this phase of training.
441.5 Does the applicant have any alternative plans for simulator (13.2.2) refresher training as described in Paragraph 13.2.2.1.6 if the_GE BWR-6 simulator is not operational. We believe it to be highly desirable that individuals who will sit for a license examination prior to criticality participate in a short simulator course imediately prior to the T
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examination.
In addition, for scheduling purposes, the, applicant should understand that license examinations are administered within two months of fuel loa ~ ding, not 5 or 6 mnnths prior as shown on Figure 13.2-1.
441.6 The licensed operator requalification program described (13.2.2) in Paragraphs 13.2.2.2, 13.2.2.2.1, 13.2.2.2.2 and 13.2.2.2.3 must include additional detail. The applicant may wish to consult ANSI /ANS-3.1-1978, "American National Standard for Selection and Training.f Nuclear Power Plant Personnel", which contains an acceptably detailed re-qualification program.
In any event, the program a
description must specify:
1.
That the minimum of lectures is 6, spaced throughout
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i the year and taking into consideration heavy vacation periods and infrequent operations such as forced outages, etc; 2.
the specific reactivity manipulations for which credit will be taken; 3.
that the emergency and abnormal procedures review will be conducted annually; 4
that the minimum acceptable grade on a periodic examination is 807.;
5.
that the annual examination will be comparable in scope and degree of difficulty to an NRC examination m
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consistent" with the type of license held; 6.
that a licensee scoring less than 80% in a category of the annual examination shall be equir'ed to attend a lecture (s) in that subject; 7.
that an individual scoring less then 70% overall on the annual examination shall be removed from licensed duties and placed in an accelerated requal-e ification program and that the individual shall score at least 70% on any written reexamination prior to return to licensed duties; 8.
that each licensed operator shall receive a perfor-mance evaluatiori annually; 9.
that individuals who maintain licenses for the purpose
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of providing backup capability shall, as a minimum, participate in the requalification program as follows:
a.
Be administered the annual written examination and participate in the lecture series based on a
the results thereof; b.
manipulate the controls or supervise the manipula-tion of controls through 10 reactivity changes; c.
systematically review design changes, procedure changes and facility license changes; d.
systematically review the contents of all abnomal and emergency procedures en a regularly scheduled basis ;
5.
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i e.
be syst'ematically evaluated regarding actions I
to be taken during simulated abnomal and emergency conditions by a walk through of the pr'ocedural steps.
441.7 In addition to the retraining program for licensed person-(13.2. 3) 4 nel, a description of the retraining of other position categories on the plant s+3ff should be provided. The description should include the nature, scope and frequency of such retraining. As a minimum, refresher training for non-licensed personnel should be periodic and not less than biennial and should include as a minimum refresher instruction on administrative, radiation protection,
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security and emergency procedures.
441.8 Describe the means for evaluating the training program (13.2) l effectiveness for each employee. For applicants for l
license examinations prior to criticality, the means I
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l employed to certify that each applicant has had extensive actual operating experience pursuant to Section 55.25(b) j of 10 CFR Part 55.
i 442.1 Provide a schedule for the planned completion of pro-(13.5) cedure development. A generally acceptable target date 4
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for completion of administrative, operating and emergency procedures is six months before fuel loading.
Familiarization with these procedures is an an essential part of the staff training prqgram, including preparation for cold operator license examinations; therefore, procedure preparation should be completed in a timely manner.
442.2 A statement is made that "Section 13.4 additionally (13.5) defines types of procedures or instructions requiring Plant Safety Review Committee review." Section 13.4.2.d, Responsibility - Plant Safety Review Cor:mittee, makes no 2
mention of procedure review. Please clarify this apparent y
discrepancy.
N. 3 Indicate your intention to provide Fire Protection (13.5.1)
Procedures.
42.4 This section of the FSAR should include a diagram of (13.5.1) the control room area which indicates the area designated "at the controls".
i 442.5 Indicate your intention to provide Radioactive Waste (13.5.3)
Management Procedures and :taterials Control Prc adures.
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