ML19248C462
| ML19248C462 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 09/20/1978 |
| From: | Collins P Office of Nuclear Reactor Regulation |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7809250156 | |
| Download: ML19248C462 (8) | |
Text
{{#Wiki_filter:i '</<. t ~ 1978 SEP 2 0 OPM J. F. Stolz. Chief, LWR Branch #1, sing Branch, DP!i Docket !{o I'.EMOPAliDU!i FOR:P. F. Collins, Chief, Operator Licen RESPO1SE TO REVIEN Plo.?! ASSIG!N Et4T } FR0!!: REVIEW 0F C0tiDtICT OF OPEPATIO'l StEJECT: Grand Gulf ?!uclear Station PLAtlT ftA'!E: i, 50-416/417 1 00CV,ET !!05: OL Cor.plete UIR 1, C. Thomas LICEtiSit!G STAGE: TING ASSISTA!1CE: BRAftcil A?!9 PROJECT mat:AGER REQUES OP't:0LB l REVIC-! RRA!iCH INVOLVED: 22, 1978 Sept.rhnr Sections 13.2 REQUESTED COMPLETIO:: DME:Revic'a of Conduct { DESCRIPT10:10F REVIEU: and 13.5 f First Round Ouestions 4 REVIDI STATU3: Based on our revic+t, 3 5 of the FSAR. ified in the Ue have reviewed Sections l'.2 and 1 additional info i i molete our revie.v. I h We have detemined that t eenclosura, is necess applicant so desire. l hould the able to discuss these iters, s l C O " *3 ' ",w m vy e om r -,
- w Paul F. Collins, Chief Operator Licensing Branc EncTosure:
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I ATTACPJiENT A h 't OPERATOR LICENSIMG BRANCH i 440.0 Provide the nurber of persons who will be trai'ned f 440.1 (NONE) for licensing pursuar.t to Section 55.25 of 10 CFR The number of persons for whom training t Part 55. is planned in preparation for senior operator and i i i operator examinations prior to criticality should be sufficient to assure that applicable technical I specifications conditions with respect to the nurber of licensed operators on shift crews can be met from i Due allowance the time of initial fuel loading. should be made for examination contingencies and the need to avoid plarned overtime for superviso./ I personnel during the startup phase. 1 i Provide contingency plans for additional training 440.2 (NONE) for individuals to be licensed prior to criticality in the event fuel loadin'g is subsequently delayed I following completion of the formal training portion' i of the program. Provide a detailed description of the fire protection 441.1 (13.2) training and retraining for the initial plant staff and replacement personnel so that the findings addressed i. 1032 1 5
-{? in Paragraphs TI.6.A-E of Section 13.2 of NUREG-75/087 I can be made. (Rev.1), "S tandard Review Plan..." f Figure 13.2-1 indicates that, at this point in time, J 441.2 l (13.2.1) ll of the training schedule has been , essentially a The descriptive material, however, implies completed. that only the Basic Nuclear Course has been compieted s Specifically identify which courses have been cond i to date and correct Figure 13.2-1, if needed. .I I What is the duration of the GGNS Technology Course a 441.3 (13.2.2) what organization is ' responsible for teaching it? i ~ What facility or facilities will be used for the BWR k 441.4 Observation Training described in Paragraph 13.2.2.1.5? (13.2.2) ~ Describe the supervision that the trainees will receive during this phase of training. i Does the applicant have ary alternative plans for simu i 441.5 13.2.2.1.6 (13'.2.2) refresher training as described in Paragraph We believe if the GE BWR-6 simulator is not operational. it to be highly desirable that individuals who will sit [ for a license examination prior to criticality participate in a short simulator course immediately prior to the I h 1032 v*o i 1 exarcination. In addition, for scheduling purposes, i I the applicant should understind that license examinations I are administered within two months of fuel loa' ding, not 5 or 6 months 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 s 13.2.2.2.3 must include additional detail. The applicant may wish to consult ANSI,JANS-3.1-1978, "American National Standard for Selection at Training of Nuclear Power Plent i Personnel", which contains an acceptably detailed re-qualification program. In any event, t~e program a d'scription must specify: i I ~ 1. That the minimum of lectures is 6, spaced throughos. t the year and taking into consideration heavy vacation ~ periods and infrequent operations such as forced outages, etc; 2. the specific reactivity nanipulations for which credit \\ will be taken; 3. that the emergency and abnonnal procedures review will be conducted annually; 4. that the minimum acceptable grade on a periodic examination is 80%; 5. that the annual examination will be comparable in scope and degree of difficulty to an NRC examination h 1032 ,'7 consistent' with the type of license held; 6. that a licensee noring less than 80% in a category of the annual exanination shall be requir'ed to attend 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-s ification proqram 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 evaluation annually; I 9. that individuals who maintain licenses for the purpose ~ of providing backup capability shall, as a minimum, participate in the requalification program as i follows : a. Be administered the annual written examination s and participate in the lecture series based on j the results thereof; b. manipulate the controls or supervise the manipula-tion of controls through 10 reactivity changes; I c. systematically review design changes, procedure { changes and facility license changes; d. systematically r eview the contents of all abnomal and emergency procedures on a regularly scheduled basis; 1032 ,'S be syst'ematically evaluated regarding actions e. to be taken during simulated abnormal and emergency conditions by a walk through of the pr'ocedural steps. l In addition to the retraining program for sicensed person-441.7 (13.2. 3) nel, a description of the retraining of other position The categories on the plant staff should be provided. description should include the nature, scope and frequency I of such retraining. As a minimum, refresher training for i non-licensed personnel should be periodic and not less than biennial and should include as a minime: refresher a instruction on administrative, radiation protection, ~ security and emergency procedures. t l Describe the means for evaluating the training program 441.8 effectiveness for each enployee. For applicants for ~ license examinations prior to criticality, the means employed to certify that each applicant has had extensive actual operating experience pursuant to Section 55.25(b) of 10 CFR Part 55. Provide a schedule for the planned completion of pro-442.1 (13.5) cedure development. A generally acceptable target date i. ~ l032 ,*9
,.~ for completion of administrative, operating and emergency procedures is six nonths before fuel .j loading. Familiarization with these procedures is an en essential part of the staff training program, including preparation for cold operator license examinations; therefore, procedure preparation should be completed in a timely manner. I 442.2 A statement is made that "Section 13.4 additionally (13.5) ,;i defines types of proceduras or instructions requiring 1 j Plant Safety Review Comm',ttee review." Section 13.4.2.d, I Responsibility - Plant Safety Review Connittee, makes no i 2 mention of procedure review. Please clarify this apparent ,e disc repancy. I j 442.3 Indicate your intention to provide Fire Protection (13.5.1) g Pmcedu res. A2.4 This section of the FSAR should include a diagram of (13.5.1) the control room area which indicates the ama designated "at the controls". 442.5 Indicate your intention to provide Radioactive h'aste (13.5.3) Management Procedures and liaterials Control Procedures. i i i i-1032 C3}}