ML20012E988
| ML20012E988 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 03/30/1990 |
| From: | Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-90084, NUDOCS 9004090254 | |
| Download: ML20012E988 (33) | |
Text
{{#Wiki_filter:i , y . New Hampshire l u c, n., Senior Vice dent l'resi and ; ChielOperating Officer ; l NYN-90084 l 1 March 30, 1990 l United States Nuclear Regulatory Commission Washington, DC 20555 -{ i i Attention: Document Control Desk '
References:
(a) Facility Operating License No. NPF-86, Docket No. 50-443 i ( (b) NHY Letter NYli-89144 dated November 13, 1989, 'FSAR Section 13.2', T. C. Feigenbaum to USNRC
Subject:
FSAR Section 13.2 Descriptive Enhancements ' Gentlemen: ; New Hampshire Yankee (NHY) committed in Reference (b), to submit FSAR
- Section 13.2 (Training) descriptive enhancements by March 30, 1990. The enclosed FSAR Section 13.2 descriptive enhancements are responsive to NRC ?
Staff comments / questions which were provided to NHY representatives in conference calls on October 13, 1989 and October 25, 1989. Additionally, the enclosed FSAR Section 13.2 revisions reflect the current NHY Training organization and editorial revisions. ' The enclosed FSAR Section 13.2 descriptive enhancements are in the form of annotated pages to facilitate identification of revisions. It is NHY's ; intent to include these revisions in its next FSAR Amendment (63) which is scheduled to be submitted by April 15, 1990. If you have any questions regarding this letter please contact Mr. Terry L. Harpster, Director of Licensing Services at (603) 474-9521 extension 2765. Very truly yours, f hNf Ted C. Feigenbaum ; 9004090234 900330 PDR h ADOCK 05000443 PDC New Hampshire Yankee Division of Public Service Company of New Hampshire P.O. Box 300
- Seabrook, NH 03874
- Telephone (603) 4744521
.- . ~ ._
$ e b
United States. Nuclear Regulatory Commission Nkrch 30, 1990 i Attention: Document Control Page 2 ! cci Mr. William T. Russell ! Regional Administrator , United States Nuclear Regulatory Commission i Region I l 475 Allendale Road King of Prussia, PA 19406 Mr. Victor Norses Project Manager [ Project Directorate I-3 . United States Nuclear Regulatory Commission } Division of Reactor Projects l Washington, DC 20555 l Mr. Noel Dudley . NRC Senior Resident Inspector i i P.O. Box 1149 Seabrook, NH 03874 i a i f J l r .i
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March 30, 1990 l NYN 90084 r FSAR SECTION 13.2. DESCRIPTIVE ENEANCEMENTS i P Duffett, J. C. PSNil l Hart, J. B. 01-48 Kline, G. J. 02 08 ; Krohn, R. L. 01-48 Moody D. E. 49-SS ; Sweeney, R. E. Bethesda Richardson, P. M. 09-15 Temple W. J. 49-CE ' Tsouderos, G. YAEC Vargas, J. M. 01-62 02-07 ! Warnock, J. J. Ropes and Gray Boston ! Executive Offices 01-40 i LIC Routing Copy 01-48 Subject File 01-48 l I File 0001 01-48 E RMD 02-06 I l l E l 1 l l
e . $8 1 & 2 Amend:ent 62 T$AR 13.2 TRAININC { 13.2.1 1.icensed Operator Training /
- a. General Discussio3 .
3 The licensed operator training progress will provide personneliskills and knowledge related to the operatici of Seabrook Station necessary to ensure that each individual can safely and ef f ectively perf ore , various assignments. Eligibility of individuals to license or renew , a license pursuant to the requirements of 20CTR55 vill be certified j by the t'in hW'" - Nuclear production.
- Rerutive, IXrec%r i
The overall objectives of the licensed operator training prograss are f o To train a staff to operate and anintain the units safely, , dependably and economically. I o To prepare shif t superintendents, unit shif t supervisors, control j q room operators 7and selected seaberu of the Station Staff for the NRC licensing examination f or Reactor Operator (RO) and Senior Reactor Operator ($RO). s .,. .
- The safe, ef ficient operatinn of a nuclear power plant depends on the qualifications and proficiency of its personnel. Several t
l basic categories of training are necessary to provide licensed [ personnel with a high degree of competence and professionalism. Specifically, these categories of training are as follows:
- 1. Licensed Operator Initial Trainint I
i All personnel requiring NRC operating licenses, as speci-
--? fled in 10CFR55, will have to undergo intensive training l
L which will meet or exceed the miniaua requirements of 10CTR$5. I
- 2. Shift Technical Advisor Trainint New Hampshire Yankee has a training program for the Shif t l Superintendents or Urc * $hif t $9pervisors to meet the long 6L tera plan of s a t i s f y'..ig the need for a Shif t Technical y Advisor on shif t. The Shift Technical Advisor Training is designed to meet or exceed the recommended guidelines referenced by NUREG-0737.'
- 3. Licensed Operator Requalification Training Progras' This category describes the training necessary to maintain the proficiency of all Seabrook licensed personnel. This rogran vill acet or exceed the mintaus requirements of p!
. Tai.4;r m S.
l0 C F PL 1T E*. '59 c. . 13.2.1
e . $81&2 Amendoe:t g 15kR ett - $6 -0Vy
- y. gj, s c i 4 Progree Atereditation and Instructor Certification _
y i New Hampshire Yankee is consitted to the accreditation i ' process endorsed under the Tinal Policy St at ement on ' Training and Qualification of Nuclear Power Plant Personne1 I g Arnendt.d. To meet this commitment, the company instituted a procedur 7 l ally administered accreditation process. The process is i carried out by an accreditation tean working under a ' s q rri q ; consittee known as the Steering Committee. eu;:M &; , It is Seabrook Training policy that all training instructors l who provide instruction in safety systems, integrated ! response, transients, and simulator courses vill be NRC ! ve.n4 */ - licensed or @ & certified. f4 ail-4*etenetese .he have-not. t ogg.g.,d-a-f eeHitMitenee-styd; ;;stified-fee-etteffft l su bj e cts-i n--whi ch--t her-heve--deoene t ee r ed-l i sens e--n evel comprehenrivn and ekM1. t'he-detteeinetton ci this- I eee4444ee t-t en-1, wh. ;;;;;;e4+t m 7 ri shs :Upsrsttent ! l Training-Menegen i l Cuest lecturers considered to be experts by nature of 'A ! their work responsibilities will be used on a Itaited f
-) basis to supplement the TIraining Staff instructors. :
, These guest lecturers are exempt from the senior operator l' i-criteria. l i l b. Responsibilities O i i The following Seabrook personnel are responsible for various areas of i Seabrook's 1.icensed Operator Progras ' c%m Dir.4Sr' ;
- 1. 4'i+e-P ete44 ewe- - Nu c l e a r P r od u c t i on !
ra e u ve. C ir#c)>r l The Vice-Peeefdene - Nuclear Production has overall responsibility ! for qualification and proficiency of Seabrook Station personnel.
- 2. _Trainint Manager The Training Manager provides direction and control for the ;
conduct of training at Seabrook Station. The Training Manager , reports to the H ;;- h;;N e..s - Nuclear Production. ! E.e e p..oor j
- 3. Operations Training Manager i The Operations Train'ing Manager is responsible for the develop-ment and implementation of training conducted in support of the operator training programs, including licensed operator, non-1 licensed operator, technical training for engineering staff. *l simulator training, and fire protection training. l i
6k 13.2.2 l l l l q
i .
$51 & 2 Amendment 62 !
TSAR fc4Ap h \ 4 Technical Training Manager t, , F $ 5- 1 i t The Technical Training Manager is responsible for general employee . training and for supporting organisational training, including l saintenance, oh ni:::y, i;;lik r"i a s, instrumentation and con-l l lmrb db ee del +v W mi.eand quality assurance and supervisory /sanagement training. brol t
$ll [p /. Training Suppor,-
t Services v h - Manager '
" i The Training Support Services Hawager is responsible for the
[ i i administrative support of training activities, including program l development, evaluation.pnd accreditation activities. ' l ro*nl K.a.e@$ 13.2.1.1 Program Description - Licensed operator Initial Training ! i II ') h This prog' ram will provide an individual with the knowledge and skill / ! ) level necessary to safely operate Seabrook I' nit I and obtain an NRC l j Senior Operator's License or Operator's License. The program acets ! i or exceeds the requirements of 10CTR$5. l I : oreure O The license training program schedule will enette that a suf ficient. l 1 h number of licensed personnel will' be available prior to fuel loade , and will continue to meet applicable technical specification condi- ' i j i tions with respect to the number of licensed operators on shif t crews. ' t I~ f ' p:---:: -h; ;i! :ti;::::: :: 1t :ing -h ;;;;SihL;d 6: :11 2:::: lg$4(b ! !?;.ne; :::hhg. h:h;;d:: :! ;;;; :: e!S;;h::::: :h;11 h- t j pot 4::;;d by. jl) ;;;. hug ;;;;;e .ui r e r udh r a == ===nt af c h ;; -- M , M . room-preeeo ut40: :d ci :h :: h;;;::tien' (M " etude-t -- erst:t [ svalu*tizen 'eyh h : ::: --ft *^ t he licente i s;.bh; ;-^-e a- t-ei.wngsnwu .;;h ::::: identi-' th: r;k t' k evelvasion pioceTn Thefollowingparagraphsprovideageneral{escrigtionofthgvar gra g se en
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- a. Nuclear Resetor Fundamentals '
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- b. Reactor Startup Experience
- m bM ] Th>r e t -^9 *^"ema 4-00-'t;i;d .i . ..;;:::S ;; ;;;! h; heil-i t !er el! -^14-11er- ::eep:- E ;tri--ata; dina" eie-- --d M ) demone;;etivus are condun.4-t: :::;11;;;; th: 7:1 ei;1^-
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- c. Operating Plant Observation
- m e. ,n I A i This segment, conducted for cold license group's only, consists of l !
four weeks of plant observation at a NR s milar in sise and 6b i design characteristics to Seabrook. The aef}ee- objective is to j
' familiarise each license candidate with the daily routine involved )
in the operation of a commercial nuclear facility. Other specific l areas of observation will be made in security, radiation protec-tion, maintenance, quality control / assurance, fuel handling, and [ vaste disposal / management. l , 6b i
- d. Detailed Systems Traininz -
F This ten-week course is designed to ensure that license candidates ! acquire the systess knowledge and skills needed to support safe and efficient plant operation. The content and structure of the , course are determined through needs analysis supported by a f ) plant-specific task list. The instruction covers the major i plant systems, including the electrical distribution system. l the primary and secondary systems, and balance of plant systems. Ig((q . The training also covers appropriate th;rory review, integrated systems resE2nse, procedures, and administrative controls.J [ a The training methods include classroom instruction, in-p1' ant ! valk-throught, and simulator demonstrations. Aln-plant activities ! are conducted during the Detailed Systess course to provide : structured plant systems training under the supervision of an ! instructor. Systems tracing is carried on independently by the . license candidates. When requested, instruc tors and operations i personnel help license candidates who are having difficulty i with in-plant assignments. P j
, e .Commes of VC9wt MMec.
en ,5amg/f, wog wer abo +i u mpW
- e. Mitigatinge ore Damere and Transientand[ccidentAnalysis r I
At least three weeks of inst ruction are devoted to mitigating Mc : c es equent.t 5 cy core damage and transient and accident analysis. This training [ consists of classroom instruction, sessions on the simulator. ' and supervised study with prol'len solving. ;
- f. $1mulater Training l
Sesbrook has the distinct adv intage of including a site-specific 4 t
+ ~
staulator as part of the oper ator training program. The simulator was modeled and bu ,1t to duplicate the Seabrook main , control board as well as real time system response. The simula-tor will be certified in accordance with 10CTR$5.45. ( Wrd}<n cieumre,hyna we, ** \V*n O*"
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13.2-4 6"
I l SB 1 2 Amendte The purpose of staulator training is to give each license candi-date practice in applying knowledge and skills to perfora control room tasks during normal and abnormal conditions. Teawvork and diagnostics are stressed throughout the course. Topics covered during the simulator training includet control panels, integrated plant operation, normal procedures reactor startups, abnormal procedures, emergency response proc,edures, and emergency plan,
- g. On-thift partiefpation This course, is designed to give each license candidate an opportunity to observe plant operations and complete work assignments in the control room alongside licensed operators.
The license candidates must perform, observe, or discuss activi-ties and tasks as specified in the Qualification Cuide. In addition, they will carry out any duties assigned by the opera-tors on shif t. The on-shif t participation is at the level of the license being sought. h5N Onash144-pect4+4 t et4 = !; -e : ;;;;; ;;h :=:ee ! : eeH 11:;;n c.sadidatu, -- e : else ::::!*s !=: .;;h; ;.f Op nt:ai; 71 4 4h d Chastatie ?:staing- Fer ha' !!+ene, s. mii J . ; ;; , : :h!h pettitirot e:: 100t: thr^t ""'ha.
- h. Pre-License Evaluation n
- A final pre-license evaluation of each license candidate may be i' W administered by an independent party. This evaluation is usually conduct ed in two parts /, The first will be a vritten exam to determine the candidate's comprehension and retention. The exam
} contents and degree of difficulty parallels that of a current NRC Operator examination or Senior Operator examination, as applic-able. The second portion of the evaluation is an oral walk-through and simulator demonsttation to further evaluate practical knowledge and experience. et 13.2.1.2 Coordination with Pre-operational Tests and Tuel 1,oading h79W oninn
.Jer 1%cessh o.er_y..Te.s4 <m Prograni re: r- has been developed and vill be scheduled to minimize any conflicts testing and fuel loading. in aanpower requirements during the unit's preep:=ti;nL pft-*ferde.*
The positive training effects gained by actual 4 participation in the start-up will be incorporated in the training )togram. 13.2.1.3 Shif t Technical Adviser Treintnr Gryt This course of study, presented by the Trainingf$taff or an outside vendor is - designed to provide the Shif t Superintendent and Unit Shift Supervisor with an added depth of knowledge of engineering principles found in nuclear reactor fundamental applications. Selected courses are based upon an analysis of the Shif t Technical Advisor's qualifications and responsibilities outlined in NUREG-0578. The courses include the following l 13.2-5 ' l' l l l l l l l
. SB1&2 Amendment 62 TSAR g7 WsS Differential Calculus Integral Calculus Advanced Reactor Physics Material Study Course Fracture Mechanics Corrosion Processes Electric Ceneration and Transmission Thermodynantes Heat Transfer T1uld Mechanics When Seabrook Station's STA training is included in a program of study leading to a bachelor's degree, it provides a level of technical course work that satisfies the formal education criteria specified in the NRC Policy Statement on
-) Engineering Expertise on Sh1(ty issued in October 1985.
Individuals completing the STA training receive a Bachelor of Science or Bachelor of Professional Studies degree, including a level of technical training that meets or exceeds the usual requirements for a bachelor's degree in engineering technology. Although this training does not lead to any of the degrees specfied i in the NRC holicy Statement on Engineering Expertise on Shif t (October 1985), it does satisfy the intent of Option 1, Alternative 3 in that policy st at ement. ( Alternative 3 calls for a bachelot's degree in engineering technology f rom an accredited institution, including course work in the physical, anthematical, or engineering sciences.) The NRC staff has reviewed Seabrook Station's STA training and concluded that it is equivalent to that envisioned by the policy statement. 13.2.1.4 1.ieensed Operator Recualiffeation Trainter A comprehensive requalification training program will be conducted for all 4 licensed operators and vill be implemented within three (3) months af ter the initial licensing of operators. This requalification training program has been l n l developed and vill be 1eptemented to maintain a high level of knowledge and skill in licensed reactor operators and senior reactor operators. The basis for this program is to enhance safety, productivity, and ef ficiency in operating i the plant during normal and abnormal situations. I l ' The Licensed Operator Requalifieation Training Program has been prepared, within the 1f ramework of a systems approach to training, to comply with 10CTR55 " Opera-y tors Licenses.* The content and schedule of requalification training are established by the Operations Curriculus Advisory Committee (CAC). The CAC includes, but is not limited to, the Operations Training Manager, the Opstations l Training Supervisor, and a representative of Operations Department management. I A minimum of ten weeks per two-year cycle will be dedicated to the requalifica- W l, tion training program. All licensed %9 huten. instructors will partici- - pate in the program in order to remain cognie nnt of current operating history, o procedural changes, design changes, and admi nistrative policies, except to the L extent that their normal duties preclude the need for specific retraining in V
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13.2-6 l l 1
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particular areas. Each application license w!!! be accompanied by afstatement, or renewal signed of an operator by the W or =senior
% N..noperator
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Nuclear Production, certifying that the applicant has satisf actorily completed the requalification progran during the offective term of his or her current license and that he or she has discharged license responsibilities competently and safely. The requalification training program consists of four interrelated elementst o Requalification Examinations o On-the-Job Training o Pre-Planned Lecture Series o Special Retraining Prograss Specific retraining programs may be necessary for certain licensees. Exam f ailure or unsatisf actory performance will require that the deficient licensee IM M meet with the appropriate academic review board.+ The academic review process d r) is a three-tiered program of progressive corrective actions designed to upgrade
/ knowledge and skills identified as deficient. The three levels in'the academic review process ares
- 1. Staff Counselor Interviews '
- 2. Alert Status Review Board, and
- 3. Performance Review Board.
Any academic review board that is convened will aske recommendatione as it deems t necessary to upgrade deficient areas. The recommendations of the Performance Review Board may include itnmediate removal from licensed duties. The following paragraphs provide a general description of the requalification i programs
- a. Recualiffeation Examinations Each licensee will be administered examinations at the end of each t raining module that will parallel, in content and degree of dif fi-culty, segments of an NRC Licensing Exam. These examinations are designed to meet the requirements of the requalification modules' obj ect i ves. At the completion of each annual cycle, a sufficient number of exams vill have been administered to parallel, in content and degree of dif ficulty, a complete NRC Licensing Exas. All graded exams will be retained as a part of the trainirt records. The results 4 of the exama vill be used to evaluate past training and to aid in determining future retraining. The licensee must achieve an overall grade average of 80% or greater at the completion of each annual cycle. Any licensee with an exam score of less than 70% vill be '
required to meet with the appropriate academic review board.
- 1. Written Examinations i
' A vritten examination will be administered to all Af censed indi-viduals upon the completion of each requalification module. 13.2-7
e . SB1&2 Amendment 6 r, p i
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( V 1 The written examinations will be consistent with the individual's
." license level and will contain appropriate questions from the following topics:
o Theory and Principles of Reactor Operations o Heat Transfer, Fluid Flow and Thermodyantes o Testures of Tacility Design o Ceneral and Specific Plant Operating Characteristics o Plant Instrumentation and Control System o Plant Protection Systems o Engineered Safety Systems l o Radiation Control and Safety o Applicable Portions of Title 10. Code of Tederal Regulations l o Puel Handling and Core Parameters r o o Technital Specifications u4l M A Administrative Procedures, bk /4hlent-and-l.ie Md MMWli atlena l o Nuclear Industry Operating Experience I i
- 2. Operational Examination may ine.Ld e. -
--? operationalexaminatjons cc- 5: :Hhi staulator evaluations.
) oral examinations [Ee in plant walk-throughs. Oral examinations are verbal question and answer sessions between student and 6 1.-
instructor, usually in a one-on-one setting. In plant walk-l
- throughs are oral examinations that take place on-site, generally at the location of the equipment being discussed.
A licensee receiving a module grade of less than 70% will meet with the Alert Status Review Board and carry out the recommenda-tions handed down by the Board. A licensee receiving a module grade of less than 70% acre than once will meet with the Perfora-ance Review Board. The licensee must achieve an overall grade average of 80% or greater at the completion of each annual cycle.
- b. On-the-Job Training In order to maintain an acceptable level of skills and f amiliarity associated with the Seabrook Station systems, controls, and operation-al procedures, each licensee will participate in plant evolutions.
Each licensee will demonstrate operational proficiency through partici-pation in the following activities o Required control manipulations and plant evolutions I o Plant simulator exercises W . o In plant training o Design change, procedure revision, and industry experience review l 13.2-8 . e'
SB &2 Amendsen pM d s6 ) To maintain these skills, itcensed operators will attually manipulate the controls; licensed senior operators may either sanipulate or j actively supervise sanipulation of the controls. The simulator may j also be used for this purpose. If the instructor has documented that [ participation on the simulator is unsatisf actory, the licensee will : seet with the Alert Status Review Board and carry out the recommenda- ; tions handed down by the Board. Each licensee will perform or, in i the case of an SRO, directly supervise the perforsance of the control ! manipulations identifled in 10CFR55.59. The control manipulations ! will be performed, as a minimum, within the intervals stated in the ; regulation. ; Response to abnormal / emergency conditions should include use of ( 1-alternate methods of accomplishing a given function, such as alternate i sethods of core cooling. Exercises involving multiple f ailures may be included. Utt11:stion of applicable plant procedures and Technical Specifications during the training exercises will be maximited. f 1 Individual and team performance during the abnormal /eeergency training exercises will be monitored and a post-exercise critique conducted j with the licensees. In the event that an actual abnormal / emergency condition occurs at 6k , the plant and performance of the licensed personnel coping with the ! l condition is satisf actory (as determined by their Unit Shift Super-l visor), credit for completion of that evolution may be taken. l Completion of actual abnormal / emergency conditions that occur at the ! plant will be documented by the ^:t.Mi-Mi+L, __________. end L l forwarded to the Training Center tc be filed in the licensees' train- ' ing records. 3$ff. SwpvinitMt hr altsyet) In addition to actual control manipulations accomplished while on shif t in the control room, on-the-job training includes . l o Design Change, Procedure Revision and Industry Experience Review i This portion of the program will ensure that completed changes 3 and revisions to plant design, changes to procedures and Techni-cal Specifications and industry experiences are reviewed by each c licensee. Desi h rc rtAlme ed lad 4+r EW*ac bite " r.k Pw=DerdW wew. .r.kecd, ykn eNes EeuwimWd* a (T0f4 ). A pp reveel ~f D6 5 o NnomafTrII!Te#igInYy e Ir b ig Y oIe%u N N iew l Each licensee will review the contents of all abnormal and ) emergency procedures annually. - 1 o . Simulator Exercises This portion of the program will ensure that required control manipulations that are not performed at the plant will be 13.2-9 1
, SR1&2 Amendoe:t jps[/
ySAR h performed during the ters of the operator's license. The simulator portion of the requalifiestion program will emphasise such areas as infrequently accesplished procedures, required responses to abnormal and energency procedures, and significant operating events. l o In-Plant Training l This portion of the progran vill ensure that training which is best suited to be conducted in plant is performed on actual plant equipment. This includes review of major plant modifica-tions, equipment which is provided with local controls, and simulation of selected procedures (e.g., remote safe shutdown).
- c. Desf rn Change. Procedure Revision, and Industry Exterience Review This element provides a system for on-shift review of selected I
operational experiences and changes to existing operating guidance or 2 I equipment. The operational review enables continuous up' dating of on-shift personnel and establishes a means of disseminating new or changing information that has not been posted in the Standing Orders l I Book or the Night Orders Book. This portion of requalification training vill ensure that changes or
-9 revisions to de Technical Specifications, ySARg significant changes 7 to procedures, and completed f acility design changes, are reviewed.
When determined by the W,4hifi- 7tes"-- --"'-" an appropriate i. ' procedure revision or completed f acility design change will be in-cluded in the review process. j vg Lperirdd*WL (* d*siyM, In addition, a continuing systen will be established so that all licensees review the operating experience ,of Seabrook Station and
- "/ F applicable exp@tnces of the nuclear industry. Selected operational
=$- events and reportable occurrences at Seabrook Statfor.?;11 h u,;1y;ed y " and w a retica p :tinent te t' eum --!!::t::. selected operation-OM ry 0 al information from the nGlear industry will also be reviewed. The following sources of inf ormation vill be considered, but not limited tot
- o Licensee Event Reports
- o Audit, evaluation, and inspection reports j l4,,,,,g o NRC IE, Notices and Bulletins l o Publications and periodicals covering nuclear industry I
information I g o INPOSignificantEventkeportsandSignificantOperating Experience Reports , 13.2-10 Rn o( & Ab:M. Yesu Lb (L $C n c he vt I h* h cev> % M M kk ed,No.d.,, h K14wh t'1 #' or ex eg % nme- shat r s iehb ce l roc., ms 9e d 0,441koh h . y r<-g.asg
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SB1&2 Amendae:t TSAR f
- d. Steulator Trainimt 1Y
.ap The Seabrook-specific simulator will be utill ed, whenever practical, to fortify the on-going operator requalification program. Simulator exercises and evolujient will be preplanned and scheduled to f requent-9 ly interf ace with *We formal .jecture series. The simulator Requalifi-cation Training Program will emphasise such areas as infrequently accosplished procedures, required responses to abnormal and energency procedures, and algiticant operating events.
Exercises will include analysing the effects of potential equipment / system salfunctions, possible causes and recommended n?arator responses. l A program objective shall be involvement of Unit Shift Supervisors and Shitt Superintendents in the capacity of operations assessment and accident analysis during ref resher exercise training. I
- e. Retraining Lectures for License Holders A formal classroom lecture series, including exass, will be conducted each year as part of the Requalification Frogram. The level of instruction f or the retraining lectures will be consistent with the i
level of license held. The lecture series will be organized into i separate training modules of instruction divided among the program topics and appropriately scheduled throughout the year. This lecture series will cover two general areast o Fundamentals and Systems Review l o procedures and Administrative Controls l Tundamentals and Systess Review lectures will cover topics in which the standard source asterial is relatively constant; for example, reactor theory, plant design, radiation control, etc. These lectures will include instruction in heat transfer, fluid flow, thermodynamics, andmitigationofgaccidentsinvolvingadegradedcore. ne. wms p ua of Procedures and Administrative Controls lectures will cover topics involving essential plant operational guidelines; for example, techni-cal specifications, administrative procedures, major plant evolutions, etc. All licensed individuals will be required to attend each lecture included in the annual program. Attendance will be recorded and absence vill be made up during the current annual cycle by rescheduling or by utilizing self-study and discussion with knowledgeable personnel. The absentee will be required to pass an exam covering the material presented during the missed lectures.
- f. Performance Evaluation and Review At least I once per year, each licensed operator will be observed and 62-evaluated while responding to either real or simulated abnormal or energency conditions. The evaluation will be performed the individ-ual's supervisor / manager or a member of the Training Staff. l if a tiev nt.e Wdw receives e -[4 ting e)t nale, cL4 win %, rcya.lifes#'W 41 exom -We d
- N es k+Tfil re m edi h g4 re,emmina4 ism is qldadl3.2-IlWividd is Wmediedely runws2. fem li
SB1&2 Amendme:t M
- f. Cd TSAR g$ r An acadesic when any of review board situations the following as described in 13.2.1.3 w!!1 be conducted occurt o A licensed operator receives a modular exam score of less than !
70 percent during the annual cycle, or an anttual overall grade ' average of less thn 80 percent. , o A licensed operator receives a poor performance evaluation. , The purpose of the review will be to determine a course of action , t, necessary to upgrade an i ndi vidual 's performance to an acceptable level. A supplemental training program will be established to up- . grade areas where deficiencies are shown. l' The review vill be conducted as soon as practical af ter one of the above conditions occur. The action taken will be dependent on such i f actors as examination performance, watch standing performance, ob- ! 4 served operational performance and judged overall competence.
- g. _Recualification Training program Records d r. !
-D Requalificat on training program records will be maintained for a -
minimum of Myears f rom the date of the recorded event to document the participation of each licensed operator and senior licensed operator in the program. The records will include copies of written examinations adelnistered, the answers given by the licensee, results [ i of evaluations, and documentation of any additional training in areas
$ in which the 144enets liten St e, had exhibited deficiencies, 13.2.1.5 Activatten of Inactive ti,cgsg program '
i An inactive license is defined as a lic)nse held by an individual who has participated fully in the Seabrook Station Licensed Operator Requalification Prograta but has not actively perforced the functions of an operator or senior operator for a minimum of seven eight-hour shif ts or five twelve-hour shif ts per quarter. : An individual who holds an inactive license and is required to restore the > license to active status will participate in the Activation of Inactive License Program. The program includes a minimum of forty hours of shif t functions in the position to which the licensee will be assigned af ter the program. The ; licensee will stand watch on shif t but will not be the watchstander of record. i y The Operations Training Manager provides a checklist of activities /a,$ asks that must be successin11y completed by the individual who is activating his or her license. Upon completion of these requirements, t se licensee participates in i two separate i n t e rviews , one with a Shif t Superintendent and the other with either the Operations Manager or the Assistant Operations Manager. When the ' interviewers are satisfied that the Itcensee has suf ficient knowledge of the ; ! plant operations to stand watch as a crew member, they sign a Certification of Completion of Training, activating the license. The Operations Training Manager ; also signs the certification form. ,
* ).-
13.2-12 l l
v r SB1&2 Av.endme nt 7f Y
&Jfh TSAR 13.2.1.6 Applicable NRC pocuments l
( ?- The training program vill be conducted in accordance with the applicable requirements of the NRC Code of Tederal Pegulations and meet the intent of the recommendations provided by the applicable Reguletory Guides and applicable NRC reports I!sted belowl 10CTR Part 50,
- Don.estic Licensing of Production and Utilisation Tactitties*
$ 10CTR Part $$, " Operator #sI Licenses
- 10CTR Part 19, " Notices, Instructions and Reports to Workerst Inspection
- 9 4 Regulatory Guide 1.8,
- Personnel Selection and Trair.ing", Revision FR1 September 444-4ee-f eeveu nay, a u r i, with the exception that ANSI /ANS 3.1-1981 vill be use(asthestandardinlieuofANS3.1/ ANSI 18.1-1971, m s' Regulatory Cus)de 1.101,
- Emergency Planning for Nuclear Power Plants".
-> Revision 2. October 1981.
Regulatory Guide 1.149, " Nuclear Power Plant Simulators for Use in Operator
-b Training *, Revision 0, April 1981.
Regulatory Guide 8.2, *Cuide f or Admiriistrative Practices in, Radiation Monitor-3 ing*, Tebruary 1973, RegulatoryrCuide 8.8, "Information Relevant to Insuring that Occupational ! 4 Radiation R.xposures at Nuc. ear Power Stations will be as Low as Reasonably 4
- ) Achievable", Revision 3, June 1978.
Regulatory Guide 8.10. " Operating Philosophy for Maintaining Occupation Raota-tion Exposures as Low as is Reasonably Achievable", Revision 1-R, S ep tembe r
--) 1975,
, Regulatory Guide 8.13 " Instruction Concerning Prenatal Radiation Exposure",
,_7 Revision 1. November 1"87$.
l l
) " Utility Staf fing and Training for Nuclear Power". WASH-1130. Revised June,1973.
' Rex Nem T p " Operator Licensing Examiner Standards", NVREC-1021, 0:::M - m ? Mary 140.
l I (/
"TMI-2 Lessons Lentned Task Terce Status Report and Short-Term Recommendations",
1 NUREC-0$78. July 1979. ANSI /ANS 3.1-1981, "American National Standard f or Selection and Training of . Nuclear Power Plant Personnel." ANSI /ANS 3.$~1985, " Nuclear Power Plant Simulators f or Use in Operator Training." u j 13.2-13 l
SB1&2 pe[l Asend r.sent 2 , TSAR 7g-1
- Nuclear plant Fire protection Tuncticnal Responsibilities. Adminis t ra tive !'
Controls and Quality As s u r a n c e , issued by USNRC letter in August, 1977. NURIC 0737, Novee.ber 1960,
- Clarification of TM) Action plan Requirements *. ,
l 13.2.2. Training for Technical and Manarement Staff i i
- a. Ceneral Discussion A comprehensive training program is in place for t echni cal and h the provisions and intent of NRC i g management Regulatory Guidepersonnel, coeplying 1.6, Revision 4 v(4 vith ANS2/ANS 3.1-1978 used as the standard in lieu of ANS 18.1-1971.
The program vill provide personnel involved with the'nea+vy W4.nf and operation of Seabrook Station training in various disciplines necessary to ensure that eat an safely and ef f ectively perform his assignments. The degree to which an employee is trained will be consistent with his experience, test lists for his position, and regulatory require- l ments. 4,;Q e 4. The overall objectives of the training program aret o To train a staff to operate and maintain the units safely, dependably, and economically, o To prepare technical service groups for their functions neces-sary for the support and saf ety of plant operation.
- b. Responsibilites The responsibilities for implementation of training programs are described in Subsection 13.2.1.b.
13.2.2.1 prortam Description 61 Several basic categories of training help technical personnel to attain a high level of competence and professionalism. Specifically, these categories include the followingt
- a. Initial Orientation All persons joining the Seabrook Station operational organisation, regardless of job assignment. initially v111 receive orientation training. This phase of training consists of a brief informational program explaining site organisation, employee benefits, company' policies and procedures. ,
13.2,-14
~
f.^i o SB 1 & 2 Amendme:t 62 MR h TSAR v [fntas $r y estbri f ret ekr<t s i
- b. Ceneral EPPloyee Training h*)k'd r** 6
***l" ** le f Us $ft* 't* b# bat ,
Ceneral Employee Training is provided to all personnel requiring
-y unescorted access to the prote'ted area. 'It consists of see programs covering site f amiliarisation.esecurity, radiation protection. 3k indust rial saf ety incJuding fire safety, the radiological esergency plan, and quality assurance. The program assumes that a new employee has no familiarity with nuclear power plants. A test is given i f ollovf or the class. AH 6A* repet., w4xeried c6cce31 -to o rmml@ll cid61I'd l necs. n d c m fists t&rg \n rake.Wr. (rHu+ ion Insh4s3 a,. grsLMs4yfs,Lht'$ 6L
- c. NEeNsoryTraining Supervisory training is provided for working foreman, supervisors, senior engineers, managers, and section leaders.
Supervisory indoctrination training includes but is not limited to (1) company organization, (2) purchasing procedures,(3) records f amiliarization. (4) techniques of supervision including hiring and personnel appraisal, (5) technical writing. (6) behavior observation / fitness f or duty, and (7) oral communication, ,g In addition, all supervisors receive a program in problem analysis, decision analysis, and potential problem analysis. AW ean d en;. eneept--ttr non-t tehniaal-af eas--ouciaa6ewti t7 - nd - edehrtettative-pa r t i ci t e t e -11t-pi ent-Syst ***-tt e6ei nt? N 4 ev d* W h eervi+seqb
\n % e.r..<3+=n+ tal krwevloery %t ran) P,.. , (D,5wlp%m . f fd'd
- d. Technical Staff Training The Technical Staff Training Program provides traintnr for the engineers and supervisors employed by New Hampshire Yankee. The program is systematically developed to provide broad-based training f or supervisors, engineers, and technical staff who support the day-to-day operation of the plant. The program is intended to supplement position-specific education and training in order to broaden the knowledge of the plant's technical staff, thus enhancing their
, abilities to perform assigned duties in a manner that promotes safe and reliable plant operations,
- e. Fire Protection Traintnr The fire protection training program for Seabrook Station follows the guidance provided in the NRC document entitled " Nuclear Plant Fire Protection Tunctional Responsibilities, Administrative Controls, and Quality Assurance." A description of that training program follows here.
13.2-15
$516 2 TSAR Ame:dme;t 62 V[
i l a i
- 1. Fire Brirade b l
(a) ins t ruc tion j i Fire Brigade members receive instruction in the topics l below, as well as in any others deemed necessary by the ; ins t ruct ors. l (1) Fire hazards and associated types of fires that ; could occur in the station, and the location of the ; hasards, including areas where breathing apparatus l 1s required, regardless of the size of the fire. l ' (2) The location of installed and portable fire fighting ! equipment in each area, and familiarisation with ! layout of the station including access and egress . routes to each area. I i (3) Use of available equipment, and a recommended method i of fighting different types of fires. The types of , fires covered vill include electrical fires, fires ! in cables and cable tray, hydrogen fires, flammable ! liquids, vaste/ debris fires, record file fires, l 7 hasardous process chemical firespand fires resulting t i from construction or modification work. 1 (4) Indoctrination in the station fire fighting plan, ' with coverage of each individuals's responsibilities. : including changes thereto. i ($) Use of breathing equipment, communication lighting ' i and portable ventilation equipment.
\
(6) A deta!!ed review of fire fighting strategies with ' particular emphasis on what equipment might be used in particular areas. (7) A review of latest modifications, additions or changes to the facility, fire fighting equipment, fire I fighting plan, or fire fighting strategies. (8) Fighting fires inside buildings, tunnels, and other ! confined spaces. (9) Fighting fires when a radiological hazard exists. ! (10) The toxic and corrosive characteristics of expected ! products of combustion. 6 Fire Brigade leaders vill receive the above listed instruc-tions and special instruction in directing and coordinating ! fire fighting activities. i 13.2-16 1 i
$31 & 2 Ame:dme;t rsa O'6N
,}&66(
(b) p _ractice In addition to the classroom instruction above. all fire brigade members will attend regularly scheduled (at least annual) practice sessions on the proper method of fighting various types of fires. These sessions will provide brigade sembers with hands-on experience on extinguishing actual fires using the equipment available to them in the station. Practice sessions will also be held which require fire brigade members to don protective equipment. including emergency breathing apparatus. (c) Drills Brigads members will practice as a team in periodic drills. These dr!!!s will include the following (1) Simulated use of equipment for the various situations and types of fires which could reasonably occur in each safety-related area. (2) Conformance, where possible, to the established station fire fighting plans. (3) Operating fire fighting equipment, where practical. This includes self-contained breathing apparatns, communication equipment and portable and/or installed ventilation equipment. The drills will occur at regular intervals, but not to exceed quarterly for each fire brigade.- The minimum number of fire brigade drills conducted within a quarter will equal the number of operating shif ts at the station. Each individual member of the fire brigade will participate in at least two drills per year. At least one drill per year for each fire brigade will be unannounced. At least one drill per year per brigade will be on a backshift. ; Pre-ptpag Periodies11y (at least annually) L a drill will involve of f-
@ site fire d epart ment s. M:;hn.h;; will establish the training objectives of the drills. A critique will determine how well the training objectives have been met.
At a minimum, the critique will assess i (1) Fire alarm ef fectiveness, response timo, selection, , placement and use of equipment. (2) The leader's direction of the of fort and each member's response. 13.2-17 l l l t
. . . SB1&2 Ame:dsent 62 p'?
FSAR
- 2. Other Station reployees f N
All f ull-time esployees will receive instruction on fire protec- : g- tion safety, evacuation routes.pthe procedures for reporting a ftre. g 6 1.- I Security personnel vill receive instruction on procedures for entry of off-site fire departments, crowd control, and procedures for reporting potential fire hasards observed when touring the : facility. i I Temporary employees and construction personnel vill receive the ( instruction in reporting fires, alare response, and evacuation i 1 routes as part of general employee training. {- n
- 3. Fire Protection Staff !
Training for the fire brigade and personnel responp4b,le for q issuing ! Source { andFire Protection Permits v G11 include ;
-7 courses in(nition the design operation of fire detection, suppres- '
sion and extinguishing systems, and fire preventio i techniques and procedures. ;
- 4. Off-Site Fire Department The training for the Town tsf Seabrook Tire Department will i
*nclude information on basic radiation principles and practices, and typical radiation hazards that may be encountered when ;
fighting fires. i
- 5. Refresher Training !
The fire protection ref resher training program for fire brigade > members and for off-site fire departments will be conducted on >
--9 a two-year cycle. Ref resher instruction vill be provided to all !
fire brigade seabers on a quarterly schedule and will include a ! review of any changes in the fire protection program. Other ! station employees receive annual refresher training. i
- f. TrainingforMitigatibetheConsequencesofCoreDamage Special training for mitigating the consequences of core damage is in '
place for applicable technical, annagement, and supervisory personnel. > Instruction for this progran reflects INP0 guidelines for subj ect l p g, ; arterial. ' 13.2-18 t
. . . $8 1 & 2 Anendeent
, yggy, pfp>
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13.2.2.2 Coordination with Pre-Operatiens) Tests and Fue) 1.ca di nt
' The training fcr technicsj and management employees is er$eduledte ministre any
-P conflicts in manpower requirements during the unit 's 544:;:r;;;,.. ; testing and fuel Joading. The positive training ef fects gained by acto'si participation in these phases of the startup will be incorporated in the training program.
.9 14a,t + v r v i 33.242.3 Training Department Staff prs .cqsf*E5** ** I I g, p,,
Toes Maryf/ and several t echnical last ructors.The TM b. training
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- ! n!- , : ;::"!!!: . ^" r:- ;---- ll. L. L 6 n :i;;;' :;.;; 0,,, ; _
- 1!-: i in one or niore :echnica) ( 'eJds. 4r ch training instructor has significant experience [ g g
;, n , _ L;_ , 7 __ ,; M-p't ^t f:d ::i U,.,nc, The staf fing Jevels of the Training De,partment are based on a periodic evaluation of station training requirements.
23.2.2.4 Department Trainint Prerrans in addition to the training described in 13.2.2.2, the programs described below will train the individuals who coeprise the initial staffs of various station departments. { I i
- a. General Technical Training
-)
I
+'
Instrument and control, chemist ry%and health physics t e chni ci ans , ent maintenance techanicsp and electricians receive :- !9:::In;; ten i 4 pr:4r:: fell: :d by nuclear power plant fundamentals, radiation worker training, and site tagging instruction, if n. m r. Pretests may s5 h k.coh2hn i
*+*P4 any employee f rom portions of this training. AFurther training l 6
bg;g3 44 is s'ecific p to the departtent as described below. W
- 1. health Physics personnel receive a progran en h;;1th t hyH +e 44 ) O 4 O ;.ael; :nd a pe; :: :
h::!!'- 2::d:: 7::::2 ..., AThese g programs are based on a site-specific task list. '
- 2. Chemistry technician training course contents and duration are }nSUf based on a site-specific task list. The :eut u s--ere d! eihd l
Sate 'eur fu-d :-t:1 : uu ht
.fc u. mord semas I
- ic ew hcriannel atr awMa.i reede. ceungs in t a rau/ cmat Al cMdy, {
p*e~w m.al ar,u!yges, e " l
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+ eim 13.2-19 1
SB1&2
. ,. TsAn Amendme nt 62 [
99,ai>n 7% d 3 5 o m a;-eystese d:d e;i, a d :!; G e; wuiiel snad4e:? ::totsy .ad1.J ::M:t n! -!;n: Chemistry technicians are also trained on some specific analyses through OJT modules which are also based on job task lists. Tin-ally, the t echnician's qualification to perf orm chemical analyses f or plant systems is reviewed by chesistry department personnel, and signed off individually on the technician's Qualification ! Card.
- 3. *b Instrument and control technicians receive training in process instrumentation and controls. Selected technicians, based on a site-specific task list, are trained on selected plant protection I
and control systems including the solid state protection system, the 7300 process system, the nuclear instrumentation system, the red controJ system and the rod position indication system. Also, based on a site-specific task list, selected technicians 1 are trained on additional plant systems including the radiation monitoring system, the main turbine ele ct rohydrauli c control l 4 systes and sole ted ulant fl id and eleptrical systems. I nd Im MNMI Mechanic receiv training in hand tools, basic% I 4 mechanical natntenan e, and mechanical saintenance of site equipment, based i
- on a site-specific position task list. Training in such a as as bolting, snubbers, velding, non-destructive examination, crane j
" Tral] o%
- operationetadvanced vibration and hydraulic wrenches is available
, for those who perform work requiring such training. 4 S. Electricians receive training in hand tools, basic electrical maintenance, and applied electrical maintenance of site equipment as determined by a site-specific task list. '
- 6. Auxiliary operators receive twenty to forty weeks of initial l training. The length of the training depends on the entry-level 4 skills and knowledge of the trainees. The training consists of classroom instruction on the primary and secondary plant systems and structured on-the-job training perf ormed under the super-vision of a qualified watchstander.
Activities included in the on-the-job training are systems walk-throughs, performance of shift duties, equipment and systems operations using plant operating procedures, and implementing surveillance inspections and checks on operating equipment. Tollowing the initial training and assignment to regular shif t - duties, the auxiliary operators return to training on a rotation plan to receive continuing instruction on plant equipment and systems. 13.2-20
o $81& 2 Amendment 62
$h 1 -1 13.2.2.5 Position Task Ansivses g Sp+ Ser.M Gbep F Initial training utilizes descriptions o f jobs and tasks ar, provided by each department. The with input from the station technical departner.ts, developed site specifit-task lists based upon the INPO generic task 11 stag new job activities vill be identified in later revisions of these task lists. Training progress are modified based on these task lists.
13.2.2.6 Premras Evaluation 8b Testing accompanies most orientation and all skills training. Tests include proficiency exams and written exams. Training ptoredures provide for the regular evaluation of programs to ensure training effectiveness. t 13.2.2.7 Retraining "k Technical personnel vill receive retraining in the following subjects:
- Appropriate Administrative f rocedures Radiation Protection i Security Procedures j Radiological Energency Plan Tire Safety Safe Work Procedures l
Skills Training as-RegtriTra (to reVU'M l This ref resher training vill be scheduled on a periodic basis following receipt of an operating license. Also. periodic drills will reinforce procedures to be 6v followed in the event of radiological or fire emergencies. 13.2.2.8 Replacement Training Training to fill vacancies in the supervisory, technical. and maintenance staf f s asrures a sufficient reserve of qualified individuals. This training will be essentially equivalent to the program described in 13.2.2.1g ard 01.1 A . 13.2.2.9 Emergency Plan Trainint All persons assigned to the emergency response team vill receive training to perf orm the functions of their position. They will also participate in periodic , drills to ensure that they have maintained the ability to pgrform their tasks effectively. A w q rtu miu % Li#le icAl Eqm Ph $r unbot Sh 6 Fwi4 ca ( s ywa e. va6% in chem IL2 of A Se d "o*C. 84 A N h la p J E em. g..~g Pl n . 13.2.21
$81 & 2 Amendment $2 r$AR December 19'4)q 1
-cf W,(.CO ?
Tall.E 13.P-1 ' ' ($heet I c., 2) L Corparison of WUREC 0737 ' APPENDIX C t TO SEABROOK STATION OPERATOR LICENSE PROCRAM r i CUMULATIVE f CONTACT HOURS [ APP C RO USS ; SUCCESTED SCR0 SS i Prerequisite Beyond High School , Mathematics 90 45 45 ?
; Chemistry 30 45 45 Physics }
150 165 165 ; College Level Fundamentals r Mathematics 90 . 120 i Reac tor Theory 100 90 135 Reactor Chemistry 30 4$ t Nuclear Materials 40 90 Thermal Sciences l 120 i l Thermodynamics 90 ! Fluids . 45 Heat Transfer 45 Eleeerical seienees 60 45 I Nuclear Instrumentation & Control 40 45 45 L ! Nuclear Radiation Protection & Health Physics ! 40 45 45 i ! Applied Fundamentals 460 350 $30 Plant Specifics 120 Plant Systems 200 Administrative Controls 80 f l i i operating Procedures 30 ' Transient / Accident Analysis & ' Emergency Procedures 30 ! ! Ma nagement / Supervisory 40 215 } simulator Training 100 280 '280* ; i 45 52 : I l r I l I
SB1&2 Amendme:.t & FSAR June 1 1 4 0 '99 ( TABLE 13. N (Sheet 2 c:' 2)
* - Minimum of 100 hours in the position of a supervisor directing activities.
RO - Reactor Operator SCR0 - Supervisory Control Room Operator USS - Unit Shift Supervisor
$$ - Shift Superintendent 46 a
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5E xs - c m a s OPERATOR PUBLIC SERVICE COMPANY OF NEW HAMPSHIRE LICENSE TRAINING PROGRAM SEABROOK ST ATION - UNITS 1 & 2 COORDINATION WITH PRE-OPERATIONAL TEST AND FUEL LOADING FINAL SAFETY ANALYSIS REPORT FIGURE 13.2-1
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c to MO JTHS PRIOR TO FUEL LOAD Ob h,hg 60 58 5G 54 52 50 48 46 44 42 40 38 36 34 32 38 28 26 24 22 20 18 16 14 12 10 8 6 4 2M
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,pt PSAR Amendment 62 3k i 36 '
insert #1 The Specialty Training Manager is responsible for chemistry, health physics, and emergoney plan training. I insert #2 A program for effectiveness monitoring is established for all areas of license training. Program reviews and evaluations will be conducted as directed by the Curriculum Advisory Committee (CAC) and/or the Operations Training Manager. Such evaluations should include consideration of e inspection, audit and evaluation reports submitted by students, facility personnel, or independent organizations; e course examination results; e on-the-job training records; e plant operational problems identified by Licensee Event Reports (LERs), industry bulletins, Operational Engineering Section reports, and safety documentation. Training program deficiencies identified through evaluation or review will be brought to the attention of the Training Supervisor as soon as practical for disposition and/or presentation to the CAC. Recommendations for corrective action may be submitted to the CAC by the Operations Training Manager or other management representatives. l
.. . g AD-#F7 f; insert #3 This is an eight to twelve week program presented by the Training Group Staff or an outside vendor. The Nuclear Reactor Fundamentals Course provides license candidates with ; the scientific and engineering background knowledge required ' for the control room tasks that are selected for training. To a lesser degree, the course also addresses identified needs for skills training. This courso consists of , radiation considerations, reactor theory, large PWR core physics, thermodynamics, power plant chemistry, material considerations, applied electrical technology, and instrumentation and control. , The training methods include classroom instruction, in-plant walk-throughs, laboratory exercises, and simulator demonstrations. insert #4 Each license candidate will receive one week of instruction at a pool reactor facility. Subsequent to full power , licensing, all candidates will receive.this instruction at Seabrook Station. The course consists of experiments which are preceded by a brief classroom session (approximately one hour) and followed by classroom session (approximately one hour) to reinforce the day's activities. Typical subjects to be taught includes coefficients, suberitical multiplication, rod worth, and other related topics. Each student will learn through " hands-on" experience and discussion of experiments. In all cases, each student will perform ten reactivity manipulations, insert #5 (insert deleted) ' insert #6 Candidates submitting applications prior to the issuance of a full power license will be considered cold ljcense candidates. On-shift participation is a seven-week course for cold license candidates, who also receive four weeks of Operating Plant Observation Training. For hot license candidates, on-shift participation lasts thirteen weeks. Subsequent to full power license, all new applicants will be considered hot license candidates.
e' 7ce, 9 o-ort c insert #7 / If a license holder receives a failing grade on any annual exam, the individual is immediately removed from licensed duties until remediation and reexamination is completed. insert 48
...and other plants will be analyzed by using Program Team Leaders (or designees). The Program Team Leader (or designee) will provide pertinent information to be included in the plant update of each phase, insert 49 (insert deleted) i insert #10 On-the-job training is subject to Training Group training procedures. Those individuale qualified to perform specific '
tasks and trained to conduct on-the-job training for these
- tasks are selected by the Department Supervisor to serve as OJT instructors / evaluators.
1 insert #11
... including on-the-job training, systems, health physics practices, procedures, and equipment.
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