ML20008D736
| ML20008D736 | |
| Person / Time | |
|---|---|
| Issue date: | 01/21/1980 |
| From: | Kammerer C NRC OFFICE OF CONGRESSIONAL AFFAIRS (OCA) |
| To: | Glenn J SENATE, GOVERNMENTAL AFFAIRS |
| References | |
| FOIA-81-131 NUDOCS 8004240414 | |
| Download: ML20008D736 (29) | |
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The Honorable John Glenn Chainnan _
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Subconnittee on Energy, Nuclear Proliferation and Federal Services Connittee on Governmental Affairs United States S*nate Washington, D.C. 20510
Dear Mr. Chairman:
In your letter to Chairman Hendrie dated May 30,1979,eyou stated that there is some opinion that reactor operator training is better in the United Kingdom and West Germany than in the United States and asked several questions concerning operator training in these countries.
I am enclosing for the information of the Suben:mtittee the staff's responses to these questions as well as the attached infonr.ation obtained from the United Kingdom and the Federal Republic of Gemany.
Sincerely, Ca*lton Kamerer, Director Office of Congressional Affairs
Enclosure:
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7 OUESTION.
There is some opinion that reactor operator training is better in the United Kingdom and in West Germany than in the United States, i
How do regulatory requirements for training co= par,e? To what
- extent are foreign operators drilled in emergency situations l
rather than routine operations?. How do.the professional quhliff-cations of their and our opepators compare?
Should operator.
training require engineering background pather than only high-?.._
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school diploma?
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Comparison of the United States practice with info'mation provided by the gover
.ments of the United Kingdom and West Gemany shows a general similarity in the k^
degrees of w,.,etency required for reactor operators and supervisors, but cone siderable difference in government roles and requirements related to achieving such competency.
Comparisons based on each of the first three questions contained in this inquiry as well as appraisal of United States educational requirements requested in question 4, are outlined below. More detailed material provided by each foreign e.,untry and a description of United States programs are attached.
OUESTION How do regulatory requirements for training compar,e?
j ANSWER 1
l Initial trainino programs for the three countries are similar in scope [ but, vary sligntly in :1me allotted to particular subjects.
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In the United States and West Gemany, shift supervisors and control rocm operators
, are examined by covernment officials and issued licenses by government agencies.
In the United Kingdom, the utilities administer examinations to the senior shift staff.and day management staff.(equivalent to our supervisors).
The utility then forwarcs the details on an individual's training, his technical qualifications and previous e=ployment to the Health and Safety Executive (the regulatory body con-i cerned).
Based on its review of this information, the HSE then may register the individual.as a " Duly Authorized Person".
Neither the United Kingdom nor West l
Germany have specific. regulatory requirements for reactor operator training.
They do, however, provide guida: ice regarding sub.kets to be taught. The NRC provides similar guidance but, in addition, must yprove the content and scope of j
the training programs, including approval of the simulators used in the programs.
l The NRC also audits the administration of the programs and conducts some exami-nrtions.
I With regard to retrainine, the United Kingdom and West Gem.any report they do not have retraining requ1rements, per se, however, both say that the utilities conduct informal retraining programs.
In the United States NRC regulations require licensed individuals to be requalified annually.
The. requirements specify l
the licensees must take written or oral examinations; attend certain lectures; i
review plant desicns and license changes as well as normal and emergency pro-cedures, ar.d manipulate controls through a specified nu-ber (usually 10) of sienifica.. reactivity changes.
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QUESTION To what extent,are foreign operators drilled in emergency situations rather than routine operation,s?
AMSWER
~Betweso' thirty and thirty-five percent of the training programs in the United States are devoted to study of abnormal and. emergency situations.
In West German programs, about twenty percent is devoted to these situations. The United Kingdom was not able to provide a breakdown of time devoted to study i
of abnormal and emergency situations.
OUESTION How do the professional qualifications of their and our operators compar,e?
ij' AUSWER Ja/$hh united. Kingdom, operators are required to have "several years of experience tin an appropriate position in an operating nuclear. power station."
Supervisory i
are " qualified to university personnel (assistant shift charge enoineer and above)ineering or scientific organ 1-degree' standard" or ~by membership in~ professional eng zations.
The West. Germans did not report any minimum education or minimum experience l
requirements, however, they do indicate that skilled workers, technicians. and 2
craftsman normally are required to have three years of experience in their craft to qualify or entrance into a training program.
i The CRC requires operators and senior operators to have high school education-or j
equivaient, plus two years of power plant experience for an operator rating and four years of power plant experience for a senior operator.
OdESTION Should operator training require engineering background rather j
than only high schoold diploma?
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ANSWER.
I The American Nuclear Society Standards Subcommittee ANS-3 is reviewing and re-commending changes to the ANSI /ANS Standards for which they are responsible.
One of the standards ANSI /ANS 3.1-1978, addresses the selection and training cf nuclear power plant' personnel, and a significant area cf review will be the edu:ation'.
i re;uirements for operators and senior operators.
It is pointed out that individuals presently operating nuclear power plants, because of their participation in the training procrams, have an education which goes far beyond a high schoci education, and the NRC feels that the extensive evaluatiens of operator competence which are i
a :cr.clished by f acility management curing training and' by URC examiners af ter - -
. raining are =:re significant than the formal education requirements fer selection To obtain a " third-party" view, however, the NRC is now ir. the into trainin:.
rocess ci selecting an outsice' consulting agency o examine the whole field of It is expe:ted that a contract for such a study will be let
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U. 5. C'omercial Power Reactor Training Programs Reviewed by the NRC
- p The following outlines the training program as set forth -in the NRC Regulatory L:1 Guid' 1.8, " Personnel Selection and Training" that endorses, in part, ANSI - '
e N18.1-1571, " Selection and Training of Nuclear Power Plant Personnel.".
'In accordance with 10 CFR Part 55,.the NRC issues two types of licenses.
In
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, general, anyone who manipialates reactor controls must be licensed as an operator, t
and those who direct the activities of licensed operators must be licensed as senior operator.r'- In pract' ice, the control room operators at a power station will be the licensed operators and their imediate supervisor will normally be the senior cperator.
l Cold Training Programs I
i Cold trahin; programs provide the necessary training for personnel who will sit for the NRC license examination prior to the initial f0el l' ading of the e
r.uclear plant.
Since it is impossible to perform plant operations at that time, these. examinations are referred to as cold ext =inations.
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Applicants for reactor operator and senior Ora c:. licenses hired by the ukility come from (1) convent.ional plants throughout the utility, (2) government-operated nuclear reactors, and (3) new hires.. A few power: plant applicants have come from research and test reactors at various universities.
However, the majority have come from the first group.
Over one,-half of the operators have little, if any, nuclear experience at the time they are selected for training.
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Many utilities employ a preselection screening process using tests designed to t
determine' an individt.al's suitability for nuclear training.
Because many of those selected for training have been'out of school for a number of years,
-seme companies have found it advantageous to first conduct a review of basic
!Gjlatics and physics for the candidate.
Generally these reviews last 4 weeks.
' Training programs, together with the training schedule prior to fuel loading, are. submitted tb the NiC for approval.
Usually the training program for applicants with no previous nuclear experience starts 2 years before fuel loading.
l Applicants who have previous nuclear experier.ce are phased in at the proper times in accordance with their experience.
Applicants with no previous experience are required to complete the entire training program outlined below.
The programs outlined below are minimal programs.
Applicants must be highly motivated and dedicated to successfully. complete these programs.
Many applict.nts will require additional tutoring.and time to become competent operators.
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Basic C:urses,
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i Basic courses,
- ch normally last 12 weM.s, are usually presented at nuclear trainingcenhrsoruniversities.
The courses include approxirately 10 weeks of basic study, which includes nuclear physics, health physics, chemistry, and plant technology.
The study program is followed by 2 weeks of practical cparationai training on a nucinar training or research reactor, where the cpplicants participate in fuel-lading experiments and coefficierit measurement
" experiments, perform reactivity calculations, ind manipulate the crintrols during 10 reactor startups.
Pha d :
Observation and Simulator Training
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4 Observation training involves the day-to-day operation of a nuclear power plant.
This training is conducted in conjunction with the plant operating organi:atien.
During the observation training, the trainee observes various i
l operations, surveillance testir.,
and the practical aspects of the radiation i
protection program.
All training must be documented and must be supervised by knowledgeable individuals.
The training period varies from 1 to 3 months.
In conjunction with the plant observation, the trainee receives training on a power plant simulator.
Simulater training varies from 2 to 3 n.onths.
While at the simulator training center, the applicant observes and participates in all phases of power plant operations (e.g., reactor and plant startups, loading t'.e turbine generator, and power-les :1 changes) and learns to ure normal procedures and other procedures to ;cpe with abnormal and emergency conditions.
The si=ulator must ce simi a-tc the f acility for which the trainee will seek a license.
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The observation and s'imuister training must be under the administration of the
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sa.me organization.
The minimum time required for Phase II is 4 months of combined power plant observation and simulator training.
Phase Design Lecture Series This phase of the training consists of a 'ecture series to familiarize the traine't with the design features of his plant.
This phase normally takes S weeks'.
Lectures c.an be devoted completely to the individual's plant ano can 9
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be given after Phase II, or some of the lectures can be given prior to Phase II and some of them after Phase II.
When the course is split in this uanner, the l
Minee vill be taught the general design characteristics during the first i
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session and his plant's special characteristics during the second session.
Phase IV:
On-Site Testing l
The applicant for a cold examination cust successfully complete an approved on-site training program that covers informati";n on the plant for which he will seek a license.
In addition to classroom training, the applicant will engage ir. the day-to-day plant activities, such as procedure writing, const,ructica check-out, and preoperational testing, for a period of approximm
.y 1 year prior to fuel loading.
The ti.y.e spent in this phase varies accc.-ding to the experience of the applicant; however, the minimum require:.ime is 5 months.
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q HOT TRAINING PROGRAM 5' Hot training programs provide the necessary training for applicants who will RC license examinatien following criticality of the reactor.
sit for the Training or hot licensing begins by selecting candidates from among plant auxiliary operators who normally have had 1.5 to 2 years of opera. ting experien.:e at that facility and p'tacing them in a formal training program.
Appl: cants for hot examinations must complete the same technical training that is required for applicants for cold examinations.
Applicants will also
%icipate.in a program of on-the-job training which involves manipulations of controls during five reactivity changes and at least two training startups cf the reactor.
Their training usually includes self-stucy programs and tutoring by more experienced personnel on plant operating characteristics, plant syster. performance characteristics, and the use of normal, abnormal, and emergency cperating procedures.
An appropriate nuclear power plant simulator 4
can be used in the training in lieu of two training startups on the reactor.
The first gro::p of hot license applicants must participate in reactor and f
plant. operations during the commissioning phase of the facility until the facility has, been operated at a power level of at least 20% prior to taking the examination.
This is done to give t.be applicants actual hands-on experience ir, operating the reactor and to give the NRC e.ssurance that they have participated in integrated plant operations.
The training program folicws the material outlined under the cold licensing program u.nd covers a period of 5 :c 5 months.
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LICENSE EXAMM ATIONS *
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j Title 10 CFR Part 55.11 states that."an application for a license pursuant to the regulations in this part will be approved if the Commission finds that,"
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among other things, "the applicant has passed a written examination and
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operating test as nay be prescribed by the Commission to determine that he has learned to operate and, in the case lof a ranior operator, to operat:- and to t
direct the lice.nsed activities of licensed operators in a competent and safe manner." The scope of the examinations is addressed in Sections 55.20 through 55.23.
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t Written Examinations The written examinations for reactor operators (Section 55.21) consists of.
seven categories and generally requires 6 to 8 hr to co=plete.
Most of the i
questions require essay-type answers.
The sever. categories in the operator
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examination are:
A.
Principles of Reactor Operation.
3.
Features of Facility Design.
C.
General Operating Characteristics.
D.
Instrumentation and Controls.
E.
Safety and Emergency Systems.
F.
Standard and Emergency Operating Procedures.
G.
P.adiation Control and Safety.
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The written examination for senior reactor operators (Section 55.22) consists
.of the same seven categories acove plus an additional five.
Approximately 4 to 6 hr are required to complete tne five senior categories, which are:
H.
Reactor Theory.
I.
Eadioactive Materials Handling,. Disposal, and Hazards.
J.
Specific Operating Characteristics.
K.
Fuel. Handling and Core Parameters.
L. ' Administrative Proceduras, Controls,' and Limitat. ions.
Ce rating Tests
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s The purpose of the operating test (Se: tion 55.23) is to determine the following for each applicant:
A.
/bility to ; ead and interpret the control instri.=nentation of the facility.
5.
Ability to manipulate the control equipment in a safe and competent canner.
C.
Kno ledge of how to operate the facility, including operating under
- e. ergency conditions.
C.
Knowledge of radiological safety practices and the purpose and function. of radiation monitoring equipment.
A typicai perating test takes from 4 to 5 hr and proceeds as follows.
In the
.priva:y of an office or conference room, the examiner explores the applicant's kno le:ge :f reactivity effects, theory of operation, and radiation protection
- ra:t::es and pro:edures.
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The major portion of the operating test is conducted in the control room. The applicant's ability to read and interpret the control instrumentation is determined by discussing both normal and off-normal operation.
The applicant points out on the operating board the controls used and explains the instrumentation involved in accordance with the facili,ty procedures.
If the applicant was previously certified on reactor startup on an approved simulater, actual startup of the reactor is waived.
At a minimum the examiner
- ' will have the applicant talk through the starthp, indicating controls and instrumentation used in taking the reactor to criticality.
The examiner determines the applicar.t's knowledge of suberitical multiplication and d'e ayed-neutron effects, his understanding of when the reactor is suberitical or. supercritical, and his knowledge of the effects of coefficients on the startup of the reactor.
The applicant's ability to operate equipment in a safe manner is determined by discussing such operating situttions as load changes, ecuipment operation, and eff-ncrmal operation.
The applicant must demonstrate his knowledge of the actions to take and indicate to the examiner the controls he wil'1 manipulate and the instrumentation he will observe.
The exaniner also determines the applicant's knowledge of.how to operate the facility under emergency conditions.
This is accomplished by postulating symptoms of an incident to the applicant.
. rom the sy=ptoms the applicant must determine the immediate a:tions required by procedure.
He must cemenstrate a knowledge of the emergency systems anc be able to evaluate instrument readings to know that the emergency systems are operating in the
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manner in which they w'ere designed to operate.
He must also demonstrate what
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actions he would take if any part of the system fails to operate properly by mock manipulation of the controls.
j The procer use of normal, abnormal, and emergency procedures and evaluated throughout the control room. exercise.
The applicant's knowledge and' understanding of the Technical Specifications, administrative procedures, emergency plan,. operating curves, and data are explored.
4 The final phase of the operating test is touring the plant with the applicant.
Here the applicant's knowledge of the radiological practices and monitoring e
ipment is evaluated.
The applicant must demonstrate the use of portable radiation monitoring instruments, how to proper'iy enter and exit a controlled area, and how to use the facility radiation procedures.
During the plant tour '
the applicant must review local procedures and demonstrate his knowledge and understanding of local plant operations.
Typical systems explored include electrical control centers, diesel generators, engineered safety feature, plant instrument air systems, and selected operating equipment.
Examination Evaluation After the examination the applicant's knowledge and understanding are evaluated by the examiner and reviewed by group leaders and/or the Chief of the Operating License Branch.
On the basis of the results of the evaluations and review, the applicant receives a license or his application is denied.
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If an individual has his senior operation application denied, an evaluation is made to determine if he should be licensadas an operator.
If he p"assed the operator's written examination and demonstrated sufficient knowledge and understanding at an operator level during the operating test, he is issued an operator's license.
4 Raoualification Program Periodic requalification for all operators and' senior operators is necessary to maintain their continued competence.
The following is an outline of the NRC requalification requirements, i
1.
Schedule.
The requalification program shall be conducted for a continuous period not to exceed two years, and upon conclusion shall be promptly followed, pursuant to a continuous schedule, by successive 1
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requalification programs.
2.
Lectures.
The requalification program shall include preplanned lectures on a regular and continuing basis throughout the license period in those e
areas where annual operator and senior operator written examinations
. indicate that emphasis in scope and depth of coverage is needed in the following subjects:
1 a.
Theory and prin:iples of operation.
b.
General and spe:ific plant operating chara:teris.ics.
c.
Plant instrumer.:ation and control systems.
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d.
Plant protection syste:ns.
e.
Engineered safety systems.
- f. - Noma 1, abnormal, and emergency operating procedures.
g.
Radiation control and safety.
h.
Technical specifications.
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Applicable portions of Tiule 10, Chapter I Code of Federal Regulations.
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dth'er training techniques including filmsi videotzpes and other effective training aids may also be used.
Individual study on the part of each operator shall be encouraged.
However, a requalification program based solely upon the use of films, 4
videotapes and/or individual study is not an acceptable substitute for a lecture series.
3.
On-the-job training.
The requalification program shall include on-the-job training so that:
a.
Each licensed operator of a production or utili:tation facili,ty manipulates the plant controls and each licensed senior operator e
ei'her manipulates the controls or directs the activities of individuals during plant control canipulations during the tem of their licenses.
For reactor operators and senior operators, these manipulations shall consist of at least 10 reactivity control manipulations in any combination of. reactor startups, reactor shu-downs or other control manipulations which demonstrate skill
.and/or familiarity with reactivity con.rol systems.
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Each licensed operator and senior operator has demonstrated b.
satisfactory, understanding of the operation of all apparatus and n.
?i mechanism; and knows the operating procedures in each area for which he is licensed.
i Each licensed operator and senior operator is cognizant of facility
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i design changes, procedure changes, and facility license changes.
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Each licensed operator and senior op'erator reviews the contents of.
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all abnormal and emergency procedures on a regularly scheduled N/
basis.
A simulator may be used in meeting the requirements of paragraphs 3a e.
and 3b if the simular reproduces the general operating characteristics of the facility involved, and the arrangement of the instrumentation and controls of the simulator is similar to that of the facility involved.
The requalification program shall include:
4.
Evaluation.
Annual written examinations which determine areas in which
.a.
retraining is needed to upgrade licensed operator and senior operator knowledge, 4
and senior
' Written examinations which determine licensed operators' b.
operators' knowledge of subjects covered in the requalification program and provide a basis for evaluating their knowledge of atnormal and emergency procedures.
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c.
Systematic o'bservation and evaluation of the performance and ccepetency of licensed operators and senior operators by' supervisors
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and/or traihing staff members including evaluation of actions taken or to be taken during actual or simulated abnormal and emergency conditions.
d.
Simulation of emergency or abnormal conditions that may be accomplished by using the control panel of the facility involved or by using a simulator.
Where the control panel of the facility is used for simulation, the actions taken or to be taken for the i
emergency or abnormal condition shall be discussed; actual 4
manipulation of the plant controls is not required.
If a simulator is used in meeting the requirements of paragraph 4c, the simulator shall accurately reproduce the operating characteristics of.the facility involved and the arrangement of the instrumentation and controls of the simulator shall closely parallel that of the j
facility involved.
l e.
Provisions for each licensed operator and senior operator to i
participate in an accelerated requalification program where I
performance evaluations conducted pursuant to paragraphs 4a through i
4d clearly indicate the need.
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Enclecure 2
. Training Progra.ms of the UK and FRG HRC asked appropriate nuclear agencies of the United Kingdom and the Federal Republic of Gemany to provide training infomation in response to eight specific questions. The bodies of the replies from each country are attached. The eight questions are as follows:
1.
PLEASE PROVIDE US WITH A BRIEF DESCRIPTION 20F THE TRAINING PR0 GRAMS AND -
LICENSING OF HUCLEAR POWER PLANT OPERATORS.
3 2.
SPECIFICALLY, WHAT POSITIONS ARE SUBJECT TO LICENSING, EITHER FEDERAL OR STATE 7 3.
WHAT MINIMUM EDUCATION AND EXPERIENCE REQUIREMENTS ARE NEED T TO QUALIFY TO ENTER TRAINING PROGRAMS 7 4.
WHAT PERCiNT OF THE TRAINING PROGRAMS ARE DEVOTED TO CO?ING WITH EMERGENCY
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SITUATI0"5 VS. TRAINING TO PERFORM ROUTINE DRILLS AT THE PLANT?
5.
H3W KJOH TIME IS SPENT ON DRILI.S USING A SIMULATOR?
6.
0"CE IN3IVIDL'ALS COMPLETE THEIR INITIAL TRAINING, ARE THEY EXAMINED 7 IF SD, EY W.*T ORGANIZATION (COMPANY, FEDERAL GOVERNMENT, OR STATE GOVERIF.ENT,)?
7.
A.RE I:;O!VIOUALS REQUIRED TO REQUALIFY PERIODICALLY?
IF SD, DESCRIEE THE REQ'JALIFICATION PROGRAMS.
IF NOT, WHAT MEANS ARE USED TO ASSURE THAT EACH IkDIVICUALMAINTAINSHISCbMPETENCE7 S.
DESCRIEE THE TYPICAL OPERATING SHIFT MAKEUP.
HOW MANY OF EACH POSITION
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- E RECUIRED ON EACH SHIFT? WHAT ARE THE EDUCATION AND EXPERIENCE REQUIRE-MENTS FC3 E,ACH SHIFT POSITIO,N7 5
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E_.WERS FROM THE UNITED KINGDOM 6.5
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Each of the r.ajer nationalised utilities in the UK, i.e. the Central Cectricity Generating Board and the South of Scotland Iloctricity Board, have for=al staff recruitment and traini=g policies which aim to ensure the safe and sa.tisfact*,ry' operation of their plants. The details contained 1.n this reply,.altheIugh strictly applicable to the Central Electricity Board, can bei considered as typ'. cal for both of the major suppliers of electrical power in the UK.
puestion 1 - Licensing of Ooerators I
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No formal licensing of ' operators' in nuc1' ear power stations is required in the UK. However, operation of each station is subject to Conditions attached to a i
Nuclear Site Licence.
This licence is issued by the Health and Safety Executive i
of the United Ki gdos of Great 3ritain and Northern Ireland (the ESE).
The Nuclear Installations I=spectorate (NII) is that part of the ESI which deals -
with the regulation of nuclear power plants.
i ye conditions of the Nuclear Site Lice =ce require that the licensee (the utility) rappoint persc=s to ca.f out functicus specified is the licence and one of these l
functions is "to control and supervise" the operation of the plant.
- Details, i
Jeludi:g the nucla=- training, technical qualifications and previous positions
, held by these personr, are furnished to the Regulatory Sody and they are registered as a ' W.y Auth=rised person". If in the opinio= of the Regulatory Body a pere - __ cc.csidered as unfit to act in this capacity either upon appoint:r it or e n other time, the licensee vill be notified by the 2egulatory Body ac<.ardingly.
'uly Autherised Perse=s' appointed to ec= trol and supervise the operatic = *of the plant are the senior shif t staff a:d day management staff.
i Trainine i
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Tech =ical Sta'f The nuclear trai=iss of technical s' Vf 1 cluding se:icr shif t operating staff is heed on the starting point that staff are technically qualified to graduane, l
cr equ'ivale:t level, (see answer to questic: 3), is engiseerimg or science and are either fully traised and experienced is fossil fired power static: practice, i
experienced i: :.
appropriate positien in so=e allied indastry or have undergone a g-adua:e trainee eeurse.
The nuclear traisi g is carried, out at the Ge erating Board's Nuclear training Centre, at Oldbu.-y which is organised and run by the CEG3 Headquarters Education j
a:d Trai:i:g 3ra ch.
i Every traimee Operati=g E=gineer en selectic: by the C*erating Eesien of the CIG3 attends the.following training course:-
1 (a)
I::roductics to Nuclear Engineering (4 weaks duratica).
l (b) plant fa=iliarisatics at his parent nuclear power station i
i cludi g a learning project specified by the. Training Centre l
(6-8 weeks).
I
..sgsc= Cperaticas (3 weeks)
(e) er AGE Tech =olcgy (4 weeks) w (dependi g upo: the type of reacter he vill be e= ployed on).
a: the e:.c'= sic: cf these cou ses a: asseassent is =ade cf each student's level
..m.:iacer who ha-cf atta ::e : ar.d a report se : te the appropriate Statio: w
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VEp he objectives of the formal courses are as followe:-
Introduction to Nuclear Power Incineering To givs tlietrainee:
. (1) a knowled e of the principles of nuclear power generation; 6
(ii) a knowledge of the different types of nuclear power systems, associated control systems and ancilliary plant; (iii) a working knowledge of safety eqnipment and special safety procedures on nuclear plant; l
(iv) an istroduction to =uclear reactor operation.
i Marnex doerations Course (for exa=ple)
' D e give the trai=ee:
(i) a'cowledge of the, principles of the desip and construction
%l cf =a pex reacters; i
(ii) a working knowledge of mapex reactor operation;
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(iii) a working k=owledge of factors affecting mag =ox power station availability and efficiency; i
4 (iv) a thorough knowledge of health physica practices and cafety procedures adopted in mapex power stations.
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Le shi't engineering staff are scheduled to attend a biennial refresher course j
at the Trai=i=g Ce:tre of one week duration. This ccese enables the shift as j
a group to discuss reacter operation and nuclear engineering =atters relevant to their particula station. Tne course contens is decided by the Training i
Staff in censultation with the Management of the parent power station and deals vith special proble=s er difficulties that have arise: at other si=ilar stations.
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':he Shif t Charge Engiseer (or Shift Manager) who leads the shif t is respe=sible j
ter ensuri=g the effective utilisation of the course by all se=bers of the shift.
Tne responsibility for ensuring that appropriate staff attend initial and revision trainisg courses rests with the Station Manager.
In addition to this schedule <i training, the Traising Centre runs Nuclear Safety Courses of one week duration i
for these grades of staff.
This course deals specifically with faults and fault studies, e:erge ey actions, operating rules, experience of unsafe incidents and the philescphy of risk.
Staff selected by Station Masagers attend and a large proper: ion of tech =ical staff at power static =s have iow attended.
No fe==al assess =ents of staff attending this course are involved.
I=dustrial Staff The industrial staff, training, both for plant operaters and attendants and
=ainte.a=ce crafts =e=, is carried out at the power statics site by the Station Manager and his staff.
Sc=e specielis: training ecurses at enzufacturers' works cav be invclved and se=e attach en: to construction organisatie s and =a=ufacturera dEiss cens::.:ctics a:d ec==issioni s h.as been used in the pa.st.
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The staff which are ' Duly Authorised' to control and supervise the operatian of the plaat,and to take responsibility for various radiological protection duties reenized by hhe Nuclear Site licence are shown on the attached sheet.
The Se=ior Authorised Persons (NR) marked on this aheet are suitably qualified persons authorised in writing by the Generating Soard to take responsibility for radiological safety in accordance with the Board's own Safety Rules (Radiological)
Tasse rules are submitted to the Regulatory' 3ody for approval. These people are invariably the Shift Charge Ingineer, Assistant Charge Engineers and Assistant Ingfaeers (Operation) if employed on spscific duties.
4
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Senior Autho sed Persons (NR) are given hupplementary training en the Power-D Station and are, examined by the Station Management and a representative of the
~
Board's HQ Health and Safety. Department before authorisation. A typical traindag
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programme is attached.
J
- Accredited Health physicists are professional b'ealth physica staff who also I
have a specific role defined by'the Safety Rules (Radiological) and are always Dprofessionally qualified. Their acade=ic trabing is supplemente'd by attendance lat adva ced radiological protectics courses at u:.iversities er the.UY.AIA.
Before
' appoint =ent as Accredited Health Physicists, candidates are exa=ined by a panel i*
i dincludi=g the Station Manager and a high-ranking representative of the Realth and
' Safety Department of the Board's HQ.
i, Ouestion 3 1
The ci=i=== education and experience require =ents for entry isto the various training prog e=mes referred to above are decided by the c= ploying Region and i
l Stati== but result generally is the follovsg standards:-
i 8
1.
Technical Staff 4
l j
(a) Education - Eigher National Certificate or Diploma.
However the =ajority of staff, in particular those who are j
pro =oted to the level equivalent to Assista t 5' #'t Charge l
I=gineer or above, are qualified to university degree stasdard asd membership of professienal engineering institutions or equivalent scientific organisations.
i (b) Exeerience - Mini =us experience required for the various posta
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will vary with the seniority of the posts. For appointments a't levels above the Assistant Engiseer (Operatio=.s) level, j
several years' experience is as appropriate position is as operatisg nuclear power station is usual.
2.
.riustrial Staff
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(a) Iducatien. Sta:dards vary depe=:iimg on the i=tencied e= ploy =ent
' cut generally no for=al education er technical cualificaticas are specified, except for craft qualifications usual in Eritish isdustry.
() Ireerience - Supervisors are generally, expected =c have appr:priate f.cus:r:.a1 experience and s==e of the industrial e:aff opera:cra vill be recruited frc: vithin unskilled sta.fr c the station er fro: other stations.
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Question 4 L.,
he for=al training courses for technical staff referred to is answerto Q.1
- ...5..
i are basically aimed at ecuipping the staff with a thorough understanding of Z
the engineeFisg, physics and health physics aspects of nuclear power.' These W-4 enurses in:1ude theoretical and simulator training in the fault conditions f
which can arise en nuclear reactors, bu no specific distinction can be drawn Tm addition, 4
between the t*me spent in routine duties and emergency situations.
iii.
the technical staff at' the power station and the industrial staff are trained in f.i For example, at one typical cpecific emergency procedures on as annual basis.ctation all shif t op gi f
This is formal training provided by a specialist rescue, fire p
In addition to this, each Shift Charge si l
overy. year.
fighting and health physica staff.
Engineer arranges for his staff, both technical and industrialE E-The whole emergency arra=gements are demonstrated to the NII as
-E license requirement.
cr four hours.
required, but at least cace per year at each station, as amand postulated on-site 5
j Thisf e=enstration includes a si=.: lated reactor accident, Local public services suc
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and /off-site rr.diological hasards.'These a==ual exercises are ec=sidered to be as and ambulance are involved.
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I d portant tra.i=ing period.
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'CuestionJj, I
A magner reactor si=ulator and several s= aller simulation aids are used during The mag =ex simulator the P.agnox Operations Courses referred to in a:swer to Qu 1.is l
Tso full days of the three weeks' course are al. located to si=ulator i
the simulater is used to a li=ited extent traising.
work.
Q2 the biennial revisic course for discussion of reacter behaviour including fault conditions.
digital si=ulation
?cr AGE reactors, the Soard has provided =cre sophiscicaterd 1
l desks fer mechasistic tr=%g.
These that can be used via replica reae:c si=ulators are nearly ec=plete, the si=clatics having benefitted from the early j
Ve ava-l_lable, they will be opera:isg experience at the first AGR reacters.
to supplement the four i
used to provide as additional two weeks' operating course q.1, and for the bie: ial weeks AGR Technology Course referred to in a:swer to revisic traini=g.
4 i
Ouestics 6 As =e$ tic ed in answer to Qa.1, assess =ent is by the licensee.
b Cuestion ?_
i Essager to assess the perfor ance of staff is the responsibility cf the Static:
specificall-- for nuclect power It
.--uelly and formal assecs=ent procedu es, no:s a.!f, include previsics fer th j
4 a:a:ic:
trais-3g where this is thcugn: =ecessary.
of nuclear power staticas is subject to su_--reillance by the 1;
"his sunle ents but does not
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ne ocera:ic:
licensees' oc EQ Eealth asi Sa.fety Depart =est.
for =.uclear saf ety incluN g F.a: age =e :
replace the respessibility of the Statie:S e NII carry cut i:Cepende:: evaluations of ::e the ec:petence of staff.
-ad check for co=71iance vin the perferna ce of Opera:cre' crga:isatic=.
cc:di:ic:s of the nuclear site licence.
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_uestion 8 Q
A typical shift staff for an operating nuclear power station would. consist of:-
Te'chnical Staff Shitt Charge Engineer Assistant Shift Charge I. gineer (Control Room Supervisor)
Assistant Shift Charge I=gineer.
(Plant) Reactor 1 b
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Assistant Shift Charge Engir.eer (Plant) Reactor 2 Assistant Engineer (Operatione) 3 Reactor 1 Desk Operator Assistant Engineer (Operations) 3
('*
3enctor 2 Desk Operator
[
Assistant Engineer ~(Operations)
.s nefuelling Assistant Engineer (Operations)
Turbine Hall Industrial Staff Operatic s Fore =e and about 30 akilled plant operators and seni-sk m d plant attendants.
e Health physics P.enitor Fore an and about four or five monitors.
NOII:
Ia sc=e cases =aintenasce is carried out by staff on shift is which case there would be a Shif t.W.ainte asce I.:gineer (Assistant Shift Charge Engineer level) and ?crecen a d craf tsmen.
Tne shift staff detailed above previde for nor=al operatica a:d for emergency (fault / accident) conditions; teams are rehearsed in cperatio:s which =ight be required under accident ce=ditions.
In additic~ to this, the I:ergency Plan for each statio requires no=isated staff to be available on telephone call.1 on a rota basis.
Typically such staff c: call comprise as E=ergency Controller (Static: Manager and other senior staff in rota), Health.:hysicist, Reactor Faysicist, Ad=i=istrative Officers. Tnese nominated staff could be on site withis about 30 =i=utes of call.
If further support were reenired during a=
e:ergency, other staff would be called in by telephene as needed; the statics staff includes appropriate expertise is reacter physics, che=istry, health physics, and isstruse:: technology in addition te electrical and =echa:ical e:S meering.
Other nuclear power static s a:d the Soard's EQ Departments i
would provide, tech:ical assistance if required.
l n.e pegulatm Authority vecid aise be i=fc=ed en the occasion of a=y e=ergesey.
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1 UCLE Ai: SITE LICCflCE !!c.CC, VARI ATIC!! 2.
Duty Authorised Persons Condi ti on lin. *.
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The following personnel are appointed to perform the functions assigned to duty cu hori:ed per: ar under the followthD conditione contained in lluelear Site Licence lio.83, variation tro.2, dated 31st July 1970.,
Condition Brief Descriptien of' Functions Duty Authorised Persons No.
Performed (Designation) 26 To designate an area, place or Station 14aaager space as a controlled area.
Deputy Statien Manager Opera:.' ens Superintendent Accredited Health Physicists Senior Authorised Persons CHR)-
27 To authorise entry of non-Station Manager classified peren into Deputy Station Manager centrolled areas.
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To 'ssue ins; ructions to allow a Sta: ion Manager
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contacinated person to leave Deputy Station Manager
's site other than under cedical Shif: Charge Engineers.
s upe rvi sion.
37 To direct in what circues:ences, Station Manager at what ticle and in wha ccnner Deputy Station Mcnager persons en the site shculd Accredi:cd Health Physicists.
wear desece:crs.
Senior Authorised Persons (NR) 38 To do:crains as accurately as Statien Manager 39 possible, the dose of rediation Deputy S ntion Manage.r i
received by' a persen when that Operations Superintenden-
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st!!!On A'c.tonism PIR3c:1 (Im) Ti<AIllIr:c CO'Jnt: OCTonrn 1970 j
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Day 1 9.00 as, safety Rulos, (NR)
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(2.i occc6er) i 1.30 pm site Licence and Radicactive i
Substances Act 1960
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Day.2 9.00 as Practical !!ealth Physies Aspects gi (25 octqber)
Pa:t Incidents II
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g 1.30 ps Int:cduction to EP Ints. Air j
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St=ple Counting, Liquid Geiger, Counting, HTO M:nitoring CO/CO2 Monitoring
.a Day 3 9.00 am Action Levels iI (26 c:.cber)
' Active Waste Manage =ent,
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.7cb Cent:cl Aspects,.
N. D.T.,
I 1.30 pm Foru=/ Discussion t
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1 1
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1.
Prr.::ical A:sig.=ents will be se: af ter the course a..d these wi2.1 be cc:pletsf c: :hif.
2.
l.11 ca.. dice.es shculd have read their Saf ety P.ules (NR) before attending the course.
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5 ANSWERS @M THE FEDERAL REPUBLIC OF GEMt3Y e
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---70 QUESTION 1--
'i
'egarding the scope and context of the training programs for shift supervisors i
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dep'uty shift supervisors and reactor operators; there exist no official regu-The formulation of the existi,ng training programs is exclusively the
+-
- 1stions.
Nevertheless, the knowledge concern of the licenseVi.e. the operating coinpany, and reactor
, and abilities of the sh.ift supervisors, deputy shift supervisor Th,is knowledge is to be demonstrated in the scope of an operators are fixed.
examination over against the licensing or inspection authorities,.
he training prograts of the operating companies are executed naturally However, they c:nfoming to the providing of this. knowledge and ability.
are structured differently depending on the specific operating organization.
' The following major training divisions are ordinarily ec=pleted by the responsible shift personnel (shift supervisors, deputy shift supervisors, reactor operators)
---Provision of the fundamentals of nuclear technology (nuclear physics, reactor safety, radiation, fire, and occupational - protection, atomic law) through attendance of a nuclear technology classroom (about 3 months).
---Provision of plant-specific subjects (layout, service and accident investigation of the nuclear power station, knowledge of the operating procedures, alarm plan safety spe,cifications, rules and guidelines as well as capability for operation of the installation and for assurance of safety) by means of on-the-job training partly in ecllaboratior) with specialists employed by the manufacturer (
This inservice internsMp training enco: passes theory one and a half years).
and practice of, nuclear power station service and is extended to all signific stations cf the nuclear pcwer plant, e.g. the reactor syste=s, nuclear auxilia sys:s s, censurement, control and regulation systems, electrical techn
.t:ia: ion pr::e:tien, ventilation systems, cooking water syste=s, feedwater, re.avW of the installation, transients and accicents.
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. ---si=ulato'r. school (4 to 6 weeks)
---speciili.ted's.ourses,,at system c.r com.ponen* manufacturers on the, question of the electronics, the fire, radiation, and occupational-protection.
--Participation in the placing in service
--Participation in normal shift service'.
Th3 total time required for the required practici experience fri the nuclear power station is at least 2 yeart for reactor pperators, at least 21/2 years
~
fcr shift supervisors and deputy shift supervisors. The shift supervisor or
' deputy shift supervisor can take credit for up to two years of' practical P
exparie'nce; he is required, in fact, to make use of 1/2 year of reactor operator duty.
---TO QUESTION 2---
All persons who wish to be employed in nuclear power stations are required to receive the consent of the appropriate licensing or inspection authorities.
In this canner, according to Part 7 Section 2 Number 1 of the A. tom Law,' all persons responsible for the operation of the installation (strtion superhntendict,
' division or section chiefs, radiation protectien agents, shift supervisors,-
deputy shift supervisors, reactor operators, shift engineers) r::.zst demonstrate their possessien of the reuisite expertise, before they may take up their duties.
According to Part 7 Section 2 Number 2 of the Atom Law, all persons othersise employed in cperation of the station (.e.g. maintenance persennel, radiation protection personnel, supervisory personnel, fire protection personnel, and ethers) cust de=nstrate to the appropriate authorities that they possess the necessary kn:xledge of the operation.of the station and the applicable safety precautter.s, before.they may take up the.ir duties.
The oemonstration of upertise er knceledge is prerecuisite. for the issuance of the license for operation of the particular nuclear power station.
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---T0-QUESU ON 3:
g Tne minimum prerequisites with re' Ject to professional training for the
~
.l persens responsible for the
- operation of nuciear power staticos are laid j
However, these criteria listed here are not formal do.wn in a guideline.
requirements for the beginnins of a training program, but instead are cinimum requirements for the approval.cf the. licensing authorities,for the In the case of the practical und:rtaking of the appropriate activity.
exp;rience time mentioned for shift supervisors, deputy shift supervisors and reactor oper'ators, it is to be noted that the professional entrance qualifications of sktfisd w:rkers, master craftsmen or technicians, and of engineers already
/
n:hnally means ::re than 3 years in professional prectics.
---TO QUESTION 4:--
About 20 per cent of the training program for new nuclear power station personnei is dev:ted to transients and accidents; the remaining 80 percent is
- revided for operation in conformance with regulations and knowled i
Practice for the....
installa-icn as well as or'gani:ational data.
- s C:ntrol cf distu-ban:es in the installation as well as theoretical case studies are :arried out, as also in the form of alarm drills, and in any Tnis comprises case by the :arrying out of reactor protection examinaticns.
I about 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> ;er year.
---TO O' JEST *0N 5:
?ractices r si:::lators, which are devoted 50 per cent to the control of
, disturban:es and transients, are carried out from one to two weeks per-year.
---70 C'JESTION 5:--
f separv. sors, deputy shift supervisors, reactor operators a 3
Only shif:
i i n after the engineers are s hie:t Ic an oral and written technical exam nat o training. The te:hnical en.ination af ter the c:mple:i:- :'.efr firs:
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completion of their first training.
The technical examination is given by an examination comission, which is composed of representatives of the licensee
^
(operating coo;ianyl, the appropr.iate licensing authority (highest ste.e authority) and from their consulting experts.
---TO OUESTION 7---
Basically, the effort to preserve the training condition is the same for all responsible personnel employed in the nuclear power station. However, repeated cxaminations are not provided for.
Also, persopnel othemise employed in the op /eration of the facility (e.g. maintenance personnel, radiation protection girsonnell must be included in the measures for the upkeep of the condition t
of, training.
---TO 00ESTION S:---
A typical operation shi.ft crew consists. of a shi.ft supervisor, a deputy citift supervisor, one or two reactor operators., one or two control station operators for the turbine and e.g. tne ventilation works on designated cooling motor circulation, as also one or two installation attendants, who are entrusted with designated control actions. and minor maintenance work. - Control station operators must demonstrate the following oualifications:
---Fass.ing of a journeyman examination it, th6 ser.se of the trade rules in a technical skill, or a final training program as a sk.iiled worker in a technical skill..
---A thorouch introduction in the interaction of the portion of the plant cperated by the control station with the balance of the plant,
---Knowledge of Oe areas of reactor safety, radiation and accident protection, t; the extent that his duties as a control station opeator are affected.
---Knewied;e of the secure cperation of the nuclear power station', the
?:ss':le ha:ards and the prc:ee:f ve neasures to be empicyed,
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---A four week practical experience period in the operation of the appropriate control station under supervision.
j Station caretakers must denenstrate a s.imilar e.ualification; however, only a two week practical experience period under supervision in the performance of their
~
duties.
Tho nuclear power stations. in the Federil Republic of' Ger any are operated
~
by 5 to 6 operating shifts ar a rule.
The3ederalMinisteroftheInteri.or R5 R0d4 12-518 231 USA - 2/6.3 t
E:nn, June 25,'1979 with warmsst greetings.
(on behalf of) Dr. Schmurer o
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