ML19207A139

Licensing & Certification of Personnel at Nuclear Power Plants

ML19207A139
Person / Time
Issue date:	05/22/1979
From:	Office of Nuclear Reactor Regulation
To:
References
FOIA-79-98 NUDOCS 7905300278
Download: ML19207A139 (12)

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er LICENSIfKi AND CERTIFICATION 5, /,

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Chapter 10, Code of Federal Regulations Part 50 requires that applications for a license to operate a nuclear power plant include information concerni w organizational structure, personnei qualifications, and related matters.

Among the related matters are training, evaluation and certification to tne competency of personnel.

In addition to this general requirement,10 CFR Part 50, Part 19 and Part 20 indicates that the facility licensees have a responsiblity to assume that individuals who work at a nuclear facility are properly trained so that tney may perform their tasks in a safe and competent manner.

In addition to the above requirements,10 CFR Part 55, " Operators' Licensas" describes the procedures and criteria for the issuance of licen'.es to in-dividuals who will manipulate the controls of a reactor or direct the acti.f::1; of those who manipulate the controls. These are the only individuals require-:

to be licensed by NRC to perform their jobs.

It is the intent of this paper to make you aware of these requirements, but not to explore the details of each. Appendix A contair.s a listing of the regulations, regulatory guides and industry standards that address training, certification and licensing of persennel. -

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I will, hcwever, discuss the contents of two documents that address I

j certification and licensing of personnel at nuclear povier plants, i:UREG-i 0094, NRC OPERATOR LICENSING GUIDE and Regulatory Guide 1.8, PERSONNEL SELECTION A'iD TRAINING.

NUREG-0094 This guide describes the procedures and criteria for the issuance of operatcr and senior operator licenses. It is intended to assist applicants and facility licensees to better understand the pertinent provisions of the r

I Comissions regulations in this regard.

The requirement that reactor operators must demonstrate their qualifications and receive licenses from the NRC to perform their functions was established as a statutory requiremen't by the U. S. Atomic Energy Act of 1954. Further, pursuant to the Act, the Code of Federal Regulations, Part 50, Chapter 10, Licensing of Production and Utilization Facilities, provides that the controls of any reactor licensed under Part 50 shall not be manipulated by anycne who is not a licensed operator or a senior cperator as provided in 10 CFR Part 55, Operator's Licenses. Part 55 establishes the procedures and criteria for the issuance of licenses.to operators and senior operators and therefore governs the regulatory program of operator licensir.g.

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i TYPES OF LICENSES A.ND EXA'1INATIONS i

The Comission presently issues two types of licenses.

In general, anyone who manipulates reactor controls must be licensed as a reactor I

l operator, and those who direct the activities of licensed operators must be licensed as senior reactor operators. Practically speaking, the i

reactor operator in a power station would be the control room operator, i

and his shift supervisor would normally be the senior reactor operator.

Herein, the two types will be referred to as " operator" and " senior operator."

The Camission examiners administer both written and operating examina-tions to test the knowledge of applicants for licenses. The written examination for the operator consists of questions regarding principles of reactor operation, features of facility design, including instrumenta-tion, safety and emergency systems, facility procedures, including radiation control procecuzes, and general operating characteristics.

s The written examination for the senior operator consists of the above

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and additional questions regarding reactor theory, handling and disposal of radioactive materials, specific operating characteristics, fuel handlin; procedures and administrative procedures," conditions and limitations.

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_4 The operating test at a nuclear pcwer station normally consists of both l

an oral examination during a plant walk-through and an actual demonstra-l l

tion at the reactor console during a reactor startup. The scope of both portions of the operating test is the same for both operators and I

senior operators, except that the senior operator is expected to answer i

i questions as if he were the operator's supervisor.

The scope of the crai and operating test consists of (1) interpretation of control instrumenta-i tion, (2) manipulation of the control equipment, (3) ability to operate l

j other facility equipment, and (4) kncwledge of radiological safety practice and radiation monitoring equipment.

LICENSE APPLICATION A?:D ELIGIBILITY l

i Applicants for operator or senior operator licenses must submit a signed application to the Commission.

In addition, an authorized l

representative of the facility at which the applicant will be wcrking I

must certify that the applicant has a need for the license, has com-pleted a training program tsupplying the details of such), and has f

learned to operate the reactor controls competently and safety. A report of medical examination of the applicant on an NRC fcrm must also be submitted. ANSI 546-1976 provided guidance regarding physical eligi-bility of license applicants.

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5-REQUIREMENTS FOR EXAMINATION PRIOR TO CRIT!CALITY (COLD EXAMINATION)

Prior to the advent of nuclear power plant simulators, an applicant was eligible for cold examination provided (1) he had er had held an operator's license at a comparable facility; (2) ne had a certifica-tion of the necessary experiences if the comparable facility was not subject to licensing (e.g., reactors operated by the Depart. Tent of Defense); or (3) he had passed an NRC-administered written examina-tien and operating test at a comparable facility, but was not issued a license.

It should be stressed that most trainees receive experience in excess of the programs outlined herein to acquire the desired competence.

PROGRAMS UTILIZING NUCLEAR POWER PLANT SIMULATORS Although one pcwer plint was being utilized part time as a 1 raining facility in the nineteen-sixties, it was apparent that the number of facilities that were available for training would be very linited.

Consequently, General Electric Company proposed that a nuclear power plant simulator be incorporated in a training program to provide trainees with the necessary control manipulation to meet eligibility requirements for cold examination.

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' Individuals who successfully complete a training program that utilizes a nuclear plant simulator will be considered eligible for cold examina-tions provided that they have completed an appropriate course in nuclear technology fundamentals, they have manipulated the controls of any nuclear reactor throughout ten complete startups, and they have observed several months cf daily operation of power reactors as members of shift operating crews.

The decision to implement these procedures is based on several pertinent considerations, including (1) the completeness and accuracy with which the simulators are constructed; (2) the extent to which the simulators provide various types of control room ex-perience to the trainee, including the ability to simulate normal startup and shutdown operations and a multitude of casualty drill situations; and (3) the extent of operating experience of the simulator instructors.

Training programs utilizing nuclear power plant simulators were first put into effect by the NSSS vendors: General Electric, Westing-house. Babcock & Wilcox, and Combustion Engineering.

P resently, nine utilities have simulators in operation or planned, and two vendors are building additional simulators.

To date, over 1500 individuals have been trained at the centers that utilize the simulators.

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/ REQUIREMENTS FOR H0T EXAMINATION FIRST METHOD In order to be eligible for an exanination after a facility achieves criticality, an individual must receive on-the-job training that includes plant maneuvering and two reactor startups under the direct supervision of a licensed operator or senior operator in addition to formal classroom training.

During the administration of examinations, applicants must demon-strate their proficiency at the reactor controls by performing reactor startups from a substantially subtritical condition until generation of nuclear heat. These startups can involve a substantial arount of downtime at a facility to properly prepare individuals for examinations and to administer examinations.

In addition, scheduling of the examinations can be complicated by unexpected requirements for power, which is outside the control of the plant staff.

SECOND METHOD Thus, NRC has approved of training prcgrams that utilize simulators for the training startups and for the control manipulation portion of our examinations. To date, these programs have been limited to personnel of plants having control rooms that closely resemble that of the simulator.

In addition to the training center maneuvering, the applicant must have manipulated the controls of a reactor during 8 0?I U S)

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power changes or other significant reactivity changes that may or i

may not include reactor startups. These training programs require i

several months residence at the training center, one of which is i

j devoted to operation of the simulator controls.

i THIRD METHC0 NRC has determined that it is acceptable to use nuclear power plant simulators in determining the qualification of individuals who apply for licensas after initial criticality.

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'l The Operator Licensing Branch will consider training programs that utilize appropriate nuclear power plant simulators for startup l

experience for meeting the eligibility requirements of examinations.

,l In addition, a reactor startup will not be required as part of the

'l.j operating test, providing that appropriate certification regarding i

an individual's ability,to manipulate the controls is contained in his application.

REGULATORY GUICE 1.8 (AMSI/AMS 3.1-1978) i The NRC, and its predecessor the AEC, has encouraged the industry to deve!:?.

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Safety Standards for the operation of Nuclear Pcwer Plants.

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' After a standard has been developed and approved by the American Nuclear Society and the American National Standards Institute, the Commission will issue an endorsing Regulatory Guide with, or without, exceptions to the standard.

In the nineteen-sixties, it became apparent that guidance was needed regarding the staffing of nuclear pcwer plants.

An ANS subcommittee was formed vnsisting of nine utility representatives with nuclear power plant operating experience, and three individuals with nuclear operating experience at the National Laboratories. Their efforts resulted in American National Stit tard ANSI N18.1-1971, Selection and Training of Nuclear Pcwer Plant Personnel.

The AEC issued Regulatory Guide 1.8, Selection and Training of Personnel that endorsed the standard with some exceptions.

ANS I-N18.1-1971 has recently been revised and reissued as ANS!/A!!" 3.1-1978.

The NRC is processing a revision to Regulatory Guide 1.8.

s ANSI /ANS 3.1-1978 indicates the experience, nuclear and non-nuclear academic training and license requirements for personnel at a nuclear power plant for plant management, professional technical personnel, h

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s operators, technicians, repairmen and technical suppcrt personnel.

In addition to the minimum recommended qualifications, th'e standard decribes additional education that would be desirable.

The requiremants include that all of the positions in the operations chain of co.ntand require previous power plant experience, a portion of which must be nuclear. These pcsitions include plant manager, assistant plant managers and supervisors and operators requiring NRC licenses.

In addition, the maintenance manager and technical manager must have pcwer plant experience, including nuclear.

Other individuals in responsible positions must have several years of experience in their discipline prior to assuming their duties.

Appendix B cutlines the experience and training requirements for the nuclear pcwer plant staff.

CONCLUSION:

The Nuclear Regulatory Ccamission requires that nuclear power plants be staffed oy trained and well-qualified personnel that will competently and safely operate the facilities, so that there is reasonable assurance that the health and safe:

of the general public will be protected. This paper gives some indication to the means emoloyed for us to have this assurance.

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-l APPE!OIX A I

l Regulations, Regulatery Guides and Industry Standards 1.

10 CFR Part 50, Licensing of Production and Utili:ation Facilities 2.

10 CFR Part 55, Operators' Licenses 3.

10 CFR Part 19, fictices, Instructions and Repcrts to ilorkers; Inspections 4.

10 CFR Part 20, Standards for Protection Against Radiation 5.

Regulatcry Guide 1.8, Selection and Training of Personnel 1

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Regulatcry Guide 1.58, Qualification of Nuclear Pcwer Plant Inspectin, l

Examination and Testing Personnel 7.

Regulatory Guides 1.17, Protection of Nuclear Pcwer Plants Againn Industrial Sabotage 8.

Regulatory Guide 1.134, Medical Certification and Monitoring of Personnel Requiring Operator Licenses 9.

Regulatory Guide 1.33, Quality Assurance Program Requirements

10. Regulatory Guide 8.8, Information Relevant to Maintaining Occupaticnal Radiation Exposure As Lcw as Is Reasonably Achievaale ll. Regulatory Guide 8.10, Operating Philosophy for Maintaining Occupational Radiation Exposures As Lcw As Is Reasonable Achievable I

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12. fiUREG-0094, NRC Operator Licensing Guida

13. ANSI /ANS 3.1-1978, Selection and Training of Nuclear Pcwer Plant i

Personnel

14. ANSI N18.17, Security for Nuclear Pcwer Plants i

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