Text

Action Plan to Improve Technical Capability of Licensee Personnel
	ML19240A162
Person / Time
Issue date:	05/31/1980
From:	; Office of Nuclear Reactor Regulation
To:	;
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ML19240A157	List: ML19240A156; ML19240A162; ML20004F676; ML20004F683;
References
	FOIA-81-145 SECY-81-192, NUDOCS 8104030018
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a O

ENCLOSi!RE 1 ACTION PLAN TO IMPROVE THE TECHNICAL CAPABILITY OF LICENSEE PERSONNEL I

IlllS DOCUIAENT CONTAINS A P00}_QUnlliY P;tGES L

j slo 40 3 0 01%

ENCLOSURE 1 CONTENTS TASK A.

NRC ACTION PL AN TASKS DEVELOPED AS A RESULT OF THE TMI-2 ACCIDENT 1.

Training and Oualification of Operating Personnel......

I.A.2 2.

Licensing and Requalification of Operating Personnel.....

I.A.3 3.

Simulator Use and Development...........

I.A.4 B.

LONG RANGE RESEARCH PLAN Task I Operating Personnel and Staffing Task II Educational and Training Requirements Task III Operator Licensing Examinations Task IV Use of Simulators in Training Programs for Nuclear Power Plant Operators and Senior Operators

ENCLOSURE I Task I.A.2 PART A May 1980 TASK I.A.2 TRAINING AND QUALIFICATIONS OF OPERATING PERSONNEL A.

OBJECTIVE:

Improve the capability of operators and supervisors to under-stand and control complex reactor transients and accidents, and improve the general capability of an operations organization to respond rapidly and effec-tively to upset conditions.

Increase the education, experience, and training requirements for operators, senior operators, supervisors, and other personrei in the operations organization to substantially improve their capability to perform their duties.

B.

NRC ACTIONS 1.

Immediate upgrading of operator and senior operator training and qualifications.

a.

==

Description:==

NRR will require all operating plant licensees and all license applicants to provide specific improvements in training and qualifica-tions ci senior operators and control room operators.

NRR will also require that a level of corporate operations management higher clan previously required must certify the fitness of candidates for operator licensing by NRC.

The NRR staff will review the contents of revised training programs, and the IE staff will audit the implementation.

NRR will indicate that licensees need to make every effort to meet the requiremc.ts as soon as possible within the time limits specified below for each change.

Long-term upgrading of training and qualifications of operating personnel is discussed in Item I.A.2.6.

(1) Qualifications - Experience.

(a) Senior operators" - Effective May 1, 1980, applicants for senior operator licenses will be required to meet the experience requirements of Recommendation 1 of SECY 79-330E.

Effective December 1, 1980, an applicant for a senior operator license will be required to have been a licensed operator for one year (Recommendation 2 of SECY 79-330E as modified by the Commission).

Precritical applicants will be required to meet unique qualifications designed to accommodate the fact that their facility has not yet been in operation.

I.A.2-1

Task I.A.2 May 1980 s

(b) Contro! roem operators:

There is no immediate change required.

I (2) Training.

(a) Senior operators *:

Effective August 1, 1980, applicants will be required to have three months of continucus on-the-jo's training as an extra person on shift (Recommendation 3 of SECY 79-330E).

(b) Control roem operators *-

Effective August 1, 1980, applicants will be required to have three months' training on shift as an extra person in the co.. trol room (Recommendation 3 of SECY 79-330E).

(c) Training programs will be modified, as necessary, to providc:

(1) craining in heat transfer, fluid flow, and thermodynamics;

(~.) training in the use of installed plant systems to control on mitigate.7 accident in which the core is severely damaged (see also Item II.B.4); and (3) increased emphasis nn reactor arid plant transients.

(3) Facility certification of competence and fitness of applicants

)

for operator and senior operator licenses.

Effective May 1,1980, certifications completed pursuant to Sections 55.10(a)(6) and 55.33a(4) and (5) of 10 CFR Part 55 will be signed by the highest level of corporate management for plant opere.1ce (for example, Vice President for Operations).

b.

Schedule:

The requirements were issued by NRR on March 28, 1980.

c.

Resources:

NRR FY80 - 0.6 my; ADM FY80 - 0.1 my and $8,000, FY81 -

0.1 my and $3,000; IE FY80 - 1.0 my.

2.

Training and qualifications of operations personnel.

a.

==

Description:==

Each licensee will be required to review its training progrsm for all operations personnel, including maintenance and technical

Precritical appiIcants will be required to meet uniqua qualifications designed

~

to accommodate the fact that their facility has not yet beeti in operation.

I.A.2-2

i,sk I.A.2 May 1980 personnal, and to justify the acceptability of training programs on the basis that these programs provide sufficient asscrance that safety-related functions will be effectively carried out.

Documentation of this review and justification will be retained onsite for inspection, but need not be submitted to the NRC for review.

The preferred method of fulfiliing this recommendation is a position task anal; sis, in whicn the tasPs performed by the person in each position are defined, and ths train',g, in conjunction with education and experience, is identified to provide assurance that the tasks can be effectively carried out.

The position task analysis will include normal and emergency duties (such as maintenance activities), and place emphasis nn the role played by every member of an operations organiza+#nn that a'sures safe plant operations.

All levels of the operations organization will be included.

This task is arenable to a generic approach.

INPO could perform a task analysis for those position; generally used throughout industry.

Each utility could then evaluate in a similar manner any unique,1sition in its organization not covered in the INP0 study.

(See also Table C.1, Items 1, 2, 11 and Table C.2, Item 11.)

Licensees will also be required to upgrade training and qualifications of personnel found to be necessary as a result of the review.

The team aspect of

+he shift operating organization will be emphasized in training, particularly during simulator training and requalification and plant drilio.

IE will check to assure that the training evaluation has been performed and p trsonnel are properly qualified.

In addition, they will perform evaluation of personnel changes in key plant management positions and changes in organi-zational structurer. (see also Item I.B.1.1).

5.

Schedule:

NRR will issue requirement by October 1, 1980.

c.

Resources:

NRR FY80 0.1 my and $10,003, IE FY81 - 1.0 my.

3.

Administration of trainirg programs.

a.

==

Description:==

NRR will develop criteria and procedures to be used in auditing training programs, including those provided by reactor vendors, and I.A.2-3

Task I.A.2 May 1980 3

increase the amount of auditing.

The cudit criteria will place emphasis on i

the instructors' abilities to +each as well as their technical knowledge (NUREG-0585, Recommendation 1.4(6), Retomaendation 6 of SECY 79-330E).

The audits to be conducted by NRR will assure that training is formalized and structured, inclcdit,g the use of lesson plans, qualified instructors, qualified supervision of instructors, and proper conduct of testing.

The audits will eventually be in conformance with training institute accr9ditation (see Item I.A.2.7).

NRR will also conduct all cold certification examinations at simulator trair.ing centers (Recommendation 5 of SECY 79-330E as modified by the Commission).

Pending accredi tation of training irstitutions, NRR will require that training center and f acility instructors who teach systems, integrated responses, transient, and simulator courses demonstrate their competence to NRC by successful completion of a senior operator examination.

These instructors will also be required to successfully pc?ticipate in requalification programs to retain instructor status, or possess instructor certification from INPO, provided that such a certification program has been examined by NRC and found to be acceptable.

b.

Schedule:

NRR will initiate procedure development in FY81 and will begin augmented auditing in FY82.

NRR issued requirements on March 28, 1980, for certain instructors to demonstrate senior reactor operator (Sk0) qualifica-tions and to be enrolled in requalification programs.

NRR will conduct certification examinations for some trainees from each simL'ator training class to audit the training program effectiveness starting October 1, 1980.

c.

' e sources :

NRR FY80 - 0.5 my; FY81 - 1.3 my ADM FY80 - 0.1 my; FY81 - 0.1 my and $7,000.

g 4.

NRR participation in inspector training.

a.

==

Description:==

As part of the established IE inspector training program, operator licensing and human factors personnel in NRR will provide instruction on the role and licensing of reactor operations staff, including the types of I.A.2-4

Task I.A.2 May 1980 feedback of field observations needed by the NRR staff [NUREG-0585, Recommen-dation 1.4(1)].

b.

Schedule:

The program will be initiated in FY82.

c.

Resources:

Annual recurring requirements, NRR - 0.1 my.

5.

Plant drills.

a.

==

Description:==

NRR will-require licensees to develop and conduct in-plant drills by shift onerating personnel.

Normal and of f-normal operating maneuvers will be required to be simulated for walk-through drills on a plant-wide basis.

Orills will also be required to test the adequacy of reactor and plant operating procedures (NUREG-0585, Recommendation 1.3).

Subject:

"NRC Interim Report No. 3 on Three Mile Island Nuclear Station Unit 2" Letter from Chairman, ACRS, to Chairman, NRC, dated February 13, 1980,

Subject:

" Qualification of Radioactive Waste System Operating Personnel" NUREG/CR-1250, Vol. I, pp. 105. 106, and 146; Vol. II, Part 1, p. 130, Part 2, pp. 419, 423, 458, 612, Part 3, pp. 854, 874, 920 Memorandum from J. M. Allan, NRC Region I, to N. C. Moseley, October 16, 1979,

Subject:

" Operations Team Recommendations-IE/TMI Unit 2 Investigation" Recommendations B.2.d C.2.a, C.2.b, C.3.c I.A.2-11

Task I.A.3 May 1980 TASK I.A.3 LICENSING AND REQUALIFICATION OF OPERATING PERSONNEL A.

OBJECTIVE:

Upgrade the requirements and procedures for nuclear newer p~ 3nts operator and supervisor licensing to assure that safe and competerc operators and senior operators are in charge of the day-to-day operation of nuclear power plants.

Increase the requirements for initial issuance of licensas and for license renewals and provide closer NRC monitoring of licensed activities.

B.

NRC ACTIONS 1.

Revise scope and criteria for licensing examinations.

a.

==

Description:==

NRR will notify all operator license holders and appli-cants of the new scope of examinations and criteria for issuance of reactor operator (RO) and senior reactor operator (SRO) licenses and renewal of licenses based on Commission Action on SECY 79-330E (Recommendations 1, 11, 12, 13).

The notification will include a new category on operator and senior operator examinations dealing with thermodynamics and related subjects; establish time limits for applicants to complete the examination; increase the passing grade to 80 percent overall with a minimum grade of 70 percent in each category; require that senior operators take oral examinations; and change requalifica-tion programs to reflect new initial requirements for issuance of licenses (Task I.A.2.1).

NRR will include simulator examinations as a portion of the license examination.

The increased examination requirements will ave a substantial resources impact on NRC and a moderate impact on licensees.

Appli-cants for examinations will also be required to grant permission to NRC to inform their facility management regarding the results of the examinations for purposes of enrollment in requalification programs (SECY 79-330E, Recommenda-tion 14).

See also Table C.1, Items 1, 2, 4d, 11, 26; Table C.2, Items 4, 11; and Table C.3, Item 56.

b.

Schedule:

NRR issued requirements on March 28, 1980, and will begin examining to the new criteria by May 1,1980 for operating reacters.

Applicants for operating licenses must prepare employees for new examinations prior to I.A.3-1

Task I.A.3 May 1980 fuel load.

Simulator examinations as a part of the license examination will start by June 1,1980 at f acilities where there is a simulator.

Starting FY81, simulator examinations will be conducted for f acilities where simulators are not available at the facility, depending on availability and suitability of simulators.

c.

Resources:

NRR FY80 - 5.5 my, FY81 - 4.3 my 2.

Operator licensing program changer.

a.

==

Description:==

NRC will develop and implement a plan to relocate operator licensing branch (OLB) examiners at Nuclear Power Plant Simulator 1.-aining Centers or in IE regions (Recommendation 1.4(7), NUREG-0585) and factor in the results of the study being made under contract NRR-80-117.

A study of the staffing of the operator licensing program and the qualifications and training of examiners will be initiated (Recommendation 16, SECY 79-330E).

A plan to report operator errors and to act on operator errors with respect to continuation of licensing will be developed and implemented (Recommendation 1.4(2), NUREG-0585).

1'j b.

Schedule:

Ini+,iate work in FY82 or later except fo-regional relocation of examiners, which will proceed in the interim on a personnel availability basis.

c.

Resources:

NRR first year - 1.2 my, secuno year - 1.5 my, third year -

0.5 my.

3.

Requirements for operator fitness.

a.

==

Description:==

A regulatory approach will be developed for Commission consideration to provide assurance that applicants for operator and senior operator licenses are psychologically fit (stress and malevolence), and to prohibit licensing of persons with histories of drug and alcohol abuse or with histories of criminal backgrounds.

Studies, criteria development, public comment, criteria issuance, and implementation are involved.

Two studies of interest are already under way in SD:

(1) standards for psychological assessment of I.A.3-2

Task I.A.3 May 1980 plant personnel, and (2) behavioral observation program to assure continued reliability of employees.

b.

Schedule:

This is a Decision Group D item.

Therefore, schedules and resources will be developed in connection with routine NRC budgetary processes.

c.

Resources:

See " Schedule" above.

4.

Licensing of additional operations personnel.

a.

==

Description:==

NRR will continue to study the question of which plant personnel, other than reactor operators and senior operators, may need to be licensed by NRC.

The study submitted to the Commission for review will include consideration of managers, engineers, auxiliary operators, maintenance personnel, technicians, and shift technical advisors.

The study will also include consider-atien of the training, qualification, and certification efforts for such personnel undertaken by the Institute for Nuclear Power Operations.

Furthermore, the study will also include consideration of the results of contract NRR-80-117, which is planned for completion in September 1980.

The pending petition for rulemaking iPRM 20-13) concerning radiation protection personnel will be held in abeyance until the comprehensive study is completed.

b.

Schedule:

Work will be initiated in FY82 or later.

c.

Resources: NRR first year - 1.0 my; ADM first year - 0.2 my and $15,000.

5.

Establish statement of understanding with INP0 and DOE.

a.

==

Description:==

A statement of understanding between the Institute for Nuclear Power Operations, the Department of Energy, and the NRC will be developed for consideration by the Commission.

The statement will address the mutual intent of NRC and INPO concerning the extent, if any, to which NRC should review or rely upon the training, cortification, and other activities of the Institute and the general cunditions for such reliance in the future.

I.A.3-3

Task I.A.3 May 1980 3

i Consideration will also be given in the development of a statement of understanding that will prJvide alternative mechanisms for industry to inform NRC of its general pregress on needed safety reforms.

This will be necesscry for NRC to evaluate and accredit those efforts as appropriate.

The staff will report periodically to the Commission on its interactions with IMDO.

b.

Schedule:

This is a Decision Group D item.

Therefore, schedules end resources will be developed in connection with routine NRC budgetary processes.

c.

Resources:

See " Schedule" above.

C.

LICENSEE ACTIONS 1.

Revice scope and criteria for licensing examinations.

a.

==

Description:==

Licensees will prepare applicants for new examinations

)

and will develop and implement new examination criteria and lecture schedules for the requalification program.

Specific requirements related to new examinations include-(1) All reactor operator license applicants shall take a written examination with a new category dealing with the principles of heat transfer and fluid mechanics, a time limit of nine hours, and a passing grade of 80 percent overall and 70 percent in each category.

(2) All senior reactor operator license applicants shall take the reactor operator examination, an operating test, and a senior reactor operator written examination with a new category dealing with the theory of fluids and thermodynamics, a time limit of seven hours, and a passing grade of 80 percent overall and 70 percent in each category.

(3) Applicants for operator licenses will be required to grant permission to the NRC to inform their facility management regarding the results of examinations.

I.A.3-4

Task I.A.3 May 1980 (4) Simulator examinations will be included as part of the licensee exadination.

Specific requirements related to requalification programs include:

(1) Contents of the licensed operator requalification program shall be modified to include instruction in heat transfer, fluid flow, thermodynamics, and mitigation of accidents involving a degraded core.

(2) The criteria for requiring a licensed individual to participate in accelerated requalification shall be modified to be consistent with the new passing grade for issuance of a license.

(3) Requalification programs shall be modified to require specific reactivity control manipulations.

Normal control manipulations, such as plant or reactor startups, must be performed.

Control manipulations during abnormal or emergency operations shall be walked through and evaluated by a member of the training staff.

An appropriate simulator may be used to satisfy th require-ments for control manipulations.

b.

Implementation:

New examination requirements for operating reactors will be effective May 1,1980, and for applicants for operating licenses require-ments must be satisfied before fuel loading.

By May 1,1980 requalification programs must include instruction in heat transfer, fluid flow, thermodynamics, and mitigation of accidents involving a degraded core.

The grading criteria for accelerated requalification shall apply to all annual requalification exams conducted after March 28, 1980.

Requalification programs must be modified by August 1, 1980 to require specific reactivity control manipulations.

Renewal applications received after November 1, 1980, must reflect compliance with the new requalification program.

After May 1, 1980 applicants for operator licenses will be required to grant permission to NRC to inform their fac,lity managemut regarding results of examinations.

The requirement to include simulator examina-tions as a part of the licensee examination will apply by June 1, 1980 to applicants where a simulator is located at the facility.

Starting in FY81, simulator examina-tions will be conducted as part of the licensee examination for applicants where I.A.3-5

Task I.A.3 May 1980 simulators are not available at the facility, depending on availability and suitability of simulators.

c.

Resources:

$100,000 per plant for initial implementation and $100,000 per plant per year for recurring costs.

2.

Operator licensing program changes:

No licensee action is required other than reporting operating performance after requirements are developed.

3.

Requirements for operator fitness:

This is a Decision Group D item.

4.

Licensing of a"

.i.ional operations personnel:

Licensee action is to be determined.

5.

Establish statement of understanding with INP0 and DOE:

This is a Decision Group D item.

D.

OTHER ACTIONS:

None.

m

)

E.

REFERENCES President's Commission Report:

Items A.4.a, A.5, A.8.b, 8.1.a, C.1, C.2, C.3.a and C.3.d President's Response dated December 7, 1979:

Proposal B.1.c, B.1.f, C.l.a and C.1.b Other:

NUREG-0585, Recommendations 1.4(2), 1.4(7), and 1.8 NUREG-0616, Recommendation 2.4.2 NUREG/CR-1250, Vol. I, pp. 105, 110 and 146; Vol. II, Part 2, pp. 423, 424, 458, 612, Part 3, pp. 854 SECY-79-330E, Qualifications of Reactor Operators, Recommendations 8, 10, 11, 12, 13, 14, 16 Memorandum from J. M. Allan, NRC Region I, to N. C. Moseley, October 16, 1979,

Subject:

" Operations Team Recommendations-IE/TMI Unit 2 Investigation" Recommendations C.2.b, C.2.c, C 3.c, 0.3 1.A.3-6

Task I.A.3 May 1980 Memorandum from J. M. Allan, NRC Region I, to J. H. Sniezek, September 28, 1979,

Subject:

"IE/TMI Radiological Investigation Team Recommendations for "Long-Term" TMI Improvements and/cr For Other Power Reactor Sites" Recommendations 2.1, 23 I.A.3-7

Task I.A.4 May 1980 TASK I.A.4 SIMULATOR USE AND DEVELOPMENT A.

OBJECTIVE:

The objective is to establish and sustain a high level of realism in the training and retraining of operatcrs, including dealing with complex transients involving multiple per.nutt.tions and combinations of failures and errors.

Another overall objective is to improve operators' diagnostic capability and general knowledge of nuclear power plant systems.

B.

NRC ACTIONS 1.

Initial simulator improvement.

a.

==

Description:==

(1) Short-term study of training simulators:

NRR and RES will collaborate on a short-term study to collect and develop corrections for the presently identified weaknesses of training simulators.

The short-term objective is to establish and sustain a higher level of realism in the training of operators, including dealing with transients, where such gains can be quickly made.

In the study, explicit consideration will be given to the programmatic views of Admiral H. G. Rickover in his statement to the Congress on May 24, 1979, and his amplifying remarks in his memorandum to Chairman Ahearne dated December 14, 1979.

(2) Interim changes in training simulators.

Based on the results of the short-term study described above, study NRR-80-117, " Requirements for Operator Licensing" (Item I.A.2.6), and the proposed regulatory guide on simulators (Item I.A.4.2), NRR will require that specific weaknesses be corrected in the simulators used to train licensed operators.

Subject:

" Operations Team Recommendations-IE/THI Unit 2 Investigation" Recommendation C.2.c I.A.4-7

ENCLOSURE 1 PART B LONG RANGE RESEARCH PLAN The following research needs are aimed at impre ting the technical basis for operator licensing requirements:

TASK I OPERATING PERSONNEL AND STAFFING A. Objective:

Complex transients in nuclear power plants place high demands on the operators in the control room.

Conduct research that will help to assure that concetent individuals capable of responding to off-normal conditions are on duty at all times.

B. Research Needs 1.

Job Task Analyses a.

==

Description:==

Analysis of the operator tasks in a nuclear power plant control room is necessary to address personnel qualifice"ons and training, staffing, operating orocedures, and improved technology to assist the operator in safety-critical functions.

In-depth job task analyses will be conducted to describe the skills and knowledges essential for the tasks performed by control roon personnel, b.

Schedule:

To begin in FY'81.

Results due FY'83, c.

Resources:

NRR 0.1 PSY FY'81

- 0.4 PSY FY ' 82 0.2 PSY FY'83 RES 0.1 PSY FY'81 0.4 PSY FY'82 0.2 PSY FY'83 Contract assistance required:

100K FY'81 400K FY'82 200K FY'83 2.

Personnel Oualifications a.

==

Description:==

Investigate methods to assure that safe and competent operators and senior operators are in charge of the day-to-day operation of nuclear power plants.

This will include the validation of present and proposed require-ments and procedures for op erator selection including use of standardized tests and screening interviews.

Evaluation of similar procedures and practices currently used by agencies such as D0D, FAA, etc. in personnel screening may provide guidance for standards, b.

Schedule:

2 years; possible starting date FY'82.

c.

Resources:

NRR 0.1 PSY RES/SD 0.2 PSY RES Outside contracts ($300K) 3.

Effects of Post TMI requirements on Operators.

a.

==

Description:==

In coordination with INP0, develop a methodology and conduct a comprehensive survey to ascertain

. the turnover rate of licensed plant personnel and the associated causative factors.

Of particular interest are job stress related factors resulting from post TMI requirements and their impact on job performance and satisfaction of licensed plant personnel.

b.

Sciredule:

1 Year; startir.g in FY'82 - Pending application of post TMI requirements.

c.

Resources:

NRR-OLB 0.1 PSY RES-Contract-INP0 (35-50K) 4.

Operator Performance a.

==

Description:==

An approach will be developed to provide assurance that candidates for operator and senior operator licenses maintain an appropriate level of performance of duties. Methods and criteria for measuring satisfactory job performance and operator reliability should be deter-mined.

If feasible, a non-intrusive method for identifying serious degradation in job performance due to job-related stress will be developed.

b.

Schedule:

May await results of job task analysis (See Task II.P.1), due by FY 83 for control room personnel.

c.

Resources:

RES Contracts 200K RES 0.2 PSY

TASK II EDUCATIONAL AND TRAINING RE0VIREMENTS A.

Objective:

As a result of the TMI-2 accident, increased education, training and experience requirements for operators, senior operators, and supervisors have been proposed to inprove the cartbility of personnel to perform their duties and particularly to respond to off-normal plant operations.

There is a need to validate these requirements and to formulate alternative courses of action where appropriate.

B.

Research Needs

1. Validation of Present Educational and Training Requirements.

a.

==

Description:==

This effort will be focused on performance of job / task analyses to be performed in coordination with INP0 to identify performance objectives of the operators' duties.

Initially, a generic, job / task analysis will be required for both normal and emergency duties of operators, senior oper-attrs, supervisors, and shift technical advisors, b.

Schedule:

INP0 task analysis underway (12/1980).

Results for licensed, control room personnel due FY 83; for control room support and maintenance personnel FY 84.

Fur

.g is from D0E.

c.

Resources:

DOE Contracts 500 K FY 81 - 82 500 K FY 83

. 2.

Guidelines for Improved Education and Training Requirements a.

==

Description:==

NRR will develop criteria and objectives tc, De met by training programs and to justify training curricula.

These training objectives will provide assurance t!,at licensed personnel are capable of rarrying out safety-related functions effectively.

The preferred method of accomplishing this goal is a position task analysis in which tasks perfo,ued by each person are defined, and the requisite skills and know-ledgts for the tasks are identified (See Tasks I.B.1 & II.B.1).

Based on this task analysis, a consistent set of training, educatien, and experience objectives will be developed for positio7s of reactor operator, senior reactor operator, sh.'ft zechnical advisor and shift supervisor.

Education equivalency requirements shculd be defined where appropriate for other operating personnel.

b.

Sct'dule:

Started in FY El current initial effort underway.

Comple' ion date dependent on performance of II.B.1.

Desults for licensed, control room personnel due by FY 83; for controi room support and maintenance' personnel by FY 84.

c, Resources:

NRR-lLB

.5 PSY - FY'82 1.5 PSY FY'83 RES:

Outside Cont, acts-200K RES:

0.2 PSY

TASK III OPERATOR LICENSING EXAMINATIONS A.

Objective:

Increased emphasis on operator candidate qualifications underscores a need for alternative examination methods.

The proposed requirement for the NRC to administer requalification exam-inations on an annual basis would cause an enormous increase in the workload of examiners.

There is need to validate the current exan-ination process ar' i find more efficient examination technioues.

Alternatives should be considered in requalification exanination reqJirements.

B.

Research Needs 1.

Exant auon validation a.

==

Description:==

Critically evaluate the operator license examination process with the objective of validating that the techniques employed meet the educational objectives as determined in Task II.B.2.

Conduct controlled studies to establish the correlation of exanination with measures of satisfactory job performance as identified in Task I.8.3.

Determine the feasibility of alternative methods of written examinat-lons, including use of objective format and scoring criteria.

In considering alternative techniques, determine degree cf 39phasis appropriate for the oral, written, plant walk-through, and simulatcr portions of both initial and requalificatina exams.

. b.

Schedule:

Depends on developing criteria for neasuring satisfactory job performance (see Tas( T.B.3),

due FY 83.

Pilot study in FY 81 - NUREG/CR 1750 out for comment.

Anticipated results by FY 84 c.

Resources:

NRR

.5 PSY - FY'83 RES:

Contract Resources

$175K RES:

0.2 PSY 2.

Improved Examination Methodology a.

nescription:

Determine the feasibility of usirig standardized format for oral, plant walk-through, and simulator examinations.

This could be accomplished ?y developing an examination check-list or questionnaire protocol which would be anenable to quantitative scoring of applicants knowledge and performance.

Improved examination format and methods would foster inter-and intra-examiner reliability and facilitate validation of examination scores with on-the-job performance criteria, b.

3chedule:

Depends on Task III.B.I.

Anticipated results by start of FY 84.

c.

Resources:

DHFS

.1 PSY - FY'82

.1 PSY - FY'53 RES-Contract assistance 75K FY 83 PES:

0.1 PSY FY 83

ZASK IV THE USE OF SIMULATOPS IN TRAINING PROGRAMS FOR NHCLEAR P0WEP rLANT OPERATORS AND SENIOR OPERATORS A.

Objective:

ihe objective is to achieve and mair,tain a high degree of realism in the trcining cad retraining of operators, thereby thereby improving their diagnostic skills, as well as their general knowledge of nuclear power plant systems.

The use and further development of sinalators would be particularly beneficial in training and requalifying applicants to deal wita complex transients which involve various constellations of errors and component mal-functions. The TMI accident has revealed a need to upgrade train-ing simulators which has been partially addressed through hardware /

sof tware modifications in some sectors of private industry.

Draft Reaulatory Guide RS 110-5, " Nuclear Power Plant Simulators for Use in Ope ator Training," provices guidelines for considerable enhancement of simulator capabilitit..

Fowever, the guide neither confronts the issue of accurately simulating 2 phase flow conditions, nor does it address what capabilities are necessnry for effective training. Therefore, the objective of any proposed research program should be to address these specific needs as well.

In light of these considerations, such research objectives could orocably best be accomplished in 2 stages.

B.

Research Needs 1.

Stage 1 - Assessing Simulator Capabilities a.

==

Description:==

Research on training simulators, will be perfomed to systematically establish the degree of sintlator capability required to insure adequate training for conditions resulting in or from complex transients, including those events that can be characterized as abnormal 2 phase flow conditions.

Accident sequences and risk analyses will be reviewed to determine which permutations of component malfunctions and operator errors can be accurately simulated.

To insure that the simulators effectively reflect these events, advanced codes will be employed to compute the actual physical responses of plant systems during these conditions.

Cooperative work with FAA is envisioned, b.

Schedule: Work underway in FY 81 - ORNL (with Memphis State, General Physics Corp.) initial assessment of sim-ulator capability and use (NUREG/CR-1482); Plant Status Monitoring Study underway - INEL.

c.

Resources:

RES - contracts ORNL, GP 250K RES:

0.3 PSY 2.

Sinulator Experiments a.

==

Description:==

Experiments will be designed and implemented that can yield data on operator error rates in controlled settings providing a necessary data base upon which an evaluation of the effectiveness of proposed changes can be

made, b.

Schedule:

Initial effort FY 81, NUREG/CR-1278 complete.

Research on training simulators. Work underway - ORNL c.

Resources:

NRR 0.2 PSY FY 82 SD/RES 0.4 PSY Contract 300K 3.

Stage 2 - Upgrading and Further Development a.

Advanced Simulator Studies:

Due to the technological upgrade of simulators to comply with proposed standards and guide-lines, experiments will be designed and implemented to.ssess the following:

1) prediction of plant response and checkout of emergency procedures; 2) plant and operator response to define non-linearities affecting safety; 3) effectiveness of simulations; 4) alternative simulator concepts.

b.

Schedule:

Advanced Simulator Studies:

effort to be initiated

- Ff'82 and completed by end of FY'83.

c.

Resources:

RES/SD 0.4 PSY FY 82 0.4 PSY FY 83 NRR a.0 PSY FY 83 RES contracts - FY'82 250K FY'83 250K

ENCLOSURE 2 PEVIEW 0F FOREICN OPERATOR PRACTICE

2 REVIEW 0F FOREIGN OPERATOR PRACTICE 1.

Responsible Organization:

OPE Task Leader:

G. Eysymontt and J. Miihoan End Date:

July 15,1981 2.

Statement of Problem

Background:

The NRC is considering amending its regulations to inprove and strengthen the criteria for issuing a license to reactor operators and senior reactor operators.

The amendments will focus on requirements for operator education, training, and experience; requirements for use of simulatorsin operator training; requirements for maintaining operator proficiency; and NRC conduct of initial cperator examinations and requalification examinations.

Information on operator practice in other countries could be highly bcneficial to NRC's assessment of its own regulations.

3.

Plan for problem resolution:

A questionnaire has been prepared for transmittal to other countries.

Tne questionnaire is a means by which the NRC can be specific with regard to the type of information that could be helpful in assessment of NRC regulations.

By mid February 1981, the Office of International Programs will transmit the questionnaire to the following countries:

Japan, France, Sweden, Switzerland, Spain, UK, FRG, Italy, Korea, the Netherlands, Taiwan, Belgium, Finland, Mexico, Argentina, Canada, and India.

2-The t!RC will request that responses to the questionnaire be completed by April 1, 1981. A collation of information from responses to the questionnaire will be complete.1 by mid July, 1981 and forwarded to the Commission and cognizant staff offices for consideration in developing amendments to 10 CFR Part 55.

(The time between receipt of responses and the completion of the collation considers the time to obtain translations and the time to rev1ew and collate the supplied information.)

4.

Organization involved and manpower estimates:

OPE: 1 person month IP:

1 person month (this includes manpower estimate to obtain translations of foreign country responses.)

5.

Contract assistance:

Contract assistance to review the supplied information should not be required.

Foreign travel to obtain information is not contemplated.

6.

Interaction with outside organizations and the topics for interactions:

a.

It1P0 - Pesults of the collation of information on foreign practice will be provided to It4P0.

This information may be useful to INPO programs.

b.

International Atomic Energy Agency - Results of thr, collation of informatipn will be supplied tc the IAEA Tennnical Review Committee on Operations.

The collation of information may be useful in revision of IAEA Safety Guide ';G-01, " Staffing of fluclear Power Plants and the Recruitme it, Training and Authorization of Operating Personnel.

, c.

NEA/INP0/NRC Specialist Meeting on Nuclear Power Plant Operators -

Selection, Training and Support During Abnormal Events.

The meeting to be held October 12-14, 1981 will deal with the selection, training and licensing of nuclear power operators from the standpoints of both utilities and regulatory bodies.

The results of the collation of information will be made available t.. INP0 and NRC staff participants for their use during this meeting.

7.

Identification of potential problems tnat could significantly n.'odify the program or delay its completion:

Delay in receipt of inforination from foreign countries.

a.

b.

Delay in sotaining translation of responses to questionnaires.

c.

Incomplete responses to questionnaire which may necessitate additional effort to obtain information.

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