ML19256B692

Training & Certification of Met Ed TMI-2 Licensed Personnel

ML19256B692
Person / Time
Site:	Crane
Issue date:	04/07/1978
From:	Metropolitan Edison Co
To:
Shared Package
ML19256B685	List: ML19256B684 ML19256B686 ML19256B687 ML19256B688 ML19256B689 ML19256B690 ML19256B691 ML19256B692
References
TASK-TF, TASK-TMR G-712-9.9-2, PROC-780407, NUDOCS 7908230277
Download: ML19256B692 (47)

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t TRAINING & CERTIFICATION OF METROPOLITAN EDISON COMPANY THREE MILE ISLAND UNIT LICENSED PERSONNEL The following is a succary description of the training and certification relevant to Three Mile Island Unit II operation for personnel in the following job classifications:

Classification License Recuirer.ent I.

Control Roon Operator

- Reactor Operator (RO)

II.

Shift Foreman Senior Reactor Operator (SRO)

III.

Shift Supervisor Dual Unit Senior Reactor Operator (SRO)

IV.

Supervisor of Operations - Senior Reactor Operator (SRO)

V.

Unit Superintendent

• Senior Reactor Operator (SRO)

The information provided is based on documentation retained by the TMI Training Depart =ent.

The extent of an individual's participation in the various programs outlined may vary according to the individual's previous experience, prior academic / technical training, and date of selection or appointment to a particular job classification.

• Unit Superintendents are not required by regulation to hold SRO Licenses, however, it is Co=pany Policy for individuals assigned to this position to obtain an SRO License.

119 i 9 o85-j f,ypy 3 3,377

INDEX Pace I.

Control Roon Operator (CRO) Training and Certification 2

I.A Auxiliary Operator Training 3

I.B

" Cold" License Training 4

I.C

" Hot" License (Replace =ent Operator) Training 8

I.D Control Rocm Operator Certification 12 I.E Reactor Operator Requalification 13 II.

Shift Foreman Training and Certification 14 II.A Previous TMI-l SRO Licensees 15 II.B SRO Licensees from Other Reactor Facilities 18 II.C Selectees From Initial THI-2 CR0 staff 21 III.

Shift Supervisor Training and Certification 23 IV.

Suoervisor of Onerations - Unit II 26 V.

Unit Superintendent V.A Unit Superintendent: Certification and Training 27 V.B Unit II Superintendent - Technical Support:

Certification and Training 28 - TMI-2 FSAR, Section 13 2 Metropolitan Edison Operator Requalifi-cation Program" - 10 CFR 55 " Operators' Licenses" Reference 1 - ANSI N18.1-1971 " Selection and Training of Nuclear Power Plant Personnel" Reference 2 - ANSI /ANS-3 1-1978 " Selection and Training of Nuclear Power Plant Personnel" 1919 086

-l_

e 8

I.

Control Roon Operator (CRO) Training and Certification Certification of CR0 qualification is achieved through NRC examinations, successful coupletion of which results in operator licensing by the NRC.

Training to ensura operator qualification prior to application for operator licensing will include Auxiliary Operator training and either

" Cold" (prior to initial core fuel load) or " Hot" (subsequent to initial, criticality) operator licensing programs. Replacenent operator training is also accomplished using the " Hot" license training program.

Operator proficiency and certification are naintained through the licensed operator requalification progran and periodic (annual) requal-ification exaninations.

I.A Auxiliary Operator Training With but 1 exception, all of the initial Control Room Operator staff at TMI-2 were graduates of the U. S. Navy nuclear training program with several years of operating experie.. on naval nuclear propulsion plants.

All were initially e= played as Auxiliary Operators-A-Nuclear.

In this classification they participated in a tranining program which typically included the following:

l.

Mathematics (160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br />) 2.

General Science (80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />) 3 Atomic & Nuclear Physics (240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />) 4.

Reactor Physics (200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />) 5.

Radiation Protection (160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br />) 6.

Core Performance (80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />) including:

a.

Ther=odynamics b.

Fluid Flow c.

Core Thermal Perfor=ance d.

Reactor Materials 7.

Plant Chemistry (80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />) 8.

Instru=entation and Control (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />) 9.

Plant Operation (30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />)

This training was conducted using the " Nuclear Power Preparatory Training" program developed by NUS Corporation of Rockvill, Md.

Initial Auxiliary Operator training also included approxi=ately 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> of trainin,g on TMI-l systems.

I.B

" Cold" License Training The content of a " cold' license training program is defined by ANS 3.1 (for=erly ANS 181) with additional guidance and classification provided in section 13 2 of the TMI-2 FSAR. The initial TMI-2 staff " cold" RO license traning program was reviewed with and approved by the Operator Licensing branch of the NRC with respect to compliance with the estab-lished standards. The requirements were met by participation in the following programs:

1.

Unit II CR0 Training Program Math Review (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) conducted by TMI Training Department.

a.

b.

Reactor Theory (104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />) conducted by IMI Training Depart =ent.

c.

TMI-2 Systems (144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br />) conducted by TMI Training Depart =ent and TMI-2 Shift Foremen.

d.

TMI-l Control Room Observation (160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br />) 2.

Penn State University Training Program Console experience, startup experience and experimentation at a.

the PSU TRICA research reactor facility (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />).

3.

TMI-2 Cross-License Training a.

TMI-2 Systems (75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />) 4.

TMI-2 on-the-Job Training for CR0 Candidates Guided self-study on TMI-2 systems and their respective sections of:

Burns & Roe System Descriptions a.

b.

TMI-2 FSAR f}'

c.

EdI-2 Standard Technical Specifications 89 d.

TMI-2 Procedures e.

Burns & Roe Drawings & Prints (Totaling 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per individual) 5.

Babcock & Wilcox Simulator " Cold" License Training a.

Classroom instruction (180 hours0.00208 days <br />0.05 hours <br />2.97619e-4 weeks <br />6.849e-5 months <br />)

(1) Plant fluid systems and components (2) Heat transfer (3) Reactor physics (4) Control / protective systems (5) Instrumentation (6) Normal and emergency procedures b.

Simulator Operation '100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />)

(1) Plant startup/ shutdown (2) Power operation including load changes (3) Abnormal and emergency procedures (4) Plant operation with unannounced casualties c.

Examinations (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />)

(1) Start-up exams (2) Operating and oral exams (3) Simulated NRC written exam 6.

Technical Specification Review Program (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />)

Review of updated TMI-2 Standard Technical Specifications a.

b.

Abnormal /E=ergency procedures c.

Instrument / Control review d.

Case History of other plants

()i?

090 7

Babcock & Wilcox Simulator Refresher Training a.

Classroom instruction (20. hours)

(1) Plant control and response b.

Si=ulator Operation (20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />)

(1)

Start-up (2) Turbine / Reactor Trip (3) Power Operacion with unannounced casualties 8.

Independent Audit of Operator Qualification General Physics Corporation, Columbia, Maryland was contracted to perform an independent audit of potential licensed operator weaknesses through in-depth oral examination on an individual basis. Any weak areas identified could then be e=phasized in the Pre-License Review Program.

9 Pre-License Review Program (80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />) a.

Reactor Theory b.

Instrumentation and Control c.

Standard Technical Specifications d.

Fuel Handling e.

Normal / Emergency Procedures f.

Environ = ental Technical Specifications g.

Safety / Emergency systems h.

RCS chemistrv

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1.

Health Physics review j.

Radiation E=ergency Plan 10.

Additional In-Plant Experience In addition to the for=al classroom and On-the-Job training programs already discussed, TMI-2 operations personnel have received signi-ficant experience through participation in the following:

System testing and turnover to Metropolitan Edison Company from a.

General Public Utilities Service Corporation.

b.

TMI-2 Hot Functional Testing c.

TMI-2 Low Power Core Physics Testing d.

TMI-2 Escalation to Power 11 Company Administration Examinations These included both oral and written comprehensive examinations similar in nature to those administered by the NRC.

The results of this final check of operator qualification were used in reco==ending individuals to the NRC for examination and licensing.

I.C

" Hot" License (Replace =ent Operator) Training 1.

" Hot" license training and experience require =ents are also-specified in ANS 3.1 (formerly ANS 18 11 and the IMI-2 FSAR. Candidates for

" Hot" licensing programs are selected either from the fully qualified Auxiliary Operators-A-Nuclear at the station or from off-site appli-cants with the requisite experience and qualifications. In either case, the " Hot" license replacement operator candidate will have a' minimum of two (2) years of operating experience at a nuclear recctor facility.

Once designated as a " Hot" license candidate and assigned to the position of Control Room Operator (CRO), the individual enters a training program. This program consists of:

Specific self-study assignments a.

b.

Oral checkouts in which the individusi actually performs or simulates performing certain evolutions c.

Written exam' nations i

d.

Oral examinations and e.

Classroom sessions 2.

The replace =ent operator program provides in-depth coverage of all areas specified in ANS 3 1 and the TMI-2 FSAR over a nine (9) month period. (Note: This program is cocparable to the TMI-l Replace-ment Operator Program). These areas include:

a.

Reactor Theory b.

Features of Facility Design 093 c.

General Operating Characteristics d.

Instrumentation and Control Safety and Emergency Systems e.

f.

Standard and Emergency Operating Procedures g.

Radiation Control and Safety 3

Adminsitrative guidelines for the conduct of this program to ensure operator proficiency prior to application for NRC licensing are as follows:

Upon being advanced to CRO, the individual will fall i==ediately a.

into the Shift organization as it exists at the time. Two (2) hours, as a minimum, of each day on shif t will be specifically devoted to training. The individual will be provided with a desk or other suitable place to study in the Control Room area. The two (2) hour period will occur at a definite time of each day on shift insofar as practical.

b.

While on shift, the individual receives a series of preprogra==ed written assignments. The individual is administered written and oral examinations every 3 and 6 weeks respectively. The written tests will be corrected and returned. Errors and weak areas will be covered with the individual, and reassigned. Weak areas on written and oral examinations will be covered with the individual.

Failure of a written exam or oral exam will be discussed with the individual and a retest will be administered on the =aterial.

Additionally, the CR0 will be required to complete a Practical c.

Evolutions Sheet. This sheet will be completed either during the individuals' daily training period, or during other, times

while on shift as situations dictate. Most of the items involve performing evolutions, simulating performing evolutions, and understanding and being able to explain while simulating or performing. The individual's Shift Supervisor, Shif t Foreman, an SRO Licensed individual, or (in specifically designated cases) the licensed Training Coordinator may sign the practical evolution sheet. Assignments detailed in paragraph b. above, on which written and oral tests kill be given, will come largely from items on the Practical Evolution Sheet, with some assign-ments specifically incer.a'd to obtain signatures on this form.

Checkouts for items on the Practical Evolution Sheet which cust be si=ulated will be conducted in front of the Control Room Consoles and Panels, with the individual being required to point ta specific ite=s and controls. The checkout must be satis-factory prior to a signature for the evolution. The evolutions are assigned a point value to track the progress of an individual through the nine (9) conth program.

d.

To aid the individual in the training assignment completion, the CR0 may come off shift to attend lectures on specific topics, listed below, as determined by the Supervisor of the Training Depart =ent and the Supervisor of Operations.

(1)

Reactor Theory 1 day - 1 week (2)

ICS Review 1 day - 1 week (3)

Simulator 1 week - 2 weeks (4) Health Physics Review 1 day - 1 week (5) Refueling Review 1 day - I week These off shift lectures should aid the individual in obtaining signatures on the Practical Evolution Sheet.

The first 90 days of the CR0 Training Program are designated e.

as a Probationary Period during which the individual will be evaluated. At the end of this 90 day period, the Shift Supervisor, Supervisor of Operations and the Supervisor of Training will recommend whether or not the individual should continue in the program.

f.

Prior to the co=pletion of the 9 month time period for the pro-gram, the CR) will be given a comprehensive written examination approved by the Supervisor of Operations and the Supervisor of Training. The results will be available for review by the CRO. Additionally, within the Training Program time period, the CR0 will be given a comprehensive oral examination by an SRO licensed individual designated by the Supervisor of Oper-ations. Any examination failed, written or oral, will be reviewed with the CRO.

g.

If the CR0 has not successfully completed the program within 9 months, and fails either the written and/or the oral examin-atton, the individual vill be returned to the position held prior to being advanced to CRO.

If the individual successfully completes the training program within 9 months, and fails either the written or oral examination, a re-exam will be considered based upon an evaluation by the Supervisor of Oper-ations and the Supervisor of Training.

If the individual successfully completes the training program within the nine (9) months and passes the final cocprehensive written and oral examinations, that individual may be recommended for exacination by the tiRC and subsequent R0 licensing.

1919'096

I.D Control Rocm Operator Certif.' cation The NRC's issuing of Reactor Operator Licenses constitutes official certification of Control Room Operator personnel to operate the reactor facility on which the RO license was achieved.

)h I.E Reactor Operator Requalification The philosophy, content and condu t of the training program designed to maintain licensed operator qualification and proficiency is described by the TMI-2 FSAR, Chapter 13, Section 13 2.2 " Metropolitan Edison Operator Requalification Program". This is provided as Attach =ent 1 e

191-9 096 13 -

II.

Shift Foreman Training and Certification As with the reactor operator level training and certificati'on dis-cussed in Section I of this report, certification at the senior reactor operator (SRO) level is also achieved through satisfactory completion of NRC examinations. Certification is maintained by participation in the operator requalification program and satisfactory completion of the atnual

~

evaluation axaminatian.

Training to ensure SRO qualification prior to application fr-c operator licensing is accomplished through the administration of programs which comply with the requirements of ANS 3.1 and the EdI-2 FSAR, and which have been approved by the NRC.

Personnel selected who currently fill shif t foreman positions for TMI-2 can be classified as I.;ving come from any of three slightly different backgrounds.

A.

Individuals who had achieved and =aintained SRO lice.4eu on TMI-l B.

Individuals who had achieved SRO licenses on other reactor facilities C.

Individuals selected from the initial group of TMI-2 Control Room Operator trainee's The training, qualification and certification of each of these groups is discussed in this section.

() { 9 h 17.A Previous TMI-l SRO Licensees 1.

These individuals were typically graduates of the U. S. Navy nuclear program. They had been initially enployed by Met-Ed as Auxiliary Operators-A-Nuclear and as such had received training as outlined in section I.A of this report.

2.

They had been promoted to shift fore =en on TMI-l and had all achieved and maintained SRO licenses on that unit.

3.

Upon assignment to TMI-2, they participated in the following portions of the " Cold" license training program:

a.

Unit II CR0 Training Program (270 hours0.00313 days <br />0.075 hours <br />4.464286e-4 weeks <br />1.02735e-4 months <br />) (participated as systems instructors - program as described in section I.B.1 of this report) b.

TMI-2 Cross-License Lectures (75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />) (as described in section I.B.3 of this report) c.

TMI-2 On-the-Job Training for SRO Candidates (300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />) (essen-tially as described in I.B.4 but modified to SRO level) d.

Technical Specification Review Program (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />) (as described in I.B.6 of this report)

Babcock & Wilcox Simulator Refresher Training (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />) (as e.

described in I.B.7 of this report) f.

Pre-Licensed Review Program (98 hours0.00113 days <br />0.0272 hours <br />1.62037e-4 weeks <br />3.7289e-5 months <br />) as described in sect. ton I.B.9 of this t2 port with the following additional training (18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />) for SRO candidates:

(1) Departure from Nucleate Boiling (DNB), DNB Ratio (DNBR) and hot channel factors (2) Soluble poison control (3) Liquid and gaseous radioactive releases (4) Administrative procedures (5) Standard Technical Specifications g.

Additional In-Plant Experience (1) Development of TMI-2 normal, abcornal and emer2ency pro-cedures (2) THI-2 system testing and turnover (3)

IMI-2 'iot functional testing (4) IMI-2 law power core physics testing (5) TMI-2 esc.alaccion to power h.

Company Administered Examinations (1) Both oral and written examinations at the SRO level, similar in nature to those administered by the NRC but emphasizing comparisons and differences between TMI-l and IMI-2.

(2) Results of these examinations were used in recommending individuals for final examination and subsequent cross-licen-sing by the NRC.

4.

Certification Accomplished by Company administered examinations as outlined

s..

below:

(1)

Comprehensive written examinations developed, administered and graded by the Company. Ihese were SRO level examinatione similar to those administered by the NRC which emphasized co=parisons and differences between TMI Units 1 and 2.

(2) The examinations, grading of the exams, and final results were reviewed and approved by the NRC.

01 (3) NRC a= mended their SRO licenses to include Unit 2 b.

Certification is maintained by participation in the licensed operator requalification program and satisfactory completion of the annual evaluation examinations as discussed in At*ach-nent 1.

o e

0 919 102 II.B SRO Licensees from Other Reactor Facilities 1.

These individuals were typically graduates of the U. S. Navy nuclear program.

2.

Subsequent to naval service and experience they had achieved SRO level certification (licensing) at other com=ercial power reactors.

3.

Upon selection and assign =ent to IMI-2 they participated in the fol'-

lowing training programs:

a.

Unit II cold license r ee-simulator training (80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />) including formal classroom instruction in the following areas:

(1)

Integrated Control System (2) Control Rod Drive (3) Non-Nuclear Instrumentation (4)

Reactor Theory (5)

Electrical Distribution (6) Reactor Protection System (7)

Standard and Technical Specifications (8) TMI-2 Fluid Systems b.

Babcock & Wilcox Simulator Training (80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />)

(1)

Classroom instruction (a) Reactor Theory (b)

Instrumentation / Control systems (2)

Simulator operation (a) Plant start-up/ shutdown (b) Power operation with unannounced casualties (3)

Start-up Certification

' g{9

\\

c.

TMI-2 Cross-License Training (75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />)

(1) TMI-2 systems classrbom instruction d.

TMI-2 On-the-Job Training for SRO Candidates (500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />)

(1) Essentially as described in I.B.4 but modified to SRO level TMI-2 Standardized Technical Specifications (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />) e.

(1) As described in I.B.6 of this report f.

Babcock & Wilcox St=ulator Refresher Training (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />)

(1) As described in I.B.7 of this report g.

Pre-License Review Program (98 hours0.00113 days <br />0.0272 hours <br />1.62037e-4 weeks <br />3.7289e-5 months <br />)

(1) As described in II.A.3.f. of this report h.

Additional In-Plant Experience (1) TMI-2 nor=al, abnormal and emergency procedure development and review (2) IMI-2 system testing and turnover (3) TMI-2 hot functional testing (4) TMI-2 low power core physics testing (5) IdI-2 escalation to power 1.

Company Administered Examinations (1) Oral and written examinat ons at the SRO level similar i

to those administered by the NRC.

(2) Results of these examinations were used in determining whether individuals vould be reco= mended for NRC licensing g' { Ok examinations.

4.

Certification Certification was achieved through successful completion of

a.

NRC licensing examinations and subsequent issuing of SRO licenses to operate TMI-2.

b.

Certification is maintained through participation in the licensed operator requalification program and successful co=pletion of the annual evaluation examination as described in Attachment 1.

a e

1919 105 II.C Selectees From Initial TMI-2 CR0 staff 1.

These individuals had completed the following training previously outlined in this report:

Section I.A. - Auxiliary Operator Training a.

b.

Section I.3.

" Cold" License Training 2.

Typically, they had been certified to operate the plant by successful completion of NRC licensing examinations at the RO level.

3 They had maintained this certification through participation in the licensed operation requalification program as described in Attach-ment 1.

4.

These individuals also attended a Senior Operator Review Program which provided additional training at the SRO level in the following areas:

a.

Procedure Review (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />) b.

Health Physics Review (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />)

Plant Characteristics (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />) c.

d.

Pland Design Review (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />) jgjg jQh e.

Reactor Theory Review (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />)

This program was administered pri=arily through guided self-study augmented by classroom instruction as necessary to achieve SRO level qualification.

5.

Sao level qualification was checked by Company administered examina-tions as discussed in Section II.B.3 1. of this report.

6.

Certification was achieved through satisfactory completion of SRO level examinations administered by the NRC and subsequent issuing of SEC licenses to operate TMI-2.

7.

SRO qualification and certification are maintained through parti-cipation in the licensed operator requalification program as described in Attach =ent 1.

191.7 107

~

III.

Shift Supervisor Training and Certification Shif t Supervisor _ must be certified at the Senior Reactor Operator (SRO) level for both TMI-I and TMI-2.

This is achieved through satisfactory completion of NRC approved examinations. Certification is caintained by participation in the operator requalification program and satisfactory completion of the annual evaluation exacination (Attachment 1).

Personnel selected for the position of Shif t Supervisor held SRO licenses for Unti I or Unit II or in the case of one individual, held a. current, dual SRO license. In addition, many of these individuals had graduated from the U.S. Navy Nuclear Power Program, and in all cases their experience met or exceeded the require =ents of ANS 3 1.

For initial dual unit staffing, a cross License Training Program was administered to obtain Unit II SRO licenses. The Shif t Supervisors received the following training or the eqelvalent:

1.

One hundred (100) hours of Cross License Training 2

One (1) week of Unit II Standardi:ed Technical Specifications Training 3

Twenty (20) hours of Turbine Controls Training given by Westinghouse Electric Corp.

4.

One (1) week of Unit II Si=ulator Training at B&W's Training Center in Lynchburg, Virginia.

5.

Two (2) weeks of Pre-License Review Training 6.

Unit II OJT Program 7.

Unit I Requalification Training Program (67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br />).

Periodic tests were given throughout the program to monitor the students' level of knowledge. At the conclusion of the program, a mock NRC examina-tion wc; administered with emphasis on Unit II Systems and differences between the Unit I and Unit II Nuclear Steam Supply Systets (NS SS),

Secondary and Balance of Plant Systems. Following successful co=pletion

~

of the above program and tests, a final company prepared qualification exam vac administered. The program docu=entation, exam and exam results were forwarded to the !iRC for approval.

This ;ulminated in those applicants already SRO licensed in Unit I having their license amended to include an SRO on Unit II.

Subsequent to " Cold" Licensing, a " Hot" Cross License training program was developed 'by the 'r

!ning Department to cross qualify SRO License holders frem either unit.

This program is approximately 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> in length and is predominantly a self-study course with periodic written and oral exams to monitor the individual's progress. Listed below are the major topics contained in the program.

1.

Technical Specification Training 2.

Unit Systems with e=phasis in unit differences a) Turbine Generator & Auxiliaries b) Solid, Liquid & Casecus Waste System c) Steam Systems (Main, Auxiliary, & Bleed) d) Cooling Water Systems (Primary and Secondary) e) Electrical Systems (Balance of Plant, Vital Power, and Diesel Generator).

f)

Emergency Safeguards Systems g) Reactor Coolant System h) Primary Volume Control Systems

1) Secondary Water Systems 3.

On-the-job training (oral checkouts by a Shif t Supervisor of various plant evolutions).

4.

Adcinistrative controls.

5.

Operator Requalification Program (Attachment 1)

The program culminates with the individual taking a written exam adminis-tered by the Training Department. The exam and results are reviewed and approved by the NRC. Approval by the NRC v111 then result in the indi-vidual's SRO license being ammended to include the other unit.

e 19i 9 ' l 10

IV.

Suoervisor of Ocerations - Unit II This individual is a graduate of the Navy Nuclear Power School. Folle.iing his service obligation, he graduated from college as a Chemical Engiaeer.

His com=ercial power plant experience co==enced as a Staff Engineer at the Saxton Experimental Corporation. During his tenure there he was awarded a Senior Reactor Operators license.

After transfer to TMI, he initially held the position of Nuclear Engineer-Unit 1. His next appointment was that of Supervisor of Operations Unit 1 He participated in a Cold License program and achieved an SRO license on Unit 1.

The general outline of this training program was as follows:

1.

Pressurized Water Reactor Technology Course by Babcock and Wilcox Co. - 1969 - (320 hrs.)

2.

Shift Fore =en Review Seminar - 11/24/71 (2 hrs /wk) 3.

Pressurized Water Reactor Simulator Orientation Course by Babcock and Wilcox - 1973 - (32 hrs.)

4.

PWR Simulator Training Program by Babcock and Wilcox Co., - 1973 -

(80 hrs.)

5.

Pre-licensing Review Program by Babcock and Wilcox Co., Ceneral Physics and NUS Corp. - 1973 - (204 hrs.)

6.

Various vendor familiarization programs (38 hrs.)

He was then appointed to his present position of Supervisor of Operations Unit II.

In this position he participated in the Startup and Test Program and achieved a " Cold" SRO license on Unit II by participating in training si=ilar in scope to that detailed in Sections II and III.

This person's total nuclear power plant experience is in excess of fif teen years.

<..*."'i 1919:lli h.

A.

Unit Superintendent: Certification and Training This individual's experience greatly exceeds the requirements of ANS

~

3.1. He is a U.S. Naval Academy graduate with twenty y, ears in the Navy Nuclear Power Program. This service inc!uded command of a nuclear submarine.

Certification of the Unit Superintendent position was achieved through successful ompletion of NRC examinations which culminated in the receipt of a Senior Reactor Operator License.

This training program was a modified " Hot" License Training Program.

The program was specially tailored to the needs of the individual, with special e=phasis on those areas in which the individual did not have prior experience, or expertise.

Specific areas of the program included but were not limited to:

a.

Specific self-study assignments

1) Systems Training

2) Reactor Theory

3) Integrated Control Systems

4) Radiation Protection

5) Fuel Handling Training

6) Technical Specifications b.

Si=ulator Training (280 hrs.)

Oral checkouts within the plant performing or simulating c.

performance of the evolution d.

Written examinations e.

Classroom lectures Approxicately 900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> were spent in for=alized t sining in the above program.

i919'i12 V.

B.

Unit II Suoerintendent - Technical Suenort: Certification and Training This individual has been an employee of Met-Ed for a period of ten years. He is a graduate Mechanical Engineer and a registered Profes-sional Engineer. He has ten years power plant experience and has been involved in various engineering duties at TMI over the past nine years. Previous positicus he?,d at TMI include Operations Engineer, Supervisor of Operations and Unit 'l Superintendent - Technical Support.

During the period of his assignment as Operations Engineer, he achi'eved a " Hot" SRO license in Unit 1 This was accceptished through a training program similar to that described in Sections I and II of this document. He has maintained his license current by meeting the require =ents of the Requalification Program (Attachment 1).

During his assign =ent as Unit I Superintendent - Technical Support he served as chair =an for the Unit 1 Plant Operations Review Committee.

Following his appoint =ent to Unit II Superintendent - Technical Support, he entered a program to achieve a dual unit SRO license.

.g l').2.2.2 P e-Planned Lectures 13.2.2.2.1 0:erational Re.-iev (CR) Lee'n:re Series During each year, personnel shall attend the Operational Reviev (CR)

Lectu e Series on the following basis:

(a) Licensed station ad 'nistratiVe and technical perscnnel vill participate in the OR Lecture Series as either students or instructors, except to the extent that their nor-a7 duties preclude the need for specific re-training in particular areas.

(b) 03 Lecture Series attendsnee is required of all licensed operators and senior operators who are nor-a'ly on shift assig =ents.

'~ne follov*.=g topjes shall be covered as a -ht-u= during the OR Lecture Series each year:

(a) Reportable Occurrences (b) Unit Modifications (c) Operating History and Proble=s (d) Procedure Changes kh j4 r

(e) Abnor-a7 And E=ergency Procedure Reviev (f) Technical Specificaticns (g) Major Operational Evolutions (such as refueling)

(h) Applicable portions of Title 10, Chapter I, Code of Federal Regulations (i) FSR Progran Material Additional topics which cay be presented include:

(but are not li=ited to)

(a) Cperational Q/A (b) Standing Orders (c) Operating -Experiences - Reactor Safety and other pertinent NRC publications.

Lectures sh be held en a continuing basis and consist of a -f f m of 60 scheduled hours per requalification progran cycle.

Credit for the classrocs pcrtion of the sd ator training progran relating to either LII Unit 1 or II may be credited toward the 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> of CR Lecture.

Attendance of all licensed perscnnel vill be recorded. Absences vf" be made up by reviening lecture =aterials and/or discussions with en-shift superviso y personnel or the technical staff.

The progras for each session vill be deter =ined by unit operations er pro-jected operations. Records of the topics covered in each. session vill be naintained by the Training Department.

periodic evaluation qui::es covering the content of the CR lecture series vill be ad-*M stered. De qui :es =27 be ad-*nistered in either the closed bcok or open book fcr=at, as classroc cr en-shift qui::es. If an unsatis-faa.tcry grade (less than 805) is received, ~ *eup sessions with assigned instructors vill be conducted. The nakeup session vill conclude when an cral evaluatien is satisfactorily conpleted. The centent of the quin vill

(

be different for RO cnd SRO license holders and vill re' lect the topic areas

(

end degrees of responsibility needed by the license holder. Examples of a"fne'se lectures nay be given en-shift by Shift Forecen or Shift Supervisors 13.2-7 A. 6k

( L-T-73 )

the =aterials to be used during the OR lecture series are:

(a) Unit records and logs (b) Pertinent con =unications to and from the URC (c) Unit procedures and changes (d) Test results

(

(e) Applicable training progra =aterials 13 2.2.2.2 Funda=entals an:1 Syste= Reviev (FSR) Prce-as During each year, licensed personnel shall participate in the Funknentals and Syste=s Review (FSR) Progra= based on their annual vritten er.'ni ation scores as identified in Section IV - Evaluations.

The FSR Progra

=ay consist of prepla-ed lectures, self-study assign =ents, possible tutorial sessions with designated te *a-f cal instructors, and evaluation quis:es. The study assign =ents and preplanned lectuies stil be in keeping with the license level of the individual license holder.

Individual study assign =ents, f4'~s, and video tapes vill consist of no = ore than 507, of the FSR Program.

4-Preplanned FSR lectures shall be scheduled in those areas where annual operator and senior operator written ern-f nations indicate that e=phasis in scope and depth of coverage is needed.

Any or all of the following topics may be included in a particular year's FSR Progra=:

(a) Principles of Operatica (b) Features of Facility Design (c) General Operating Characteristics (d) Ihstru=entation and Control (e) Safety and E=ergency Syste=s including unit / station protection syste=s (f) Nor~'1 and E=ergency Operating Procedures (g) Radiation Centrol and Safety For Senior Operators the FSR Progra= vill also include:

(h) Reactor Theory (1) Radioactive Material Handling, Disposal, and Hazards (j) Specific Operating Characteristic 3 (k) Fuel Handling a=d Core Parc=eters (1) k*ninistrative Procedures, Conditions and Li=itaticas Pe for-aace of FSR assign =ents vill be dete--4 ed through written evalte acn quizzes. These qui::es vill be specifically directed toward RO and SRO knculedge require =ents.

The quizzes nay ba ad 4"4stered in either the closed bock, or open bock for=at, as classroc= or en-shift quiz:es.

A satisfactory grade on the FSR evaluatica quis vill'be 807.

If a grade belov SOf is achieved by a license holder, a deficiency is assigned and the li-cense holder vill be assigned an accelerated requalification prog a= as per

• Section VI.

19f9115 13.2-8 A=.

6h (h-7-781

13.2.2.3 Cn-7ne-Job Traininz

- ~

During the two-year ters of his license, each licensed operator shM1 participate in en-the-job training which. has the following goals:

(

(a) Each licensed reactor operator or senior operator shall participate in a =inimu= cf 10 reactivity nanipulaticas as defined in this sec-tion of the requalification prog s=.

Reactor operators or senier operators licensed en both 55 Units can perfor= or supervise these,

reactivity =anipulations on either mit.

(b) Each licensed reactor operator er senior operator shall participate as appropriate, in applicable sur-sillance testing, systes checkout ana equip =ent operation based on license le'.el and relevant to the area of license responsibility.

(c) Each licensed reactor operator er senior operator shC' review precedura changes, unit mcdifications, technical specification '

changes, repcr:able occurrences and incidents, eith-r en-the-job or during sessiens of the OR Tecture series.3 Each licensed reactor operator shall "e-*pulate the unit controls to effect reasonable reactivity changes. Each licensed senior reactor operator sh,11 either =anipulate or direct the =anipulation of the unit controls to effect reasonable reactivity changes. Reactor operators or senior operators licensed on both SE Units can perfora or supertise these =anipulations of unit controls to effect reasonable reactivity changes on either unit.

Reactivity -*"4pulations which de castrate sV#11 and or fa=iliarity with reactivity centrol syste=s and which ara d4 ted to meeting on-the-job training vill include, but are not li=ited to:

(

l.

Power change of greater than 10% full pover with the reactor control statica in -' cal.

2.

Control red =anipulation fres suberitical condition to point of adding nuclear heat.

3 Boration and deboration maneuvers involving control red manipulation.

4.

Tarbine startup and shutdown.

5 Reactor trips and subsequent actions.

The participatics of licensed personnel in the on-the-job prog as vill be reviewed quarterly by appropriate supertisors to insure that ouerators participate in a variety of evolutions.

If diversity of operations is lac.%i:.g,.

specific assignments =g be made to ensure vide operator experience.

Incl.:ded in the folleving list are ena=ples of additional operation:

which may be considered in this category.

'~nese samples are not to be considered for reactivity =anipulation credit.

1.

Surveillance testing including a.

Contain=ent spray syste i

b.,

Safecy injectica

-k9 jh c.

Energency Diesel Generators d.

Chemical addition syste:

2.

Makeup and Purification Syste= Operatien

(

3 Decay Heat Renov11 Syste cperation

!.. Feedvater Sysee= Operatica 2

'Cnly these ch1nges, incidents, etc., which sre selected 57 the Supertiser of Operaticas or Supervisor of Training as pc.-inant to =it operacica.

3a~.m ny e.n.

ok 4-t i.O) s 1

~-

5 Reactor Coolant Systes 6.

Turbine Valve Testing 7

Pressurizer Operation 8.

Incore Monitoring Syste= Operation 9

Control Roca Calculations including a.

Heat balance b.

Quadrant tilt /i= balance / Rod withdrawal inde-c.

Reactivity balance 10.

Portable HP Instrument use.

Licensed personnef, whose joh assignments are not directly related to unit operations vill actively participate in control roos operation an average of k hours per =onth.

During this period these licensed personnel vill participate in whatever activities are in progress. Reactor operators or senior operators licensed on both TMI Units vill actively participate in, either unit's control roos operatien an average of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per conth.

A simulator may be used in meeting the requirements of this =ection. The use of a simulator to meet the on-the-job training section of the program also has been previously reviewed by the :iRC.

The following standards apply to the evaluation of on-the-job perfor=ance.

1.

Quarterly review of operator participation vill be made by the appropriate supervisors. The reviev =ust indicate a diversitf of experience. If this is not demonstrated, the operator vill be scheduled for additional operating experience.

2.

Quarterly review of reactivity control manipulations (RO) or direction (SRO) must show satisfactory progress toward the minimus of 10 oper-ations as defined in this section. If satisfactory progress is not indicated, an operator vill be assigned additional control roon operations or may acco=plish the required reactivity changes on a simulator.

3 Annual review of licensed personnel vhose job assign =ents are not directly related to unit operations cust show a ninimus of k8 hours of unit operation assignments per year.

If this is not co=plete, personnel vill be assigned to active control roos duty until the time is cade up.

A si=ulator may be used to couplete control room time. Reactor operators or senior operators licensed en both TMI Units 1 and 2 nust show a sinimus cf L8 hours of operations assignnents per year between the two units.

9 jh}h k

+

o 13.2-10 A2. 6h (L-T-78)

13 2.2.h Annual Evaluation Exa=inaticti Evaluaticas vill be conducted en an e---a' basis as follows:

(a) An annual written evaluation exanination vill be given to all licensed operators and senior operators prior to the co=pletion of each a-m-a' cycle. 1 l

(b) An annual oral. eval'uatien vill be W4-#stered to all licensed operators and senior operators pricr to ce=pletion cf each arcual cycle.1 l

The a-ual written evaluatica ex'~#natica v" be aF-*"4stered to all licensed personnel as set forth in the folleving guidelines:

1.

The ava-4 atica vill si=ulate the exa *-ation nor-ay ad 4 #stered by the Iinclear Regulatory C-4 =sion.

2.

Reactor Operaters vill take Sections A through G cf the e.va-4mation while the Senior Reactor Operators v'7 7 take Sections H through L and answer selected questions in See-tions A through G.

3.

The eva *-a-tion, eve-4 ation ansvers and a grading key vill be prepared in advance.

k.

The ex* *-ation results will be used to ide=tify specific FSR lecture series topics to be covered by each licensed individual during the subsequent annual requalifications prog en cycle.

5 The ev'-*-ation vill be *M 4-istered and graded by a = ember of the station technical staff, statica =anage=ent staff, trad-4 g department supervisor, or consultant.

6.

The persons responsible for the preparation cf the exa=inations and ansvers vill be given credit for passing the eva-4:ation.

The annual oral evaluation exa=1 cation, using a checklist, v4'1 be ad=inistered to all licensed persennel. The oral eva

• atien vill cover the folleving areas:

(a) action in event of abno.- conditions (b) action in event of e=ergency conditicns (c) response to unit transients (d) instrumentation signal interpretatien (e) procedure =cdification (f) unit modificatica (g) Techr,1 cal Specifications (h) 2:ergency plans 7.eactor cperators or senior cperators licensed en both TMI Units vill be g.ven a single annual written and cral evaluatica examination which covers d

both T:E Units.

h. k h

p. flb'

• S s-

.s

(

13.2-11 A=. ch (h_7-78)

The following standards apply to the annual evaluation examination:

1.

A license holder '.to scores higher than.805 in all sections of the annual vritten e; valuation vill not be required to parti,cipate in the F3R progrs=.

2.

If a license holder scores less than 80% of any section of the annual vritten exacination, the license holder vill participate in the FSR pro-gran related to failed sections.

3 If a license holder scored belov 80% on t o or more sections of the annual vritten exa=ination, the license holder vill be given an oral ex2=ination and evaluation by the Superrisor of Operations, Supervisor of Training, or l

other suitably qualified persons designated by the Unit Superintendent.

This exaniner vill, based on the results of his eva-f natica, -abe a reco=-

=endation in writing to the Unit Superintendent that the operator either (1) be relieved of his responsibilities and enter an accelerated training pro-gran or (2) be pe: litted to remain on shift while participating in the appropriate requalification F3R progras with suitable tutorial assistance.

k.

An unsatisfactory evaluation on the annual oral exa=ination vill require that discussions of deficiencies take place between the license holder and either the Supervisor of Operations, Supervisor of Training, or other l

suitably qualified person designated by the Unit Superintendent. A second oral evaluation ex'-Nation vill be aa,inistered.

If perfor=ance is again unsatisfactory, the license holder vill be relieved of responsibilities and placed into an accelerated requalification prog-am.

5 If an individual recieves a grade of less than 70$ overe ' on the annual examination it vill be -mdatory that (1) he be relieved of his licensed duties and (2) enter an accelerated requalification progra=. Upon (1) successfully passing a second vritten and oral examination and (2) certif-icatien of satisfactcn/ rating being sent to the NRC, the individual vill be returned to his licensed duties.

O e

g

' y.

(.

13.2-112 An. 6h

( L-7-73 )

I

13.2.2 5 Records

(

Records of licensed personnel perfor=ance on all vritten evaluation en 4%tions and qui::es shall be available for IEC er,-4-ation for the previous'two annual requalificatica cycles.

These records shall include:

{

1.

Examinatica and qui: questions 2.

Ansver cheets and Srade keys 3

Exasination papers and verk sheets Records of participation in all OR lectures and FSR prograds vill be available for ITRC review for the previous two annual requalification cycles. These records shall include:

1.

Attendance records 2.

OR lecture content 3

FSR assign =ent 4.

Absences a-d ~*eup sessions 5

Assic---nt check off lists 6.

Docu=ent review lists.

Records of annual oral evaluation exa=inations shall be ~~#e available for I'RC review for the previous two annual requalificatica

{

cycles.

Records of all on-the-job activities shall be available for IEC y

review for tha two years prior to license renewal applicatio-Nse t

records sh

ino'"da:

1.

Reactivity control ~"ipulation 2.

2 quip =ent operation 3

si-n1 at,r participation Requalificatien records covering the previcus two annual cycles vill be re=oved frc: the files following license renewal.

A sn--e/ record vill be =aintained en each license holder for the duration of his e=ployment.

e I.

13 2-12

.;=. G (h-7-TS }

13.2.2.6 Accelerated P.ecualification Fregra=

An operator who does not cicar deficiencie3 assigned due to performance belov standards en either the annual written er oral evaluation vill be relieved

(-

of responsibilities and enter a full time accelerated requalificatica program.

The progren duration and content will be dictated by the nature of the deficiency.

Progra= duration vill be deter =ined by individual performance.

voen the license holder is (1) able to satisfactorily pass en equivalent vritten or oral evs-# nation and (2) certification of his satisfactory rating is sent to the !!RC, he shall resune his on-shift responsibilities. During the period of accelerated requalification, attendance at the OR lecture series is required.

If the license holder is off-shift for = ore than h =cnths, Section 13.2.2 7 dealing with lengthy absences applies.

13.2.2.7 Four Menth Absence Prorram If a licensed person has not activel'/ carried out the functions of his license for a period in excess of four nonths, he shall:

(a) review all =aterial presented or scheduled to have been presented in the OR lecture series for the period of inactivity (b) be given an oral ev'~f nation en the applicable Section cf the OH lecture series and current unit status

' If perfoz=ancer on the oral evaluation is unsatisfactory, the individ"'1 vill be placed in an Accelerated Requalificatica Progrs= in accordance -ith Section 13 2.2.6.

Upon receipt of a satisfactory rating, the licensed person shall be certified by the Supervisor of Operations, Supervisor of Training or other suitably qualified person designated by the Unit Superintendent.

The certification of satisfactory rating vill be trans=itted to the IIRC and only after approval by the ?iRC shall the operator be returned to nor=al' licensed duties.

13.2.2.8 Iievl7 Licensed oeerators

!!ewly licensed operators shall enter the progren and participate in the annual pro ra= eycle upon receipt of their license.

u

ev operators receiving their ?!RC licecse less than six nonths prior to the annual evaluatica exanination vill be required to attend the appropriate CR ad FSR Progra=s but vill be excused fren taking the current annual evalua-tien eninination. Mcwever, he vill be respcnsible for taking all other annual evaluation examinations.

i 5

..N

. I

'l919 121 (

13.2-13 Ar. 6i r t

_m

.,6 13.2.2.9 Recualification prerren Mrinistration

/

The Supervisor of Training and his staff a e responsible for:

1.

Assigning instructors for the CR lecture series 2.

Dete-sining FSR assignnents for individual operators 3.

Maintaining and reviewing all records 4.

Assigning deficiencies, deter J.ning appropriate action to clear deficiencies and clearing deficiencies upen satisfactory cc -

pletion of assigned action 5

Arrenging accelerated requa' * "4-ation progra=s as may be necessarf 6.

Defining cral evaluatica procedures T.

SchM" ling necessarf sinulator time 8.

Prepare license applications forlicense renew _1 The Supervisor of Operations, Supertisor of Training, or other suitably qualified person designated by the Unit Superintendent is rerponsible for:

1.

Evaluatics of on-the-job perfor=ance of all; license holders 2.

Meeting with license holders who recieve unsatisfactory annual evaluation examination' grades 3

Certifying operator qualification when returning frc= a four conth absence free operation 4.

Constneting annual vritten evaluation eva-t atien, ansvers and grade key 5

Grading of the annual vritten ava-4 ation

.J

' d.t.

IYW f22

(

13.2-D A=.

6h (k-T-TS)

i ATU CEMENT II i

7(-

UNITED STATES NUCLEAR REGULATORY COMMISSION RULES and REGULATIONS TITLE 10, CHAPTER 1. CODE OF FEDERAL REGULATICHS-ENERGY PART OPER ATORS' LICENSES

~

Bb

~~

t GENERAL PROVISIONS AUTHORITY: The provisions or this Put 53

' thereto,

~

isa.ed madu uca.107, sei. os stas. 939. 94s; 41 N "Commissiod" m see-Nuclear Regulatory Comm,. e.ans 51:

Porpow, U.1C,. 2137. 2208. For the purpous or sec. 223. 63 ission or its s,,,

5s.as amaded:42 u1C. 2273. t ss.3 imwd 512 scope.

.ade, we.16ti es seas. 949.42 uic. 220e rit see.

duly authorized representatives.

35.3 t.icaw reqerements.

ss.4o inwed edu ucs is6. inr. os sua. 95s:42 (c) " Facility" means any production 55.4 cena,ucas UIC. 2236. 2237. secs. 202. 206. Pues. L 93 4)a.

facility or utilization facility as defined g3, Commua ions.

as sau.1244.1246; 42 u1C. 3:42,st4t in M 30 of tMs chpter.

(d) " Operator" is any individual EXE m ONs G: Nut AL PROvts!ONS who manipulates a control of a facility.

35.7 specine eumpeions.

An individual is deemed to manipulata a sin Additional requirements.

) 55.1 Purpose.

control if he directs another to manipul.

35.9 Exemphons from license.

ate a control.

LICENSE APPt.tCATIONS The regulations in this part establish (e) " Senior operator" is any in.

h procedures and criteria for the issuance dividual designated by a facility licensee ss.to Coniems or appsicmient

" of licenses to operators, including senior ~ under Part 50 of this chapter to direct

$ 3.18 Requirevnesta tor the approval or applica4 ion k operators, of facilities licensed pursuant g the licensed activities oflicensed o 35.12 Re.apphonoa*

N to the Atomic Energy Act of 1954, as e tors.

WR TTEN EXAMINATION AND OPERATING amended, or section 202 of the Energy g (f) " Controls" when used with TESTS Reorganization Act of 1974 and Part 50 m respect to a nuclear reactor means ap.

of this chapter; and provide for the terms Paratus and mechanisms the manipula-55.20 kop or enaminuions.

ss.2 Conian or opnuar rina nimiamion.

and conditions upon which the Commis.

tion of which directly affect the reac.

55.22.C e of waior opumor =rian sumine.

sion will issue these licenses.

tivity or

• power level of the reactor,

" Controls" when used with respect to 55.23 scope er operator and senior operano, i 55.2 Sco,pe.

any other facility means apparatus and operanas sesst mechanisms the manipulation of which 35.24 wa nr or namiem.aa and tess requ re.

The regulations contained in this part could affect the chemical, physical, Ad=Iusrauea of opermias sesi prior to ia. E apply to any individual who manipulates metallurgical, or nuclear process of the 33.25 irias uincality.

• 'the controls of any facility l, censed pur-facility in such a manner as to affect the i

emsuant to Part 50 of this chapter and to protection of health and safety against LICENSES Sany individual designated by a facility radiation, ss.3o rimance of haaws licensee to be responsible for direc' ting (g) " United States" when used in a 33 3: Coad none or the liceau, the licensed activities oflicensed opera-geographical sense, includes all territo.

5s.32 Empiranoa.

tors, ries and possessions of the United States, 53.33 Renews: or lica=*

the Canal Zone and Puerto Rico.

) 55.3 License requirements.

M ODIFICATION N EVOCATION OF 3 $5J Communications.

(a) No person may perform the func.

4 5s.4o Mod.tkuien and revocat.oa orliaaws tion of an operator as defined in this part Except where otherwise specified, all 35.41 Nouncmion of disabihiv.

• except as authorized by a license issued communications and reports concMing ENFORCEMENT by the Commission; the regulations in this part, and applica-g (b) No person may perform the func, tions filed under them should be ad.

33.3o wu as.

" tion of a senior operator as defined in $ dressed to the Director of Nuclear Reac.

S this part except as authorized by a e tor Regulation or the Director of CERTt FICATE OF M EDICAL EX AMIN ATION R license issued by the Commission.

g Nuclear Material Safety and Safe htrds.

35 6o Enm.nauoa form

• as appropriate, U.S. Nuclear Regulatory

[

} 55.4 Definitions.

Commission, Washington, D.C. 20555.

r*

APPENDICES b

Communications, reports, and applica.

As used in this part:

tions may be delivered in person at the cOwd

,cuen and$ihna.

(a) "Act" means the Atomic Energy Commission's offices at 1717 H Street, r

t rr s.on Fac.htin.

Act of 1954 including any amendments

. N.W., Washington, D.C. or at 79 0 Nor.

554 a

April 29,1975 0919 123 9

PART 55

• OPERATORS' LICENSES

[ folk Avenue, Bethesda, Md.

Washington, D.C., or 7920 Norfolk signed by the applicant.

Avenue, Bethesda, Md.

j 55.6 Interpretations.

{ 55.11 Requirernents for the ap-8 proval of application.

Except as specifically authorized by y Each application the Commission in writing, no in-e for a license shall contain the following An application for a license pursuant terpretation of the meaning of the g information:

to the regulations in this part will be ap-regulations in this part by any officer or ':

proved if the Commission finds that:

employee of the Commission other than (1) The full name, citizenship, age, (a) The physical condition and the a written interpretation by the General address and present employment of the general health of the applicant are not Counsel will be recognized to be binding applicant; such as might cause operational errors upon the Commission.

(2) The education and pertinent ex-endangering public health and safety. C perience of the applicant, including (1) Epilepsy, insanity, diabetes, hy:

EXEMPTIONS detailed information on the extent and pertension, cardiac disease, fainfirrg nature of responsibility; spells, defective hearing or vision er ary

{ 55.7 Specirle exemptions, (3) Serial numbers of any operator other physical or mental condition which and senior operator license issued by the might cause impaired judgment or motor The Commission may, upon applica.

Commission to the applicant and the ex-coordination may constitute sufficient tion by an interested person, or upon its piration date of each; cause for denial of an application.

A own initiative, grant such exemptions (4) The specific facility for which the (2) If an applicant's vision, hearing from the requirements of the regulations applicant seeks an operator or senior and general physical condition do not in this part as it determines are operator license; meet the minimum standards normally authorized by law and will not endanger (5) The written request of an considered necessary, the Commission life or property and are otherwise in the authorized representative of the facility may approve the application and include public interest.

license that the operating test be ad-conditions in the license to accommo-

~

ministered to the applicant of the date the physical defe.ct. The Commis-

,e { 55.3 Additional requirements.

facility, sion will consider the recommendations y

(6) Evidence that the applicant has of the facility licensee or holder of an The Commission may, by rule,regula-learned to operate the controls in a com-authorization and of the examining u.

, R tion, or order, impose upon any licensee petent and safe manner and has need for.

physician on Form NRC-396 in arriv-such requirements in addition to those an operator or a senior operator license ing at its decision.

established in the regulations in this part, in the performance of his duties. The (b) The soplicant has passed a writ-as it deems appropriate or necessary to Commission may accept as proof of this a E ten exam-ein and operating test as protect health and to minimize danger to certification of an authorized represen-Q may be l' n >ed by the Commiss'.on to life or property.

tative of the facility licensee where the u.determir.,

. he has learned to operate applicant's services will be utilized.This R and, in the case of a senior operator, to

} 55.9 Exemptions from license.

E certification shall include details on operate and to direct the licensed ac-y courses of instruction administered by tivities of licensed operators in a compe.

Nothing in this part sha!! be deemed to u. the facility licensee, number of course tent and safe manner.

require a license for:

R hours, number of hours of training and (c) The applicant's service as a (a) An individual who manipulates nature of training received at the facility, licensed operator or senior operator will the controls of a research or training

'and for reactors, the startup and shut-be utilized on the facility for which he reactor as part of his training as a student down experience received.

seeks a license or on a similar facility in a nuclear engineering course under (7) A report of a medical examina-within the United States.

the direction and in the presence of a tion by a licensed medical practitioner, licensed operator or senior operator; in one copy in the form prescribed in

{ 55.12 Re-applications.

(b) An individual who manipulates i 55.60.

the controls of a facility as a part of his (b) The Commission may at any time (a) Any applicant whose application training to qualify for an operator after the filing of the original applica-for a license has been denied because of license under this part under the direc-tion, and before the expiration of the failure to pass the written examination or tion and in the presence of a licensed license, require futther information in operating test or both may file a new ap-operator or senior operator.

order to enable it to determine whether plication for license two months after the the application should be granted or date of denial. Any new application shall.

LICENSE APPLICATIONS denied or whether a license should be be accompanied by a statement signed bf' revoked, modified or suspended.'

an authorized representative of thc4, f 55.10 Contents of applications *

(c) An applicant whose application facility licensee by whom the applicant-has beert denied because of his physical will be employed, stating in detail the"*

(a) Applications for licenses should be filed in triplicate, except for the condition or generat health may submit a extent of additional training which the_.

further report of medical examination at applicant has received and certifying g report of medical examination, with the any time as a supplement to his original that he is ready for re-examination. An" g Director of Nuclear Reactor Regulation application.

applicant may file a third application six; e or the Director of Nuclear Material (d) Each application and statement months after the date of denial of his se '

Safety and Safeguards, as appropriate av U.S. Nuclear Regulatory Commission',

shall contain complete and accurate dis-cond application, and may file further closure as to all matters and things re-successive applications two years after Washington, D.C. 20555. Communica-tions, reports, and applications rnay be quired to be disclosed. All applications the date of denial of each prior applica-and statements, other than the matters tion.

delivered m person at the Commission s required by items 5, 6, and 7 of (b) An applicant who has passed offices at 1717 H Street N W.,

paragraph (a) of this section shall be either the written examination or operat-April 30,1975 55 2

PART 55

• OPERATORS' !.lCENSES

'ing test and failed the other may request (I) Radiological safety principles

' the facility.

in a new application that he be excused and procedures.

(f) The control manipulation re-from re-examination on the examination quired to obtain desired

• operating or test which he has passed. The Com-9 55.22 Content of senior operator results during normal, abnormal and mission may in its discretion grant the written examination-emergency situations.

request if it determines that sufficient (g) The operation of the facility's justification is presented under all the The senior operator written examina-heat removat systems, including primary circumstances.

tion to the extent applicable to the coolant, emergency coolant, and decay facility, will include questions on the heat removal systems, and the relation of WRsTTEN EXAMINATIONS ANo OPERAr.

items specified in } 55.21 and in addi-the proper operation of these syaems to tNo Tssrs tion on the following:

the operation of the facility.

w-(a) Conditions and limitations in the (h) The operation of the ' facility's i 55.20 Scope of examinations.

facility license.

auxiliary systems which co ld, affect (b) Design and operating limitations reactivity.

'i-The written examination and operat.

in the technical specifications for the (i) Th'e use and function,of the ing test for a license as an operator or a facility.

facility's radiation monitoring'3ystems, senior operator are designed to test the (c) Facility licensee procedures re-including fixed radiation monitors.and I

applicant's understanding of the facility quired to obtain authority for design and, alarms, portable survey instrumeEts, and

~

design and his familiarity with the con-operating changes in the facility.

personnel monitoring e,quipment.

trols and operating procedures of the -

(d) Radiation hazards which may (j) The significance of radiation facility. The written, examination is arise during the performance of experi-hazards, including permissible levels of based in part on information in the final

• ments, shielding alterations, mainte-radiation, levels in excess of those safety analysis report, operating nance activities and various contamias-authorized and procedures to reduce ex-manuals, and license for the facility, tion conditions.

cessive icvels of radiation and to guard (c) Reactor theory, inc!uding details against personnel exposure.

} 55.21 Content of operator written of fission process, neutron multiplica-(k) The emergency plan for the examination.

tion, source effects, control rod effects, facility, including the operator's or and criticality indications.

senior operator's responsibility to decide The operator written examination, to (f) Specific operating characteristics, whether the plan should be executed and the extent applicable t the facility, will including coolant chemistry and causes the duties assigned under the plan.

include questions on:

and effects of temperature, pressure and (1) The necessity for a careful ap-C (a) Fundamentals of reactor theory, ~ rescrivity changes.

s proach to the responsibility associated b

9 including fission process, neutron 3 (g) Procedures and limitations in-9 with the safe operation of the facility.

A E multiplication, source effects, control c volved in initial core loading,af terations E g rod effects, and criticality indications.

$ in core configuration, control rod u.

(b) General design features of the " programming, determination of various, } 55.24 Walwr of examination and n

test requirements.

o core, including core structure, fuel etc.

internal and external effects on core ments, control rods, core instrumenta-reactivity..

waive any or all of the requirements for a On application, the Commission may tion, and coolant flow.

(h) - Fuel handling facilities and pro-(c) Mechanical design features of the ced ures.

~

~

written examination and operating test if reactor primary system.

(i) Procedures and equipment it finds that the applicant:

(d) Auxiliary systems which affect available for handling and disposal of (a) Has had extensive actual operat-the facility.

radioactive materials and effluents.

ing experience at a comparable facility (e) General operating charac-within two years prior to the date of ap-teristics, including causes and effects of

} 55,23 Scope of operator and senior plic2 tion-temperature, pressure and reactivity operator operating tests.

(b) Has discharged his respon-changes, effects of load changes, and sibilities competently and safely and is operating limitations and reasons for The operating tests adminis:ered to capable of continuing to do so. The them.

applicants for operator and senior Commission may accept as proof of the (f) Design, components and fune-operator licenses are generally similar in applicant's past performance a certifica-tions of reactivity control mechanisms scope. The operating test, to the extent tion of an authorized representative of and instrumentation.

applicable to the facility requires the ap.

the facility licensee or holderg.of an (g) Design, components and func.

plicant to demonstrate and understand.

authorization by which the applic; tat was tions of safety systems, including instru-ing of:

previously employed. The certiMation m entation, signals, interlocks, automatic

- (a) Pre. start-up procedures for the shall contain a description of thy.appli-and manual features.

facility, including associated plant cant's operating experience, including an (h) Components, capacity and func-equipment which could affect reactivity.

approximate number of hours the appli-tions of reserve and emergency systems.

(b) Required manipulation of con-cant operated the controls of the fap (i) Shielding, isolation and contain-sole controls to bring the facility from the duties performed, and the ext.:.s of ment design features, including access shutdown to designated power levela.

bis responsibility.

limitations.

(c) The source and significance of (c) Has learned the operating pro-f (j) Standard and emergency operat-annunciator signals and condition-in.

cedure for and is qualified to operate

.C-ing procedures for the facility and plant.

dicating signals and remedial action competently and safety the facility desig-L (k) Purpose and operation of radia-responsive thereto.

nated irr his application. The Commis-tion monitoring system, including alarm (d) The instrumentation system and sion may accept as proof of the appli-and survey equipment.

the source and significance of reactor in.

cant's qualifications a certi'ication of an strument readings.

authorized representative of the facility WeNed 31 FR lt??4.

(e) The behavior characteristics or licensee or holder of an authorization 55 3 April 30,1975 P919 125

PART 55

• OPERATORS' LICENSES where the applicant's services will be cept as evidence, a certatication by an an application in proper form fbr -

utilized.

authorized representative of the facility renewal or for a new license, the existing licensee by which the licensee has been

!icense shall not expire until the applica.

+

1 55.25 Administration of operatinE employed.

tion for renewal or for a new license has test prior to initial criticality.

g been finally determined by the Commis.

1(f) Such other conditions as the B sion.

Commission may administer a ~

Commission may impose to protect. 5 (c) The licensee will be renewed if The simula.ed operating test to an apphcant health or to minimize danger to life or e the Commission finds that:

for a license to operate a reactor prior to property.

(!) The physical condition and the its initial criticality if a written request ger.eral health of the licensee continue to by an authorized representative of the 1 55.32 Expiration.

te such as not to cause operational 5 facility licensee is sufficient for the Com.

. ors which migh endanger public heatsh mission to find that:

Each operator and senior operato*

a,d safety; and f

(a) There is an immediate need for license shall expire two years after che t; the applicant's services. -

date of issuance.

(2)(i) The licensee has been activily (b) The applicant has had extensive and extensively engaged as an operat,or actual operating experience at a com-E 'l 55.33 Renewal of licenses.

or as a senior operator under his existing parable reactor.

E license, has discharged his respog-(c) The applicant has a thorough 5 (a) Application for renewal of a sibilities competently and safely, and is knowledgeof the reactor control system, R license shall be signed by the applicant capable of continuing to do so.

instrumentation and operating pro.

and shall contain the following informa, m (ii) The licensee has completed a' re.

cedures under normal, abnormal, and tion:

N qualification program or is p,resently emergency conditions.

(1) The full name, citizenship, ad. E enrolled in a requalification program if (d) The reactor control mechanism dress and present employment of Ae ap, u. the completion of the requalification and instrumentation are in such condi.

plicant; 8 program will occur after the expiration tion as determined by the Commission to (2) The serial number of the license of his license as provided in sub.

permit effective administration of a for which~ renewal is sought; paragraph (a)(4) of this section.

g simulated operating test.

(3) The experience of the applicant (iii) If the requirements of paragraph n

under his existing license, including the (c)(2)(i) and (ii) of this section are not f

LICEN5E5.

approximate number of hours during met, the Commission may require the ap.

which he has operated the facility; plicant for renewal to take a written ex.

g } 55.30 Issuance of lleenses.

amination or an operating test or both.

(4) A statement that during the effec. 7 On determining that an application tive term of his current license the appli.

(3) There is a continued need for a meets the requirements of the Act and cant has satisfactorily completed the re.

license to operate or direct operators at the regulations of the Commission, the qualification program for the facility for the facility designated in the application.

Commission will issue a license in such which operator or senior operator form and containing such conditions and license renewal is sought. In the case of M ODIFICATION AND R EVOCATION OF limitations as it deems appropriate and an application foc license renewal filed LICENSES necessary.

a within two years after September 17, N 1973,if the facility licenas has not im.

I 55.40 Modification and revocation

} 55.31, Conditions of the licenses.

piemented the requalification program of IIcenses.

requirements in time for the applicant to Each lice'nse shall contain and is sub. M complete an approved requalification (a) The terms and conditions of all ject to the following conditions, whether program before the effective term of his licenses shall be subject to amendment, stated in the license or not:

current license expires, the applicant revision, or modification by reason of (a) Neither the' license nor any right shall submit a statement showing his cur.

amendments to the Act, or by reason of under the license shall be assigned or rent enrollment in an approved re.

rules, regulations or orders issued in ac.

otherwise transfered. 'N qualification program and describing, cordance with the Act or any amend.

facility for which it is issu'ed.

had completM by the date of his applica. g ments thereto.

(b) The license is limited to the those portions of the program which he (b) Any license may be revoked, sus.

a:

(c) The license is limited to those tion for license renewal.

u pended or modified,in whole or in part, R for any material false statement in the controls of the facility specified in the license.

j(5) Evidence that the licensee has application or any statement of fact re.-

(d) The beense is subject to, a' d the discharged his license responsib;ilities quired under section 182 of the Act,?

n licensee shall observe, all applic'able competent!y and safely.The Commission because of conditions revealed by suoM-rules, regulations and orders of the Com.

may accept as evidence of this a certifi. -

application or statement of fact or any mission.

% cate of an authorized representative of report, record, inspection or other t the facility licensee or holder of an means which would warrant the Com-

~

(e) If a licensee has not been actively " authorization by which the licensee has mission to refuse to grant a license on an performing the functions of a1 operator u-been employed; original application, or for violation of.

M or senior operator for a period of four R 16) A report by a licensed medical or failure to observe any of the terms and h months or longer, he shall, prior to practitioner in the form prescribed in

' conditions of the Act, or the license, or c: resuming activities licensed pursuant to

{ 55.60.

of any rule, regulation or order of the

[ this part. demonstrate to the Commission (b) In any case in which a licensee Commission. or any eonduct determined s

" that the knowledge and understanding of not less than thirty days prior to the ex.

by the Commission to be a hazard to safe facility operation and administration are piration of his existing license has filed; operation of the facility.

satisfactory. The Commission snay ac.

p.4. sn.i e ss rn :::21.

9l9'126 April 29,1975 554

e.,.

PART 55

• OPERATORS' UCENSES 7 33.41 NotiGeatiori of disa! lity.

~~

4ppgg 4 r.awd..rer3 r m.he

,4 cin.s.dm.i pes andw The licensee shall notify the Director "d'"d**'O******P'***'"'**fi*a

('

5 D2ector of Nuclear Material S3fety ar.d LICENSED OPEttATOR5 OF PROOcc.

"' 'd *****e. The nqualetes ation a, of Nuclear Reactor Regulation or the R EQU A LIFIC A TION PROGR AMS FOR TIM AW MimATlON FACILITIES 3]['

',h'f'",",**

3 Safeguards as appropriate.,U.S. Nuclear e I'egulatory Corn n:.ssion. Nashmgto.t.

ong,,,,.3

,u,:,3,,,,,,gan ag,,,,,,,,,,,,,,,

W. D.C. 20555. within.a.: teen '15) days r.f ter gun ne,.,,,w,e m,,,

.g,,,.,,,,,,.,,,,,,pg,,, g,

its occurrence of ar

y disability referred

*".'m"ie..smenru'ea 'ai d=reas the teras..s iheic

'd"'''''''''""d"'d**'8J*r'ai sea.mso.34 or t0 CFR Par 30 to in i 55.11(a)(1) v.hich occurs after d,,,d,,,a,,3,,,,,,,,,,,,,,,,,,,;,,,re q ase cs ihas in.

pran c

,,4,,,,g the subt:tission Cf hi3 medical eXarnina-ung,ntie.a tu,hnes se 1.senwd as operauirs hs me

" 8'

h' * ' * "N' *S *"d S**** "Per J' art.

~

~ tion foIIn.

Coenm.ssa.pt and that individuals ohn dared :he

'A# *'"'P"'3"""* sh4H sonmis us at lent to reac.

g,.

E

""""d'*"'"'""'"'""d*""*'b*A""d as senn.r operauws en aeordanse oah 10CFR Part W'* "# W '#Jd'* Qu6d"* 8' '* "8* Caa'fal

( 55.50 Violations.

33. seu.a 33.33 410c'FR part 33 requares that

"'8""""

• h'< h demonst rate skalt anCor ;,,

sach WenwJ ndiveJul demuestrue his c.mtm.4ed I'"*'I'") * *'h 'fd'it? C"nand sprenes.

I**"*'*d""'*"d**""P'*'

~

An injunction or other -court order 5""'P"** ""T '** 3 a" '" ord'r 'or h** l'esa'.n s

may be obtained prohibiting any viola.

ra be reae-ed. Competenee may o,demanaraied.,,

h d'.a"*osa'd Sau'8 2c"*7 vaderst2m8'.as.,'4 the r2 n,,,g,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,

me, n an,n,aius and.,e.,an.

,,4 tion of any provision of the Atomic requi,nc.no, progr,n,.h.ch has he.

re,.e.ed ha"** *** "N'aas praseduren 'a act are, sne

• • Ah''"'"*d A

Energy Act of 1954. as amended, or Ti.

ud appr==ed >> me Commamoa.

Eawn tisused upwauw and tennw mne.w is tic !! of the EnergI Reorganization Act Pumas.c squali6unna for ad opeanws am!

w senent operators of pn.dugtsos and unisaatuse ca.gnaeant auf tagility desgo changes. pruccdo,e of. I974 or any regufation or order g,ogio,,,,,,,,,,,,,,,,3,,,,,,,,,,,,,,,,,,,,

em, au w, w,ns, oga d.

Ea h teceawd..peraner =ad un e apu,n,

t issued thereunder. A court order may be compaence,,,ncga,,, io usp w i sh,,, 2 3 obtained for the payment of a civil and emersmy sau.a..a The compte =ity et duusa

'"""**"'"'"f*d'*""'"ad"""t*"c7 e penalty imposed pursuant to section 234

• • *P"anas anda ne prad mua mad in iisaiam N "'" "" * "' d *'b h d "'*d b2"'

• - 4 '""ul2 may t'e used 'a me**rs the re.

of the Act tor viotstion of section 53.57 f.caii.es reau.re iha.mto., comp,ehe,s. re.

u.

qm,,oy,,,i pr. sranis %.,.w er.r aH i.cw 9"**" "' P**dt'=p"* 3a

• aad 3b" i8 the mausar o

62.63. 81. 31.101,103.104,107,or 109

..per son aw n,o, op,,,on,a a..,,,, sou,,3 repa=8*es she seneras opcui,, charas enu,es or e

*'*[*"'['?

'"*""*d 2"d 'h' **"5*"' the 'a-of the Act,or section 206 of the Energy enacp4 aad prese.

N ",

',"g'"fx r."F *'Y' 'd*

• • d * "

l'"""d 9""'S *ad

a'"r *P"8'** af pr'.

regulation, or order.1974,or any rule, duchon one'unlization t'.calisees who have been ac, Reorganization Act of n

issued thereunder, 4

E=dme m N requi.6as program snais n,g,,,,4,,,,,,,,,,,

g,,,y,,,,,,,,,,

g or any term, condition, or fimitation of wn. e m,au,rs,h.n part,c,p,e 9, ny,,,i,f,c,,,,

u. =ctode:

g *"*'*j^a^"****h

""2*'as es =Ned u. =psnde

• • " '"'**2"***

• h'C# d*'ermiae any license issued thereunder,or for any prograns meetiss ihe requirementset ilus Appe=dia.

h violation for which a license may be I"d'..duais.ha maineain onniw w went opea.

revoked under section 136 of the Act.

nor hceaus for the purp..w or pro,..d.ng bacw, w"'u"esS' **d 5ea=* *p".a'ar kaa='ec ;e.

i N

mm m aa n.n s h.cn determ...

,,,,,,,3,,,,,3,,,,,,,,,,,,,,,3,,

Any person who willfully violates any ;; me requi.r.cannapectransencepitstheenreasinac

''"d "'"*'"$' 2ad """* *P"Ma'S' kaa=ledse provision of the Act or any regulation or R mew normal dunes praiude the nad rur spentic

• ' '"h " ""*d 'a ** "9"*8i60'u"* p'av ma 2

order issued thereunder may be guilty of " '""*a'a3 in patheular acus. Luenwd opemon oc eamde a 6aksl*.v evaivaung usew a

n teeg,ut

• 7 p" a erime and, upon conviction, may be u. wmar operators -how i,cenin are cond none eu syseemsne ohsusano,'sedures g,,,,

,,g,,,,,,,.,,.,,,,,,,g,,,,,,,,g ama,,ai,,o,, is, s.

punished by fine or impr,sonment or R p.re.op,si, in ihus, p,i,.ms og in,,equai.ricar.cn P"d*mme and wanpetmy or lesented oprrasses i

g

%+

both, as provided b) law.

program appropesate to the duhes t!*ey perfossi

• "d '#*"* "P'"n by superviuses and*ue traneing The requa!.fkanon program requirements inniv.

"* "'*'"' N'"d'ag evaluaispe ed acisems taken CE RTIFICATE CF M EDICAt. Ewiin-

'es m2mpwso"n at uar.ds me te perh<m,a -n

" '" " """ d".nuer n'ina 82'***'""*'*d**~4' ihe f.scas.sy ror whica ihe operatue is igenwd.

and c'augency c d'

I'*"' *""" "' * **'I'*'? "' *banrm at o.adi.

Humever. ihe uw of a simulatur as speuded m

("**

28

• 8 7 afcan'piashed by ussag the enetrol '

Paragraphs 3e and ad of th s appendia es permist.ble

} 55.60 Examination form.

and suca uw is encourged.

papel af de udty m.alved or by unset a i.mWarne, where the caaeras panes er the rac4hty is e,ed ro,

• '**'*' ""'a'r"'n"n"ne'"m*a*s *c*o"n'dir.on skad he d

• • • '""***"'h' An APP cant shall cornP ete and R '98 88ih"" P'"f' ** R *4="'**='S li l

(3) emasene>

a

,, sign Form NRC-396 "Certincate of n3,,,,,,,,.m,,,,,,,g,,,,,,,,,,,,,,,,,,

ace i man.pwan..n.W ine pian. co,,es,s.,,,,,'

es

" Medical Examination!'

he conducied for a ca.uaunut per.ud noii..escew qu red. tr a simulat.-.s used in mess.nl c se requ.,..

a E

(b) The examining physician shall

=a 3 ears. ud uova canous.aa ihait be prornpriy-

"'** "' P*8'*Ph '* 'h' **'28"' ' hah *ccura< ei r "n' complete and sign Form NRC-396 and

,' ""*d P*",***',',a "aah a""m'h'd u'* "1 *=c -

",",,,",,"w",n'"d,3,,",,",",',',",",',",",3,',',',,,",,,",,,,,";,',Y, shall mail the completed form to the I t.co r N ee

.r.casion pre.gra i a

""d *'"d' a' '"' *8 Mar ean clowty parzues Director of Nuclear Reactor Regulation

.aciude pu, inned icauta on a,, tea, and cnn.

'8 'd *** ' 2**> 'avahd.

"'"**6***** "8*P"***' *ad or Director of Nuclear Material Safety naums bams ihraush i the ikense peri.=a in iii..se

"",",**',,*"',',o*,,','.,'",,',,,,",,*,",,,*,,***,',',*o*d,'

ar:d Safeguards, as appropriate, U.S.

• '",'**"'"",**8"P'",""**d'**a'"P""a' qu

,,c,,,,

g NucIear ReguIatory Commiss on, 3,d g,,,n,,,,,,,,,,,,,a,a,,,3, roi,,,,,,,,,,

rions coado.;eed pursuane i. par. graphs sa in, u,,,

W"") *d "*" ** ""d -

hhington, D.C., 20555.

jari:

a.

Theney and prmcipers of operatum.

=

3. Recordt.

b.

General and 69Cc6c plani e;ersung charac.

N)TE: Copies of F..rm NRC-)% ingy be oh.

a. Records Of the requalt*. cation prgrags S.

s ensnca.

ta.e -d ny.r.i.cg in the D. rector of Nuclear Reacin, aball be malataited for a period of tiro years

88" c.

Plans inwrumearan..n and coniroi systenes frors the date of the recorded event to crocts. E Restanon or Director of h' ear %tarer.ai Safety d-II*a' pf"'fU'"a sy s4M gggg egg p3ggggggggggg gg gggg gggggge4 op, y and sJteguards. as appr tpriate. tl$. Nucitar o

e.

Eng.neered sarcey ysiems.

g erstor arid senior operstar in tDe requaldica.

-Rs.4? as..ry Comm sa.un. W avi.cgton. D.C., 3 3 3.

f.

N..emas, armormai and cmertmy aprrahat ca tion prog 2nt The records shst! contatn "L

{ 55.61 (Deleted 40 FR 37741 peacedurcs.

coptes of written enminations admtm.atered, g-Radian.we cantrol anJ safety.

{ evalustions and documentation of a 7 add 1 the answe-s gtven by the licecsee, results of h

Techn can speci6cassoas.

Applicable puru..ns of Tiile 10. Osprer t.

7 tior:al trat:13g admuitstered in areu td C..de of Federal Reguiat. ores irtitch an operstor or senior opersto? has **

Otner tenniag iechn. ques melodin g felms.

ethibited det!ctencies.

..dentapes und niner crut. e train.ng a ds may alw

b. Recorda which must be tusintsited pur.

h 'foT3-.-The raportt:c and record keepint we awd.

suant to this appendtJa may be the ortg!=al requ're:nent.s contained la tats part have laJ =edwal stuJy on the pari a(each operator shan or a rep *oduced copy or micrortem tf suc's ben approved by the Generst Accounting g,

g,,,,

C "ce under D-18Cas (Ro113), (R0334.

4,,,g,a 3, gg y $,

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4 p s-s wa. m,

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0 1919 el27 c

. s.

PART 55 e OPERATORS' LICENSES reproduced copy or microform is duly au.

thenticated by authorized personnel and the microform ts capable of productst a clear and legible copy after storage for the period o spec 12ed By Commission regulations.

s S

c. If there is a con 21ct between the Com-co misston's regulations in this part. Itcense condition, or other written Commisstatt ap-E proeal or authorization pertaintsg to tne retention perted for the same type of record.

T the retention period spec!Ced in the regula.

tions in this part for such records shall apply ss-unless the Com.minton, pursuant to i 53.7 has granted a spectae exemotion from the T

record retention recutrements speciaed in

,the regulations 1.2 this part.

e K

6.

Aferew.aiie inanin presyneens. The require.

memsof this appendis may be met by requalificatuin programs conduc:ed by persons other than the facility licensee if such requalification programs are similer to the pre'5 ram described in paragrapns I through 5 and the alternasivepram has been ag.

proved by the ComminL. *

• ~~

• y

.1.

Apriliswhlos_s on reseemh and ten rears *ws annd et w rre=*e foi-ilities. To acenmmodass specialiard t: nuedes of ope *atwin and differences in controt. equip.

ment and operas.e skills and kmmledge, the re.

?

N qual 6catires prograen for esch licensed operatsw and 8

senint nperatsw of a research or test reactor or of a non-reactor facility st.all confs.rm generally but need mie he identical to the requalificatuin prngrans out.

lined in paragraphs I through 6 of this appendia.

Hiruever, sigm6 cans deviasu.ns frewn the require.

ments af this appendia shall be permitted only if sup.

ported by written justification and approved by the Commissa.m.

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1919 128 1

i g

s.

May 21.1976 55 6

UNITED STATES NUCLEAR REGULATORY COMMISSION RULES and REGULATIONS TITLE 10. CHAPTER 1. CODE OF FEDERAL REGULATIONS-ENERGY O PER ATO RS' LICENSES 55 an-PROPOSED RULE MAKING t

39 FR 35371 Published 10/15/74 Comment Period expires 11/29/74 Preservadon of Records; Maintenance Re.

quirements for Licensees and Applicants See Part 20 Propo.ad Rule Mabng.

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~.

b 1919 129' 55 7 April 30,1975

ATTAChTF.NT 1 METROPOLITAH EDISO:I ONTOR RIC.UALIFICATIC:~ PROGRA'4 13.2.2 The Metropolitan Edisca requalification progrs=, as set forth in this dceu=ent, applies to the Three Mile Island Nuclear Station. All licensed f

personnel vill participata in the applicable po-tien of the

_,:alification pro-grm.

The basis of the requalificatica progra= is the need to =sintain operator cc=petence e.ad proficiency in the quest for continued safe operation. The guidelines for the requalification progra= are found in 10CFR55 Appendix A.

In addition, the i=ple=entation of this progra confo=s to 10CFR50.

I.

Progra= Schedule II.

Pre-ple --d - actres III.

On-the-job training IV.

Annual Evaluation Exa-#"atien V.

Records VI.

Accelerated Requalificatica 5:0 p2=

VII.

Four Month Absence Progrc=

VIII.

Newly Licensed Operators II.

Requalificat' ion progra= Ad=inistratien 13.2.2.1 P-ec-2= Sch-dule The requalificatica prog a= described herei= vill be i=ple=ented at a w

specified date vithin oO days after receipt of an operating license. March.,

and subsequent a--*versaries of this date, vill be considered to be the sta:-t-ing date of each annuall cycle of requalificatica progren operation.

The Metropolitan Edison Requalification Progra= censists of four inter-related sew a -i+ 4 4 :::n. concurrently. These ses=ents are:

i,'

1)

Operational Review Lecture Series (OR) 2)

Funda=entals and Syste= Reviev Progra= (FSR) 3)

On-The-Job Training h)

Annual Evaluation Eva* nations The OR Series is a classrec= lecture presentation which provides licensed personnel with the details of operatio=al infor=ation related to the Three Mile Island Station. As part of the OR Series, selected FSR topics are presented.

FSR topics are selected in areas where annual operator and senior operator written examinaticas indicate that e=phasis ia. scope and depth of coverage is 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per year for all needed. OR lectures are scheduled for a =in#-"-

a" single and dual license holders.

On-the-job training is designed to insure that all licensed personnel operate reactor controls and participate in =2jor unit evolutions. Records of all on-shift perfor-~ce are =sintained and periodically reviewed by supervisory personnel.

The annual evaluation exa=inations si=ulate the written and oral exa=inat ad=inistered by the Nuclear Regulatory Cc :issica. Perfor=ance en these annual evaluatica examinations deter =ine the extent of the FS?, propa= during the fol-loving twelve =enth requalification period.

lAnnual, as refer ed to in the Cperator Requalificaticn preg 2=,

is 12

[

=cnths, not to exceed 15 =cnths, in crder to accc =cdate unit operations.

1919 130 13.2-0 A=

& (L_7 73)