A05610, Responds to Generic Ltr 86-04 Re Policy Statement on Engineering Expertise on Shift.Comparison of INPO Shift Technical Advisor Guidelines W/Established Bachelors Degree Programs in Engineering Encl

Responds to Generic Ltr 86-04 Re Policy Statement on Engineering Expertise on Shift.Comparison of INPO Shift Technical Advisor Guidelines W/Established Bachelors Degree Programs in Engineering Encl

ML20211K568
Person / Time
Site:	Millstone, Haddam Neck, 05000000
Issue date:	06/13/1986
From:	Bishop R, Opeka J CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	Charemagne Grimes, Noonan V, Thadani A Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.1, TASK-TM A05610, A5610, B12125, GL-86-04, GL-86-4, TAC-67187, TAC-67188, TAC-67189, NUDOCS 8606300181
Download: ML20211K568 (55)

Text

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HARTFORD. CONNECTICUT 06141-0270 L L J 7j,[,"dU '5~, (203) 665-5000 June 13,1986 Docket Nos. 50-213 50-245 50-336 50-423 A05610 B12125 Office of Nuclear Reactor Regulation Attn: Mr. C. I. Grimes, Director Integrated Safety Assessment Project Directorate Division of PWR Licensing - B Mr. Ashok C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing - B Mr. Vincent S. Noonan, Director PWR Project Directorate #5 Division of PWR Licensing - A U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:

Haddam Neck Plant Millstone Nuclear Power Station, Unit Nos.1,2, and 3 Policy Statement on Engineering Expertise on Shif t (Generic Letter 86-04)

Generic Letter 36-04(1) provided licensees and applicants with a copy of the Final Policy Statement on Engineering Expertise on Shif t (50FR43621). The intent of the Policy Statement is to ensure that adequate engineering and accident assessment expertise is available at all times, and to provide licensees with latitude ig meeting the Shif t Technical Advisor (STA) requirements from NUREG-0737(2i and the staffing requirements of 10CFR50.54(m). The Policy Statement offers licensees two options for meeting the requirements for engineering expertise on shif t(3). Option 1 of the Policy Statement would allow (1) H. R. Denton letter to All Power Reactor Licensees and Applicants for Power Reactor Licenses, dated February 13,1986, Generic Letter 36-04.

(2) N UREG-0737, Clarification of TMI Action Plan Requirements, dated October,1980, item I.A.I.1, Shif t Technical Advisor.

(3) The only legally binding requirements regarding engineering expertise on shif t of which we are aware are contained in Item I.A.I.1 of NUREG-0737.

Although NUREG-0737 is not itself a legally binding document, the specific STA requirements from NUREG-0737 have been the subject of plant-specific confirmatory orders. It is important to note that the

" requirements" described in the Policy Statement are not legally binding upon licensees. Thus, discussion herein of " requirements for engineering expertise on shif t" refers to the NUREG-0737 requirements and not to the

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Policy Statement. i I 8606300181 860613 PDR ADOCK0500g3 V

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the STA position to be filled by one of the two Senior Reactor Operators required by 10CFR50.54(m)(2); this individual would serve in a dual role (SRO/STA) capacity. Option 2 permits licensees to continue to use an NRC-approved STA program while meeting licensed operator staffing requirements.

Additionally, although not stated in Generic Letter 36-04, the Policy Statement also provides for consideration of license proposals by the NRC Staff which are

, different from the above two options.

Generic Letter 86-04 requested that licensees provide the following information:

(1)- The licensee's current program for providing engineering expertise on shif t, (2) If the current STA program utilizes an " equivalency" criteria to an engineering degree, a description of the criteria used; and (3) A description of any planned modifications to the current program in order to take advantage of the options identified in the Commission's Policy Statement.

The purpose of this letter is to provide Connecticut Yankee Atomic Power Company's (CYAPCO's) and Northeast Nuclear Energy Company's (NNECO's) response to Generic Letter 86-04 on behalf of the Haddam Neck Plant and 4

Millstone Unit Nos.1, 2, and 3, respectively. The discussion provided below applies to the Haddam Neck Plant and Millstone Unit Nos. I and 2. Regarding Millstone Unit No. 3, we note that each shift utilizes an individual in the dual SRO/STA role who is qualified in accordance with the Policy Statement. This is documented in Section 13.1.2 of NUREG 1031, Supplement No. 4. No changes to this program are planned for Millstone Unit No. 3 at this time. If any changes to the current approach are to be made, we envision that they will.be of a type

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which will render the Millstone Unit No. 3 approach similar or identical to that in use at the other three nuclear units in the NU system. 3 Haddam Neck Plant, Millstone Unit Nos. I and 2

, CYAPCO and NNECO have for some time been actively involved in this and i other operator staffing and qualification issues and have, for over five years, -

been implementing an educational program intended to provide the on-shift operating crew with adequate engineering and accident assessment expertise.

Although this program does not meet the educational criteria specified in the Policy Statement, we believe that it provides a sound and thorough educational  !

I background. We firmly believe that an individual who possess an SRO license and who has successfully completed this program is well qualified to function in the dual role capacity. As such, we request that the Staff review our program on the

" case-by-case" basis discussed in the Policy Statement. We do not believe that providing a response only to the above questions would adequately describe our position with respect to this issue, nor would it accurately reflect the significance of our long-term commitment to improving the qualifications of our

_ operations' staff s. We are taking this opportunity to provide the Staff with a discussion of CYAPCO's and NNECO's initiatives in this area over the past 5 years, which we believe is important in the evaluation of our program.

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1 l 'o Interim STA' Program and Development of Long Term Plans One of the recommendations of the TMI Lessons Learned Task Force wa,

, that additional technical, educational, and analytical capability, dedicated to concern for the safety of the plant, needed to be provided in the control j- room to support the diagnosis of off-normal events and to advise the Shif t Supervisor on actions to terminate or mitigate the consequences of such events.(4).

The initial NRC " requirement" for the STA position was transmitted in letters from D. G. Eisenhut and H. R. Denton dated September 13, 1979 3

and October 30, 1979(5)(6). These letters required that an individual with a '

bachelor's-degree "or equivalent" and additional training in plant-specific transient and accident response be available to the control room personnel

at all times,' within 10 minutes. The STA was required to be on duty as of January 1,1980.

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In a December 31, 1979 letter (7), CYAPCO and NNECO described their plans for meeting this Staff " requirement", utilizing additional personnel (mostly degreed at the B.S. or higher level) who were assigned twenty four 4

hour rotating duty. These individuals received the required specialized training and were placed on duty on or before January 1,1980.

Subsequently, on October 31,'1980(8), the NRC issued NUREG-0737, which

- contained the set of TMI Action Plan requirements that had been approved by the Commission for implementation at that' time. Item I. A. I.1 concerned Shif t Technical Advisors. NUREG-0737 Item I.A.I.1 required

that licensees submit a description of their then-current STA program,

! along with a description of their longer -. term plans for upgrading the ,

1 qualifications of operations personnel and eventual phase-out of the *

, interim STA position. These plans were required to be submitted by January 1,1981.

4 (4) TMI-2 Lessons- Learned Task Force Status Report and Short-Term l Recommendations, NUREG-0578, July 1979, Section 2.2.1.b.

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! (5) D. G. Eisenhut letter to All Operating Nuclear Power Plants, dated September 13,1979.

2 (6) 1 H. R. Denton letter to All Operating Nuclear Power Plants, dated October 30,1979.

l (7) W. G. Counsit letter to H. R. Denton, dated December 31, 1979.

(8) D. G. Eisenhut letter to All Licensees of Operating Plants and Applicants for Operating Licenses and Holders of Construction Permits, dated October l 31, 1980, forwarding NUREG-0737.

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It was recognized by CYAPCO and NNECO (and other licensees) at the time that providing the STA function was best accomplished through an interim program and a longer term technical upgrading program. In fact, all of our correspondence with the Staff regarding the STA " requirement" specifically described both interim and longer term plans. The Staff has been aware for over 5 years that our long term plans consisted of upgrading the qualifications of shif t supervisors and supervisory control operators to meet or exceed requirements for the STA established by INPO and endorsed by the Staff.(8)(9)

In response to item I December 31,1980(10).A.l.1 of NUREG-0737 and subsequent submittals,and as described CYAPCO in the and NNECO initially contracted with Memphis State University (MSU) to implement an STA program that met the INPO guidelines. Docketed submittals since that time have made it explicitly clear that once an adequate number of shif t supervisors completed this training (and additional management and non-technical training specified by CYAPCO and NNECO) that the separate interim STA position would be eliminated and the dual role (SRO/STA) concept would be utilized. We note that, significantly, these plans were in full compliance with NRC's criteria and INPO guidelines for Shif t Technical Advisors.

Following a review of CYAPCO's and NNECO's long term program description the Staff issued Safety Evaluations for NUREG-0737 Item I.A.I.l(ll)(12) which concluded that:

"your STA training program is acceptable in meeting the intent of the guidelines set forth in the above referenced letters."

The "above referenced letters" included NUREG-0737, which clearly referred to the INPO Standard " Nuclear Power Plant Shif t Technical Advisor - Recommendations for Position Description, Qualifications, Education, and Training" as " acceptable for interim guidance for a utility (9) D. G. Eisenhut letter to All Licensees of Operating Plants and Applicants for Operating Licensees, and Holders of Construction Permits, dated September 5,1980 (10) W. G. Counsit letter to D. G. Eisenhut, dated December 31, 1980.

(11) D. M. Crutchfield letter to W. G. Counsil, dated March 31, 1982.

(12) 3. Shea letter to W. G. Counsil, dated February 22, 1982.

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i in planning its STA program over the long term," (emphasis added)(13). To our knowledge, this guidance has not been superseded.

Even though the Memphis State University program was found acceptable ,

by the Staff, after some experience had been gained in its implementation we identified several areas where the program could be improved. (As a g result, CYAPCO and NNECO elected to custom-design, in conjunction with a local technical college, an educational program specifically tailored to nuclear power plant operation. This program was developed to meet the existing NRC; and INPO criteria, with an additional objective of qualification of personnel for other positions at our nuclear facilities in addition to the STA. This program was developed in conjunedon with the Thames Valley State Technical College (TVSTC) as a two year, Associates Degree Program in Nuclear Engineering Technology. The curriculum was 'l developed jointly between NU and TVSTC, and the program has. received -'

4 formal licensure from the State of Connecticut. The Sta!! was informed of the details of this program in a letter dated November 18, 1983(14).

Implementation of the TVSTC program began in December,1983.

Alternatives to Existing Program CYAPCO and NNECO have periodically examined possible alternatives for providing engineering expertise on shift, both during development of our long-term STA plans and during NRC's deliberations on the final Policy Statement. While we believe that the TVSTC program is adequate to satisfy the intent of the Policy Statement, we have investigated alternatives.in the event it is not acceptable to the Staff. Essentially, (13) In summary, CYAPCO's and NNECO's plans were made well 1:nown to the Staff in December,1980 in response to an NRC request for information.

Approximately one year later, in early 1982, the Staff approved .these plans, implicitly approving CYAPCO's and NNECO's proposal to utilipe the

, dual role concept. Although we acknowledge that the Staff's SER states that the NUREG-0737 criteria are accepia'oie for " interim" guidasice, we note that it has been over four years since the SER's were issued and almost six years since issuance of the initial STA " requirement". CYAPCO and NNECO and other licensees have invested substantial resources in training in general, and in STA qualifications in specific based on this

" interim" g0idance. We question the value of, that " interim guidance" for ~

i establishing long term plans when it is substantially changed more than 5 years after issuance. In particular, we initiated a program that fully met NRC criteria and which was reviewed and approved by the NRC, and have been implementing it for approximately 5 years. We are very concerned '

over the potential for. the Policy Statement to invalidate this long term good f aith effort. Understandably, crite.ria changes such as this can only l have a negative effect on,the willingness of licensees to be responsive to

" interim" criteria in the future.

1 i (14) W. G. Counsil letter to D. G. Eisenhut, dated November 18, 1983.

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o Continue education to the B.S. level for shif t supervisors and supervisory control operators who have completed the TVSTC program, or -

o Resume the use of the dedicated STA.

We do not believe that the dedicated STA is a viable and worthwhile option.

First,- although the dedicated STA is required to have a B.S. degree, or equivalent, he is not required to hold an SRO license. We believe that a better perspective and integration into the shif t crew will result if the STA is one of f

• the on-shif t SROs. There is evidence that dedicated STAS have been of limited value.(15) We share the Commission's preference for a combined SRO/STA position and we do not believe that the dedicated STA position is the preferred

, approach.

During the time period that our interim STA program was in effect, the NRC reviewed and approved a number of non-degreed individuals as STAS based on the

!- degree " equivalency" provision in the NUREG-0737 criteria. It is interesting to

. note that, in the NRC's judgement, these individuals are qualified to serve as a dedicated STA (Option 2 of the Policy Statement) yet they are not qualified to serve as SRO/STA (Option 1 of the Policy Statement). This is even more difficult to understand given the much greater degree of involvement in operations of the SRO/STA, which is an additional objective of the Policy 4

Statement and, in fact, one of the primary factors in the Commission's preference for the combined role.

We also do not believe that there would be any benefit realized by continuing the TVSTC program to the B.S. degree level. First, such an undertaking would require that the same senior, SRO licensed personnel be taken off shif t for an extended (i.e. - 2 years) period of time to complete their education. We believe that this would result in a short term decrease in experience and qualifications

-available to the shif t crew, without a compensating long term benefit. There

[ would also be very significant costs associated with this option. A detailed evaluation of this option as per NRC sequirements iur imposing incisfits on operating reactors would most likely conclude that this option is not justified.

A study was conducted which compared the content of the INPO STA guidelines

(which have been endorsed by the NRC) with that provided by the Bachelor of

, Science programs in Nuclear Engineering (NE), Electrical Engineering (EE), and Mechanical Engineering (ME) at a reputable, accredited college. The results of this study are included as Attachment 1. As expected, the Nuclear Engineering

, curriculum comes closest to meeting the INPO objectives, but even it falls short in many significant areas. It is even more apparent that other engineering i programs are much less relevant to nuclear power plant operation. This leads to the obvious conclusion, which we have advocated for many years and which the TVSTC program adequately addresses, that it is very inappropriate to focus t O (15) For example, see IE Circular No. 81-04, "The Role of Shif t Technical

Advisors and Importance of Reporting Operational Events," and Enclosure A to SECY 84-106, " Proposed Rulemaking Concerning Requirements for Senior Managers."

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t 1 exclusively on the paper product (i.e. - B.S. degree) without any(16) regard to the curriculum content.

There is also a significant amount of material covered in Bachelors of Engineering programs which is irrelevant to nuclear power plant operation. We see no need to require that an individual serving in the dual role have this knowledge. The TVSTC program provides the required educational background; we see no need to expand this program to cover subject matter that is of little relevance to nuclear power operation.

It is important to understand that one of the primary objectives in developing the TVSTC Program was to structure a curriculum that would provide a thorough education in the areas of knowledge that are important in safe nuclear power plant operation. This program was specifically designed as a tailor-made Associates Degree Program in Nuclear Engineering Technology and was developed with substantial utility nuclear operations input. We are not aware of any other comparable custom-made program. We believe that this developmental effort is what makes the TVSTC program unique, and as a result, provides a comparable level of relevant knowledge as compared to the INPO guidelines. A copy of the course curriculum is included as Attachment 2 and a comparison of the curriculum to the INPO guidelines is provided in Attachment 3.

For these reasons, we believe that the TVSTC program which we have developed, combined with an SRO license, is the optimal approach to providing engineering expertise on shif t. .

Implementation of Dual-Role Qualification We believe it is apparent from the preceeding discussion that CYAPCO and NNECO have not merely been passively implementing a program that (originally) minimally met regulatory requirements. Recognizing the relatively long period of time required to upgrade the qualifications on all shif ts, we took the initiative to structure a program uniquely designed to be responsive to the engineering expertise on shif t issue. A substantial investment has been and continues to be made to ensure that individuals who are an integral part of the shift complement L have the desired level of expertise.

Further, CYAPCO and NNECO have not stopped at the point where only one individual on shift has dual role qualification. Rather, most shif ts have two dual-role qualified individuals. The attached Table 1 identifies the specifics for each unit as currently structured. We are not commiting to provide this additional

expertise to the NRC, but we have every intention of continuing to exceed the I

minimum requirements.

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! Summary As a result of the Final Policy Statement on Engineering Expertise on Shif t, no

(16) Note that any discussion of the specific knowledge that is required or the curriculum that should be followed is conspicuously absent from the Policy Statement.

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changes are planned by CYAPCO and NNECO with respect to our STA program.

Our plans for providing engineering expertise on shif t and utilizing the dual role concept with individuals qualified per the programs described above have been made explicitly clear to (and, in fact, approved by) the Staff in docketed correspondence for over five years. We firmly believe that the individuals presently serving in the dual role capacity are well qualified to provide the engineering expertise and accident assessment function, and will continue to do so. We believe that our TVSTC program should be judged acceptable by the Staff on a case-by-case basis.

In response to the second question posed by Generic Letter 86-04, we note that we do not use the concept of " equivalence" to describe our TVSTC program. We do not represent it as " equivalent" to a B.S. degree program. Rather, it is a better, more refined, and more directly relevant educational curriculum for satisfying the objectives of the Policy Statement, with which we agree completely.

We remain available to provide more details or to discuss our program with you at your convenience.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY NORTHEAST NUCLEAR ENERGY COMPANY O k b sr4

3. F. Opeka Senior Vice President By:'t. W. BIshof Secretary cc: F. R. Rowsome Division of Human Factors Technology

. .s Docket Nos. 50-213 50-245 3 50-336

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1 Attachment 1

, Comparison of INPO STA Guidelines 4

with Established Bachelors Degree Programs in Engineering 1

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i June,1986 i

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INTRODUCTION 4

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This brief compares Institute for Nuclear Power Operations (INPO)

, education and training guidelines for nuclear power plant licensed operators with course material provided by the Bachelor of Science program in Nuclear Engineering (NE). Electrical Engineering (EE) and Mechanical Engineering (ME) at Rensselaer Pol.ytechnic Institute (RPI).

In addition, this paper contains a sumary of the specialized education, specialized training and power plant experience guidelines for the Control Room Operator (CRO), Senior Control Room Operator (SCRO), Shift Supervisor (SS) and the Shift Technical Advisor (STA).

The information is formatted as follows:

1. Definitions This s,ection describes terms utilized in the paper.

2. Sumary of INPO Guidelines This section sumarizes the INPO guidelines for 1 specialized education, specialized training, power plant experience, nuclear power plant experience and site experience for the CRO, SCRO, SS and STA positions.

3. Specialized Education This section lists the specialized education subjects, the operator position requiring the subject, the number of instructional hours for each subject and g percentage of subject material covered by the nr2 progrsm.

4. Specialized Training l Same format as Specialized Education.

5. INPO Guidelines i

This last section provides a listing of topics contained,

. in each subject for both specialized education and specialized training, the operator position requiring the topics, and the number of instructional hours for each operator position. The column on the right indicates which topic is covered by the NE, EE or ME program at RPI.

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e DEFINITIONS Instructional Hour A one-hour period of training in which the course instructor (the appropriate supervisor in on-the-job training phases) is present or readily available for instructing or assisting the trainee. One hour devoted to any of the following activities is considered an instructional hour under this definition: lectures, seminars, dis-cussions, problem-solving sessions, quizzes, examinations, on-the-job training, laboratory exercises, and simulator exercises.

Power Plant Experience Experience acquired in the testing, operation, and maintenance of power generating facilities. Experience in the design, construction and operationaltraining may be considered applicable power plant experience and should be evaluated on a case-by-case basis.

Nuclear Power Plant Experience Experience acquired in the preoperational and startup testing activities or operation of nuclear power plants. Experience in design, construction, and operational training may be considered applicable nuclear power plant experience and should be evaluated on a case-by-case basis.

Experience acquired at military, non-stationary, propulsion, or production nuclear plants may qualify as equivalent to nuclear power plant experience on a one-for-two time basis up to a maximum of three years.

. Training may qualify as equivalent to nuclear power plant experience if acquired in reactor simulator training programs to a maximum of three (3) months credit.

. On-the-job training may qualify as equivalent to nuclear power plant experience on a one-for-one time basis for up to a maximum of two years credit.

On-the-Job-Training Participation in nuclear power plant startup, operation, maintenance. -

or technical services as a trainee under the direction of experienced personnel.

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SUMMARY

OF INPO GUIDELINES EDUCATION / EXPERIENCE CR0 SCR0 SS STA

1. Specialized Education (hours) 360 80 90 560

2. {

Specialized Training (hours) 835 831 40 560 -

575

3. Total Education and Training (hours) 1195 911 130 1120 -

1135

4. Power Plant Experience (years) 3 4 4 -

5. Nuclear Power Plant Experience (years) 1 2 2 1 6.

Time at the Site (months)

a. In operations, technical support, 6 engineering or training department.

b. Performing CR0 operational duties - 12 Required at site as SCR0 candidate (6)

c. Performing SCR0 operational duties -

12 Required at site as SS candidate (6)

d. At the site -

In training for STA at site 6 (3)

NOTE:

For CRO, 3 months of control room training may be credited toward the Item 5 requirement.

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MATERIAL LEVEL INPO GUIDELINES COVERAGE (%)

SPECIALIZED EDUCATION HRS NE EE ME

1. Mathematics 60/90 100 100 100

2. Reactor Chemistry 30/30 10 10 10

3. Reactor Theory 120/100 70

4. Nuclear Materials 40/40 30 30 30 CR0/STA

5. Thermal Sciences 70/120 100 30 50

6. Health Physics 40/40 70 STA 7. Electrical Sciences 60 30 STA 8. Nuclear Instrumentation and Control 40 100 SCR0/STA 9. Supervisory Skills 80/40 SS 10. Writing Skills 30 SS

11. Behavioral Sciences 60 o

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MATERIAL LEVEL INPO GUIDELINES COVERAGE (%)

SPECIALIZED TRAINING HRS NE EE ME

1. Plant Technology, Systems and Procedures 120

2. Administrative Requirements for Control 25 Room Operators

3. Control Room Training 520

4. Transient Prevention, Mitigation and 80 CR0 Response Training

5. Simulator Training 60

6. Recent Experience and Modifications 30

7. Procedures and Bases Training 120

8. Advanced Transient and Accident Analysis

a. Reactor Thermal Hydraulics 12

b. Containment of Radioactivity 20

c. Atmospheric Dispersion of 8 Radioactivity

d. Accident Assessment 40 SCR0

9. Plant Operations 15

10. In-Plant Training 520

11. Simulator Training 16 l

12. Advanced Electrical Components and 80 Systems Training SS

13. Administrative Requirements for Supervisors 40

14. Applied Fundamentals - Plant Specific 120

15. Plant Systems 200

16. Administrative Controls 80 STA ,

17. Special Operating Procedures 30 ,

18. Transient / Accident Analysis and 30-45 Emergency Procedures

19. Simulator Training (half in simulator) 100

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LEVEL INPO GUIDELINES NE EE ME MATHEMATICS

1. Functions X X X

2. Equations X X A Straight Line X X X Circle X X X

3. Slope of a line X X X

4. Polar and cartesian coordinates X X X

5. Quadric surfaces - sphere / cylinder X X X CR0/STA 6. Rate of change of a function X X X

7. Derivatives - Integration X X X Polynomial functions X X X Logarithmic functions X X X Exponential functions X X X

8. Areas by integration X X X

9. Applied solutions of differential X X X equations (first order)

Radioactive decay X X X Equilibrium activity X X X Reactor kinetics equations X X X Fission product poisons X X X General heat conduction equation X X X Hrs CR0 60

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STA 90 9

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LEVEL INPO GUIDELINES NE EE ME REACTOR CHEMISTRY

1. Metal-water reactions X X X

2. Corrosion of stainless steel and zircaloy

3. Effects of corrosion and corrosion products

4. Water chemistry control and limits CR0/STA 5. Radiochemistry

6. Sampling techniques and equipment

7. Analytical results and core conditions

8. Radiolysis and recombination

9. Hydrogen gas properties and precautions 9P

10. Inorganic chemistry associated with reactor systems Hrs CR0 30 SCR0 --

STA 30 l

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LEVEL INPO GUIDELINES NE EE ME REACTOR THEORY

1. Physics of neutrons X Sources X Energy classifications X Micro / macroscopic cross sections X Atomic concentrations X Fuels X Fission X Critical / Binding energy X 3 Mass defect and change in binding energy X Prompt / Delayed fission neutrons X

2. Neutron life cycle X Moderation X Diffusion X Leakage X Four/Six factor formula X CR0/STA 3. Reactor kinetics X Delayed neutron fractions X Reactivity X Period /Startup rate X Coefficients and reactor control X Burnable poisons X Lifetime effects X Fission product poisoning X Transient reactor behavior X

4. Reactor operations Power distribution Peaking factors Reactor startup and shutdown Fuel cycles Refueling effects Hrs CR0 120 SCR0 ---

STA 100 L

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LEVEL IMPO E DEU NES NE EE ME NUCLEAR MATERIALS

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1. Structure of metals X X X Crystal lattices X X X Phases and phase changes X X X Effects of inclusions and dislocations X X X

2. Properties of metals X X X Hardness Strength X X X Roughness Elasticity X X X Ductility Stress-strain X X X Malleability X X X

3. Characteristics of brittle fracture X X X Brittle fracture analysis Charpy V-notch X X X Nil-ductility transition temperature X X X Minimum pressurization temperature 4

4. Definition / purpose of alloying X X X Composition / properties of:

Carbon steels X X X Stainless steels Inconel Monel Copper-nickel Zircaloy CRO/STA l 5. Alloying and alloys used in reactor plant

6. Plant materials selection / applications l Bases for material selection i

Limitations of materials used

, Applications of materials

7. Fuel effects due to inclusions / core burnup "'8

8. Heatup/Cooldown limitations CR0 40

9. Irradiation effects SCR0 --

-10. Plant material problems / concerns STA 40 l Pellet- clad interaction Fuel densification Fuel / clad embrittlement i

'i Steam generator tube denting Fatigure failure

, Work hardening

LEVEL INPO GUIDELINES NE EE ME THERMAL SCIENCES

1. Thermodynamics X X X Laws X X X Water / Steam properties X X X Steam cycles X X X Efficiency X X X

2. Fluid Mechanics X X X Bernouilli's equation X X X Fluid friction X X X Head loss X X X STA Elevation head X X X Two phase flow X X X Pump / System characteristics

3. Heat Transfer X X Methods of heat transfer X X Boiling heat transfer X X Heat exchangers X X

4. Reactor heat transfer fluid flow X X Forced convection coolant flow X X Natural convection coolant flow X X Heat production after shutdown X Power density distribution anomalies X Heat transfer from fuel pellets to coolant X Boiling heat transfer X CR0 Transition boiling X Critical heat flux X Departure from nucleate boiling X Degradation of fuel pellets to coolant Vapor-binding / flow blockages Core flow distributions Fuel and cladding thermal limits Heat generation during operation Hrs i

CR0 70 SCR0 --

STA 120 l

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l LEVEL INPO GUIDELINES NE EE ME HEALTH PHYSICS

, 1. Units and concepts of radiation measurement X CR0 Roentgen X Rad X Rem X Dose X

,, Dose Rate X

. 2. Effects of radiation on matter X Plant materials X i Humans X

3. Methods of reducing exposure X Time X i

Distance X 1

Shielding X CR0/STA 4. Radiation source calculations X j Point source X Line source X Plane source X

Thumb rules for estimations X

5. Detection / measurement instruments X Personnel dosimetry X 1

Portable instruments X Process radiation monitors

Area radiation monitors

6. Detector principles i

Gas-filled detectors Scintillation detectors

' Self-powered detectors Nuclear instrumentation detectors Hrs 4

7. Provisions of 10CFR20

8. Contamination Control

. Controlled areas 30 40 1

Protective clothing SCR0 --

j Respirators i

, Decontamination STA 40 i

b, .,

LEVEL INPO GUIDELINES NE EE ME ELECTRICAL SCIENCES m

1. Electronics X Circuit theory X 3 Digttal electronics X

2. Motors X STA

3. Generators X

4. Transformers X

5. Instrumentation and control theory X

] ,

6. Switchgear X Hrs t

! CR0 --

, SCR0 --

STA 60 i

h I

___- _ i

LEVEL INPO GUIDELINES NE EE ME NUCLEAR INSTRUMENTATION AND CONTROL

~

1. Radiation detectors X

2. Reactor instrumentation X STA

3. Reactivity control X

4. Reactivity feedback X Hrs CR0 --

, SCR0 --

STA 40

o. . .

LEVEL INPO GUIDELINES NE EE ME SUPERVISORY SKILLS

1. Communication Skills Interpersonal comunication (verbal /non-verbal)

Listening Feedback Sensitivity Written communication

2. Analytical Skills Problem analysis Decision making Planning Organizing

3. Leadership Skills Motivation of personnel ,

Professionalism Attitude -

Morale Standards of perfonnance Personnel development and appraisal Combatting stress and boredom Crisis management Stress management ,

STA Directing P

Hrs CR0 --

SCR0 80 STA 40

)

l

4 &

i i LEVEL INPO GUIDELINES NE EE ME WRITING SKILLS SS 1. Effective Writing a

I l

i i

4 i

i  :

i I

f 4

1 i

. I i

Hrs

, i 1

i 1

CR0 --

SCR0 --

i~

STA --

4

. SS 30 4

h i

l i

LEVEL INPO GUIDELINES BEHAVIORAL SCIENCES

1. Behavioral S;iences SS Physcheiogical assessment Behavior modification Individual / group counseling f

I 6

Hrs -

CR0 --

SCR0 --

~

• STA --

SS 60

i LEVEL INPO GUIDELINES NE EE ME PLANT TECHNOLOGY. SYSTEMS AND PROCEDURES

1. Purpose of the system, including design bases

2. System components, including locations and characteristics

3. Normal and alternate power supplies

4. Precautions. limitations, and setpoints and their bases

5. Interrelationships with other systemt

6. Automatic features of system operation e

7. Alternate / manual / local methods of system and  !

CR0 component operation

8. Instrumentation, indications, alarms, and controls '

(with emphasis on the control room) 7

9. Failure modes of controls and instruments ,

10. Norum1 values for significant parameters  !

11. Rules of thumb .

12. Technical specifications l

13. Normal, abnormal, and emergency operating procedures

, 14. Surveillance procedures Hrs t

CR0 120 i

- - . - - - , . _ . _ - - , _ , - - _ - . . . , , _ _ . _ _ , - . . . - - . . - , - - , - - . _ , . _ . . - - , - - . _ _ - . m._-.. . _ - - , - _ - . - - . - - _ - . , . _

o, -

l l

LEVEL. INPO GUIDELINES NE EE ME ADMINISTRATIVE REQUIREMENTS FOR CONTROL ROOM OPERATORS

1. Position description of Control Room Operator position

2. 10CFR

3. Shift turnover

4. Operator logs

5. Maintaining cognizance of plant status

6. Use of normal and emergency procedures

7. Quality assurance for operators

8. Containment entry procedures and controls

9. Tagout procedures

10. Instrument out-of-service procedures

11. Reports and notification CR0 12. Shift duties and responsibilities

13. Radiation Work Permits

14. Radioactive and National Pollution Discharge Elimination System release

15. Administrative radiation protection limits

16. Plant modifications

17. Document and drawing control

18. Duties of system load dispatcher and interfaces with Control Room Operator

19. Position-related corporate policies Hrs CR0 25 -

o. .

LEVEL INPO GUIDELINES NE EE ME CONTROL ROOM TRAINING o

l. Plant or reactor startup and power escalation to a range where reactivity feedback from nuclear heat addition is noticeable and heatup rate is established

2. Plant shutdown

3. Manual control of feedwater flow during plant start-up and/or shutdown.

4. Boration and/or dilution during power operation (PWR)

5. Reactor power changes of 10% or greater where rod control is in manual or where recirculation flow is controlled manually

6. Reactor power changes of 10% or greater where load change is performed with load limit control or where flux, temperature, or speed control is on manual (HTGR)

CR0

7. Operation of turbine controls during turbine setup

8. Surveillance testing of safety-related systems, the performance of which is done or coordinated i

from the control room

9. Residual heat removal system operation

10. Control of primary pressure under solid water conditions if plant status permits (PWR)

11. Incore instrumentation system operation

12. Control room calculations including heat balance, coolant inventory balance, and reactivity balance

13. Refueling Hrs i

CR0 520

LEVEL INPO GUIDELINES NE EE ME TRANSIENT PREVENTION, MITIGATION AND RESPONSE TRAINING

1. Recognize and respond correctly to casualty sit-uations utilizing existing procedures.

2. Explain automatic and immediate operator actions in response to casualty situations.

3. Diagnose unanticipated conditions and initiate proper response.

4. Describe alternate success paths for accomplishing a function

5. Integrated plant transient response

6. Accident analysis CR0

7. Abnorum1 and emergency operating procedures

8. Site fire plan

9. Recognition and mitigation of consequences of core damage (note: The INP0 document titled

" Guidelines for Training to Recognize and Mitigate l the Consequences of Core Damage" provides guidance

! for this topic)

10. Site radiological emergency plan including meteorology and calculation of release rates (as applicable)

11. Control room abandonment procedures Hrs CR0 80

---

_______-__---__--_---__-_---_-----_--____j

LEVEL INPO GUIDELINES NE EE ME SIMULATOR TRAINING a

1. Reactor trip / runback

2. Turbine or generator trip

3. Loss of coolant including:

Steam generator leaks (PWR)

Pressurizer leaks (PWR)

Large and small leaks located inside and outside of primary containment (including leak rate determination)

Saturated Reactor Coolant System response (PWR)

4. Loss of coolant flow / natural circulation

5. Loss of all feedwater (normal and emergency)

6. Nuclear instrumentation failure (s) -

7. Non-nuclear instrumentation failure (s)

8. Loss of protective system channel (s)

9. Mispositioned control rod (s) (or rod drops)

10. Inability to drive control rods

11. Conditions requiring use of emergency boration or standby liquid control system CR0

12. Fuel cladding failure or high activity in reactor coolant or offgas

13. Malfunction of automatic control system (s) which affect reactivity l 14. Malfunction of reactor coolant pressure / volume control system

15. Loss of instrument air

16. Loss of electrical power and/or degraded power j sources Mrs

17. Loss of condenser vacuum l 18. Loss of service water

19. Loss of shutdown cooling

20. Loss of component cooling system or cooling l -

to an individual component -

l 21. Loss of normal feedwater or normal feedwater j system failure

22. Main steam line break (inside or outside

, containment)

CR0 60 e 23. Reactor coolant pump seal i

i i

l a*---%--- e- g i or- wu r'rg - wyr

e, * .

LEVEL INPO GUIDELINES NE EE ME RECENT EXPERIENCE AND MODIFICATIONS The amount of time required for this training will vary depending on the number and complexity of events or modifications to be covered. The Training Supervisor and/or Operations Supervisor should determine the operating experiences to be discussed.

CR0 Sources of information include Licensee Event Reports and analyses from the Significant Event Evaluation and Information Network (SEE-IN) program carried out by the Nuclear Safety Analysis Center (NSAC) and INP0. Any significant modifications or additions to plant systems and procedures which have been made since training in those topics was conducted should be addressed.

Hrs CR0 30

LEVEL INPO GUIDELINES NE EE ME PROCEDURES & BASES TRAINING

~

1. Administrative procedures for:

Health physics Maintenance Technical support

2. Radioactive material control procedures Containment control policies and procedures Control of calibration sources Transportation of radioactive materials, including applicable portions of 10 CFR 71 SCR0 and 49 Policies and procedures regarding off-site release of radioactive effluents

3. Facility license and design bases, including applicable portions of 10 CFR 50 and 10 CFR 100

4. Technical Specification (emphasizing bases)

5. Environmental technical specifications

6. Duties of system load dispatcher related to on-site equipment and relationship with plant operators i

Hrs i

l SCR0 120 l

k 7

4 LEVEL INPO GUIDE W ES i NE EE ME ADVANCED TRANSIENT & ACCIDENT ANALYSIS REACTOR THERMAL HYDRAULICS 1.' Forced convection coolant flow Conditions reqeired for pump operation Effects of core damage

2. Natural convection coolant flow Conditions required / initiating SCR0

. Recognizing /op_timizing Two-phase flow .

Vapor binding / flow blockage

3. Heat transfer from fuel to ultimate heat sink -

Gap conductance-Pellet / clad deformation effec'ts Departure frcm nucleate boiling Available heat sinks -

Residual heat rates. , ,

I i

f Y

., 1 i

P

.. la Hrs

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4 f ~~

'l t L

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SCR0- 12

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\

a 5

LEVEL INPO GUIDELINES NE EE ME ADVANCED TRANSIENT & ACCIDENT ANALYSIS 3 CONTAINMENT OF RADI0 ACTIVITY

1. Degradation / failure mechanisms of fuel and cladding Pellet densification Cladding creep Zirconium hydriding Pellet-clad interaction Internal-external pressure considerations Waterlogging Zirconium-water reaction Crystalline phase changes

, SCR0

2. Brittle fracture analysis and prevention

3. Containment building and penetration design

, criteria a

g 4. Plant-specific containment building features

, and limitations Pressure suppression systems Iodine removal systems

, Hydrogen control systems 4

s

\

m

.1 I Hrs

,.it

A

~

c SCR0 20 l8 ,

c.

,1

i

',.L 4 ,

z ~;

es s

t ,,

LEVEL INPO GUIDELINES NE EE ME ADVANCED TRANSIENT & ACCIDENT ANALYSIS ATOMOSPHERIC DISPERSION OF RADI0 ACTIVITY

~

1. Meteorological categories and their characteristics

2. Plant meteorological instrumentation SCR0

3. Determination of meteorological categories using installed plant systems

4. Atmospheric dispersion calculations e

Hrs

, SCR0 8 ,

.. .. l LEVEL INPO GUIDELINES NE EE ME ADVANCED TRANSIENT & ACCIDENT ANALYSIS ACCIDENT ASSESSMENT

1. Describe the sequence of events which could initiate each accident.

2. Discuss the expected values of critical parameters as the accident progresses.

3. State the anticipated indications, automatic actions, and immediate operator actions for each accident.

4. Describe the long-term actions required for core cooling and plant stabilization.

5. Describe alternate power supplies and system lineups available to cope with the accident.

6. Describe the initial plant conditions assumed SCR0 in accident analyses.

7. Discuss the effects on accident progression of initial plant conditions outside the values assuned in accident analyses.

8. Given a set of control room indications, explain what accident conditions exist.

9. Recognize a condition for which no procedures exist and recommend operator actions to maintain core cooling and stabilize the plant.

10. Analyze symptoms and ensure appropriate procedures

, are used to stabilize the plant in a safe condition.

Hrs SCR0 40

LEVEL INPO GUIDELINES NE EE ME PLANT OPERATIONS

1. Shiftduitesandresponsibilities(including position description operating positions)

2. Corporate policies affecting this and subordinate positions

3. Radiation Work Permit procedures SCR0

4. Equipment tagout and clearance procedures

5. Emergency Plan implementation

6. Routine and emergency communications capabilities

7. Routine and emergency reporting and notification requirements

8. Relationship to utility, local, state, and federal officials Hrs SCR0 15

LEVEL INPO GUIDELINES NE EE ME i

IN-PLANT TRAINING ,

A qualification check-sheet prepared by each facility is essential to provide guidance and structure for the In-Plant Training phase. This check-sheet should emphasize tFe supervisory role of the Senior Control Room Operator and state evolutions and oper-ations to be conducted, observed, or simulated by the trainee as well as items whicn the candidate should discuss with a qualified Senior Control Room Operator or Shift Supervisor. Examples of items on such a check-sheet are:

i. preparations and administrative requirements for reactor startup and shutdown

2. fuel handling and inspection

3. emergency and routine maintenance practices

4. calculations of offsite radioactive releases SCR0 during emergencies

5. requirements concerning radioactive releases and shipments

6. chemistry sample and radiation survey frequency and interpretation

7. emergency communication equipment and procedures S. coordination of surveillance testing Hrs SCR0 520 f

J

~

LEVEL INPO GUIDELINES NE EE ME SIMULATOR TRAINING

1. Develop and improve transient / accident analytical skills SCR0

2. Develop supervisory skills for the Senior Control Room Operator position

3. Develop comand responsibility skills Hrs

~

SCR0 16

LEVEL INPO GUIDELINES NE EE ME ADVANCED ELECTRICAL COMPONENTS AND SYSTEMS TRAINING m

1. Motor, generator, and transformer design types and characteristics

2. Main generator capability curves, operating limits, and precautions

3. Control circuits for in-plant electrical switchgear SCR0 4. Control circuits for utility grid switchgear

5. Utility grid and interconnections with other grids

6. Electrical ground detection systems (including main generator field)

7. Protective relaying theory and application

8. Procedures for restoring station power following blackout l

Hrs SCR0 80 -

l i

LEVEL INPO GUIDELINES NE EE ME ADMINISTRATIVE REQUIREMENTS FOR SUPERVISORS

1. Position description of Shift Supervisor and subordinate positions

2. Corporate policies affecting this and subordinate positions

3. Radiation Work Permit procedures

4. Equipment tagout and clearance procedures

5. Plant modification process

6. Quality assurance and control requirements

7. Shift relief turnover and manning

8. Unit interface controls (multi-unit plants)

SS

9. Site security and access control

10. Emergency Plan

11. Code of Federal Regulations (appropriate sections)

12. Plant and Enviornmental Technical Specifications (including bases)

13. Procedures for effecting emergency maintenance

14. Procedures for obtaining management, engineering, and technical support

15. Policy on release of information to news media

16. Relationship with bargaining unit employees (if applicable) v 17. Normal and emergency reporting requirements l

Hrs 9

SS 40 l

l l

l

INPO WIDELINES LEVEL NE EE ME APPLIED FUNDAMENTALS - PLANT SPECIFIC

1. Plant-Specific Reactor Technology (including core physics data)

2. Plant Chemistry and Corrosion Control STA

3. Reactor Instrumentation and Control

4. Reactor Plant Materials

5. Reactor Plant Thermal Cycle

! Hrs i STA 120 l .

l l

LEVEL INP0 GUIDELINES NE EE ME PLANT SYSTEMS

1. Emergency core cooling

2. Emergency cooling water

3. Emergency electrical power, AC and DC

4. Reactor Protection

5. Reactor coolant l

6. Reactor coolant inventory and chemistry control

7. Containment System (including containment cooling)

8. Closed cooling water

9. Nuclear Instrumentation

10. Non-nuclear instrumentation

11. Reactor control

12. Containment hydrogen monitoring and control STA 13. Radioactive waste disposal (liquid, gas, solid)

14. Emergency control air

15. Condensate and main feedwater

16. Auxiliary feedwater

17. Steam generator level control (PWR)

18. Reactor vessel water level control (BWR)

19. Main steam

20. Loose parts monitoring (PWR)

21. Status monitoring (including process computer)

22. Seismic monitoring

23. Residual heat removal

24. Radiation monitoring Hrs

25. Plant ventilation

26. Main turbine and generator l

STA 200

' INPO GUIDELINES LEVEL NE EE ME ADMINISTRATIVE CONTROLS

1. Responsibilities for safe operation and shutdown

2. Equipment outages and clearance procedures

3. Use of procedures

4. Plant modifications

5. Shift relief turnover and manning

6. Containmant access

7. Maintaining cognizance of plant status

8. Unit interface controls (multi-unit plants with STA one or more units still under construction)

9. Physical security

10. Control room access

11. Administrative requirements of the STA

12. Radiological emergency plan

13. Title 10 Code of Federal Regulations (appropriatesections)

14. Plant technical specifications (including bases)

15. Radiological control instructions Mrs l

I STA 80 i

INPO GUIDELINES LEVEL NE EE ME SPECIAL OPERATING PROCEDURES

1. Startup

2. Power Operations

3. Shutdown STA

4. Xenon-following while on standby

5. ECP and S.D. margin calculation

6. Others as appropriate for the station Hrs STA 30 ,

LEVEL INPO GUIDELINES

_ TRANSIENT / ACCIDENT ANALYSIS AND EMERGENCY PROCEDURES

1. Transient and accident analyses STA

2. Plant abnormal and emergency procedures emphasizing the STA role i

1 Hrs STA 30 -

40 -

I

LEVEL INPO GUIDELINES NE EE ME SIMULATOR TRAINING a

PWR Simulator Exercises

1. Reactor and plant startup

2. Load changes at power

3. Shutdown to cold condition

4. Demonstration of steam generator level manual

. control

5. Load rejections of greater than 10%

6. Failure of rod control system

7. Failure of automatic steam generator level controls

8. Failure of pressurizer level and pressure automatic controls

9. Turbine trip from full power

10. Reactor trip from full power

11. Loss of normal feedwater at full power

12. Failure open of power operated relief valve

13. Stuck open pressurizer safety valve

14. Loss of reactor coolant pumps at full power and demonstration of natural circulation STA 15. Failure open of one or more turbine bypass valves while at a) full power b) hot standby

16. Loss of all feedwater (normal and emergency)

17. Loss of reactor coolant (small and DBA)

18. Steam generator tube rupture (small and large)

19. Loss of RHR shutdown cooling with the RCS temperature 200* to 300'F Hrs

20. Inadvertent safety injection while at power

21. Loss of offsite electrical power

22. Loss of one train of onsite electrical power j BWR Simulator Exercises i 1. Reactor and plant startup

2. Load changes at power (using flow control when applicable) l

,, 3. Shutdown

LEVEL INPO GUIDELINES NE EE ME SIMULATOR TRAINING BWR Simulator Exercises (Con't)

4. Load rejection of greater than 10%

5. Turbine trip from full power

6. Turbine bypass valve failure to open following trip

7. Inadvertent closure of MSIV's while at power

8. Reactor scram from full power

9. Reactor pressure control failure

10. Dropped control rod while at power STA

11. Cold water transient at power

12. Inadvertent opening of relief valve

13. Loss of main feedwater pumps at power

{ 14. Inadvertent start of idle recirculation pump

15. Inadvertent trip of recirculation pump (s)

16. Loss of reactor coolant (small break - large break)

17. Steam Line Break (inside/outside containment)

18. Loss of offsite power

19. Loss of shutdown cooling with RCS temperature 200 - 300 F

20. Demonstration of natural circulation capabilities l

21. Malfunction of reactor water level automatic controls Mrs STA 100 t

r Docket Nos. 50-213 50-245 50-336 Attachment 2 Thames Valley State Technical College Nuclear Engineering Technology Curriculum June,1986

THAMES VALLEY STATE TECHNICAL COLLEGE NUCLEAR ENGINEERING TECHNOLOGY Effective September 1, 1985 FIRST YEAR SECOND YEAR Weekly Qtr Weekly Qtr FIRST QUARTER CI Lab Cr FOURTH QUARTER CI Lab Cr DP 238 Basic ~7 2 3 NS 120 Reactor T 0 4 Theory I MA 110 Tech. Math. I 4 0 4 MA 210 Calculus II 4 0 4 PH 111 Physics (Mech) 3 2 4 MT 231 Appl. Thermo. I 4 0 4 CH 122 Princ. of Chem. 3 2 4 MT 232' Fluid Mechanics 3 2 4 XX XXX NET P01 4/3 0/0 4/3 AS 221 Psych. &

Hum. Rel. 4 2 4 Totals........ 16/15 6 19/18 Totals......... 19 2 20 SECOND QUARTER FIFTH QUARTER ET 225 Elec. & Electr. 3 2 4 NS 210 Reactor TheoryII 4 0 4 MA 120 Tech. Math. II 4 0 4 ET 213 AC/DC Machinery 3 2 4 PH 121 Physics (HSL) 3 2 4 MT 236 Heat Transfer 3 2 4 AS 120 Basic. Comm. 4 0 4 AS 212 Economics 3 0 3 NS 110 Atomic Physics 4 0 4 MT 133 Appl. Mechanics 4 0 4 Totals......... 18 4 20 Totals....... 17 4 19 THIRD QUARTER SIXTH QUARTER XX XXX NET P02 3/4 0/0 3/4 MA 130 Calculus I 4 0 4 NS 220 Nuclear Mat. 3 2 4 AS 130 Tech. Comm. 4 0 4 ET 239 Auto. Proc. 3 2 4 NS 130 Reactor Chem. 4 0 4 Cont. Systems MF 212 Mat. of Engr. 3 3 4 NS 222 Rad. Health 3 2 4 NS 231 Topics in Nuc. 3 0 3

& Saf. Power Ops.

AS 232 Sociology 3 0 3 Totals......... 18 5 20 XX XXX NET P03 3/1 0/3 3/2 Totals...... 18/17 4/7 20/20 PROGRAM OPTIONS (PO)

Raactor Operator (RO)

P01 IM 210 Per Mgt 4 0 4 P02 MF 115 NDT 3 0 3 TOTAL QUARTER CREDITS - 118/117 P03 IM 232 Prin of Sup 3 0 3 TOTAL CONTRACT HOURS - 131/132 Non-Reactor Operator (NRO)

P01 NS 221 Nuc Sys 3 0 3 P02 AS 110 Intro to Lit 4 0 4 P03 NS 232 Nuc Reac Sim 1 3 2

. i o Docket Nos. 50-213 50-245 50-336 i 1 F i

d Attachment 3 Comparison of the Thames Valley State Technical College Nuclear Engineering Technology Curriculum to the INPO STA Guidelines 1

4 i

i d

i 4

i.

1

?

4 i

i a

l June,1986 ,

1.

l. . - - , . _ . - .. . . . - - - - , _ _ . - . - . . . - , . - , . . . -_ -- .

e ..4.- 4a L*-.-.

Attachment 3 PROGRAM TITLE - SHIFT TECHNICAL ADVISOR .

Contact Hours INPO Guidelines TVSTC Courses INPO TVSTC 4

1. Trigonometry & College MA110 Tech Math I 80 88 Algebra MA120 Tech Math II

2. Inorganic Chemistry CH122 Principles of Chemistry 35-45 44

3. Physics (Heat, mechanics, PHill Physics (Mech) 120-150 176 light sound, electricity, PH121 Physics (HLS) magnetism) ET225 Elect & Electronics MT133 Applied Mechanics

1. Engineering Mathematics MA130 Calculus I 90 88 MA210 Calculus II

2. Reactor Theory NS110 Atomic Physics 100 154 NS120 Reactor Theory I NS210 Reactor Theory II NS232 Nuclear Reactor Simulation

3. Reactor Chemistry NS130 Reactor Chemistry 30 44

4. Nuclear Materials MP212 Materials of Engineering 40 88 NS220 Nuclear Materials

5. Thermal Sciences MS231 Applied Thermo I 120 132 MT232 Fluid Mechanics MT236 Heat Transfer

6. Electrical Sciences ET213 AC/DC Machinery 45 88 ET239 Auto Process Control Systems

7. Nuclear Inst'rumentation No specialized course, intermixed 40 --

and Control with above (Part Rad detection, reactivity feedback and Rx s

instrumentation)

S Contact Hours INPO Guidelines TVSTC Courses INPO TVSTC

8. Nuclear Radiation Protection NS222 Nuclear Radiation Health 40 44 and Health Phsyics and Safety

9. Plant Specific Fundamentals NS231 Topics in Nuclear Power 120 33 (also inc. in license programs) Operations

10. Management / Supervisory Skills AS221' Psychology & Human Relations 40 308 (some non-INPO) JM210 Personnel Management IM232 Principles of Supervision AS120 Basic Communication AS130 Technical Communication DP238 Intro to Programming: BASIC (Included in License Programs)

11. Plant Systems N/A 200 N/A

12. General Operating Procedures N/A 30 N/A

13. Administrative Controls

• N/A 80 N/A

I

14. Transient & Accident Analysis e ,' N/A 30-45 N/A and Emergency Procedures i d'

15. Simulator Training N N/A 60 N/A l

l 6/1.40 i

4

~

r. ,

- a ..e, % .

4 Docket Nos. 50-213 l 50-245 50-3E -

l Table 1 ,

Haddam Neck Plant Millstone Unit Nos. I and 2 Qualified Shift Technical Advisors .

t I

I i

l l

j' ' .

'l t i,

June,1986

+ i n

. . , . - , , ,,,vn,,--__._,.-- .,,,~-~r-,.

, _ , - , . - , . . , - , - ,e . . _ , .-_-,..-,,,n,-m

r - .

.s seae Table !

Qualified Shif t Technical Advisors at Haddam N.eck, Millstone Unit No. I and Millstone Unit No. 2W Haddam Neck Millstone 1 Millstone 2 Qualified STAS (Total) 10 13 8 shif t Supervisors 6 6 6 Senior Control Room Operators 4 6 2 Control Room Operator -

1 -

(1) A total of six shif ts are utilized at each plant. Of the total of 18 shif ts,11 shif ts have two dual role qualified personnel, I shift has three, and 6 shif ts have one.

f 4

. . . , , , - . - . . , . , , , - - - - - - - -