ML20041B081
| ML20041B081 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 02/18/1982 |
| From: | Johnson W PUBLIC SERVICE CO. OF NEW HAMPSHIRE, YANKEE ATOMIC ELECTRIC CO. |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.1, TASK-1.D.1, TASK-TM SBN-215, NUDOCS 8202230253 | |
| Download: ML20041B081 (26) | |
Text
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e PUBLIC SERVICE SENM SWION Engineering Office:
Companyof NewHampshir e 1671 Worcester Road Frominoham, Massachusetts 01701 (617). 872 8100 February 18, 1982 SBN-215 g
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United States Nuclear Regulatory Cormission 9.
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Washington, D. C.
20555 Attention:
Mr. Robert L. Tedesco Assistant Director for Licensing Division of Licensing 4
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References:
(a) Construction Permits CPPR-135 and CPPR-136, Doc Hos. 50-443 and 50-444 (b) HUREG-0737 Item I. A.1.1, " Shift Technical Advisor" (c) NUREG-0737 Item I.D.1, " Control Room Design Reviews" (d) ANS 3.1, Section 4.3.1 Draft Revisions dated 12/6/79 and 10/23/80
Subject:
Upgraded Qualifications for Seabrook Station Licensed Operators
Dear Mr. Tedesco:
Public Service Company of New Hampshire (PSNH) has implemented a long-term program for Seabrook Station which substantially upgrades the qualifications of the supervisory licensed personnel on-shift and improves the man-machine interface in the control room. This program is in lieu of the short-term requirement of Reference (b) to have an STA on shift.
In developing this program, PSNH considered the requirements of published or proposed NRC and industry rules and guidelines for long-term programs.
In fact, the PSNH program meets or exceeds the requirements contained in References (b), (c),
and (d).
The PSNH program satisfies the concerns identified as a result of the Three Mile Island incident; specifically - upgraded SR0 qualification and training, improved control room man-machine interface, reduced administra-tive burden on operating shift personnel, and the performance of operational assessment and accident assessment. These issues are addressed in detail in the following attachments:
Attachment #1 - Shift Manning and Normal Operations Attachment #2 - Qualification and Training Attachment #3 - Review of the Control Room Man-Machine Interface Attachment #4 - Operational Assessment Attachment #5 - Accident Assessment Dn(
Attachment #6 - Assignment of Administrative Duties 3
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U. S. Nuclear Regulatory Commission February 18, 1982 Attention: Mr. Robert L. Tedesco Page 2 s
Several substantive factors which prompted PSNH to conclude that our long-term program is the logical and most effective way to proceed are summarized below:
1.
Five years will have elapsed between the incident at TMI II and the anticipated comercial operation of Seabrook Station I.
This span provided sufficient time in which to plan a meaning-ful approach and conduct the appropriate training of personnel.
2.
Seabrook has built a site specific simulator which will be used to practice and perfect the envisioned organizational interac-tions and plant procedures which integrate the duties and re-sponsibilities of the Shift Superintendent and Unit Shift Supervisor positions.
3.
The station operating philosophy is to provide a supervisor (the Unit Shift Supervisor) for each unit whose attention can be exclusively directed to the safe and efficient operation of the unit. This philosophy will be implemented by administrative procedures and by providing the necessary experienced technical and managerial support (the Shift Superintendent) to accomplish those functions which might distract the Unit Shift Supervisor from his unit command and control duties.
4.
PSNH had emba' ked upon a licensed training program substantially upgraded from those generally found in the industry and upon an improved control room man-machine interface before the present short-term requirements were established.
PSNH understands that the NRC has r.ot fully established the exact extent of the needed upgrade of personnel qualifications or the required improvements in the man-machine interface in the control room. However, tne NRC has pro-vided guidance in these areas which has been sufficient to develop the long-term program at Seabrook.
It is our conclusion that the comprehensive, long-term program described in the attachments to this letter obviates the need for a separate Shift Technical Advisor on shift and provides an acceptable alternative to Standard Review Plan Section 13.1.2, Acceptance Criteria II.C.8.
It is requested that a mutually convenient meeting be arranged through the NRC Seabrook Project Manager to more fully discuss this program and answer any questions you may have.
In the interest of maintaining the current Safety Evaluation Report schedule for Seabrook, it is appropriate that this meeting should take place no later than the end of March,1982.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY h
hW W. P Johnson Vice President cc: Mr. Frank Miraglia, Chief Licensing Branch #3
U. S. Nuclear Regulatory Commission February 18, 1982 Pdge 3 Attention: Mr. Robert L. Tedesco i
COMMONWEALTH OF MASSACHUSETTS)
)ss MIDDLESEX COUNTY
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Then personally appeared before me, W. P. Johnson, who, being duly sworn, did state that he is a Vice President of Yankee Atomic Electric Company, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Public Service Company of New Hampshire and that the statements therein are true to the best of his knowledge and belief.
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A. L. Legerrdre, Jr.
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Attachment #1 Shift Manning and Normal Operation Each unit is operationally staffed with licensed operators as follows:
Position License No. Per Unit Per Shift Unit Shift Supervisor SRO 1
Supervisory Control Room Operator R0 1
Control Room Operator R0 1
A Shift Superintendent (SRO) for the site and five non-licensed auxiliary opera-tors will be assigned to each shift. Two auxiliary operators will be assigned to each unit with the fifth assigned by the Shift Superintendent to Unit 1 or Unit 2 as station priorities dictate.
The senior on-shift management position at Seabrook is the Shift Superintendent.
The Shift Rup9rintendent will hold a current SRO license and will coordinate the activities of botL 'inits.
The source of direction for the Shif t Superintendent is the Assistant Operations Manager (see attached organization chart) and the Shift Superintendent provides direction and supervision to the Unit Shif t Supervisors and coordinates the activities of other personnel assigned to the shift as shown below:
Shift Superintendent i
i 1
I Unit Shift Unit Shif t On-Shift Supervisor Supervisor Support Security Unit 1 Unit 2 Personnel The Shift Superintendent provides direction, guidance or advice to the Unit Shift Supervisors and acts as the interface with the on-site staff as needed to allow the Unit Shift Supervisors to perform their functions. The Shift Superintendent will insure that station activities are coordinated and are carried out with the priorities necessary to yield maximum safe station availa-bility.
The Unit Shift Supervisor is directly responsible for the safe and efficient operation of the unit to which he is assigned. He has the authority to provide the command and control function for the unit. The Unit Shift Supervisor directs and supervises all personnel assigned to the unit and insures that they have a complete understanding of the existing unit conditions and that the unit is operated within license and administrative limits.
SEABROOK STATION ORGANIZATION CHART OPERATIONS
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An CorRATIONS MANAGER 1
OPER AOMM.
STARTUP COORDINATOR t
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SUPDMSOR I
TECH AIDE CLERICAL ASST OPER.
MANAGER I
l I
tt M
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T 4
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TRAJNEES SHf T UNIT SHFT DAY SH!FT N.E VdSTE SPERWTDCOiT SUPERVGOR/
SUPERNTD40D(T FAC1JTY SUPV.
i TRAINEE l
12 6
2 2
1 l
30 v)
I I
I RAC%"TNE UNIT SHIFT Lt.1T SHFT MSTE TECK SUPDMSOR SPD MSOR 3
6 6
SUPERVGORY SUPONS)Rf OONTROL F400M OONTR2. ROOM OPERATOR OPERATOR 6
6 CONTROL ROOM CCf4 TROL ROOM OPERATOR OPERATOR 6
6 14JX;LIARY OPERATOR 6
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i AUXILIARY AUXX.! arf OPERATOR OPERATOR I2 12
8 Attt chment #2 Qualification and Training The details of the Seabrook License Training Program are outlined in the attached paper titled Operator License Training Program. Minimum qualifications for on-shift licensed positions are as follows:
Power Plant Nuclear Plant Position Education Experience Experience Shift Superintendent H.S. + 60 College 4 yr.
2 yr.
semester hrs.
Unit Shift Supervisor H.S. + 60 College 4 yr.
2 yr.
semester hrs.
Supervisory Control Room H.S. + 30 College 4 yr.
1 yr.
Operator semester hrs.
Control Room Operator H.S.
2 yr.
1 yr.
These qualifications meet the requirements of ANS 3.1 draf t revisions 12/6/79 and 10/23/80 for both the Shif t Superintendent and the Unit Shif t Supervisor to fill the position " Shift Supervisor" without an STA. The R0 and SRO license training programs have been expanded to include 30 equivalent hours of college level instruction in appropriate engineering subjects. The Shift Superintendent and Unit Shif t Supervisor program includes more than 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> of college level instruction in appropriate engineering subjects. The Shift Superintendent and Unit Shif t Supervisor will receive all of the training recommended in NUREG-0737, Appendix C, Section 6 for an STA.
The effectiveness of the education and experience requirements in ensuring excellence in on-shif t performance is enhanced by the time spent operating the site specific simulator. The program includes exercising the functional aspects of the organizational relationships and appropriate procedures during normal, emergency and accident conditions through the use of the simulator.
The result of the combination of experience, education and practice leads to the enhanced communications between the senior on-shif t positions which are necessary during emergency and accident conditions.
i Attachment #2 PUBLIC SERVICE C0hPANY OF NEW HAMPSHIRE Seabrook Station Units 1 & 2 Operator License Training Program A.
GENERAL DISCUSSION The program will provide personnel associated with the start-up and opera-tion of Seabrook Station, Units 1 and 2, training in various disciplines necessary to insure that each individual can safely and effectively per-form his various assignments. The degree to which an employee is trained will be consistent with the individual's experience, intended position and regulatory requirements.
The overall objectives of the training program are:
To train a staf f to operate and maintain the units safely, dependably and economically.
To prepare shift superintendents, unit shift supervisors, control room operators and selected station managers for the NRC licensing examina-tion for Reactor Operator (RO) and Senior Reactor Operator (SRO).
The safe, ef ficient operation of a nuclear power plant depends extensively on the qualifications and proficiency of its personnel. Several basic cate-gories of training are necessary to provide the high degree of competence and professionalism. Specifically, these categories of training are as follows:
1.
General Employee Training This category of training involves all plant personnel, and encompasses such areas as initial orientation, general administration and organiza-tion, a radiological health and safety course, plant safety and security, and emergency plan actions.
2.
Operator License Training All personnel requiring NRC operating licenses, as specified in ANSI /ANS 3.1-draft revision 1980, will have to undergo intensive training which will meet or exceed the minimum requirements of 10CFR55.
The Licensed Operator Training Program conducted one time prior to the initial criticality is termed " Cold License Training Program". The Replacement Operator Training Programs completed af ter initial critica-lity are termed " Hot License Training Programs".
1 _
'3.
shift Technical Advisor Training Public Service Company of New Hampshire has upgraded the training program for the Shif t Superintendents and Unit Shif t Supervisors to meet the long term plan of eliminating the need 'or a Shif t Technical Advisor on shif t.
Table 13.2.2 provides the co:parison of Seabrook's license program to the recommended guidelines referenced by NUREG-0737.
4.
Operator Requalification Program This category describes the training necessary to maintain the profi-ciency of all Seabrook licensed personnel. This program will meet or exceed the minimum requirements of 10CFR55, Appendix A.
In addition, the annual requalification recommendations for shif t technical advi-sors, per Attachment C of NUREG-0737, shall be included in the requali-fication program for unit shif t supervisor and shif t superintendent positions.
5.
Replacement Training Operators joining the Seabrook organization af ter the start of power operation will be given appropriate training to satisfy their job classifications. The extent and duration of the training period depends upon their previous expecience and job aptitude.
If an NRC Operator's License is required for a specific job category, suitable classroom and practical training is provided.
Technical services and maintenance personnel also receive on-the-job training to satisfy the requirements of their job classification.
B.
RESPONSIBILITIES The following Seabrook personnel will be responsible for various areas of Seabrook's training programs, as discussed below:
1.
Station Manager The Seabrook Station Manager has the overall responsibility for qualifi-cation and proficiency of its personnel. As such, the Station Manager l
will review and approve all plant training programs, i
2.
Assistant Station Manager The Assistant Station Manager is responsible to the Station Manager for administration of all station training programs. He will review all station training programs annually.
3.
Training Center Manager l
The Training Center Manager will be responsible for development, imple-l menation and administration of Licensed Operator Training.
This will include initial as well as requalification training. I
4.
Training Manager The Training Manager will be responsible for development, implemen-tation and administration of Non-Licensed Training including General Employee Training, Fire Brigade Training and Specialized Training.
C.
PROGRAM DESCRIPfTON 1.
Initial Orientation All persont joining the Seabrook organization, regardless of job assignment, will receive initial orientation training. This phase of training consists of a brief informational program explaining site organization, employee benefits, company policies and procedures. This phase will include a general site layout familiarization and an intro-duction to job-related procedures and/or instructions. More specific areas will be addressed, including industrial safety / fire protection, quality control / assurance, security and emergency plan response. Prior to fuel load and continuing thereafter, each employee will be given a radiological health and safety course before being assigned full time duties.
2.
Operator Licensing Program This program will provide an individual with the knowledge and experience level necessary to obtain an NRC Senior Operator's Liceqse or Operator's License. The program has been developed and scheduled in a modular fashion to be implemented in segments.
In most cases, each licensing candidate will participate in each segment. However, whether an individual participates in all segnents will depend upon previous nuclear experience and previous license qualification. Prograa par-ticipation has been categorized on Table 13.2-1.
The license training program schedule will insure that a sufficient number of licensed personnel will be available prior to fuel load, and will continue to meet applicable technical specification conditions with respect to the number of licensed operators on shif t crews.
A program for effectiveness monitoring is established for all areas of license training. Evaluation of program effectiveness shall be per-formed by:
- 1) Training Center management periodic assessment of classroom presentation and simulator instructions; 2) independent third party oral and demonstrative audits conducted on at least a yearly basis; 3) student generated evaluations. Revisions are made to the license training program to strengthen weak areas identified through the evaluation process.
The following paragraphs provide a general description of the various training segments:
a a.
Introductory Training In addition to initial orientation training, those individuals spe-cifically designed to become license holders will attend an intro-ductory program on PWR systems. The first portion of the program is a generic course covering the Nuclear Steam Supply System (NSSS).
License candidates will also be given an introductory course covering the balance of Seabrook's systems. This portion of the program will be conducted internally or by an outside vendor.
b.
Nuclear Fundamentals Training Program Fundamentals I This is an eighteen to twenty week program presented by the Training Center Staff or an outside vendor. The program is designed to provide the reactor operator license candidates with a thorough understanding of the basic principles, charac-teristics and unique features of a nuclear system.
The major topic areas to be covered are technical mathematics and classi-cal physics, basic nuclear physics, reactor operations, core per-formance, radiation protection, plant chemistry, instrumentation and control, fluid flow, thermodynamics, heat transfer, and plant performance. An integral part of the Fundamentals I r
training program is reactor start-up experience. This is a one week program presented at a research or training facility by an outside vendor. Experiments, discussions and demonstrations are conducted to compliment the principles and theory taught in the fudamentals program.
Specific training objectives are selected which place additional emphasis on concepts which are difficult to visualize in the classroom environment.
Fundamentals II i
This is a forty to fifty week program presented by the Training Center staff or an outside vendor. The program is designed to provide the Shift Superintendent and Unit Shift Supervisor with an added depth of knowledge of engineering principles found in nuclear reactor fundamental applications. Selected courses are based upon an analysis of the Shif t Technical Advisor's qualifi-cations and responsibilities outlined in NUREG-0578.
The cour-ses include the following:
Differential Calculus Integral Calculus Advanced Reactor Physics Material Study Course Fracture Mechanics Corrosion Processes Computer _ Te chnology Electric Generator and Transmission Thermodynamics Etat' Transfer Fluid Mechanics ~
~
To supplement Fundamental II courses, workshops will be held to reinforce theoretical concepts learned in the courses with prac-tical Seabrook applications. Thc workshops will generally consist of a classroom phase and use of the simulator where appropriate.
An additional ten to twelve weeks of specialized training is pro-vided te supervisory level license holders. These courses include motivation of personnel, problem and decision analysis, interper-sonal communication, technical writing, stress and human behavior.
c.
Operating Plant Observation This segment consists of four to six weeks of plant observation at a PWR similar in size and design characteristics to Seabrook.
The major objective is to f amiliarize each license candidate with the daily routine involved in the operation of a commercial nuclear facility. Other specific areas of observation will be made in security, radiation protection, maintenance, quality control / assurance, fuel handling, and waste disposal / management.
d.
Formal On-Site School This segment of approximately 14 to 18 weeks duration will encom-pass the on-site formal classroom lecture series. This phase of the license program is structured at two levels of presentation, one for the reactor operator candidate and another for the senior operator candidate.
The subject areas of instruction are the same for both license can-didate groups. There is, however, a distinction between the levels at which the subject matter is presented.
The SRO program reflects a more indepth treatment of materials consistent with level of responsibility and understanding of advanced engineering p rinciples.
The instructors for this lecture series will be permanent and tem-porary members of the Seabrook Station Training Center staff, Seabrook Station Supervisory staff and Yankee Atomic staff. Other consultants and vendor representatives will be invited to discuss topics of special interest.
The subjects to be taught and/or reviewed in the formal on-site school are listed below:
Math and Physics Reactor Operations Plant Chemistry (Primary and Secondary)
Health Physics Heat Transfer Fluid Flow Materials Science Thermodynamics Specific Systems & Components Instrumentation & Controls Mitigating Core Damage Technical Specifications Administrative Controls Special Topics Included in the classroom training segment will be periodic simula-tor exercises and demonstrations.. In addition, directed in-station tours will be conducted to review system and component layout and interface.
e.
Simulator Training Seabrook has the distinct advantage of including a site specific simulator as part of the operator training program.
The simulator was modeled and built to essentially duplicate the Seabrook main control board as well as real time system response. The simulator 4
meets the requirements of NUREG 1.149, 1981 except as noted in FSAR, Section 1.8, Conformance to NRC Re clatory Guides.
A fully qualified simulator staff, with previously SRO licensed or certified instructors, will implement and conduct this segment of the operator training program. All license candidates will spend time participating in the simulator training program as needed to prepare for NRC licensing exams. This program will combine hands-on practical experiences with formal classroom instruction. Major program emphasis will be placed on obtaining complete f amiliarity with the plant's operating, emergency and surveillance procedures.
This f amiliarity will be obtained and reinforced through actual performance.
Successful completion of this program, combined with operating plant observation, will satisfy requirements of 10 CFR 55.25(b) and will establish a candidate's eligibility for cold licensing.
f.
On-the-Job Training Participation in the pre-operational testing phase of the unit start-up will provide on-the-job training to license candidates.
Operating personnel are given. departmental work assignments in addition to participating in system turnover and acceptance testing.
Throughout this period, assignments will include prepara-tion and/or review of the various operating, emergency, main-tenance, surveillance, and test procedures necessary for the start-up and operation of the unit.
g.
-Program Review and Pre-License Evaluation At the culmination of the training program, each license candidate will participate in review session followed by pre-licensed evaluation.
The review session will consist of formal classroom instruction, simulator exercises and individualized study. The review session will emphasize areas where earlier program information may have been shallow or unknown. -.
A final pre-license evaluation of each license candidate will be administered by an independent party. This evaluation will be conducted in two parts: the first will be a written exam to deter-mine the candidate's comprehension and retention.
The exam co'n-tents and degree of difficulty will parallel that of a current NRC Operator's Examination or Senior Examination, as applicable. The second portion of the evaluation will be an oral walk-through and simulator demonstration to further evaluate practical knowledge and experience.
This evaluation will insure each candidate is properly prepared for the NRC exam, and is capable of competent and safe operation of the plant controls.
D.
COORDINATION NITH PRE-OPERATIONAL TESTS AND FUEL LOADING The Station Staf f Training program has been developed and will be scheduled to minimize any conflicts in manpower requirements during the unit's preoperational testing and f uel loading.
The positive training effects gained by actual participation in these phases of the start-up will be incorporated in the training program.
The scheduling interf ace between the Operator License Training program and the start-up is illustrated in Figure 13.2-1.
v.
LICENSED OPERATORS - REQUALIFICATION TRAINING A comprehensive requalification training program will be conducted for all licensed operators and will be implemented within three (3) months after issuance of the unit's operating license. All license operators will return to the Training Center for requalification training on a one week out of six continuous rotation schedule. A portion of the available training time must address general employee refresher training, how*r,r a minimum of ten weeks per two year cycle will be dedicated to the lis se program.
The requalification program is divided into the follcaing areas:
1.
Annual Requalification Exam Each licensed individual will be administered a comprehensive examina-tion which will parallel, in content and degree of difficulty, an NRC Licensing Exam. The exam will be graded by category.
Individuals scoring 80% or greater on a particular category will be exempt from attending retraining lectures covering that category. Any licensed operator with an average exam score of less than 80% or a grade of less than 70% in any category will be relieved from licensed respon-sibilities, and will be placed in a concentrated retraining program.
He will be re-examined prior to reassignment to licensed respon-sibilities. Each license holder's graded exam will be retained as a part of the training records.
the results of the exam will be used to evaluate past training, and to aid in determining future retraining.
2.
On-The-Job Training During the term of an individual's license, he will perform, or direct, the execution of at least ten evolutions from those categories listed below. The evolutions will be a combination of manipulations distri-buted among the various categories. -
Reactor Start-up (to the point. of adding heat)
Reactor Shutdown (f rom the point of adding heat)
A Power Change of at Least 10% of Full Power A Boron Change of at least 10 ppm Reactor Trip Plant Heatup (of at least 500F)
Plant Cooldown (of at least 500F)
Plant Start-up (f rom hot standby to generator synchronization)
Plant Shutdown (f rom generator synchronized to hot standby)
Operation of Turbine Controls During Start-up Surveillance Testing of Safety Related Systems, the Performance of which is done f rom the Control Room Manual Control of Steam Generator Level During Start-up or Shutdown Rod Drop Timing Tests Refueling Operations where Fuel is Moved in the Core It will be the responsibility of the Unit Shift Supervisors to rotate their shif t compliment in an attempt to meet the minimum evolution requirement. This requirement may be met by use of the on-site simula-tor during scheduled training periods.
3.
Change and/or Revision Review This portion of the program will insure that all changes or revisions to the license document, i.e., Operational Technical Specifications, are reviewed.
It further insures that significant changes to proce-dures and completed f acility design changes will also be reviewed.
When determined by the Assistant Operations Manager, that a procedure revision or completed f acility design change will affect the operation of the unit, it is then included in the review process. Also included in the process, may be other pertinent documents such as Licensee Event Report (LER's).
The requirements of this program will be metif by placing a copy of the change or revision, along with a Document Ac$cowledgement sign-off sheet, in a review notebook.
In at least every Training Shif t, each license holder will review the contents of the notebook and, upon
- completing the review, will acknowledge by signature and date, his understanding of the change. A file of completed Document Acknowledgement Sheets will be maintained as a record of program compliance.. Changes that require immediate operator notification, as in the case ~of-significant interim procedure changes, will be covered as night orders to the Shif t Superintendent or during Operations Department Meetings, followed by a document ac'tnowledgement under this program.
The requalification lecture series will include those items applicable to the operator work responsibilities.
4.
Emergency Operating Procedure Review In order to insure a continuing awareness of the action and responses necessary during abnormal or emergency situations, a complete review of all emergency operating procedures will be conducted by each licensee, at least annually, and an acknowledgement sheet will be signed at the training center. This review will be conducted as part of the simulator training or retraining lecture series.
5.
Simulator Training The Seabrook specific simulator will be utilized, whenever practical, to fortify the on-going operator requalification program.
Simulator exercises and evolutions will be preplanned and scheduled to f re-quently interface with the Formal Lecture series. The simulator Requalification Training Program will emphasize such areas as inf re-quently accomplished procedures, required responses to abnormal and emergency procedure, and known or suspected problem areas. Exercises will include analyzing the effects of potential equipment / system malfunctions, possible causes and recommended operator responses.
Involvement of unit shif t supervisors and shif t superintendents in the capacity of operations assessment and accident analysis during refresher exercise training shall be a program objective. A portion of each weeks simulator time, not to exceed twenty percent, will be allo-cated for specific applications requested by the unit shift super-visors. The simulator will also be used as a means of evaluating and indicating areas requiring further retraining emphasis.
6.
Retraining Lectures for License Holders A formal classroom lecture series, including quizzes, will be conducted each year as part of the Requalification Program.
The level of instruction for the retraining lectures will be consistent with the level of license held. To a large extent, the results of the previous year's annual exam will determine areas to be emphasized in the f ollowing year's lectures.
As appropriate, the lecture series may also cover other topics of per-tinent information such as refueling work, current industry occurrences and topics of special interest.
Whenever appropriate, simulator exercise will be incorporated to enhance the lecture series content.
All license holders are encouraged to attend each scheduled requalifi-cation lecture. A license holder is execpt f rom attending the lecture if he scored greater than 80% on that corresponding material of the annual exam.
9
Requalification lecture quizzes will be administered to all attendees.
To further promote self-study and group discussions, some of these quizzes may be of the open book type.
7.
Performance Evaluation and Review Requalification training program ef fectiveness shall be monitored as described in Subsection C.2.
At least once per year, ecch licensed operator will be observed and evaluated while responding to either real or simulated abnormal or emergency conditions. The evaluation will be performed by the individual's immediate supervisor or a member of the Training Center Staff.
A performance review will be conducted when any of the following situations occur:
An annaul exam score of less than 70%, or A poor performance evaluation, or Prior to resuming license responsibilities after absence of more than four months.
The purpose of the review will be to determine a course of action necessary to upgrade an individual's performance to an acceptable level.
Supplemental training programs will be established to upgrade areas where deficiencies are shown. Absence from responsibilities applies to all operational shif t levels; RO, SRO, and unit shif t super-visors, shif t superintendents.
The review will be conducted as soon as practical af ter one of the above conditions occur. The action taken will be dependent on such f actors as examination performance, watch standing performance, observed operational performance and judged overall competence.
F.
REPLACEMENT TRAINING Individual advancement to increasing levels of responsibilities as oppor-tunities develop within the organization will be encouraged. For an indi-vidual to advance to a more responsible position, he must be fully qualified technically and possess sufficient experience to meet at the job require-ments.
1.
Replacement Training for Licensed Personnel Public Service Company of New Hampshire recognized the need to have a replacement program which will continually insure the same high quality of licensed personnel as the initial license program. To this end, the replacement program for licensed operators will include the same ele-ments as the initial Operator License Program detailed in Section C.2.
Credit will be taken for previous formal training and experience received in an individual's progression to the license level the person is seeking. __
s.
The training program will include as a minimum the following phases:
a.
Classroom Instruction Each license candidate will attend a formal on-site school of suf-ficient duration, to complete prescheduled lectures in the following areas:
Nuclear Reactor Fundamentals - see Section C.2.b.
Formal On-Site School - see Section C.2.d.
The lecture program may be supplemented by video tape programs, as determined by the Training Center Staff. Periodic quizzes and exams will be administered to insure student comprehension and retention. To further evaluate each student's acquired knowledge level, a final exam will be given at the conclusion of the classroom phase. The final exam contents and degree of difficulty will parallel that of an NRC operator license examination or senior operator license examination, as applicable.
1 b.
Control Room Experience Each license candidate will receive on-the-job experience by par-ticipation in discussions with on-shift operators and by the actual performance of routine control room functions. The discussions will be directed to copics such as systems interface, control capa-bilities and instrumentation available in the control room.
Particular emphasis will be placed on system operating charac-teristics and possible malfunctions. License candidates will par-ticipate on shift in the position of the license being sought, under the instruction of a licensed operator for a period of three months.
c.
Simulator Training Included in the operator license training program will be training on the Seabrook specific simulator. The emphasis for this phase of the program will be on normal, transient and emergency operations.
Each license candidate will be given the opportunity to witness and respond to numerous exercises involving system and component malfunctions.
Demonstration sessions will include transient and accident analysis.
Included in this portion of the program will be certification by the Training Center Staff that the license candidate has satisfac-torily demonstrated the following:
1.
Ability to manipulate the controls and keep the reactor under control during start-up, ii.
Ability to' predict instrument response and use the instru-mentation during a reactor start-up,,
. _ ~
n,
iii. Ability to follow the facility start-up and shutdown proce-dures, and iv.
Ability to explain alarms and annunciators that may occur during this operation.
d.
Pre-License Audit In addition to the final exam administered at completion of classtoom training, and oral station walk-through will be given to each candidate to further insure that the individual is properly prepared and is, in f act, capable of competent and safe operation of 4
the station controls. This oral walk-through will be given by a senior licensed member of the unit staff prior to the individual being permitted to take the NRC licensing exam.
The areas that are to be stressed while conducting these walk-throughs are simulated malfunction and emergency situation response, local instrumentation and control, and general plant hardware.
G.
APPLICABLE NRC DOCUMENTS 1
The training programs will be developed and implemented in accordance with the applicable requirements of the NRC Code of Federal Regulations and meet l
the intent of the recommendations provided by the applicable Regulatory Guides and applicable NRC reports listed below:
10CFR Part 50, " Licensing of Production and Utilization Facilities" 10CFR Part 55, " Operator's Licenses" 10CFR Part 19, " Notices, Instructions and Reports to Workers; Inspections" Regulatory Guide 1.8, " Personnel Selection and Training", Revision 1-R, September 1975 (re-issued May,1977), with the exception that ANSI /ANS 3.1-1978 will be used as the standard in lieu of ANS 3.1/ ANSI 18.1-1971 Regulatory Guide 1.101, " Emergency Planning for Nuclear Power Plants",
Revision 1, March 1977 Regulatory Guide 1.149, " Nuclear Power Plant Simulators for Use in Operator Training", April 1981 l
Regulatory Guide 8.2, " Guide for Administrative Practices in Radiation Monitoring", February 1973 I
Regulatory Guide 8.8, "Information Relevent to Insuring that Occupational Radiation exposures at Nuclear Power Stations will be as Low as Reasonably Achievable", Revision 3, June 1978 l
l Regulatory Guide 8.10, " Operating Philosophy for Maintaining Occupational Radiation Exposures as Low as is Reasonably Achievable", Revision 1-R,
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September 1975 Regulatory Guide 8.13, " Instruction Concerning Prenatal Radiation Exposure", Revision 1, November 1975
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" Utility Staf fing and Training for Nuclear Power", WASH-1130, Revised June, 1973 "NRC Operator Licensing Guide", NUREG-0094, July 1976 "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recoassendations", NUREG-0578, July 1979 ANSI /ANS 3.1-draf t revision 1980, "American National Standard for Selection and Training of Nuclear Power Plant Personnel:"
ANSI /ANS 3.5-1981, " Nuclear Power Plant Simulators for Use in Operator Training."
" Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls and Quality Assurance", issued by USNRC letter in Augusst, 1977.
NUREG 0737, November 1980, " Clarification of TMI Action Plan Requirements".
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TABLE 13.2-1 OPERATOR LICENSING PROGRAM PARTICIPATION g
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t s
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44 s
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gd OPERATIONS MANAGER X
X X*
X X
X X
ASSISTANT OPERATIONS MANAGER X
X X*
X X
X X
. SHIFT SUPERINTENDENT X
X X-X X*
X X
X X
UNIT SHIFT SUPERVISOR X
X X
X X*
X X
X X'
SENIOR REACTOR OPERATOR X
X X
X*
X X
X X
REACTOR OPERATOR X
X X
X*
X X
X
.X
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X Indicates required participation in that segment of the Training Program.
X* Indicated full participation required only to meet cold license eligibility.
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TABLE 13.2-2 COMPARISON OF NUREG 0737 APPENDIX C TO SEABROOK STATION OPERATOR LICENSE PROGRAM CUMULATIVE CONTACT HOURS APP C RO USS SUGGESTED SCR0 SS Prerequisite Beyond High School Mathematics 90 45 45 Chemistry 30 45 45 Physics 150 165 165 Col 1ege Level Fundamentals Mathematics 90 120 Re-~ctor Theory 100 90 135 Reactor Chemistry 30 45 Nuclear Materials 40 90 Thermal Sciences 120 Thermodynamics 90 Fluids 45 Heat Transfer 45 Electrical Sciences 60 45 Nuclear Instrumentation & Control 40 45 45 Nuclear Radiation Protection &
Health Physics 40 45 45 Applied Fundamentals 350 530 Plant Specifics 120 Plant Systems 200 Administrative Controls 80 Operating Procedures 30 Transient / Accident Analysis &
Emergency Procedures 30 Management / Supervisory 40 215 Simulator Training-100 280 380*
- Minimum of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> in the position of a supervisor directing' activities.
- Reactor Operator
.SCR0 - Supervisory Control Room Operator USS
- Unit Shif t Supervisor SS
- Shift Superintende t
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Attachment #3 Review of the Control Room Man - Machine Interface During initial design of the Main Control Board in.1976, a full size mockup was built at a PSNH fossil station. The mockup was reviewed by Operations manage-ment people who were licensed operators from Maine Yankee, Connecticut. Yankee and Yankee Nuclear Services Division (YNSD) and by engineers from YNSD, United Engineers and Constructors, and PSNH. Numerous changes were made to improve the man-machine interface.
During initial construction at Singer-Link and following installation of the site specific simulator control board at Seabrook, the control board was reviewed by Seabrook Training Center personnel, Seabrook operations management and Seabrook operators. Many changes were devised to provide a better man-machine interf ace and these are being incorporated in the simulator and control boards.
A task force of YNSD and Seabrook operating and training managers, engineers and SRO's has now been fonned and has begun a human factors review of the unntrol room. The simulator control room installed at the site will serve as a model for this review. The review will provide an additional evaluation of the man-machine interface in accordanca with the recommendations of NUREG-0700.
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. ed e-Attachment #4-Operationa'l Assessment..
The two unit Seabrook Staff will include eight Shif t Superintendent Lpositions.
.These eight individuals will _ rotate on six shif ts such that six will perform on -
cahif t -duties and - two will. report _ to the Assistant Operations. Manager :for of f-shift 1 assignments such as:
- 1) Procedure reviews.
- 2). Engineering. assessment lof operational experience.
- 3). Prepare plans for operations during scheduled outages.
- 4) Review upcoming plant design changes..
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5)
Investigate abnormal or unusual events which occurred to assess adver'se affects on the pla'nt or personnel.
4 These duties combined with the long range reviews of similar subjects by the Independent Safety Engineering Group (ISEG) provide a comprehensive program of operational assessment.
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Attachment #5 Accident Assessment In the event of an incident, the Unit Shif t Supervisor will direct the actions of the Unit operators ? rom the control room. The Shif t Superintendent will go to the affected contr.
.oom and perform an independent assessment of plant parameters to determines
- 1) The status and integrity of the core and associated systems.
- 2) The status and availability of the heat sink and heat removal capability.
3)- The status-and integrity of containment.
- 4) The status of station radiation levels and potential release paths.
Based on this assessment and any available additional information, the Shift Superintendent will provide recommendations to the Unit Shif t Supervisor to ter-minate or mitigate the consequences of the incident.
Procedures will clearly state that the Unit Shif t Supervisor is. in charge of Unit operations, and the Shift Superintendent-is an advisor unless he specifi-cally relieves the Unit Shif t Supervisor of the command and control respon-sibilities. This arrangement provides for an immediately available and qualified supervisor who -can and will take over should a Unit Shif t Supervisor be unable to perform his function correctly in an emergency for any reason.
Owing to the qualification and training requirements set out in Attachment #2, it i= less likely the Shif t Superintendent will misinterpret available infor-mation or the Unit Shif t-Supervisor will not understand a recommendation. This arrangement provides the best possible arrangement to assure that communications between the Shif t Superintendent and Unit Shif t Supervisor will be clear and understood.
A retraining program to include ' simulator exercises of emergency and accident conditions will be an ongoing requirement for individuals assigned the positions of Shif t Superintendent and Unit Shif t Supervisor. The simulator will be used to practice'and perfect the organizational interactions and station procedures which1 integrate the duties and responsibil'ities of the Shif t Superintendent and Unit Shif t. Supervisor positions.
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Attachment #6 Assignment of Administrative Duties The Unit Shif t Supervisor, as the individual with the direct responsibility for the safety of the Unit to which he is assigned, must fulfill certain inherent administrative responsibilities associated with the position. His involvement in direct administration of the Unit insures his cognizance of all ongoing acti-vities which could affect equipment or personnel safety. These administrative responsibilities include, but are not limited to, such activities as:
- 1) Review and approve Unit work authorization.
- 2) Review and approve Unit Radiation Work Permits.
- 3) Review and approve Unit jumper, bypass and lifted lead use.
- 4) Review and approve tagging request.
- 5) Review shift logs.
It is recognized by PSNH that excessive administrative responsibilities will reduce the effectiveness of the Unit Shif t Supervisor relative to his primary responsibility of insuring the safety of his Unit and assigned personnel. PSNH has addressed the "colateral" administrative responsibilities which have com-monly been assigned to the Unit Shif t Supervisor at other stations by assigning them to the Operations Administrative Supervisor and the Shif t Superintendent.
(See attachment #1). Some of the "colateral" administrative responsibilities not assigned to the Unit Shif t Supervisor include:
- 1) Call-in of necessary personnel.
- 2) Payroll administration.
- 3) Maintenance of overtime records.
4)
Surveillance procedures (other than insuring completion of scheduled surveillance).
5)
Insuring completion of:
a) Operator sign-off of required reading materials b) Resctivity Manipulation Log
- 6) Vacation scheduling and rescheduling.
The assignment of these, and other, similar colateral administrative respon-sibilities to personnel other than the Unit Shif t Supervisor ef fectively reduces the administrative burden on the Unit Shif t Supervisor to a level at which he can concentrate his effort on insuring the safe operation of his Unit.
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