ML19274E700
| ML19274E700 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/11/1979 |
| From: | Gilleland J TENNESSEE VALLEY AUTHORITY |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904170192 | |
| Download: ML19274E700 (17) | |
Text
.
e
., 5 TENNESSEE VALLEY AUTHORITY CH ATTANOOG A, TENNESSEE 37401 500C Chestnut Street Tower II APR 11 1979 Director of Nuclear Reactor Regulation Attention:
Mr. S. A. Varga, Chief Light Water Reactors Branch No. 4 Division of Project Management U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Varga:
In the Matter of the Application of
)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 Enclosed are the revisions to Section 13.2 of the Sequoyah Nuclear Plant (SNP) Final Safety Analysis Report (FSAR).
These revisions incorporate the responses to items 11 through 15 (questions 13.13 through 13.17) of your letter to N. B. Ilughes dated January 19, 1979.
This material will be included in Amendment 61 to the SNP FSAR.
Very truly yours,
\\
v jC
// J.
E. G111 eland Assistant Manager of Power Enclosure
\\
7 9 0417 0 / 9.7 >
An Equal Opportunity Employcr
A' r
ENCLOSURE
.N ~. '
REVISIONS TO SECTION L3.2 WHICH INCORPORATE RESPONSES TO QUESTIONS 13.13 THROUGH'13.17 13.2 TRAINING PROGRAM 13.2.1 PROGRAM DESCRIPTION The objec.tive of the training program is to provide plant personnel with the knowledge and skill required for the safe and efficient operation of Sequoyah Nuclear Power Plant.
In achi'ving this objective, TVA expects to meet NRC licensing requirements.
Ind.vidual training needs are established by comparing job requirements with ir dividual experience.
It is planned that the following personnel will be licensed in accordance with the. requirements of 10 CFR55 before initial fuct loading in Unit 1:
Operations supervisor, assistant Operations supervisor, at least 5 shift engineers, and at least 5 assistant shift engineers.
The power plant super-intendent or the assistant power plant superintendent will obtain the training required for a senior reactor operator's license.
It is planned to obtain reactor operator's licenses for at least 5 unit operators during startup testing of the first unit.
Training details will be described in the following paragraphs.
Selected supervisors, engineers, technicians, and craftsmen will receive training and other specialized courses to assure safe operation of the Sequoyah Nuclear Power Plant.
Training visits to operating nuclear plcats and other nuclear facilities have been, and will continue to be, scheduled as needed for selected supervisors.
The effectiveness of training programs is evaluated by the performance of employees in carrying-out their assigned duties and by performance on TVA and NRC examinations.
13.2.2 CENERAL EMPLOYEE TRAINING Personnel with specific duties and responsibilities in the plant shall receive QA training in the performance of their duties and responsibilities.
13.2.2.1 Access to Plant All persons having unescorted access to the plant regulated areas will have completed either (1) intensive nuclear training which will include radiation protection techniques and the site emergency plan, or (2) a brief plant indoctrination and radiation protection course which will include discussion of plant organization and layout, controlled zones, radiation and contamina-tion hasards, exposure limits and controls, elementary health physics, and pertinent sections of the Site Emergency Plan.
When persons have not completed either (1) or (2) above enter the plant regulated areas, they will be escorted by an employee who has received training in radiation protection and plant emergency procedures.
13.2-1
.y.'
13.2.2.2 Responsibility The individual responsible for conduct and administration of the nuclear
~
power plant training program is the assistant power plant superintendent.
13.2.3 UUCLEAR SYSTEMS OPERATOR TRAINING - COLD LICENSE The primary source of operators for the Sequoyah Nuclear Power Plant will be the large pool of operators in the conventional coal-fired plants in the TVA system.
Individual training needs will be established by carefully exam-ining the individual's experience and previous training and comparing these with job requirements. The formal training program for Licensed Senior Reac tor Operator (SRO) and Licensed' Reac tor Operator (RO) candidates should consist of the following courses.
13.2.3.1 Basic Nuclear Training Th is is a 13-week course conducted by TVA.
The first 12 weeks of this course are based on a video tape program purchased from the N.U.S. Corpora-tion.
The content of this program covered " Plant Mathematics and General Science," "3asic Nuclear Physics," " Reactor Operations," " Core Performance,"
" Plant Chemistry," and " Instrumentation and Control."
These tapes a re sup-plemented by lactures and problem-solving sessions as needed for operators with fossil plant background.
The last week of this course covers radio-logical protection training and ts taught by a member of the Radiological llygiene Branch of TVA's Diviaion of Environmental Pl'anning.
13.2.3.2 Penctor Operations Traininc - This course consists of training on a r; mall reactor involving at least ten startups and other basic nuclear subjects such as approach to critical experiments, health physics proccdures, waste disposal, rod calibration, ion chanber calibration, jmportance functicns of a neutron absorber, xenon experizents, and radioactive material handling under water.
One week of the two-week course is conducted at CRNL cnd involves use of the PCA or BSR reactors in achieving the above ex;cricents and startups.
The other week which relates to basic r.ucicar cubjects is incorporated in the basic nucicar course described
~
above.
L3. 2 -;z
13.2.3.3 observation Trainine at Comparable Operating PWR Plant - This is a fornal, documented, 2-month program conducted by TVA at an operating PWR.
It consists of overall plant familfarization, system walkthroughs,
vot ;. assignments, participation in, and observation of operating evolutions.
All cold license applicants who have not previously held an operator's license at a comparabic licensed reactor facility will participate in this program. Since all of the applicants will participate in system lectures at their own plant, this program will stress participation in and observation of operating evolutions.
The participants will be encouraged to Icarn the cause and means of correcting problems encountered with equipment similar to their own plant.
The progress of all participants in this program will be closely monitored by the training coordinator who will receive weekly reports of the time spent on particular systens for each week.
The weckly time reports will be used to vcrify that all safety-related systems are studied during this program.
Those applicants with no prior license who have extensive operating experience or have completed an organized 4-week observation period at Browns Ferry Nuclear Plant will complete 4 weeks of this program at an operating P'JR.
- 13. 2 -22 e?
13.2.3.4 PWR Simulator Training This program is a minimum of eight weeks and will be conducted at an NRC approved nuclear training center. The training will be centered around the actual operation of a nuclear plant and will utilize a total plant simulator that reproduces for training purposes all the important operational tran-sients of an ac tua l system.
The Westinghouse Nuclear Training Center at Zion, Illinois was used prior to the completion of the TVA Power Production Training Center at Daisy, Tennessee.
13.2.3.5 Onsite Training Series This training is administered on an individual basis depending on work experience and prior training.
It will consist of on-the-job training during plant testing as well as classroom lectures.
The classes will be conducted by Westinghouse personnel and/or members of the plant sta f f who have received previous nuclear training.
This is a combination work and training period which covers all safety related systems, components, and operating and safety procedures for the plant.
Review l ec t u re s are p resented by We s tinghouse personnel as part of the pro-gram for those operators who will be taking cold license examinations.
The lectures will provide a thorough review of the PWR reactor physics and engineering at the senior level with specific application to the theory of operation of the Sequoyah reactors and associated plant sy s tems.
Westinghouse personnel will administer both written and oral examinations to prospective licensees prior to NRC examinations.
13.2.3.6 Review Training If there is a delay in the fuel loading date prior to initial licensing, a
-r e v i ew program will be initiated by the Operations supervisor. Th is ;eview program will consist of selected portions of the onsite training program employing lecture series and simulator manipulation and will ensure that personnel are kept abreast of late changes in plant design, operating instructions, and administrative practices.
Individuals with na previous nuclear experience making application for cold license shall complete all programs.
Individuala who hold, or have held, license for cocparable f ac ili t ie s and making application for cold license, shall complete the onsite program.
are Individuals who have had experience on comparable facilities not subject to licensing and making application for cold license, shall complete the onsite p r a g ra m.
13.2-3
l'.24 Nuclear Systems Ou2rator training - Hot License The applicant must meet all requirements to qualify for the hot-license examinations as specified in Appendix F, "Cligibility for Examination with No Reactor Startup Demonstration," of the NRC Operator Licensing Guide, NUREC-0094 The hot-license operator trairing program is designed to prepare the trainee for the NRC reactor operator written examination and operating test.
The first 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> include clansroom lectures, and an audit type examination presented at the plant to prepare the trainee for the Nuclear Regulatory Commission (NRC) written examination.
The last 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> of training, which include 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> for review and certification examination, are schedulec at the Power Production Training Center.
This training shall satisfy reactor startup eligibility require-ments to quality for the NRC examination and prepare the trainee for the NRC operating test.
Simulator instruction is limited to no more than four trainees in the control room at one time.
Presentations totaling 500 lecture hours listed in ANSI N18.1-1971, Section 5.2.1 relate to subjects and prercquisites courses.
This 500-hour requirement is included in the Nuclear Student Operator Training Program as described in section 13.2.5" A certification examination is administered at the end of the simulator training session.
" - ~
JRAINI %
13.2.5 NUCLEAR STUCENT GENERATING PLANT OPERATGR1 PROGRAM The TVA Nuclear Student Generating Plant Operator (NSCPO) Training Program is a joint program between TVA and the International Brotherhood of Electrical Workers.
The objective of the NSGPO program is to provide qualified personnel for operating positions in the nuclear plants of the Office of Power of the Tennessee Valley Authority.
The NSGPO program is 22 months in length and is divided into 4 steps.
The first three steps are presently taught at the TVA Power Production Training Center, while the fourth step (6 months), which is basically on the job training, is conducted at one of TVA's nuclear plants.
The portion of the program which covers basic nuclear theory and primary system technology is approximately 19 weeks in length.
The students are taught by lecture, video tapes, plant tours, and simulator utilization.
The following subjects are covered in the basic nuclear and primary system technology portions of the program.
1.
Review of Math 2.
Basic Nuclear Physics 3.
Reactor Theory and Engineering 4.
Nuclear Instrumentation 5.
Neutron Economy, Coefficients, Kinetics, and Control 6.
Denien nasis Accidents
/32'4
7.
Core Thernal ilydraulics 8.
Reactor Vessel and Core Design, Flow, Materials, Instrumentation, and Control Rad Drive System 9.
Radiological llygiene, Radiation Types, Effects, Dose, Limits, Monitoring, Shielding, Instruments, and Regulations 10.
Reactor and Associated Equipment 11.
ECCS Systens, Diesel Generators, Emergency Power Systems, Demineralizers, Fuel liandling, and Radioactive Waste 12.
Control Rod Drive System, Reactivity Control, Reactor Pressure Control, Spent Fuel Cooling, and Primary and Secondary Containment 13.
Ibin Steam and Reactor Protection Systems, Normal and Emergency Cooling Water Systems, Ventilation Systems, and Radiation Monitoring Systems Approximately one-half of the students' time during the above 19 weeks is formal classroom training.
13.2.6 RETRAINING FOR OPERATORS Following initial licensing of shift personnel, a retraining program shall be insituted to maintain operator pro ficiency. The program will cons ist of three general categories:
(1) lecture series, (2). experience requirements, and ( 3) evaluation.
13.2.6.1 f.ecture Serica Preplanned lectures shall be conducted by successive annual programs.
The l ec t u re s shall include training in the following subjects:
Theory and principles of opera tion a.
b.
General and specific plant operating characteristicr.
c.
P11nt instrumentation and control systems d.
Plant protection systems e.
Engineered sa feguard systems t.
Normal, abnormal, and emergency operating procedures g.
Rad i.it ion control and safety h.
Technical spec i ficationn Applicable portions of NRC rules and re gu la t ion s i.
(3.2-44
a I
The p rogram sha ll c ons i,st of a minimum of 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> of training a year.
a licensee may be exo. sed a maximum of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of classroom training per year with justifiable cause.
!!e mu s t participat.* in the lecture series on any category in which he scores less than 80 percent on the annual written examination.
A minimuu of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> and a maximum of 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br /> of the training shall be c ond uc t e'd for each license during the first 6 months of the year.
The balance of the training hours shall be conducted the last 6 conths of the year.
Training shall be scheduled by designated groups.
'Ih e s e groups shall be relioved from regular duties for the training sessions.
Each license holder shall be assigned to a group and scheduled for training.
13.2.6.2 Experience Requirements The following control manipulations are used at the plant during normal operati:n ond/or at the sinulator to meet the required 10 recctivity centrol ranipulations.
D ployect wi'h 550 licences are credited with these activities if they direct or evaluate control manipulations as they are performed. A ~d-d um of 10 reactivity cor. trol nanipulations in any cctbinations of startup, shutdownc, or other ranipulations vill be performed by each cperator cach year.
1.
Plant or reactor ct:rtups to include a rance that reactivity fecdback from nuclccr heat addition ic noticeabic 2.
Plant shutdown 3
Fbnual centrol of steam cenerator durinc startup tr.d chutdorn 1+. Operaticn cf turbine controls in manual during stcrtup 5
Boration during power operation 6.
Dilution of the reactor c00lont cystem 7.
Refuelinc operation: where fuel ic oved into the core 8.
Rod drop tining tectc 9
Sicnificant (> 10; ) power chances in manual red control 10.
Ibnual red centrol prior to and during generator cynchronization 11.
P1nnt and reactor cperatien that involvec caercency or trancient procedure:
where reactivity in changing
[3 7 - [
13.2.6.3 Evaluation An annual written examination requiring approximately 6 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for ccm-p l e t io'- shall be adm'i n i s t e red to all license holders af ter completion of re t ra ining.
Separate reactor operator and senior reac tor operator level written examina-tions shall be administered to the respective licensed operators. The senior operator shall be expected to go into greater depth on questions on technical specifications, standard practices and administrative procedures, and Radiation Emergency Plan.
A score of less than 80 percent in any cate-nory of the annual written examination requires manda tory attendance to l ec t ure s on that particular subject.
A grade of at least 70 percent overall on the evaluation examination shall allow an individual to continue his licensed activities.
There shall be a systematic observation and evaluation of shift operations.
Each licensed operator shall receive a performance evaluation.
Th is evalua-tion will be based on his performance un shift during transients, startup, shutdown, emergency and abnormal conditions. Th is is documented by the 13.2-Sa i
I f
shift engineer on the " Operator's Retraining Documentation Sheet for Reac-tivity Changes," plus the training instructor shall make an evaluation during the simula ted abnormal and emergency condition training.
At the end of each requalification l ec tu re, a short examination shall be administered. A grade of less than 80 percent will require further study and ree xamina tion on the same subject.
When a licensee receives a score of less than 80 percent in any category of the annual written examinations, the Training Review Board shall review the training record of the individual and determine the additional retraining requirements beyond mandatory attendance of the lectures on these catego-ries.
Review must bc made within 10 days af ter the date of evaluation.
Removal from the licensed duties and placement in an accelerated retraining program is mandatory when a score of less than 70 percent overall on the annual written examination is re c e ived. The scope and duration of the accelerated training in each case shall be determined by the Training Review Hoard based on the ind ividual de ficiencies.
Any licensee assigned to accelerate retraining by the Training Review Board shall achieve a score of 70 percent or core overall on a written examination in the area or areas of his indicated weakne ss be fore he may resume the duties of the licensed position. Approval by the Training Review Board, after review by them of the training and examination received, is required before the licensee may reassume the duties of the licensed position.
The Training Review Board is composed of the superintendent, the assistant superintendent, Operations supervisor, and assistant Operation 9 supervisor.
A ninimum of three of the four members shall be present when any action is taken.
13.2.6.4 Responsibility The assistant superintendent shall be respnnsible for the overall operator requalification training program according to the guidelines of this procc-dure.
gg lie shall designate qualified ind to be. responsible for the prepara-tion of lectures, presenta tion of lec tures, lecture quizzes, scheduling of training, annua l wr it t en examinacions, pe r formance evaluations, and documen-tation of the requalification training program as required.
' training coordinators who are 2icen;ed are exempt from taking the exar.inat ica f ar which the" had pri:-ar'j r e s pon n i h il i t'j for administering.
A raaximua of three licensed pernonnel :aay be exempt.
13.2.6.5 Documentation Records shall he maintained which include sufficiently detailed, updated i n f o rma t ion to adequately document the participation record of each license holder in requalification training.
The records shall contain copies of written examinations administered, the answers given by the licensee, results of evaluations, and documentation of any additional training admini-stered in areas in which an operator or senior operator has exhibited de fi-c ienc ies.
The shift engineer shall be supplied periodically with facility 13.2-6
design changes, p ro c <;du re changes, and facility license changes.
Each licensee on shift shall be required to read and initial a signof f sheet attached to the change docu=ent.
This sheet shall be placed in the plant files.
The shift engineer shall be supplied each month with a list of a portion of t he opera t ing and emergency procedures.
The sh if t engineer shall see that each licensee in his group reviews the complete operating, abnormal, and/or emergency instruction. Each licensee after reviewing the instruction, shall initial a signoff sheet.
This sheet shall be kept in the plant files.
13.2.6.6 Condition of the Licenses Any licensee who is away from the plant site for a period of four months or longer shall be given a minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> to review all instructions and plant status changes.
A written and/or oral evaluation shall be conducted and the same criteria that is used for the annual evaluatien shall apply.
'Wh e n the Tra in ing Review Board determines his knowledge and understanding of the f acility operation and administration are satisfactory, they will recom-mend to the Commission that he resume his license activities.
13.2.7 REPLACEMENT TRAINING FOR OPERATORS TVA follows a comprehensive work-study training and advancement program designed to supply qualified operating personnel for all levels of responsi-bility. Coepletion of related technical assignments, ingrade service per iod requirements, and rigorous qualifying examinations administered by a central accrediting comnittee before advancement to the next higher position ensure the required level of proficiency in all operating positions.
Replacement
.will be drawn from a reserve of qualified candidates.
Supplemental nuclear training will be provided as required, and per 13.2.4 - Hot License.
13.2.8 SPECIALIZED TRAINING Initially, members of the plant aupport groups will receive specialized training courses necessary to the safe and ef ficient operation of che plant.
Replacement personnel will be trained on-the-job in conjunction with abbreviated courses as needed. Training visits to operating nuclear plants will be scheduled upon re q ue s t from the section supervisor.
T'/A on a continuing basia, plans and administers programs for the develop-ment of its employees and their supervision.
Relationships are maintained with both local and state educational institutions as well as with venders 01 various items of equipment for the latest information for skills develop-ment.
Advantage is taken of appropriate ceminars, specialized courses, and training ac tivities offered by these groups.
13.2-7
t 11.2.8.7 Electro-ilydraulic Control System Course fh i s is a 3-week course conducted by Westinghouse at the i r llagan,
Pennsylvania, facilities. The purpor.e of the course is to provide the students with the n. cessary technical background to calibrate and maintai1 the analog electro-hydraulic control system.
The plant lostrument Engineer and a plant Instrument Mechanic initially attended this course.
I1.2.9 RECORDS 11.2.9.1 TVA Records-Official re c o r d s of employee qualifications, experience, and retraining are maintained in the of ficial TVA Personal llistory Record (Pi!R) by the Division of Personnel.
The PilR provides in a standardized arrangement the informa-tion of ficially recognized in recording and supportind eciployee status.
The Pi!R is maintained in current and accurate status and is controlled as to av,ilability. The material admitted to this record is restricted to items for which. authenticity has been confirmed through established procedures, e.g., o f ficial TVA forms, signed statements from the employee, management representatives, etc.
11.2.9.2 Plant Records Record. of employee pa r t ic ipa t ion in training activities leading to promo-higher leve l o f compe t"nce a re maintained by the plant training tion to a coordinator.
Ilec o rd s supporting requests for 'lRC senior operator and operator licenses are maintained in th.> Sequoyah master files. These records include training courses attended,
- r. training claraes, number of reac tor startups, and other information necessary to ensure that training requirements have been met.
Some of these records are duplicated in the Pl!R.
A t ra i n i ng, file for each member of the plant organization is maintained in the plant master file.
Information regarding part icipation in training and retraining activities will be maintained in this training file.
11.2.9.3 Tra ini ng Prov.r ain Eva lua t ion The training p rog ram, as it is initially constructed, is approved by the Ch r.' f, Noe le.a r Generation 11 ranch a f ter being internally approved at the plant leval.
Th i s ensures that the content and the intent of the training prm; ram provide s the necessary t raining for personnel associated with reactor operations.
1 h.-
eltectiveness of training programs is evaluated by the performance of employees in carrying out their asnigned dutieri and by performance on TVA
.md NRC exami na t ions.
13.2-9 lh I
h r hC tld!tm ab
13.13 The approved two-week reactor operation training -
Oak Ridge National Laboratory was changed by Amendment 55 to a single day.
This change is unacceptable.
Response
Refer to FSAR Section 13.2.3.2.
13.14 The approved obrervation training at an operating PWR plant was change <l to read " observation training at an operating nuclear plant."
This is unacceptable unless the facility is a PWR.
Response
Refer to FSAR Section 13.2.3.').
13.15 Amend:nen t 55 describes the hot-license program utilizing the TVA nuclear student generating plant operator t raining program.
Additional information i t.
required to f urt her evaluate this previously unapproved program pursuant to hot-license eligibility.
Information should dencribe the trainin;; and length of courses involving lecture serieu, on-the-j ob t rain in);, reactivity changes, and simulat.or training, if any.
Response
Amendment 59 restored the Sequoyah Nuclear Plant - Final Saf ety Analysis Report to that previous to the changen made by Amendment 55.
There was no mention of the hot-license program bef ore Amendment 55.
A program content is included as Sections 13.2.4 and 13.2.5.
13.16 Specify the reactivity control manipulations that will be performed by licensed personnel as part of the retraining program.
NRC must approve the control manipulations pursuant to 10 CFR part SS, Appendix A.
E2EEonsg Refer to FSAR Section 13.2.6.2.
O
13.17 A statement should be included in the program which indicates that individuals who prepare and grade the annual retraining examination are exempt from taking the examinations. A maximum of three licensed personnel may be exempt.
M ponse Refer to FSAR Section 13.2.6.4.
9