ML20138C184

Responds to Violations Noted in Insp Repts 50-424/85-45 & 50-424/85-51.Corrective Actions:Relevant Sections of FSAR Chapter 13 Revised to Address Concerns Re Readiness Review Module 2 on Training & Qualifiication

ML20138C184
Person / Time
Site:	Vogtle
Issue date:	03/13/1986
From:	Foster D GEORGIA POWER CO.
To:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
GN-833, NUDOCS 8604020388
Download: ML20138C184 (126)

Text

{{#Wiki_filter:, Georg:a Pbwer Company (N Fbst Off;ce Box 282 {\\ {. Waynestero. Georgia 30830 LJ Te:ectone 404 554M5t, Ent. 3300 404 724 8114, Est 3360 m Georgia Power a a ro.., V:ce Prescdent w.- c w s e vog.:, pg c3 a a ru March 13, 1986 .e United States Nuclear Regulatory Commission File: X7BD102 Suite 2900 Log: GN-833 101 Marietta Street, N.W. Atlanta, GA 30323

Reference:

Vogtle Electric Generating Plant - Unit 1,' 50-424, NRC Report No. 50-424/85-454 and 50-424/85-51 Attention: Mr. J. Nelson Grace Inspection Reports 424/85-45 and 424/85-51 addressed concerns associated with Readiness Review Module 2 Training and Qualification Programs. Our letter GN-774, dated January 10, 1986 provided followup information to NRC. This letter supplements GN-774 with additional actions which have or will be completed by GPC regarding Module 2 and the NRC inspection reports. A draft copy of relevant sections of Chapter 13 of the FSAR is attached for your information regarding the changec. Changes have been annotated in the draft to resolve items noted as discrepancies in NRC inspection reports 50-424/85-45 and 50-424/85-51. These draft changes will be formally submitted to NRC in the next amendment to the FSAR. Any significant changes to the draft between now and the submittal date will be brought to the attention of your office. Examination administration practices have been substantially upgraded to improve the development, security, approval, proctoring, grading and review of examinations. Deficiencies noted by the NRC assessment team with regard to these practices have been corrected and procedures are in place to ensure that i 8604020398 860313 PDR ADOCK 05000424 O PDR \\\\ QGEc/

Mr. J. Nelson Grace March 13, 1986 Page 2 of 2 proper exam administration practices continue. Additionally, selected student examinations which demonstrate adequate completion of training are'being retained in personal training files. These requirements are also being proceduralized. Development of program description procedures which will delineate the content and conduct of courses of study at VEGP are under development. Development of these procedures has been accelerated as a result of the emphasis placed on the necessity of these procedures by the NRC assessment team. A description of the Georgia Power response to each closed IFI is also included as Attachment 2 to this letter, with the exception of those items closed via the FSAR revision. VEGP has carefully reviewed all the findings and recommendations made by the assessment team in reviewing Readiness Review Module 2. Correction of those items noted as deficiencies has been and will continue to be aggressively pursued. Other suggestions and recommendations for improvement are being considered and implemented as appropriate. This response contains no proprietary information and may be placed in the NRC Public Document Room. Very truly yours, ) .i D. O. Fos er PDR/DOF/bjd Attachments cc: See Attachment 1 0611C/072-6

c e cc: U. S.. Nuclear Regulatory Commission Document Control Desk Washington D.C. 20555 Victor J. Stello, Jr., Director U. S.. Nuclear Regulatory Commission Office of Inspection and Enforcement Washington, D.C. 20555 J. W. Thompson U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 28014 Ms. Melanie A. Miller Division of Licensing Licensing Branch #4 Washington, D.C. 20555 Senior Resident Inspector U. S. Nuclear Regulatory Commission Plant Vogtle Electric Generating Plant B. W. Churchill Shaw, Pittman, Potts & Trowbridge 1800 M Street, Northwest Washington, D.C. 20036 J. E. Joiner Troutman, Sanders, Lockerman & Ashmore Candler Building 127 Peachtree Street, N.W. Atlanta, GA 30303 D. C. Teper Georgians Against Nuclear Energy 1253 Lenox Circle Atlanta, GA 30306 i

c.

Page Two cc: William M. Hill NRC-IE (EWS-305) Building East West / South Towers 4340 East-West IIwy. Bethesda,. MD. 20555 W. II. Rankin Suite 2900 101 Marietta Street, N.W. Atlanta, GA 30323 R. E. Conway J. T. Beckham, Jr. R. A. Thomas D. E.'Dutton D. S. Read W. T. Nickerson D. T. King K. Wiedner P. D. Rice R. H. Pinson C. W. Whitney J. A. Bailey G. Bockhold C. W. Hayes W.'C. Ramsey H. Walker J. Starnes (INPO) Document Control Project File RR Reading File (Letter Only)

~ Page 1 of 5 424-85-51-05, 424-85-45-02 (Exam regrading practices were not proceduralized) The Training Department agrees that exam regrading should be performed in a controlled and documented manner. The Exam Administration Policy procedure (60001-C) has been revised to control the~ regrading of exams. Specifically, section 4.9 and Checklist 1 of 60001-C provide these controls. 424-85-51-08 (An individual was found to have failed a Re-certification Exam). The Training Department agrees that the individual who was found to have failed the Annual Re-Certification Exam should be prohibited from instructing license candidates. The Training Department has formally notified that individual not to participate in the instruction of systems, trancients, integrated plant response, or simulator training until~ certification is renewed. 424-85-51-10 (Remedial Training requirements were not proceduralized) The Training Department has generated a Remedial Training Action Form. This form will document the required remedial training an individual must complete in order to receive credit for a course he is currently taking or has previously completed with unsatisfactory results. This-form is included in procedure 60001-C (Exam Administration Policy) as Figure 8. 424-85-51-11 (Exams given in close proximity to each other.were found to have many of the same questions) Procedure 60001-C (Exam Administration Policy) has been revised, and now addresses specifically, and through references to System Master Plans, the exam question re-use policy. Procedure 60001-C sets a maximum limit of 30% for subsequent exams given to license operators.

r Page 2 of 5 424-85-51-12 (Exam security was found to be weak) Procedure 60001-C (Exam Administration Policy) has been revised to strengthen security of the exam process in order to pervent the compromising of exams. Measures taken include allowing only training staff personnel, not currently being trained, access to the exam bank and prohibiting student access to the copy room during exam preparation. 424-85-51-14 and 424-85-51-15 (Methods of ensuring timely update of training materials need to be proceduralized) Procedure 60502-C (Training Program Development) has been written to control the review and update of the Vogtle test and lesson plans. The procedure identifies the source documents used to determine the need for updating instructional material. It also provides the mechanism used to implement the changes. The Training Department has also compiled books of drawings and logic diagrams that are available for student use. 424-85-51-17 (Waiver criteria require clarification) The Training Department has revised procedure 60002-C (Training Administrative Policies and Procedures) to clarify the waiver criteria. The specific criteria which must be met are: 1) The previous course contained the same topics, and was at least the same duration of the course being waived. The course must have been completed within the last three years. 2) The trainee completes an examination that is equivalent to the course final comprehensive exam. The exam may be written or oral. 424-85-51-20 (Hot participation time requirements need to be more specific) Plant Vogtle procedure 10015-C (Hot Participation Experience Program) has been changed to require a cold license candidate to spend at least 216 work hours on shift during their six weeks assigned to the host plant. I

r-Page 3 of 5 424-85-51-22 (There were no procedural requirements for the retention of instructor evaluations) The Training Department has written procedure 60504-C (Training Program Evaluation) to require retention of Instructor Evaluations until the course they were teaching has been evaluated. This allows the effect of the instructor on the class to be evaluated. 424-85-51-26 (GET exams needed to be more diverse) The number of questions used in generating GET exams has been greatly expanded. Also, greater care is being taken by the GET instructional staff to ensure that exams given in close proximity to one another are diverse in nature. 424-85-51-27 (Acceptable qualification programs for maintenance personnel needs to be delineated) The FSAR will be revised to further delineate acceptable qualification programs for maintenance personnel as annotated in the attached draft. 424-85-51-28 (I&C technician training on MCD was considered to be inadequate) A comparative study with other utilities, vendors, and regulatory requirements was performed to determine the adequacy of Plant Vogtle's Mitigating Core Damage course for I&C Technicians. As a result of the study we determined that Plant Vogtle's course addressed NUREG 0737 requirements; considered INPO guidelines; and compared favorably with other utility / vendor training courses. Further, based on the results of this study, we determined that the MCD course for I&C Technicians is sufficient as it currently exist. 50-424/85-51-30 (QA continuing training program) Quality Assurance procedure QA-03-02 is being revised to delineate more meaningful requirements relative to advanced training in the Quality Assurance Program.

Page 4 of 5 Phase VI of the basic program for the training and development of Quality Assurance Department employees is being removed from .the Training Guide. This advanced training will be addressed in paragraph VI of the revised QA-03-02. Specifically, participation in continuing training will not be required until after certification as Lead Auditor. Beginning with the first. calendar year following certification, the Lead Auditor will participate in a minimum of two continuing training areas each year. These areas are delineated in paragraphs A. through L. of paragraph VI. The site Training Coordinator and QA Site Manager shall select the training areas to enhance the auditor's skills by choosing training _ activities outside the auditor's regular work assignments. The' training shall be documented as'shown in Exhibit II and noted as continuing QA training. 50-424/85-51-31 (QA exam controls) All trainees training files have been reviewed to assure that all examinations are on file as required. These files are maintained in a controlled access file cabinet by the site Training Coordinator. Quality Assurance procedure QA-03-05 is being revised to incorporate the preparation of examination test question banks to be' used for preparing examinations on a required basis. The Phase III and V banks are being maintained by the site Training Coordinator and corporate Training Coordinator, respectively. Whenever a trainee is ready to take an examination for either Phase III or V of the Training Guide, the appropriate Training Coordinator will develop the examination from the bank, using a random number generator as its basis for question selection. Each of these examinations will be an ORIGINAL, to be used only once. The ORIGINAL of the Phase III examination will be administered to the trainee, graded on site, and a copy made of the examination. The ORIGINAL of this examination will be maintained in the trainee's training file at the trainee's work location and the copy will be transmitted to the corporate Training Coordinator for the trainee's (duplicate) files. 1 ~_ - - _. Page 5 of 5 The original of the Phase V examination will be transmitted to the trainees work location for administration by the site Training Coordinator. This examination will be graded on site and a copy made thereof. The ORIGINAL will be transmitted to the corporate Training Coordinator and the copy will be retained in the trainees training-file - the duplicate copy. All examinations and examination materials are maintained in controlled access file cabinets. 424-85-51-35 (Course evaluation criteria need to included in procedures) The Training Department has written a procedure (60504-C, Training Program Evaluation) designed to provide for Training Program Evaluation. The procedure will be a guide to aid personnel evaluating training programs in an overall sense. i l

March 21, 1986 Mr. D. O. Foster Vice President and General Manager Vogtle Project Waynesboro, Ga. 30830 RE: Readiness Review Program Module 18A Heating, Ventilation, and Air Conditioning LOG: RR-807 FILE: X7BD102

Dear Mr. Foster:

Pursuant'to your instructions I an enclosing Module 18A of the Readiness Review Program entitled Heating, Ventilation, and Air Conditioning (HVAC). This module reports the work of the Readiness Review Team and has been prepared in order to present you with an accurate picture of the readiness for operations of the Vogtle Project, based upon a close examination of the HVAC system. The Readiness Review process included an initial assessment and review of basic licensing documents.in order to identify Project commitments within the scope of the module. The Readiness Review Team then verified implementation processes designed to meet those commitments, including programs and controls relating to work within the scope of the module. The team then engaged in a process designed to verify that implementation programs were operating as described in procedures, policy statements, and other descriptive documents. In concluding this verification process, the team then actually verified that the licensing commitments identified during the process were being fulfilled and met.

Mr. D. O. Foster March 21, 1986 Page 2 We are confident that the verification methodology used allowed the Readiness Review Team to properly appraise the actual condition of the HVAC system and provided a valid means of assessing the quality of the program, having also considered applicable past audits, inspection reports, and problems experienced by other utilities. Based on the examinations, inspections, and evaluations of the review and the responses and corrective actions committed to by the Project, it is the conclusion of the Readiness Review Team that the design and construction programs that govern the HVAC system have produced a final product that meets design requirements and licensing commitments. Additionally, none of the findings identified, either individually or collectively, are such that the adequacy of the project HVAC system is called into question. Therefore, the HVAC system meets the PSAR commitments. Members of the Readiness Review Team and I are prepared to discuss this module with you at your convenience. If we can provide you with any further information or assistance regarding this matter,-contact me. Very truly yours, William C. Ramsey WCR/bjd cc: R. E. Conway l Readiness Review Board Members Reading File Document Control 0070r/079-6 l

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RESUME NAME: Conald F. Hallman TITLE: . Health Physics Supt. DEGREE: Ph.D., Nuclear Engineering BS, Chemical Engineering DATE OF BIRTH: 11-01-38 DATE EMPLOYED: 01-23-84 WORK EXPERIENCE: ( NUCLEAR (GPC) HealthPhysicsSupt.b Position: Dates: 1-23-84 thru Present Location: Plant Vogtle Power Generation plant Status: Under Construction Job

Description:

Chemistry /HP/ Emergency Planning to support Nuclear Plant Operations. NUCLEAR (OTHER) Position: Manager, Field Service Development, Babcock & Wilcox Dates: 10/72 - 1/84 . Location: Lynchburg, VA; and Oconee-1 & TMI-1 Sites' Plant Status: Startup and Refueling Job

Description:

Emergency Specification Development, Chem /Radiochem Support, ALARA Support, Business Development Management. Position: Manager, New Product Development Radiation Technology, Inc. Dates: 4/69 - 10/72 Location: St. Hilaire, Quebec and Rockaway, NJ Plant Status: Startup and Operation of Radiation Processing Facility. Job

Description:

Develop, Manufacture and Sell New Products, Licensed Operator. Position: Nuclear Engineer, E. I. DuPont Dates: 9/67 - 4/69 Location: Savannah River Labs, Aiken SC Plant Status: Operating Job

Description:

Desigr and Startup Equipment for Califernium-252 Separation. NON-NUCLEAR (GPC) h0NE NON-NUCLEAR (OTHER) NONE TRAINING: NUCLEAR NONE OTHER NONE (Applicable to Power-Plant or Related)

ARTHUR E. DESROSIERS Sc.D., CHP EtlEi Svye m Q,M - N a c79 6%p c3 EDUCATION S.B. Physics and ~ Mathematics, Boston College, Chestnut Hill M.S. Nuclear Engineering, University of Illinois, Urbana, IL M.S. Radiation Protection, Harvard University, Cambridge, MA Sc.D. Radiation Protection and Radiobiology, Harvard University Cambridge, MA

SUMMARY

OF EXPERIENCE 1985 - Present Manager, Research and Development, Nuclear Services Division (NSD), Hydro Nuclear Services, Inc. The scope of this position includes the da.velopment of haroware systems, so f tw are, and consulting services that are needed by the nuclear industry; Principal accomplishments are: Design of a series of state-of-the-art radiological o process control monitors. These devices operate with any scintillation or gas-filled radiation detectors. Advanced human factors concepts, real time background subtractions elegint measurement algorithms, and microprocessor control distinguish these devices from all others, Design of a high sensitivity portal monitor. o Design of an advanced stand up whcie body o counter for screening nuclear workers. This unit employs a custom designed detector for short counting times, 1983 - 1985 Manager, Health Physics and Radwaste, Radiological Services Division (RSD), Hydro Nuclear Services. Responsible for sales and technical activities involving approximately 20 engineers and technicians. Specific activities covered areas of health physics, chemistry, radwaste, and emergency preparedness: o Preparation of ALARA procedures for a BWR recirculation pipe replacement outage. o Cost benefit analysis of options for reducing buildup of crud in BWR recirculation piping, o Development and implementation of man-new estimation program for BWR pipe replacement

outage, o

improvements to personnel contamination control program at one BWR and two PWR sites,

DRAFT ARTHUR E. DESROSIERS PACE 2 State-of-the-art calibration procedures for PINC-1 o and PING-3 air monitors. o Development of chemistry procedures and equipment for sampling and analysis of HTO and HT in effluents. Calibration procedures for radwaste monitors. o 1978 - 1983 Staff Scientist and Project Manager, Battelle North-west, Pacific Laboratory, initial assignments at the Pacific Northwest Laboratory included a variety of tasks: o Methods for establishing environmental limits for land disposal of radiological wastes using risk objectives. o Consultant to DOE regarding proposed EPA /FRC guidance for limiting occupational radiation doses, o Environmental assessment of proposed expansion of spent fuel storage at Morris, IL. o Review of environmental radiation levels in the vicinity of DOE laboratories and facilities. o Analysis of differences between ICRP Report 26 and DOE's occupational and environmental radia-tion regulations, o Uranium and thorium burdens in uranium ore crusher -operators: measurements and internal dosimetry study design, o Personnel dosimetry TLD system review. Since 1979 activities have centered on project manage-ment of technical assistance to the NRC in upgrading emergency preparedness at licensed reactors, fuel cycle facilities, and the NRC's operations center. Project management duties include interactions with sponsors, contracts, subcontracts, financial controls and budgets, scheduling, task definition and assign-ment, and technical review of results. Limited line management duties were also per formed. Technical assistance tasks covered a wide variety of activities and disciplines:

ARTHUR E. DESROSIERS MDACY u smii e PAGE 3 o Audits and appraisals. o Evaluation of exercises, o Review of emergency plans. Development of audit programs, o o Offsite dose calculations. o Development of dosimetry computer programs, o Studies of siren system acoustics and e f fective-

ness, Development of evacuation time estimate ' codes.

o Calculations of evacuation time estimates. o Design of emergency operations facility. p o Emergency operations training, o o Criteria for evacuation time estimates. o Guidance for developing scenarios. Evaluation of emergency response facilities. o o Ceneric emergency action levels, o Site-specific risk assessment. Staffing emergency facilities. o These projects have involved approximately 40 staff members in activities totaling $10 million. Consulting activities have included NRC,

FEMA, the Federal Republic of Germany, and the United Nations (I AEA),

1976 - 1978 Rad.ological

Engineer, Environmental Surveillance Programs, Yankee Atomic Electric Company.

The major focus of activities was licensed sites (Yankee Rowe, Vermont Yankee, Maine Yankee and Pilgrim 1). Other activities were related to the Seabrook site and the New England Power site. The cognizant engineer designed and licensed surveillance programs, w rote l procedures for technicians and engineers, verified the implementation of procedures, trained technicians and

DRAFT ARTHUR E. DESROSIERS PAGE 4 engineers, examined data, maintained data bases, and prepared routine and special reports. Special develop-ments included: Methods for improving cost-effectiveness, o o Data base management. o Automated data review. o Statistical analysis routines, o Report generation computer code. o OA program development, o OA/OC audits of three laboratories, o QA/OC for air sampling program. o LLD determination, reporting and analysis. These programs included normal surveillance activities as well as programs for analysis of transuranics, long-term terrestrial accumulation, sedimentation pro-files, and cesium uptake studies. Associated duties included analysis of occupational risks related to radiation, review of proposed regula-tory requirements, de minimus standards for waste disposal, environmental risk calculations, assistance with Safety Analysis Reports, and public speaking. 1969 - 1971 Nuclear Weapons Specialist, U.S. Army. 1968 Systems Programming, International Business Machines. PUBLICATIONS Approximately one hundred reports, articles, manuals, books, and presenta-tions have been authored or coauthored in' English, German, French, Spanish and Russian. AWARDS AND HONORS Distinctions include: o Baccalaureate cum laude

E RTHUR E. DESROSIERS g{ AEC Special Fellowship in Health Physics o Member of interagency committee for federal occupational expo. o sure guidance o Chairman of IAEA Advisory Group 318 o Member of ANSI 15.14 committee o Past Chairperson, Radiological Health Sectio', American Public n Health Association

DRAFT RESL?I g yftCIL10Wg NAME: Wal t e r P. L'agne r TITLE: Quality ControlQgervisor DATE OF BIRTH: January 1, 1941 DATE EMPLOYED: October 6, 1980 L'ORK EXPERIENCE: NUCLEAR (GPC) Postrion: Ouality Control Supervisor Dates: 8/20/83.co Present Location: Plant Vogtle Plant Status: Under Construction Job

Description:

Develop plant operational Quality Control Program and implement progree once developed. Position: Senior Q. A. Field Representative Dates: 10/6/80 to 8/19/83 t Location: Plant Hatch Plant Status: Operational Ek? Job

Description:

Planned and performed periodic audits of the operation of Plant Hatch to assure compliance with codes, stan-dards, regulations and specifications as required by the Quality Assurance Program. Reviewed plant procedures for technical adequacy and quality requirerents. Performed surveillances nf plant activities. Assisted in the auditing of the nuclear fuel supplier for the plant. Provided assistance to plant personnel in quality related matters. Also served as alternate member en Plant Review Board, repre-senting Quality Assurance. NUCLEAR (OTHER) Position: Staff Specialist Dates: 1/21/80 to 9/30/50 Location: Millstone Unit 2 Plant Status: Operational PWR Job

Description:

Employed by General Physics Corpora tion, under contract to plant to clear up backlog in design change packages. Duties included preliminary design work, drawing revisions design change implementation supervision, testing and design package closecut. Other duties included providing inter-face with contractors and vendors during major hanger and baseplate modifications.

DRAFT Resume Calter P. Wagner Page 2 NUCLEAR (OTHER) Position: Mechanical Maintenance Supervisor (Cont'd) Dates: 2/77 to 1/78 Location: U. S. Army Nuclear Power Barge Plant Status: Undergoing Decommissioning Job

Description:

In charge of mechanical maintenance shop. Responsible for preparing reactor vessel, spent fuel tank and containment vessel for decommissioning. Perf ormed visual inspectiers, penetrant testing and hydro-static tests to ensure quality control. Also assisted in defueling of reactor and loadirg and shipping fuel and con-trol rod casks. Position: Senior Reactor Operator Dates: 10/76 to 6/77 Location: U. S. Army Nuclear Power Barge Plant Status: Shurdown Job

Description:

Performed duties of Shif t Supervisor. Responsible for the safe and prcper operation of the reactor and associated plant systems in accordance with regu-lations, Technical Specificatiens erd procedures. Assisted in preparing the vessel to be towed free the Parama Canal Zone to Fort Belvoir, Virginia. Per-formed repairs to vessel and plant sys-tems resulting f rom storm damage while at sea. These tasks focluded welding, weld inspection, rigging, inspection 'of compenects and nuclear systems and cleanup of contaminated debris. Position: Pechanical Maintenance Supervisor Dates: 4/74 to 9/76 Location: U. S. Army Nuclear Power Barge Plant Status: Operational Job

Description:

Supervised mechanical maintensuce on reactor and balance of plant systems. Duties included providing quality con-trol for peebanical work. This included visual inspection, dye penetrant, ultra-sonic testing, vibratien analysis and hydrostatic testing. Was certified welder on N.S.S. systems. Duties also included training mechanical technicians in the repair and maintenance of plant systems. During this period, also trained and certified as reactor operator on plant.

DRAFT Resume Walter P. Wagner Page 3 NUCLEAR (OTHER) Mechanical Maintenance Technician Position: Dates: 4/73 to 3/74 Location: U. S. Army Nuclear Power Barge Plant Status: Operatienal Job

Description:

Performed preventative maintenence and corrective maintenance on reactor and balance of plant systems. Duties included welding, turbine governor system overhaul, control rod drive system inspection and overhaul and - machining replacement parts. Also served as a member on reactor refueling team. During time frare also trained and certified as plant equipment operator. Position: Operator / Mechanical Maintenance Technician y Dates: 3/71 to 3/73 Location: U. S. Army Nuclear Plant (FM*1) Plant Status: Operational Job

Description:

Duties as mechanical maintenance techni cian included preventative maintenance and corrective maintenance on plant equip-cent, defueling and refueling reactor ard welding. Major task accomplished during this period was the fabrication and installation of new mainsteam piping and valves. During this period of *1=e, also trained and certified as plant equipment operator and reactor operator. Duties included the sefe operation of the plant and the training of student operators. NON-NUCLEAR (OTHER) Position: Power Plant Chief / Team Supervisor Dates: 2/78 to 9/79 Location: Fort Gillem, Georgia Jcb

Description:

Supervisor of a team of technicians providing technical support to U. S. Army and U. S. government facilities world-wide. Tasks included overheul and testing of large diesel generators, infrared surveys of electrical trans-mission systems for f aults and buildings for heat losses ar.d the Inspection and repair of security systems.

DRAFT Resume Walter P. Wagner Page 4 TRAINING: NUCLEAR Course

Title:

Nuclear Power Plant Operators Course Dates: 3/70 to 3/71 Total Course Lgth: 1 year Military School School: U. S. Army Nuclear Power Program

== Description:== Course taught in 3 4-month phases Academic subjects, operations, and specialty. Academic subjects included math, physics, water chemistry, cechani-cal engince'rirg, electrical engineering, nuclear engineering, and health physics. The operations phase consisted of working as a trainee in a nuclear power plant. The equipment operar.or trainee learned equipment operation, system components, system function, systems interactions, turbine-generator operations, cortcin-ment entry procedures, startup and shutdown. The control room operator trainee learned and manipulated *re controls of a nuclear power plant for startup, shutdown, and at power. The control rocc operator trainee was trained on emergency precedure response on the simulator for the nuclear power plant. The specialty phese censisted of additional training in one area as directed by the schcol. Mechanical specialty consisted of training in machinists trainirg welding, equip-ment repair, governor overhaul, rigging, control rod drive maintenance, NDT methods and pipefitting. Course

Title:

Operation & Maintenance of Governors Uates: 4/72 Total Course Hrs: 40 hcurs Vendor: Woodward Governor Co.

== Description:== The course provided instruction in the operation of hydraulic and electro-hydraulic governors. Trouble shooting, overhaul and repair of governors was also taught.

DRAFT aes" Walter P. Wagner Page 5 TRAINING (Cont'd) NUCLEAR Course

Title:

NDT Basic Course Dates: 11/72 Total Course Hrs: 40 hours Vendor: U. S. Army Watertown Arsenal

== Description:== Course consisted of instruction in fundamental concepts of non-destruc-tive testing and the applicatien of techniques used in NUT. Course

Title:

Radiograph inspection Course Dates: 3/73 Total Course Hrs: 80 hours Vendor: U. S. Army Watertown Arsenal

== Description:== The course consisted of lecture and laboratory sessiors in Radiography Theory, X-Ray and Gamma Radiography, Exposure Techniques Quality Require-ments, Application of Specifications and Standards and defect identifiertien. Ccurse

Title:

Auditor Training Dates: 4/81 Total Course Hrs: 40 hours Vendor: Bechtel Corporation

== Description:== Course presented the technicues of nuclear auditing, report writing, interface with personnel, require-ments of regulations and standards and practical audit exercises. Course

Title:

Nuclear Crane Fr.rdling Dates: 5/83 Total Course Hrs: Vendor: U. S. Crane Certification Bureau

== Description:== Course covered the inspection of cranes and crate components, the operation of ' I overhead gantry cranes and standards s ., s and regulations applicable to nuclear industry cranes. i OTHER Course

Title:

Electromotive Diesel Engines i Dates; /78; Total Course Hrs: 40 hours Vendor: EMD Corporation Course covered the description, function

== Description:== and operation of Electromotive diesels.

DRAFT Resume Walter P. Wagner Page 6 TRAINING (Cont'd) OTHER Description Cont'd.: Maintenance and trouble-shooting were presented through lecture presentations erd practical exer-cises. Course

Title:

Weld Inspection Dates: 3/79 Total Course Hrs: 40 hours Vendor: Hobart/ Corps. of Engineers

== Description:== Course presented recuirements and techniques of weld inspection. Students inspected sample welds and observed techniques of welding which resulted in flavs. p Course

Title:

Supervisory Team Building Dates: IC/E3 Total Course Hrs: 40 hours Vendor: GPC/Neillson

== Description:== Course was designed to achieve team attitude among plant supervisory and ranagement personnel through inter-action and dialogue. Course also instructed in public speaking, effective writing and other princi-pals of ccemunication and management. Course

Title:

Visual Inspection Dates: 9/81 Total Course Hrs: 32 hours Vendor: Georgia Power Company

== Description:== The course provided the requirements and techniques of performing visual inspections. Successful passage of the course and required physical testing resulted in a certificate of qualification. Course

Title:

New Supervisors Ccurse Dates: 11/83 Total Course Hrs: 36 hours Vendor: Georgia Power Company

== Description:== The course addressed the principles of supervision, good supervisory characteristics and techniques and the handling of conflict. The

Resume Walter P. Wagner. gy T l Page 7 TRAINING (Cont'd) OTHER Description Cont'd: course also provided orientation by several GPC Departments such as Labor Relations, Human Pescurces and Training. Certifications: ~ Equipment Operator - SM-1 Nuclear Power Plant Control Room Operator - SM-1 Nuclear Power Plant Certified Welder - GTRW - U. S. Army Engineer' Power Group Certified Welder - SMAV - U. S. Army Engineer Power Group Mechanical Technician - SM-1 Nuclear t Power Plant Equipment Operator - MH-1A Floating Nuclear Power Plan

• Control Room Operator - MH-1A Floating Nuclear Power Plant Shift Superviser - FF-1A Floating Nuclear Power Plant Radiograph Inspector - U. S. Army Watertown Arsenal Visual Inspection - Level I - Georgia Power Company O. A. Lead Auditor - Georgia Power Company

[.' '5 Q '.- ffa- - RESUME ,, _l } ' gyncd S A?EOISCL ~C.' : NAME: Michael J. Rowe o $. y a Qociate Ekineer MMT ?C-TITLE: '.'. i '. I DEGREE: 8.S. in Nuclear Engineering ~ i..,. WOmi DATE OF BIRTH: November 11, 1954 L..:.-V.Q DATE.0F EMPLOYMENT: August 31,'1981 r;r; :. if0RK EXPERIENCE: g. Offfp4MS. NUCLEAR (GPC) Position: ///$y'ar-' '- Niamer 8#$tpOL to Present Dates: F Location: VEGP .L;.., Plant Status: Constrvction - Unit 1 107, Unit 2 Job

Description:

Operations Department, Emergency and Abnormal Operating Procedures. Position: Jr. Engineer Dates: 1/04/82 to 4/23/82 Location: HNP t Plant Status: Operation of 2 units ~ Job

Description:

Qualified new fuel inspector for GE supplied fuel and outage support including activities in: core discharge, core reload, new fuel inspection, fuel I reconstitution, fuel sipping and general outage support. NUCLEAR (OTHER) Position: Vice President RTS Laborat:: ries, Inc. Dates: 3/80 to 3/81 Location: Gainesville, Florica l Plan: Status: l Joe Descri::: ton: Coorcina: ton of C:n:ric: Eff:r., i Resear:n Cirac :r I i l I I \\ l l i i _~_

e. RESUME Mic6ael J. Rowe DRAFT Position: Engineer I. University of Florida ( Dates: 3/79 to 3/80 Lacetion: Gainesville, Florida Plant Status: Job

Description:

Group Coordinator and Chief Engineer for contracts / grants in the Department of Nuclear Engineering, Phontonics Group. Position: Consultant Dates: 3/79 to 8/81 Location: Gainesville, Florida Plant. Status: Job

Description:

Various consulting for NSWC, NASA DOE, U of 4 FL. NON-NUCLEAR (GPC) None t nc f3 '7 NON-NUCLEAR (OTHER) Position: President, SARACO, Inc. / y, k Dates: 11/79 to 8/81

g. r >.

Location: Gainesville, Florida [$& Plant Status: ,f Job

Description:

Operation and develop-a P-ment of Aviation Corporation. TRAINING: i l NUCLEAR Course

Title:

Operation Technology Training (OTT) v E Dates: 8/30/82 to 12/23/82 ~ Vendor: General Physics l

== Description:== A 16 week course on Theory and Systems i specific to VEGP. Course

Title:

Simulator Training Dates: 1/04/83 to 3/18/83 Total Course Hrs.: 240 1 Vendor: General Physics l

== Description:== A 6 week simulator course on the VEGP Simulator. ~ h I aw WE _ ' #.. y;.sg. g ....g. M :R *i:N.* ~~'=.*? ' T.*.~ W'"i'WA""" *- ~ ~~ ~' T~:.T"F*r ~ - ~

,. RESkmE Mictia21 J. Rowe DRAFT Course

Title:

PWR Class i. Dates: 9/81 ^ Total Course Mrs.: 40 Vendor: General Physics

== Description:== Introduction to Pressurized Water Reactors with a'VEGP systems description. Course

Title:

Reactor Operations Second Person / Qualifications (1977) Dates: / Total Course Hrs.: 80 / Vendor: University of Florida l

== Description:== Qu'alification of the- - second person on the UFTR - 100KW Reactor. Course

Title:

Graduate School Dates: 1/79 to 6/81 Total Course Hrs.: 35 credit hours t l Vendor: University of Florida

== Description:== Graduate School in f l Engineering with a l major in physics. NON-NUCLEAR Course

Title:

Problem Solving Class Dates: 6/28/82 to 6/30/82 Total Course Hrs.: 24

== Description:== Techniques for solving job related problems. OTHER I (Applicable to Related Publications (of'14) Co author with Power Production) " Coal Burning Issues" A. E. Green i " Nuclear Pumped Lasers" - Co author R. T. Scnneioer, F. Holh Author for j " Coal Gasification" Researen Prcoosal, RTS Laos RELWr.D EXPES.IENCE: Position: Researc-Assistant Cates: 6/75 o 3/79 i b m-

RESLME Micha21 J. Rowe Page 4 DRAFT Location: Plant Status: Job

Description:

R/D in the nuclear field including working radiation environments - military and civilian facilities. 4 years O f e t i h h I h h h. L 5/28/85

RESUME DRAFT NAME: Henry H. Butterworth, III DATE OF BIRTH: September 29, 1958 $prM'r d"'3 f DATE EMPLOYED: June 22, 1981 g TITLE: _ Shif t S ;rch (SR0/ Cert) EDUCATION: BNE,1981, Georgia Institute of Technology LICENSE / CERTIFICATIONS: Nuclear Regulatory Comission Senior Reactor Operator Certification WORK EXPERIENCE:

SUMMARY

Thirty-four months experience with Georgia Power Company. Thirty-four and one-half months nuclear experience with NTOL Utility Working Group weighting factors. Mditional experience is being involved with Unit 1 outage at Farley Nuclear Plant, February,1984 thru April, 1984. 9 NUCLEAR (GPC) Position: ShiftSupervisor(SR0/ Cert) Dates: March 9, 1984 - April 22, 1984 Location: Farley Nuclear Plant Plant Status: Unit 1 & 2 operational with Unit 1 in a refueling outage. Job

Description:

I was envolved in Hot Partici-pation experience at Farley Nuclear Plant, and was the Plant Coordinator for VEGP at Farley Nuclear Plant. Position: Shift Technical Advisor (SR0/ Cert) Dates: October 1,1983 - March 8,1984 Location: Farley Nuclear Plant Plant Status: Unit 1 & Unit 2 operational with periods of Unit 1 or Unit 2 in a refueling outage. Job

Description:

I was envolved in Hot Partici-pation experience at Farley Nuclear Plant, and was the Plant Coordinator for VEGP at Farley Nuclear Plant. I also reviewed various VEGP Startup procedures and developed an Observation Training Checklist. Position: Shift Technical Advisor (SR0/ Cert) Dates: . Sept.10,198 3 - Sept. 30,19 83 Location: Vogtle Electric Generating Plant Plant Status: Units 1 & 2 under construction

Henry H. Butterworth, III DRAFT Resume Page Two NUCLEAR (GPC) CONT'D Job

Description:

I coordinated a simulator training program for SRO candidates and administered and developed a final written exam using NRC format. Position: SimulatorEngineer(SR0/ Cert) Dates: Jan. 28, 1983 - Sept. 9, 1983 Location: Vogtle Electric Generating Plant Plant-Status: Units 1 & 2 under construction Job

Description:

As a Simulator Engineer (SR0/ Cert), I evaluated the Vogtle Simulator computer codes and compared them to actual conditions, assisted in the development of an SRO training program, taught SRO training course simulator and classroom sessions, t participated as a third operator in the Control Room Simulator during a NRC-SR0 Certification exam, and developed an action plan for the VEGP Training Dept. Position: Simulator Engineer Dates: Jan. 22, 1982 - Jan. 27, 1923 Location: Vogtle Electric Generating Plant Plant Status: Units 1 & 2 under construction Job

Description:

As a Simulator Engineer I assisted in acceptance of the Vogtle Control Room Simulator at the factory and on site, I assisted in the development and teaching of the Operations Orientation Course, the E. I. Hatch Emergency Plan Training, and Customer Relations l Training at Plant Vogtle, and I was envolved in on-the-job instructor training in preparation for an NRC SR0 Certification exam. m.___. , ~. - __y_._yy y.

Resume Henry H. Butterworth, III Page Thre* DRAFT NUCLEAR (GPC) CONT'D Position: Junior Engineer Dates: June 22,1981 - Jan. 21,1982 Location: Vogtle Electric Generating Plant Plant Status: Units 1 & 2 under construction Job

Description:

As a Jr. Engineer I perfonned miscellaneous projects and reviewed plant documents for consistency. I also attended a Shift Technical Advisor course and filled in as a Radwaste Operator at Plant Hatch during an IBEW strike. TRAINING: NUCLEAR Course Titie: Hot. Participation Experience Farley Nuclear Plant October 1,(1983 - April 22,1984 Dates: 1100 hrs. approx.) y Total Course Hrs.: Vendor: N/A

== Description:== On-shift Hot Participation Experience at Farley Nuclear Plant Course

Title:

Operations Department Refresher Training Program Dates: Jan.1,1984 - on going Total Course Hrs.: 20 hrs / month Vendor: Georgia Power Company

== Description:== This course is a monthly topical training program, including references, assignments and a exam. This course is designed to assist in the self study of infonnation needed to pass a SRO Cold License i exam. I Course

Title:

ALARA Awareness Seminar Date: March 30, 1983 Total Course Hrs.: 8 hrs. Vendor: Westinghouse Nuclear Technology Division

== Description:== This course was given to provide engineers with criteria, i design features, operational guidelines and operating l plant experience relevant l to radiation protection and the minimization of i occupational dose. l l

Resume Henry H. Butterworth, III hkfff Page Four TRAINING: NUCLEAR (CONT'D) Course

Title:

Advanced SimulatorOperational Training,NPO-461)f Pressurized Considerations o Thermal Shock Dates: Spring, 1983 Total Course Hrs.: 24 hrs. Course

Description:

This ccurse reviewed the theory of materials science and pressurized thermal shock, discussed operation during a PTS event, and described PTS events with specific examples. There also was a demonstration of the use of FR-P.1 in the Control Room Simulator during a PTS event. Course

Title:

Observation Training / Farley Nuclear Plant t Dates: October & November,1982 Total Course Hrs.: 120 hrs. Vendor: N/A Course

Description:

This training was on-shift observation of the Operations Department at Farley Nuclear Plant, to get a big picture perspective of the Control Room environment. Course

Title:

Simulator Training Dates: August 9, 1982 - Sept. 17, 1982 Total Course Hrs.: 240 hrs. Vendor: General Physics Corporation Course

Description:

This course was the simulator portion of the 23 week Operations Technology training course. It covered ANS category's 1, 2, 3 and 4 conditions in the Control Room Simulator, using Unit Operating and Emergency Operating Procedures. There was a final written and oral exam. Course

Title:

Hardware & Software Overview for Vogtle & Hatch Simulators Dates: Spring, 1982 Total Course Hrs.: 30 hrs. Vendor: Singer, Link Division Course

Description:

This course gave an overview l of the hardware and software delivered with the Vogtle and Hatch Simulators. L

i Resume Dgn y Butterworth, III TRAINING: 1 NUCLEAR (CONT'D) Course

Title:

Shift Technical Advisor 4 Training 4 Dates: Sept. 28,1981 - Jan. 22,1984 Total Course Hrs: (17 weeks), 680 hrs. Vendor: General Physics Corporation Course

Description:

This course was the classroom portion of SRO academic training for entry level engineers. It covered theory, systems, and integrated plant operations with weekly exams and a final exam. Course

Title:

PWR Orientation Course Dates: Sept. 14, 1981 -. Sept. 18, 1981 Total Course Hrs.: 40 hrs. Vendor: General Physics Course

Description:

This class was an overview of theory, systems and plant l operations; with a worksheet. TRAINING OTHER Course

Title:

Quest For Excellence I Dates: April 30, 1984 - May 1, 1984 Total Course Hrs.: 16 hrs. Vendor: Georgia Power Co. Course

Description:

This course reviewed the i history of management, discussed i different methods of management, and presented Georgia Power's new philosophy on management. Course

Title:

Technical Comunications Dates: April 23,1984 - #pril 27,1984' Total Course Hrs.: 40 hrs. i Vendor: Nilsson Professional Consulting, Inc. Course

Description:

This course reviewed principles i of writing and speaking in public. It used numerous exercies to improve writing and speaking skills. Course

Title:

Project Management C.P.M. t Dates: January 17,1983 - Jan.19,1983 i Total Course Hrs.: 20 hrs. Vendor: Georgia Power Company i 1

4 Resume Henry H. Butterworth, III DRAFT Page Six TRAINING: OTHER CONTINUED Course

Description:

This course gave an overview of project management with subjects on Network Analysis, Time / Cost Trade-off, Resource Leveling, PERT, Project Simulation, and Project Control. The course also included a class project and questions for each section. Course

Title:

Customer Service Instructor Training Dates: Fall,1982 Total Course Hrs.: 8 hrs. Vendor: Georgia Power Co. Course

Description:

This course gave an overview of the Customer Relations I course presenting methods to teach the course, visual aids and general direction of the intent of the course. ~ Course

Title:

Instructor Training Course Dates: June 22, 1982 - June 25, 1982 Total Course Hrs.: 28 hrs. Vendor: Georgia Power Co. Course

Description:

This course covered methods to present and prepair classroom courses. This course included individual presentations and group presentations with critique and video tape review. Course

Title:

Effective Speaking Course Dates: Feb. 8,1982 - Feb.10,1982 Total Course Hrs.: 20 hrs. Vendor: Georgia Power Co. Course

Description:

The purpose of this course was to develop the skills to prepare an ef fective presentation and to give a precise and forcefull delivery. Thr. course included two 5 to 7 minute speaches and a mock city council meeting. I 5/28/85

=

DRAFT NAE: Samuel Blair Poteate III DATE OF BIRTH: June 5, 1957 DATE EMPLOYED: June 22,1981 TITLE: Operations Supervisor EDUCATION: Bachelor of Science in Mechanical Engineering from Virginia Polytechnic Institute State University LICENSE / CERTIFICATIONS: STA Certification (Hatch) by GPC,0ct.1982 Engineer In Training (VA.),1981 New Fuel Inspection Certification by General Electric Sept.1983 WORK EXPERIENCE: SUP9tARY 4 years power plant experience 4S years nuclear power plant experience Participated in startup. shutdown. power operation, and refueling at Plant Hatch,1982-1984 Worked as Undergraduate Research Assistant in the Turbomachinery Dept, at VPI & SU. NUCLEAR (GPC) Position: Operations Supervisor Dates: 09-28 Present Location: Plant Yogtle, Burke Co.,Ga. Plant Status: Under construction and startup Job

Description:

Senior nuclear operations representative on shift with responsibility for all plant operations, Initial Test Program and Nuclear Construct-ion support. Additional temporary assignments include:

1) Reactor coolant system primary hydrostatic test coordinator for Operations Department-Report to the Operations Superintendent and Test and Outage Manager.

Responsible for overall coordination. Operations Dept, training, and procedure development to support the RCS hydrostatic test.

2) Construction liason-report to the General Manager, Nuclear Operations. Responsible for coordination of activities and priorities between Nuclear Construction and Nuclear l

Operations.. l

Resume e Blair Poteate,IU WORK EXPERIENCE: NUCLEAR GPC CONT'O Position: Shif t Supervisor uates: 06-01-84 thru 09-27-85 Location: Plant Vogtle. Burke Co.,Ga. Plant Status: Under Construction & startup Job

Description:

Responsible for directing activities of on-shift personnel in support of Unit I startup. Responsible for coordination of all ter. ting activities to ensure safe and efficient utilization of available resources. Position: Shift Supervisor Dates: 03-17 06-01-84 Location: Plant Vogtle, Burke Co.,Ga. Plant Status: Under construction and startup Job

Description:

On temporary assignment at t Plant Hatch from August 1982 until May,1984. Hatch assignment involved STA and Reactor Engineerir; responsibilities that include: 1)STA-Required to maintain an STA Certification and perfom the duties of STA on shift that include, perfoming transient analysis, investigat-ing abnonnal or unusual operating events, being present in the control room during all planned evolutions (i.e. turbine testing MSIV surveillance, rod pattern adjustments.startup, shut-down, load changes, etc). Serve in advisory capacity to the Operations Supervisor.

2) Reactor Engineering-monitor control rod depletion, schedule purchasing and re-placement of control rods, nuissance annunciator control program, writing and engineer-ing review of plant procedures, coordination of Nuclear Network program, control rod scram time analysis program.

._~ Resume Samuel Blair Poteate,III DRAFT Page Three WORK EXPERIENCE: NUCLEAR GPC (CONT'D) Position: Initial Test Program Test Director Dates: Feb.5, 1985-June 14,1985 Location: Plant Vogtle. Burke Co.,GA. Plant Status: Under construction and startup. Job

Description:

Responsible for 1)Providing overall priorit-fration on a daily basis to the Initial Test Program personnel and act as chair-person for the weekly priorities and plan of the day meetings. 2)Providing guidance and assistance to Test Personnel in anticipating and resolving problems. 3)Providing the Initial Test Program Manager with feedbacI on daily activities focusing on problem requiring attention.

4) Assisting Lead Test Supervisors in development of Test Supvisors.

5) Ensuring that assigned project milestones are completed in a timely manner, by priorit-ization and coordination of available resources.

6) Ensuring that daily and weekly work plans are developed and distributed on time.

Position: Shif t Technical Advisor Dates: 01-02-83 thru 03-17-84 Location: Plant Hatch,Baxley,Ga. Plant Status: Full power operation Units 1 4 2 Job

Description:

STA and Reactor Engineering responsibilities as described above under Shift Supervisor. Position: Associate Plant Engineer Dates: 12-25-82 thru 01-02-83 Location: Plant Vogtle, Burke Co. GA. Plant Status: Under construction Job

Description:

On temporary assignment to ( Plant Hatch to perform STA and Reactor Engineering duties as described above under Shfft Supervisor, a

Samuel Blair Poteate,III T Resume.. Page Four-4 WORK EXPERIENCE: NUCLEAR GPC CONT'D l Position: Plant Equipment Operator (during employee strike) July 8,1981 - July 27,1981 Dates: Plant Hatch,Baxley,GA. Location: Plant Status: Power Operation, Units 1 & 2 Job

Description:

Inspection and data recording of operating equipment in i the Reactor, Turbine, and Control Buf1 dings. Position: Junior Plant Engineer June 22,1981 - Dec.25,1982 Dates: Location: Plant Vogtle,8urke Co.,GA. l Plant Status: Under construction Job

Description:

FSAR review, development of Plant Vogtle, Plant Hatch, and Georgia Power Corporate ! Emergency Plans. Participate in Hatch STA ~ ( training program. 2 I None NUCLEAR (OTHER) None NON-NUCLEAR (GPC) NON-NUCLEAR (OTHER) Position: Undergraduate Research Assistant in the Turbomachinery Department at VPI & SU March 1981 - June 1981 j Dates: Job

Description:

Provided research assistance to Ph.D candidates and faculty members in the Turbomachinery i Lab. TRAINING: Course

Title:

Turbine Generator Training NUCLEAR August 1984 Dates: Total Course Hrs.: 40 hrs. Spectrum Technical Training Inc. Vendor: i

== Description:== Design and operation of Plant 1 Vogtle main turbine generator, turbine generator auxilliaries, l and the steam generator feed pump turbine. ( 1

Resume e Blair Poteate,111 g TRAINING: NUCLEAR CONT'D Course

Title:

Plant Hatch STA Certification Dates: August 9,1982 - October 24, 1982 Total Course Hrs.: 11 weeks Vendor: General Physics

== Description:== A detailed study of Plant Hatch systems and operation, BWR reactor physics, BWR themal hydraulics, operating and.abnomal operating procedures, and plant Technical Specifications. The course included 6 weeks of classroom instrcction and 5 weeks of Plant Hatch simulator instruction. Testing consisted of weekly tests as well as an STA Certification written examination and a simulator oral examination at the end of the course Course

Title:

On-The-Job Reactor Engineering Training Dates: October 1982 - December 1982 Total Course Mrs.: 7h weeks Vendor: N/A

== Description:== This on-the-job training consisted of working regular shif t hours with an existing STA/idactor Engineer and detailed study in the areas of Reactor Physics, nuclear instrumentation, power distribution calculations, core flow deteminations. Technical Specifications, the process computer, Preconditioning Interim Operating Management Recomendations (PC10MR), control rod pattern sequence development, and operating strategies. j (

Sa u Blair Poteate, III Page Six TRAINING: NUCLEAR CONT'D Course

Title:

New Fuel Inspection Dates: September 22, 1983 Total Course Hrs.: 8 hrs. Vendor: General Electric

== Description:== Instruction on inspection methods and acceptance criteria for new fuel. Personnel with this training are required to inspect all new fuel as it arrives on site, prior to placement in the fuel pool. Course

Title:

Plant Vogtle STA Training Dates: March 1,1982_ - July 26,1982 Total Course Hrs.: 22 weeks t Vendor: General Physics

== Description:== A detailed study of Plant Vogtle systems and operation, PWR reactor physics, operating procedures. The course included 15 weeks of classroom instruction and 7 weeks of Plant Vogtle simulator instruction. Testing consisted of daily quizzes, weekly tests as well as written and oral simulator examinations at the end of the course. Course

Title:

PWR Orientation Course Dates: Sept.14,1984 - Sept.18,1981 Total Course Hrs.: 40 hrs. Vendor: General Physics

== Description:== PWR fundamentals and systems NUCLEAR (OTHER) Course

Title:

Control Room Management Dates: 08-29-83 thru 08-31-83 Total Course Hrs.: 24 hrs. Vendor: General Electric

== Description:== The Kepner-Tregoe methods of situation appraisal, problem analysis, decision analysis, and potential problem analysis were taught. Text: The Rational Manager ( by Kepner & Tregoe.

r DRAFT u Blair Poteate,!!! Page Seven NUCLEAR OTHER(CONT'Q) Course

Title:

Technical Communications Dates: April 23,1984 - April 27,1984 Total Course Mrs.: 40 hrs. Vendor: Nilson Professional Consulting, Inc.

== Description:== Technical writing, preparing and presenting briefings and technical presentations, stress management, meetings management, self management, and interpersonal communications. Course

Title:

Managing in a Changing Environment Date: May 8,1984 Total Course Hrs.: 8 hrs. Vendor: Nilson Professional Consulting, Inc.

== Description:== Communication skills, coaching, self confidence, and stress management. Course

Title:

New Supervisors Schools Dates: May 21,1984 - May 25,1984,- Total Course Hrs.: 40 hrs. Vendor: N/A, Georgia Power Company

== Description:== Effective communication skills and techniques, positive and negative feedback, employee compliants, Georgia Power Company Human Resources procedures. Course

Title:

Labor Relations Training Dates: Septeraber 27, 1984 Total Course Hrs.: 8 hrs. Vendor: N/A, Georgia Power Company

== Description:== Labor contract interpretation and implementation. I i t

Dkk(( VEGP-FSAR-13 D. The superintendent-plant engineering and services, who is responsible for onsite engineering and technical support of the plant. E. The superintendent-engineering liaison, who has responsibility for coordinating construction and technical support activities in making plant modifications. F. The superintendent-maintenance, who is responsible for performance of preventive maintenance and repairs on plant equipment. physicsbucerintendenth,whodirects G. The and health physics activities, and who is responsible for the radiation protection program of the plant. H 4 Ser Ws tr84'uer4 pag 4-jg. The superintendent-regulatory compliance, who is responsible for advising plant management on matters concerning compliance with the Final Safety Analysis Report (FSAR), operating license, technical y specifications, approved plant procedures, emergency plan, security plan, etc., and other applicable federal, state, and local regulations. 16 sq (m r f 3 [. The -qmm:y wL.,9,g t ro. t (m%\\. .it, .n muperv+ soc, who is responsible for 1, performance of work inspections, verification of procedures used in the control of special processes, and material equipment control of the plant. This supervisor reports to the Superintendent of Regulatory Compliance. ( jf. The superintendent-administration, who is responsible for developing and implementing office practices which enable correspondence, document control activities, and other general office activities to be accomplished efficiently. L )[ The superintendent-nuclear training, who is responsible for the development and implementation of the training and retraining programs for the plant staff. The superintendent-nuclear training is also responsible for administering use of the training simulator. NN [. The materials supervisor, who is responsible for preparing requisitions for all operational spare parts, equipment, and miscellaneous supplies for plant use. The materials supervisor is also responsible for receiving, inspecting, shipping, otoring, and Amend. 16 4/85 13.1.2-2 Amend. 17 7/85 i i

[ VEGP-ESAR-13 l17 ma' staining an inventory of spare parts equipment and supplies.

1. )f.

The procurement review section (PRS) site supervisor, who is responsible for ensuring that requisitions for parts, materials, and services specify the correct I h4N" 4. Ika_ f o p vin O 4 - G e m*o h, w b ' 1 '

• E " ' '

ld Nio bs,J.W,Ases J =4 A e r ) .... ~ ) / 13.1.2-2a Amend. 17 7/85

3 DRApr' VEGP-F^AP-13 13.2 TRAINING 13.2.1 LICENSED OPERATOR TRAINING The VEGP licensed staf f will consist of individuals with training, and stgnificant differences in previous education, The licensed training programs have been experience. formulated to provide the required training based upon the individual's prior experience. These programs are desi7ned to provide the highest degree of operator proficiency by effectively using the VEGP simulator. 13.2.1.1 Training Programs The details of typical training programa. Including syllabus, duration, classroom, and on-the-job training, are contained in l19 tables 13.2.1-1 through 13.2.1-6. The programs described in for both units before and thece tables will remain the same after initial fuel loadingu.n/en spddl g4 t / l These programs are designed to train perconnel with varicus sackgrounds as indicated in the above tables. These tables 16 include position, titles, and experience of the individual. The VEGP training department la responsible for the coordination of teaching cources and cupervising the instruction. The VEGP training department is shcwn in floure 13.2.1-1. The qualificaticns of i n n t ruc t o r r, and a descript1or. found in >f the instructor requalification program are caragraph 13.2.1.3.3. v,,1ved on a Indi"1 dual specific training requirements may no case-by-case basis with adequate justli1:attun ind approval o! the superintendent of nuclear training. Specific criteria must be net prior tc ap:+ro. al o f a wa. ver. Waivers wil.1 be granted only if one at rne conditions listed below has been satisfied, A previous course of instruction has been completed and was3 Fat least the o 'thich contained the same topics duration of the course being waived. The course may have been completed at VEGP or another facility. Ecr of instruction trainee who completes a course example, a at Plant Hatch meeting the above criteria would not be required to repeat the courne at VEGP. A preytcus course of instruction has been completed o the cource which contained all of the objectives of This would be determined by comparison of being waived. Amend. 16 4/85 13.2.1-1 Amend. 19 9/85

VEOF-FEAF-13 the objectives of the course completed and the course being waived. If the already completed ccurse et instruction did not meet all required objectives, these additional topics may be taught and course completion may be granted. fy / Completionofanexamination)bythe trainee which is o equivalent to a course eted, comprehensive examination. The examination may be written or cral and must be retained as a recera of successful course completion. 13.2.1.1.1 Nuclear Power Plant Theory Training shall be providec in relevant aspects of nucl.nar power plant theory as required by 10 CEF 55 and NUREG 0737, paragraph I.A.2.1, enclosure 2. The amount of train;ng required is estimated in tables 13.2.1-1 through 13.2.1-6. l 13.2.1.1.2 VEGP systems and Procedures y Training shall be provided in VECP systemn a.5 t. quired by 10 CEF l 55, as indicated in tables 12.2.1-1 thrcugh 13.2 1-6. DELE *TE. f 13.2.1.1.3 VECP Licenae and Technical Specifications 16 Training shall be provuled in VEGP licenae and t e.ht.ical specifications as required by 10 CFR 55, a-

ndicated in tablos 13.2.1-1 through 13.2.1-5.

i 13.2.1.1.4 Fuel Handling and Core Alterations } Training shall be provided in iuel handling an:1 co re alteraticns an indicated t r4 tables 13.2.1-1 as required by 10 CFR 55, @h 13.2.1-5. y 3 13.2.1.1.jf Control Room Cperationc Training shall be provided in control room operations as required by 10 CFR 55, as indicated in taoles 13.2 1-1 through I 13.2.1-6. The training ~ hall be accomplished by utilt;;ng a combination of classroom instruction and hands-on operating practice on the VEGP plant-re f erenced sir ul a tor. The t r.1 ! ri t nq will prepare the candtdste for th. MRC t i r,u l a t.a t portion at the operating examination. Amend. 16 4/e5 13.2.1-2 Amend. 19 9/85

Y0r O '1 furfoSes of hbh hr w inq 4 Sniw weeks skalI k, jef[ng),,, g j,f m-> Wde%-maen'Soh DRAFT Su calede weeu VEGF-E3AF e13 I \\ 13.2.1.1./ Mitigating Core Damage \\ Training for mitigating core damage will have the course content as described in NUREG-0737, item II.B.4, and will be { taught during the courses scheduled in the syllabus, as shown i a i 2n tables 13.2.1-1 through 13.2.1-6. t l19 t 5 23.2.1.1.)I Het Participation /Cbservation and Walkthrough h Training the terms het ) The following paragraphs define the meaning of and walkthrouahl participation experience, observation trainina. f training. Approximate duration for these types of training are specified in tables 13.2.1-1 through 13.2.1-6. The training / l19 will prepare the license applicants for the plant walkthrough.' portion of Nuclear Regulatory Licence examination.4 is direct involvement in review and Hot participation experience discussions leading to decisions relative to operation of a commercial nuclear power plant, or direct hands-on operation as a trainee at a commercial nuclear power plant. Hot participation experien e requirenents ap;'ly onl y prior to VEGP 16 achieving 20 percent power. Gbservaticn training constitutes 4:signmant to an operatinq chite for the purpose cf training. Empna: Is is placed on obsertir.; .n many chifr activities as ;- se:ble, a.g., shift .eitet, operato: rounds, local equipment oporations, control oom activities. Hands on participat.o:. may be conducted undet M bh] observat;on of a qualified operater. cu t .,t. t-^ r' a-le afteu sSK r ': M ; ettt pe=er, - r e e m pr. i s..l f Waikthrough training is a systematic program to become familiar utth plant equipment and layout. It may be conducted ~oncurrently with observation trainir.g or may be conducted as a .eparate program. 6 13.2.1 ld Review and Audit j A 2hort ;srlod of time will be allocated for each individual Itcenso candidate to review material and prapare for a comprehensive audit examination. The effectiveneas of the training program in the case of each trainee will be evaluated from the results of a series of written, oral, and manipulation examinations. Applicants for Nuclear Regulatory Commission (NPC) license examinat ions are given an audit examination which has the same structure as the NRC examination, including a VECP simulator examination. Since applicatie.3 for license must be made before the audit examination resultc are usually available, Amend. 16 4/85 13.2.1-3 Amend. 19 9/85

VEGI-FSAF-13 Georgia Power Company (GPC) will certify to the extensive operating experience based upon the individual's satisfactory progress in the training program. If the individual falls to demonstrate the ability to pass an audit examination or the 3 ability to properly manipulate VEGP simulator controls, GPC will request that the NRC not administer an examination to this individual. Occasionally, the audit examination may uncover a weak area in an individual's knowledge, but if CPC be>!1 eves that the individual has sufficient time to correct the ra cblem mWrawr G/C muu eineaf ,y, [ ec/,c ficacava -l-ce; ekial adien A c. ienl;u.ef an reme e n la at,, & f k ;,,jjg 13.2.1.1 Ope a Tral ing S e le /" 'i//na ft, yf The bar chart in 11gure 13. 1-2 : nows the schedule of the d,*t licensed operator training program .n relation to the schadule for preoperational tests, fuel lead, criticality, and the expected time for licenae examinatiens. If fuel loading la significantly delayed, the '/EGP license requalt11 cation progra-will be used to maintain operatar proficiency. Several specific training i t em.4 for licenr.ed operators identified in tables 13.2.1-1 through 13.2.1-6 (and includ*d in l general topic format in figure 13.2.1-2) will be taught ;ust prior to the precritical license examinations. The item, nct yet included as a part of training, but to be taught pr:or

• 3 licensing include:

a o VEGP Operatir.3 Procedures o VEGP Fuel Hind!1ng and Core Alteration o Mitigating Core Damage o VEGP walkthrough Training o Reactor Startup (if required by Cection 13.2 1.z) o Plant Walkthrouah Audit Exam Personnel listed on figure 13.2.1-2 without an antertsk have completed training in the time frames indicated with the exception of items listed above. 13.2.1.2 ope _ra t io.n Expe r t enc e Reactor operations experience training will be provided by the VEGP plant-specific.31 mu l a to r, the experience gained from the VEGP staff partietpating in the preoperational test program, and the experien.e recsived by the VEGP staff observing and participating in plant startup or operations of other Itght-Amend. 3 1/84 Amend. 16 4/95 13.2.1-4 Amend. 19 9/85

S VEGP-FSAR-13 The cold license tra:ning program will also water reactors. contain a program of 10 reactor startups on a research/ test type reactor to gain actual "at the controls" experience. Personnel with prior Navy nuclear experience as an engineering watch engineering watch supervisor, reactor operator, or

officer, other equivalent positions or~those who have prior commercial nuclear plant licensed operator experience or those who have prior test reactor experience shall be exempted from 10 reactor 10 startup requirements.

A combination of the preceding will satisfy the experience requirements of NUREG-0737, items I.A.2.1. The details of the simulator program are contained in tables 13.2.1-1through13.2.1-{. The VEOP simulator will conform to the guidance given in Regulatory Guide 1.149. Performance testing of the simulator will be specified in paragraph 5.4 of ANSI /ANS-3.5-1981 accomplished in the following manner: 1. Comparison of the steady state operating values of critical and noncritical parameters between the VEGP Unit 1 control room and the simulator at various power 1evels. 2. Maneuvering of the simulator through the following 16 plant evolutions listed in paragraph 3.1.1 of the standard. A. Plant startup - cold to hot standby. The starting conditions shall be refueling conditions of 17 temperature and pressure. B. Nuclear startup from hot standby to rated power. C. Turbine startup and generator synchronization. D. Reactor trip followed by recovery to rated power. E. Operations at hot standby. F. Load changes (manual and automatic control). G. Plant shutdown from rated power to hot standby to cooldown to cold (refueling) conditions, i H. Startup, shutdown, and power operations with lecs than full reactor coolant flow is not permitted by the VEGP operating license and therefore will not be conducted. Amend. 10 9/84 i Amend. 16 4/85 13.2.1-5 Amend. 17 7/85

VEGP-FSAR-13 3. Core physics testing will be comprised of an evaluation of simulation of: A. Estimated critical position computation. B. Estimated critical concentration computation. C. Shutdown margin computation. D. Estimating criticality by the I/M plotting method. 4. Operations surveillance procedure testing will be comprised of those control room operations which are required to conduct the operability tests of the following systems: A. Diesel generators. B. Auxiliary, feedwater. hsri C. High imme safety injection. ? D. Safety injection. 17 E. Residual heat removal. ) F. Nuclear service cooling water. 5. Simulator malfunction conditions shall be evaluated by experienced staff members for best estimate response or compared to actual plant data or other best estimate data. 6. The simulators response to transient conditions will be compared to design information from the simulator data base or other best estimate data. specific performance 7. When a limited change is made, a test on the affected systems and components shall be i performed. All l'esting will be performed independently from any classroom activity, with testing of the simulator as the only objective. The results of all testing will be documented as the testing is being performed. Factory acceptance testing of the VEGP simulator has already been completed. The performance test described above will be completed prior to August 1, 1988 and not less than every 4 years thereafter. 13.2.1-Sa Amend. 17 7/85

DRAFi VEGP-FSAR-13 13.2.1.3 Qualification and Requalification Pro _ gram licensed The qualification and requalification program for cperators and the training department is described in the following paragraphs. 16 13.2.1.3.1 Licensed Operator Qualification Reactor operator and senior reactor operator training programs include the qualification requirements contained in NUREG-0737, item I.A.2.1, and are described in tables 13.2.1-1 through a [19 13.2.1-6. ? f / l Amend. 16 4/85 Amend. 17 7/85 13.2.1-5b Amend. 19 9/85

VEGP-ESAR-13 13.2.1.3.2 Licensed Operator Requalification Program The licensed operator requalification training program will be implemented within 3 months after issuance of an operating license. The program shall be continuous and may be conducted as an intensive program of several weeks duration each year or may be spaced out over a period of up to 24 months, with elements of the program occurring on a periodic basis. Records of the requalification program shall be maintained for a period of 2 years from the date of the recorded event to document the participation of each licensed operator or senior operator in the requalification program. The records shall contain copies of written examinations administered, the answers given by the licensee, results of evaluations, and documentation of any additional training administered in areas in which an operator or senior operator has exhibited deficiencies. An original or reproduced copy or microfilm copy will fulfill these record retention requ:rements. The reproduced ccpy or microfi(p copy will be authenticated by authorized personnel and will be' capable of producing a clear and legible copy after storage for a period of 2 years. For-ooses of 4hese nuns Ann & skll be de}{ng] U Cnd fer calendV feu Sennid SQl be &nd a,ence y eve

2. celendy,

13.2.1.3.2.1 Classroom s_tudy. A planned lecture series will /q ' g be presented annually (i.e., each calendar year) covering those g subjects where training feedback indicates a need for additional training. The lecture series will be based on the following subjects as outlined in 10 CFR 55. A. Theory and principles. B. General and specific plant operating characteristics. C. Plant instruments and controls. D. Plant protection systems. E. Engineered safety systems. F. Procedures. G. Radiation control and safety. H. Technical specifications. I. Applicable portions of 10 CFR. i 13.2.1-6 Amend. 16 4/85

a DRAFT VEGP-FSAR-13 J. Quality assurance for operations. K. Major upcoming events. L. Heat transfer, fluid flow, and thermodynamics. 1. Fluids and matter. 2. Fluid statics. 3. Fluid dynamics. 4. Heat transfer by conduction, convection, and radiation. 5. Change of phase - boiling. 6. Burnout and flow instability. g 7. Reactor heat transfer limits. M. Mitigation of accidents involving a degraded core. 1 1. Incore instrumentation. 2. Excore instrumentation. 3. Vital instrumentation. 4. Primary chemistry. 5. Radiation monitoring. 6. Gas generation. 13.2.1.3.2.2 On-the-Job Training. A. Reactivity Controls Each licensed operator will, during the term of his license, perform a minimum of 10 reactivity control manipulations in a combination of reactor startups, reactor shutdowns, or other control manipulations which demonstrate his skill and/or familiarity with reactivity control systems. Each senior reactor operator shall direct or evaluate the activities of at least 10 control manipulations during his license These control manipulations will normally be term. performed on the VEGP simulator. 13.2.1-7 Amend. 16 4/85

VEGP-FSAR-13 The following control manipulations and plant evolutions are acceptable for meeting the reactivity control manipulations required by Appendix A, Paragraph 3.a., of 10 CFR 55. The starred items shall be performed on an annual basis (once each calendar year); M all other items shall be performed on a 2-year cycle (once each 2 calendar years).

• 1.

Plant or reactor startups to include a range that reactivity feedback from nuclear heat addition is noticeable and heatup rate is established. 2. Plant shutdown. +3. Manual control of steam generators and/or feedwater during startup and shutdown. 4. Boration and/or dilution during power operation. +5. Any significant (10 percent) power changes in manual rod control. 16

• 6.

Loss of coolant including: 4 a. Significant pressurized water reactor (PWR) steam generator leaks. b. Inside and outside primary containment. c. Large and small, including leak rate determination. d. Saturated reactor coolant response. 7. Loss of instrument air. 8. Loss of electrical power (and/or degraded power sources).

• 9.

Loss of core coolant flow / natural circulation. 10. Loss of condenser vacuum. 11. Loss of service water. 12. Loss of shutdown cooling. 13. Loss of componen' cooling system or cooling to an individual component. Amend. 10 9/84 13.2.1-8 Amend. 16 4/85

l' DRAFT VEGP-FSAR-13 14. Loss of normal feedwater or normal feedwater system failure.

• 15.

Loss of all feedwater (normal and emergency). 16. Loss of protective system channel. 17. Mispositioned control rod or rods (or rod drops). 18.

• Inability to drive control rods.

19. Conditions requiring use of emergency boration. 20. Fuel cladding failure or high activity in reactor coolant or offgas. 21. Turbine or generator trip. p 22. Malfunction of automatic control system (s) which affects reactivity. 1 23. Malfunction of reactor coolant pressure / volume control system. 24. Reactor trip. 25. Main steam line break (inside or outside containment). 26. Nuclear instrumentation failure (s). B. Knowledge of Systems Each licensed operator will demonstrate, in the performance of his duties, his satisfactory understanding of the operation of systems and apparatus and his knowledge of operating procedures in each area for which he is licensed. for 4 or Any licensed operator who has been inactive more months, before resuming licensed activities, will demonstrate adequate knowledge of current plant This shall be accomplished by a review of operations. applicable plant and procedure changes made during.the period the operator was inactive, followed by an evaluation by either a certified instructor on the VEGP simulator, the superintendent-operations, manager of unit operations, deputy general manager, or general evaluation manager.jg n unsatisfactory result on the A frict -f a fhis enla.1hion $be NLC. s$n]l be ncNkh/ (or at sha)l l, ave frevima/ ceneurrd Jf f],e l ccecarrsnct LV11m}ic 1 ro ra.m".1-9 Amend. 16 4/85 3.2

~ VEGP-FSAR-13 shall require the operator to have on-the-job training in areas determined as weak. To remain on active status, a reactor operator or senior reactor operator is required to have a minimum of 8 h/ quarter active carticioation in operation of theplant,[theVEGP_ simulat C. Plant Changes Each licensed operator will be kept informed of significant plant design changes, procedure changes, and license changes. Changes of a magnitude requiring detailed explanation will be reviewed by special instruction with 100 percent participation of licensed personnel. D. Procedures I Each licensed operator will review abnormal and emergency procedures at a minimum of once per calendar year. Failure to complete a procedure review will require that the licensee be removed from license lj duties until such review is conpleted, a 13.2.1.3.2.3 Evaluation. A. Observation The performance of licensed operators will be evaluated annually by operating supervision or by a certified instructor usually on the VEGP simulator. This shall include evaluation of actions taken or to be taken during actual or simulated abnormal or emergency conditions. Observation reports are required for personnel (supervisory and nonsupervisory)_who hold an IIRC license. with t exception of ([the-superintendent-operations, manager of unit operations, deputy general manager,_or general manager, and,fcertified simulator instructors. B. Annual Examinations Annual written examinations will be given to all ' licensed personnel to determine areas in which requalification training is needed. These examinations are normally evaluated within 30 days (2 months for unusual conditions with corporate office approval). A minimum grade of 80 percent correct on any section shall exempt an operator or senior operator from required attendance at requalification 13.2.1-10 Amend. 16 4/85

VEGP-FSAR-13 lectures pertinent to that section. Any section grade less than 80 percent but greater than 70 percent will require attendance at requalification lectures pertinent to that section within 12 months from the examination date. An overall grade of less than 80 percent correct on an annual written examination, a section grade of less than 70 percent, or an unsatisfactory performance evaluation will require an operator or senior operator to be relieved of licensed duties so that he may participate is an accelerated requalification program. This will be documented with written notification to the individual and to the appropriate department head. An operator or senior operator who has been relieved may return to his licensed duties following completion of accelerated requalification training in areas where he was weak, including a grade of not less than 80 percent correct on examinations given over such areas. The NRC may participate in the annual examination process. Annual examinations will be given at the conclusion of the requalification training program 16 so as to measure the overall effectiveness of the complete program and not to disrupt shift manning and training schedules. C. Lecture Examinations Writt n examin

• ions w~11 be iven o individuals who receis ditss t n 80 p rcent

,n'th perti nt section f the nndal exa inatio cove ng m erial resented i .the d(ogr m-lec ure sc ies. gra,e of 1 1 s than 80' erce R on ny r ire lecru serg es exadd nation KEE hal reqdire d lice ed o rator to b ' resche led g g g g ll a. iti al itstru ion d tes ing that - bject f in\\s e n xt 3 mont. Tl 3 mo ths.sy be wi 13.1.l.3.1.1.C i ute. eds yte le geh tim of a. ref eling o tage falli. w hin that eri L :ture-pres nted fo informa io of ajor upco..i ng e ents nd/o plant b,modifica 'on ma be ocum ted y att ndan. recorc. s( \\p 13.2.1.3.3 Instructor Qualification and Requalification Program The qualification and requalification program for instructors as described below includes requirements of NUREG-0737, item I.A.2.3. This program will be fully implemented prior to fuel load. 13.2.'l-11 Amend. 16 4/85

VE3 -FSA.:-13 A. Initial Qualification The training department will use a qualification checklist to establish the Initial qualification requirements for all new instructors and for instructors whose teaching responsibilities are going to significantly change. These special qualification checklists shall include the folli. wing requirerent.e 1. The ins t ruc to r ' s aupervisor will review t.h e employee's background and establish quallilcat:vn goals and qualification deadlines. Besides other qualift:ations. the fcilowing minimum goals will be established: a. For new instructors who do not have'a

lussroom teaching background, the empicyee will have to present a lecture to a arcup ct exr,erienced instructors before lecturing plant students.

The company's instructor : curse as a min. mum shall satisfy this requirement. ,f b.4 col :nstructors who teach licensed s_udents, 16 before the new instructor conducts a comprehensive program, the employee will meet 8 NRC requirer.ents by cbtaining the appropriate certification. This requirement does not prevent noncertiiled members of the training sta;f from teaching licensed per.sonnel in thr 'nstructor's area of expertise. 2. The superintendent-nuclear training shall apprcve the qualification checklist (st the time or ayA) 7 and shall approve the final qualification of each i instructor. I Before these instructors teach systens, integrated response, transients, and cimulator courses to licensed operators, they will demonstrate their competence by successful completion of a senior reactor operator oxamination.A} _ ~ i B. Certified Instructor Requalification Licensed or certified instructors will complete the requirements of the licensed operator requalificatien program annually by teaching, performing. or taking examinations for each required element of the requalification program. Conducting simulator training will be considered the same as supervising license duties in the plant control room. If an bri $sh h r Wko &EAmend. C/5enne((end&n 7 5/84 Nou CErii : gh./[ fd af, in f Amend. 16 4/95 $ces o ffe // ense nof re alar

• P s sh Micdar suh)ecir sa:A a r,L ier 4 6

^2""j.** sics ched&,de. may $ 'yesf fede"; j,, fj"*g"js { f i

r /d ATTAcHueur ia.2.l.3.2 3.c- ~ xg se IUrlNen exwr}ndiens wlll$e fiven Ioftndiisdcoueng mderal reseded in & prym,1 lek senes-A p y,de of less A,, 80 pwed on ay ledn seaes e n m d e abJl La venewed ancL ava7aaled. T&is evdadion witt Le Lach on & scoce received and mdecid wssed. ANec eudadim., k lae>, sed ope >&v will be seledJed av addihkJ adrack and edesliny w&,14ree inods. Flikes la creeH4e accepeeeraer on k refed d,JI e w<e kadide e a ,asi-accse, a - w,. a s-c, Yed 5'er, fody.

// / VEGP-FSAR-13 [nstructorisnot involved in the pEceding l requalification program, he may renew his certification by preparing for and taking or 16 conducting a comprehensive wrE ten audit examination. Instructors who fail to complete.these annual instructor requalification requirements will not teach ~ integrated plant response to licensed students until they renew their certification. An,,,3f Jor,,, ,.e,,e s j re Viewi'31 ll1e mbertk,l cca,fIzio, ,,, l};( bis C e d sY icc htc+1 b rtl1Cvl550C wr~gNey; det $1Llci q. rn r ualsb5 561 o} ntr, 6XisvlindiC#1. {c>tlrac! iM h cNrs ca ks cerbhef are J'*}ual'hC!rlicm i,a 7ll f ath c afale />t Yke. raas k Wa ex.l tat $ re a ;> ed by p t~o A/ U/(C-O O737, f/c,n 1,4 2. ) 644"/*

1. f

~ co)m2 ant. o f ca rc e.s f cp e ra h hshq i t'~ L", " "d 'L u b ('"'y are y ,j a d,,w sd,a he kn.-4An s. 1 T 0366V 13.2.1-13 Amend. 16 4/85

DRAFT VEGP-FSAR-13 TABLE 13.2.1-1 (SHEET 1 OF 3) LICENSED SENIOR OPERATOR ONSITE TRAINING SYLLABUS - PERSONNEL WITH COMMERCIAL PWR LICENSE OR NRC CERTIFICATION 10 (ANY SUPERVISOR OR STAFF POSITION) Minimum Description Type Integral Duration Nuclear power plant Classroom or 1 week theory self-study Fundamentals of reactor theory General core design Radiological safety and radiation hazards Heat transfer, fluid flow, and thermody-10 namics Fluids and matter l' Fluid statics 4 Fluid dynamics Heat transfer by conduction, convection and radiation Change of phase'- boiling Burnout and flow instability Reactor heat transfer limits n-VEGP systems Classroom or ((( weeks self-study Procedures for design and operating changes Reactor coolant system mechanical design Reactivity control mechanisms and indications Reactor safety systems Amend. 4 2/84 Amend, 10 9/84 Amend. 15 4/85

/.5 DRAFT VEGP-FSAR-13 TABLE 13.2.1-1 (SHEET 2 OF 3) Minimum Description Tm Integral Duration Emergency and reserve systems Containment and shielding Radiation monitoring ATWW Radioactive waste / g gy Au a y systems / 7~ VEGP license and Classroom or 1 weekT ? technical specifi-self-study l cations gl pggIE Lic=;.se conditions and limitations Design limitations i 4 If Fuel handling and Classroom or 3' days ( core alterations self-study \\ \\ Facilities and procedures x f Classroom Simulator '\\ 4 weeks (Controlroomopera-(including 80 h) tions General operating X X VEGP/simulato r )/ characteristics Specific operating X X f' l l characteristics e' l l Load changes X X i ' Operating limita-X X f tions l Standard, emergency, X X / ~'~ l and plant pro-( sedures X V CoritrclNKdipulation t Transients X Amend. 4 2/84 Amend. 16 4/85

I -t rrunwr a 1 H DRAFT Fuel handling and ' core alterations Facilities and ~ procedures Classroom Simulator Control room opera- ~ - - " ~~~~ 5 weeks l tions (including h s 4 16 3 General operating X X VEGP/ simulator) ~haracteristics 8 c Specific operating X X characteristics Load changes X .X Operating limita-X X tions ( Standard, emergency, X X i and plant pro-ceduras Control manipulation X Transients X VEGP license and )( g technical specifi-cations License conditions and limitations Design limitations ,e-,--,-,,-----,4, - +,-,, _ n

DRAFT VEGP-FSAR-13 TABLE 13.2.1-1 (SHEET 3 OF 3) Minimum Description Type Integral Duration Mitigating core Classroom or 1 day damage self-study Incore instrumen-tation Excore instrumen-4 tation Vital instrumen-tation Primary chemistry Radiation monitor-ing Gas generation () ? ,L 3- ,/ Observation training including walkthrough 'j Prior to VEGP VEGP 3 weeks l' achieving 20% power * ,I After VEGP VEGP 3 months 10 achieves I 20% power \\ Review and audit I week \\ Yiniahl Obsc.rgkion 3 m'"f4' metaknlenF umeve? 237, watufes (AHer p,oce) Tn-Pla. cl e ersience 4-> G week tecludiny ula-ecyk (Peso-4o kse adfeg$ zoy, fodeV)- a.'4 Applican,.a w ho h a ce p. ci w u o l, b e c.Nt e a r P, egatetery- [ Corr.iccion 4 licen2ed er ceetrfi'ed will comptete 3 weeks-ofM EGP // valkthrcugh training. 6. Applicaits who havUr'eviNh held an E~PIO liI: w I ' be required to complete the 3 months of observation training. / 10 NThey will complete 3 weeks VECP walkthrough training instead.) l "~ \\ C*Ik liclesc. Qof w!S Will also but Six(4) tottks b Amend.4 2/84 N Amend. 10 9

1. Y[M/C#Me'a+r'expericect as og//,

,, g . g /4,

r DRAFT vEcP-rSAR-TABLE 13.2.1-2 (SHEET 1 OF 3) - PERSONNEL LICENSED SENIOR OPERATOR ONSITE TRAINING SYLLABUS WITH OTHER THAN PWR LICENSE CR NBC CERTIFICATION (ANY SUPERV!SOR OR STAFF POSITION) s ' Minimum In_egral_ Duration t Desgription Typ_e 10 Nuclear power plant Classroom or 1 week theory self-study Fundamentals of reactor theory General core design Radiological safety and radiation hazards Heat transfer, fluid flow, and thermody-y namics Fluids and matter 16 Fluid statics Fluid dynamics 4 Heat transfer by conduction, convection, and radiation Change of phase - boiling Burnout and tiow instability Peactor heat transfer 11mitu 5[ eeks 10 VEGF systems Classtoom or Procedures for self-study desig.. and operating changes Peacto r coolant system machanical design Reacttcity controt mechanisms and indications Amend. 4 2/84 Amend. 7 S/84 Amend. 10 9/84 Amend. 16 4/85

'7 v -n- [.,_ ef Nfkf 1 VEGP-ESAP-13 TABLE 13.2.1-2 (SHEET 2 OF 3) ) Minimum Description Tvoe Integral _ Duration Reactor safety systems Emergency and reser/e systems Containment and shielding QWrfh1-Padiation monitoring "IpsEfT Auy.iliar tem -' / system Y N[ gt P.ad i acti'le waste VEGP license and Classroom or 1 week } technical specifi-self-study l lcations i E License conditions and limitations Design limitations 4 16 19 Euel handling and Classroom or 3 days core alterations self-study Facilities and s procedures 'Ns ss i Classroem Simulator ~ ~ ~ ~ ~ ~ ~ ~ } Control room opera-5 weeks tions (including 100 h' General operating X X VEGP/ simulator), characteristics Specific operating X X characteristics Load changes X X Operating limita-X X tions Standard, emergency, X X and plant pro-ceduras Control manipulation X Transients X Amend. 4 2/84 Amend. 10 9/84 Amend. 16 4/85 Amend. 19 9/85

/c DRAFT

• m unear is.1. n Fuel handling and

' core alterations Facilities and procedures Classrcom Simulator Control room opera-5 weeks l go tions (includinga h I General operating X X VEGP/sinulator) 4 16 ' characteristics Specific operating X X characteristics Load changes X X Operating limita-X X tions ( Standard, emergency, X X t and plant pro-ceduras Control manipulation X Transients X VEGP license and )( y, technical specifi-cations License conditions and limitations Design limitations

l9 h VEGF-FsAR-13 TABLE 13.2.1-2 (SHEET 3 OF 3) i Minimum Description Type Integral Duration Mitigating core Classroom or 1 day damage self-study i Incore instrumen-10 tation Excore instrumen-tation Vital instrumen-tation Primary chemistry Radiation monitor-ing / Gas generation G./ e A Observation training' VEGP 3 months g including walkthrough

• raining

~ Review and audit I week \\ 16 19 \\ Obsttvedier) %ning ~ " *,

• Ineludo'n welk0rcuk (A#er t/5C,/ a.di$es fo%

power) In p/zd ergedenc.c ca> 6 wee h Inclu bny a jy s, k 06r 6 VEGF ad;eg,7 LD 7a fewer) a.g P riss.Tisdf' a3 hic-. ;n; 20 per m pvo-.r, 'ppi th l4 c?!d licensas shell lia.e C iie e k u uf hot pttrticips"icr ey m nce-as J: Lined cy Cer.aric Letter 00 15 at a ='-e t y,n a pi nt In ac least 6 w,.- h a._ n f UMP

• i Et e-bit On, applicantc will itave 10 e pcricncc which i r.c lude c valkthrough--bra i ni ne Amend.

4 2/84 'Cdd. Ikuse a,yILfs will have six 09 weeg,l y ^g_ to 934 7adw/'arwn ev, eneae as oJhe]in Genm. Ler.ixe sy-a. gay,, c _, ~. ? '7," _[ ^ L - _ _ ' ' - 'h ^* , _l % 21 _ _, 3

lo DRAFT VEGP-FSAR-13 TABLE 13.2.1-3 (SHEET 1 OF 3) LICENSFD SENIOR OPERATOR ONSITE TRAINING SYLLABUS - PERSONNEL WITH 1 YEAR OF MILITARY PWR EXPERIENCE AS A REACTOR OPERATOR, ENGINEERING WATCH SUPERVISOR, OR ENGINEERING WATCH OFFICER (ANY SUPERVISOR OR STAFF POSITION) Minimum Description Type Integral Duration Nuclear power plant Classroom or 1 dI eeks l7 8 theory self-study Fundamentals of reactor theory General core design Radiological safety and radiation y hazards Heat transfer, fluid 10 flow, and thermody-namics 4 l~ Fluids and matter Fluid statics Fluid dynamics Heat transfer by conduction, convention, and radiation Change of phase - boiling Burnout and flow instability Reactor heat transfer limits VEGP systems Classroom or 6 weeks l7 self-study l Procedures for design and operating changes Reactor coolant systen mechanical design Reactivity control mechanisms and indications Amend. 4 2/84 Amend. 7 S/84 Amend. 10 9/84 Amend. 16 4/85 t

1/ DRAFT VEGP-FSAR-13 TABLE 13.2.1-3 (SHEET 2 OF 3) Minimum Description Type Integral Duration Reactor safety systems Emergency and reserve systems TAcWREPT '~ Ig,1' -) Containment and shielding AT Radiation monitoring y MSEbI /,' system g [ggg-gg Auxiliary systems Rad 3oactive was jte VEGP license and Classroom or 1 week technical specifi-self-study cations { License conditions i and limitations 4 Design limitations !{Fuelhandlingand Classroom or 3 days icore alterations self-study I Facilities and procedures Classroom Simulator 5 weeks Control room opera- 'tions (including 100 h General operating X X VEGP/ simulator) characteristics Specific operating X X characteristics Load changes X X Operating limita-X X tions Standard, emergency, X X and plant pro-cedures Control manipulation X ' Transient X Mitigating core Classroom or 1 day damage self-study 4v Amend. 4 2/84 Amend, 10 9/84 Amend. 16 4/85

a ATTACHVEAT Tt3 LI-3 DRAFT Fuel handling and ' core alterations Facilities and I procedures b 4 l00 ~ Classroom Simulator ($Iwe eks l Control room opera-( L.ic luding h tions 1 General operating X X VEGP/ simul'ator) 4 16 ' characteristics Specific operating X X characteristics Load changes X .X Operating limita-X X tions ( Standard, emergency, X X i and plant pro-ceduras Control manipulation X Transients X VEGP license and )( g technical specifi-cations License conditions and limitations Design limitations l l l l

O DRAFT VEGP-ESAR-13 TABLE 13.2.1-3 (SHEET 3 0F 3) Minimum Description Type Integral Duration Incore instrumen-tation Excore instrumen-tation Vital instrumen-4 tation Primary chemistry Radiation monitor-ing U Gas generation ~ A Observation training'** VEGP 3 months including walkthrough 10 training 1 week i Review and audit lf Observafbn %niny 3 "'0'ik includiny waklbm,t (Mk vece aNe a 2n% v power) L, Id e ence w 6 week.r cf incl h u]& Wioe o l/EriP achieving M7ofoWeh ,7aQ rrier

• n VEGP_ achicting 20-percent power, applican' for cold 4 1_i c o m a e chl-1--hava-6-week s o f -ho t-participation--eyperiencus definM by Generic Lmt.ter S' 15-aL a sen+ myge p i arrt.

In addi* h applicoute vill ha;c at ica d h of VEOF lu f t 10 experi,5us wiiich inc1dee un1kthrmagh--tralning-CeR Ikerse, applads will have sixg) weeks d bd y'kjt,fn,c" 4,,g4 '.'f,',I'nCL M *Ethtl "lM* le L& gy-lb.~ ,hmend. 10 9/84 f f,,. Amend. 16 4/85 <m ~.e as weeu u, ,[ // 6.. c --,,n~,,y.

av DRAFT VEGP-FSAR-13 TABLE 13.2.1-4 (SHEET 1 OF 3) LICENSED SENIOR OPERATOR ONSITE TRAINING SYLLABUS - PERSONNEL WITH DEGREE IN ENGINEERING OR APPLICABLE SCIENCES (ANY SUPERVISOR OR STAFF POSITION) Minimum Description Type Integral Duration l7 Nuclear power plant Classroom or 5 weeks theory self-study Fundamentals of reactor theory General core design Radiological safety and radiation hazards t Heat transfer, fluid 10 flow, and thernody-namics Fluids and matter 4 1 Fluid statics Fluid dynamics Heat transfer by conduction, convection, and radiation I Change of phase - boiling Burnout and flow instability l Reactor heat I transfer limits 7 l f) eks VEGP systems Classroom or l7 self-study Procedures for design and operating changes Reactor coolant I system mechanical design Reactivity control mechanisms and indications Amend. 4 2/84 Amend. 7 5/84 Amend. 10 9/84 Amend. 16 4/85

26 VEGP-FSAR-13 TABLE 13.2.1-4 (SHEET 2 OF 3) Minimum Description Type Integral Duration Reactor safety systems Emergency and reserve . g. 2.[-Y systems . ggf A Containment and M56gg 'i$ gy7 shielding Radiation monitoring 4 Radioactive wastej -- _ _ _ _ _. _ _ _.. _ [7[$bb7d system Auxiliary systems / A VEGP license and Classroom or 1 9eek i technical specifi-self-study l cations i License conditions and limitations l Design limitations Fuel handling and Classroom or 3 days core alterations self-study Facilities and procedures Classroom Simulator 5 weeks Control room opera-f tions (including 100 h General operating X X VEGP/ simulator) / characteristics Specific operating X X characteristies ,e Load changes X X Operating limita-X X tions Standard, emergency, X X and plant pro-cedures Control manipulation X X Transients Mitigating core Classroom or i day damage self-study Incore instrumen-tation Amend. 4 2/84 Amend. 10 9/84 Amend. 16 4/85

"24 ATTAcefAtE#T T 13 LI-T g g "[ Euel handling and v ' core alterations Facilities and procedures ~ Classroom Simulator 6 god l (includingx[ weeks Control room opera- / 'h tions 4 16 3 General operating X X VEGP/ simulator) ' characteristics Specific operating X X characteristics Lor.d changes X X Cperating limita-X X tions ( Standard, emergency, X X 1 and plant pro-ceduras Control manipulation X Transients X VEGP license and g g technical specifi-cations License conditions and limitations Design limitations 1 i l i l l l 1 -,m, y .-.-4

17 i i DRAFT VEGP-FSAR-13 TABLE 13.2.1-4 (SHEET 3 OF 3) Minimum Description T_yp e Integral Duration Excore instrumen-tation Vital instrumen-tation 4 Primary chemistry Radiation monitor-ing Gas generation / Observation training VEGP 3 months I including walkthrough 10 training 9 Review and audit 1 week 16 ObseYv$hn VM nin* 3 menHs J uneldy wa./k % yb (hNer VEG P acfjege, 2.07, p,wer) L,- /td ex enence <o b wee,c,: InelaYin wal i l, n &loy 0 VEG f.tclueyin 2.Df, puer) l4 m.__ ___ '"_,__,- u ____ ^ ' ' ;~-* m n o,. 4 m, _ a h - ^^ ~'av 3 _c w,, - - _ ; _ 1 _., 4 _ -___4,- tm+--- ce 'c --- *.. - - 1 m e.- 2 ,_7 7, 2AA4*4 mm icaou _.m..._ 10 w -- src axtuum n a Amend. 4 2/84 Amend. 10 9/84 Amend. 16 4/85

n DRAFT A m cuueer A - puduqak upenexe a o&d a, Go,em eHt. % ^ ' u ..t uci-p 1 -L .. i - 1 il L se v'^ LW "~ L .[ ,7f... ~ ws. 1 i t it.- 1 ii " " ^ ";^ M a,***1 V h jcpy - y ri u u g w-- mF. - i vir T n .T., v i. i: f I b i I ii l i' l-a i i-l' !l

2+t h ff VEOP-FSAR-13 TABLE 13.2.1-5 (SHEET 1 OF 3) LICENSED SENIOR OPERATOR ONSITE TRAINING SY%ABUS-PERSONNEL WITH HIGH SCHOOL DIPLOMA OR EQUIVALENT (ANY SUPERVISOR OR STAFF POSITION) rescriction IZ22 I.n;egral Duration Nuctear power plant Classroom or 32 weeks I theory self-study l10 Ma.hematics Fundamentals of reactor theory Ceneral core design Peactor and health physics and radio-logical safety Materials Heat transfer, fluid. flow, and thermodynamics Fluids and matter 4 Fluid statics Fluid dynamics 16 19 Heat transfer c3 ccnducticn, conrention, and radiation Change of phase - bolling Burnout and flew l instabi ity l Reactor heat transfer limita 7 / l10 VEGE systems Classrcem cr 6 weeks I self-study u l Procedures for i design and operating char.;es Reactor ccolant system mechanical design Reacti nty control mechanisms and indications Amend. 4 2/84 Amend. 10 9/84 Amend. 16 4/85 Amend. 19 9/85

x VEGP-FSAR-13 TABLE 13.2.1-5 (SHEET 2 OF 3) Minimun Descriction Type Integral Duration Reactor, safety g 'T13 ", J-d systems Emergency and reserve i systems gf c bufEST Containment and shielding e Radiation monitoring system .g f Auxiliary systenis Radioactive w p r~ A 3 VEGP license and Classroom or 1 week technical specifi-self-study y cations License conditions and limitations Design limitations h \\' 19 Fuel handling and Classroom or 3 days 4 16 core alterations self-study Facilities and procedures Classroom Simulator Control room opera-5 weeks tions (including 100 h General operating X X VEGP/ simulator) characteristics ' Specific operating X X characteristies Load changes X X Operating limita-X X ,/ \\ tions j Standard, emergency, X X and piant pro-cedures Control manipulation X Transients X __ Mitigating core Classroom or 1 day damage self-study ,Incore instrumen-tation Amend. 4 2/84 Amend. 16 4/85 Amend. 19 9/85

hTTf.Ch'MEr:T T 131.1-T DRAFT Euel handling and ' core alterations Facilities and procedures ~ Classroom Simulator Control room opera-5 weeks g l ~" ~ ~ ' ~ tions (including h 4 16 I General operating X X VEGP/ simulator) ~haracteristics c Specific operating X X characteristics Load changes X X Operating limita-X X tions ( Standard, emergency, X X 1 and plant pro-ceduras Control manipulation X Transients X VECP license and g z technical specifi-cations License conditions and limitations Design limitations

s2 DRMT VEGP-ESAR-13 TABLE 13.2.1-5 (SHEET 3 OF 3) Minimun Description ~ge Integral Duration Excore instrumen-tation vital instrumen-10 tation Primary chemistry Radiation monitor-ing Gas generation' [ Observation training'S' VEGP 3 months i including walkthrough training I Review and audit I week l0 19 Weseruhion ra ninq 3 't w0017nS 1 v Wle<y walkdbccyk held v%f act,ieser 2c7, puer) h plad escrience wid o> G weetr y walkMrad J ( frior Yo VEGP acNeviny 20% fower) l4 P: ar to '!EGP 26 a' ring-20 pe rc'ehmuc r, a pph a u t 3 for g heli ha'ta4 wee ks - o f - ho t -par tic-s pe+.4en-exp2r i e nce cald-11-- ac 2r dcfin-:d-by Cener4c-Lete 1 es-i6 at-sai,; i. f p 2 plant. Lv ed<ii t i o n. epplicants will-he-ie h st C wemf---VEGP--shi f t to -exp^r;:nuc uhi-b i nc i'_'d e ~ wa-ttthrough t ra ining, .DJ5EttT ATTAcph6@ A. Amend. 4 2/84 Amend. 10 9/84 Amend. 16 4/85 Amend. 19 9/85

53 DRAFT A m cunear A _ & luiem ag f, a;llj,,e sa (_cj w,,j, d' fd g a oe%ed in Generie 8Y-it. % ak) dan a$11 L e. eneme --j, . u ..t uen p sa 1

w...

i...ti 1 i c, i 1.. I % sv u u - - a i < n rii n,,. m 1 mn 't .i l' t' I:: i'. I l 11

34 VEGP-FSAR-13 TABLE 13.2.1-6 (SHEET 1 OF 3) LICENSED OPERATOR ONSITE TRAINING SYLLABUS (PLANT OPERATOR OR ASSISTANT PLANT OPERATOR) Minimum Description Tvp_e Integral Duration Nuclear power plant Classroom or 12 weeks theory self-study Mathematics Fundamentals of reactor theory General core design Reactor and health physics and radio-logical safety t Materials Heat transfer, fluid flow, and thermodynamics Fluids and matter Fluid statics Fluid dynamics liea t transfer by conduction, convention, and radiation Change of phase - boiling Burnout and flow instability Reactor heat transfer limits VECP systems for Classroom or 12 weeks electrical and self-study reactor control Reactor coolant system mechani-cal design Reactivity control mechanisms and indicators Reactor safety systems I 1 Amend. 19 9/85

M DRAFT VEGP-FSAR-13 TABLE 13.2.1-6 (SHEET 2 OF 3) Minimum Description Tyoe Integral Duration Emergency and reserve systems Containment shielding Radiation monitoring systems Auxiliary systems Classrcom Simulator 6 weeks Control room (including 100 h operations General operating X X VEGP/ simulator) characteristics Load changes X X Operating limita-X X tions Standard, emergency, X X and. plant pro-cedures X Control manipu-lation X Transients Mitigating core Classroom or 1 day damage self-study Incore instrumen-tation Excore instrumen-tation Vital instrumen-tation Primary chemistry Radiation moni-toring Gas generation t ) Amend. 19 9/85

VEGP-FSAR-13 TABLE 13. 2.1-6 ( SHEET 3 0F .1 ) Minimum w Description T_yp~e Integral Duration A Observation training'** VEGP 3 months including walkthrough k training ~ \\\\ Review and audit I week \\ \\ \\N\\ 0b75ertidien ht2 nIn 3 n'en 15 n,e la L hy w a.it< b oa k (ANer VEGP acinker 2c7, pw-) h tLT)h EXOLlhct b,pgb t l uneludin. usa.!k%y h NfrIbr VE.GfxcQev,Jn o zo% pac) .g A m t Lc 'fEcD m e h i ~f i,,g 20 parroe 4,er, 2 pp l i c:-, t c for cmiA 1ican e ti1Igletewbeervation--training-etm ompa-rable 4-semised com== rc i a l -nuettra r pe=r-plant--for--+--pe a ud o f G 4 In.-add 16e nts--w-i44--ha ve-e t--de a e t -&-w e e ks af-VEOP ebi f N ( experience whl.ch-inc-ludes-walkt>nrough-tra-mu.g. K resea.r Amunwr A 0366V Amend. 19 9/85

= = - _ _- - =- _ - - - - - - _. _- _ ~ - 31 DRAFT ATTACHMEM A Y I'knse /ki$s uill baue SIX (C) cuech of boI y pd.s e eneme a o & ed in G w ie eHc.% 46 d wae.=,i? up: h Miwk'- 'u-lhyb l,unij. i i ! i l e 9 6 i i l l t l. -l

DRAFT n MANAGER GENERAL MANAGER NUCLEAR TRAINING I _ _ _ _ _ _ _ _ _ _ _ _.i SUPERINTENDENT NUCLEAR TRAIN 4NG sao OR AFTSM AN CLERK I I SUPERVISOR SIMULATOR OPERATIONS MOOlF'CAflON TRAINING SUPERVISOR sao SIMULATOR PLANT INSTRUMENT SIMULATOR INSTRUCTOR ENGINEER TECHNICIAN ENGINEER sea sno l l SUPERVISOR SUPERVISOR PLANT HP' CHEMIST RY TRAINING T R AINING I I I I METHOOS AND SENIOR METHOOS METHOOS AND SENIOR METHOOS TRAINING AND TRAINING TR AINING AND TRAINING $PECIALIST* SPECIALIST SPECI ALIST

• SPECIALIST LEGsNO.

S*(O Sensor reactor operator lecensed or certified.

• Methods and traening specialists will have eapenance en electrical or mechnical maentenance. enstrumentation and controis techno6ogy or health physecs and chemistry-i Arend. 16 4/85 VEGP TRAINING OFGANIZATION V0GTLE ELECTRIC GENERATING PL ANT

@ONia NhtT w UNIT 1 AND UNIT 2 l FIGUPE 13.2.1-1 3605-0

i SOL ge/ JAN 81 JUL 84 JAN 85 APR -3 tit 86 SRO = senior reactor c gcTO TO TO TO yygTO o7 op,,,,o, JUN 84 DEC 84 4tML86 &H. 86 49P 86 RO reactor operator = m o r-r-m m ng g NLO = nonlicensed g 5' Initial Classroom m Training SRO 18 m RO 18 g !g ? operator o (Fundamentals, Systems) m NLO 18 g

• g 8

c. e, . Estimated number of m x RO*9 ${ { students expected to Simulator SRO 18 3 RO 9 complete future training. E H C CH O Hot Participation SRO 10 2 SRO*4 2. 2.3 2 " Sufficient operators (Extra Man on Shif t) RO 12 E RO'6 ~5 g will be available for ~ Unit 2 Operation at = = RO4 E RO'14 9 99 4 Unit 1 fuelload. Review and Audit SRO 18 NLO 18 g ga c 1 SRO* 9 1" SRO*9 A ~ NRC License Exam RO'9 RO'9 Technical Specification Minimum Statfing g

1. Unit Operation 2-Unit Operation a

s (M Statfing for 6 Shifts) NO.D Staffing for 6 Shif ts) Available Personnel Senior reactor operator O (including shitt technical 18 18 18 advisors) Reactor operators 12 18 18 Nonlicensad operators 12 18 18 Amend. 16 4/85 VEGP UNITS 1 AND 7 VoGTLE ELECTRIC GE NERATING PLANT OPERATIONAL TRAINING (,JCOIMldbthVCf UNIT 1 ANo UNIT 2 FIGUPE 13.2.1-2 Y 360S O

MONTHS TO FUEL LOAD 51 48 45 42 39 36 33 30 27 24 21 18 15 12 9 6 3 Prooperational License Fuel Load Tests Exams and Unit 2' Criticality 1 a 1 m = Licensed Operators (12S) (6M) to Support Preoperational Tests Nonlicensed Operators (S* *) (6M) j to Support Preoperational Tests 1 l Licensed Supervisors (7S) (6M) j to Support Fuel Load i, j Licensed Operators (12S) (6M) to Support Fuel Load i l Legend f M = Minimum staffing plans q l S = Students who start training 2 i i For the operation of Unit 2, GPC expects to license a minimum of 18 Tg j additional individuals. Licensed individuals will have a dual license mum i for both Units 1 and 2. f

• Depends upon turnover.

ADDITIONAL VEGP UNIT 2 voGTLE ELECTRIC GENERATING PLANT OPERATIONS TRAINING l Geoigialinver-u T i A=o u. T a FIGURE 13.2.1-3 I d i m, i

wr " ~ DRAFT' 1@M VEGP-ESAR-13 13.2.2 TRAINING FOR NONLICENSED PLANT STAFF The VEGP staff will consist of individuals with significant differences in previous education, training, and experience. / The training programs have been formulated to provide the gs/ required training based upon _the individual's prior experience.,/ A Personnel will either meet the minimum education and, experience F recommendation of ANSI /ANS 18.1-1971 or complete a ) qualification program which will demonstrate their ability to I perform the specific taska ( The organization conductTng the y training for the nonlicensed plant staff is the same as that for the licensed plant staff and is shown in figure 13.2.1-1. 74SEE{,p.HNrNT

13. 2 g

~~ 13.2.2.1 Training Program A training program has been established for each VECP organizational group.AfAt the time of fuel 1oaa, personnel t (assigned to a partic riar group will complete the initial training before performing independent tasks or will meet the minimum education and experience required by ANSI /ANS 18.1-1971. The training programs will be the same before and after 16 ! initial fuel load. Significant amounts of nonlicensed personnel training were accomplished prior to the start of preoperational (tests f Individual specific training requirements may be waived on a case-by-case basis with adequate justification and approval of the superintendent of nuclear training. Specific criteria must be met prior to approval of a waiver. listed Waivers will be granted only if one of the conditions below has been satisfied. A previous course of instruction has been completed which e contained the same topics and was at least the duration of the course being waived. The course may have been completed at VEGP or another facility. For example, a trainee who completes a course of instruction at Plant Hatch meeting the above criteria would not be required to repeat the course at VEGP. A previous course of instruction has been completed which e contained all of the objectives of the course being waived. This would be determined by comparison of the objectives of the course completed and the course being waived. If the already completed course of instruction did not meet all required objectives, these additional topics may be taught and course completion may be granted. 13.2.2-1 Amend.16 4/85

Q"07 s3.1.z.u. VEGP-FSAR-13 Completion of an examination by the trainee which is final comprehensive examination. e equivalent to a course be The examination may be written or oral and must retained as a record of successful course completion. Training programs for the following organizational groups have been established: ealth physicshc.di: 9 13.2.2.1.1 13.2.2.1.. 3 I strumentation and controls 13.2.2.1. Y Mechanical maintenance 13.2.2.1,.5 5 Electrical maintenance 13.2.2.1.% 6 Shift technical advisor 13.2.2.1.% 7 Nonlicensed operator 13.2.1 Licensed operator 13.2.2.1.% 8 Training (instructor qualification) 13.2.2.1.h 9 General employee training 13.2.2.1.9 10 Fire team training 13.2.2.1.M.11 Quality control 13.2.2.1.14 12. Engineering and technical support including the duration The syllabus for each training program, is described 'f and the organizational group receiving the training, in the following subsection or paragraphs. / Tdein2 Yny.tre q HealthPhysics[adiochemistryTrainingProgramN 13.2.2.1.1 A. Initial training de#<An ic.4n Technicians vill meet the minimum education and experience requirements of ANSI 18.1-1971 prior to being considered qualified to y i Prior to meeting all ANS1 18.1-1971 perform all tasks independently. requirements, technicians may be trained to perform specific tasks and Technicians vill be qualified to perform those tasks independently. required to complete general employee training per the requirements of section 13.2.2.1.%. T The numbers of technicians indicated in Table 13.2.2-1 vill have 5 completed the training indicated in the Table in order to support I preoperational testing. Following fuel load and initial criticality, replacement technicians vill normally complete initial training Initial requirements within one year of assignment to the position. training shall consist of pressurized water and balance of plant systems, nuclear physics fundamentals, radiation protection, The initial program mitigating core damage and on-the-job t. <ining. ~ vill have a minimum duration of 6 weeks. On-the-job training prior to fuel load and initial criticality, shall be comprised of participation in preoperational program activities, procedure review and preparation. After fuel load and initial criticality, on-the-job training shall be comprised of activities which build upon the initial classroom training. ./85 ..w m,%.7 3-n.>.s.>

DRAFT dTTAcgHenrr /3 2.2. fersonne) will meeb Ibe mihdnurn e$tica ton and epjenee iremest/s of AusI 18. /-l.97/ rier /c bejn consbred r gu.a/iY]ed }ojerform aE ktsks indpenles frior /o meebthy aff AAtst 17l-197/ ascents, psonnel be. } rained fo iAc bc <nd gdel o peArm L kerform s m2,oecyededfr. sks i 4 I

u ATTACHNEdr /3.1.2./ The n Lecs af ersonnel i;&cded in TeWe ts.z.z-t ded fle h uk h adxWed a fAe fd/e ik wiUbase. dder k scomlderda fesh. fo'Howy Ad lodet??Wlcbce au L, <,06e?ch,oas.,nJ o a e, .-4,, assynmed A,The,_ pny-l as n,4ce. ud der Ad /p one yee o Le d wi/I Le he wrie excy ded in aakk/ pcy<ai,, descephos. e L

vw DRAFT VEGP-FSAR-13 ,A Approximate Duration Curriculum Outline 6-10 h'** General employee badge and health physics training 4h Industrial safety 2h New employee fire training 1 week General pressurized water reactor systems 1 week Ger.eral balance of plant systems 2 weeks Nuclear physics fundamentals 1 week Radiation protection 1 week Chemistry fundamentals Mitigating core damage (commensurate 2h 4 with responsibilities) 1 week on-the-job training w qgGruMaA B. Continuing 3 Training One of the following listed programs or other specific programs as requested by the health physics Tedggw Eer s o. n c l-superintendent will be conducted annually. 1, who have not completed the offered course will normally attend. Approximate Duration Curriculum Outline Advanced health physics ,_1 week l week ~~~ / Analytical chemistry 1 week Radiochemistry d6 LC.grrosion I week. Gantme Spec {rescopy Annual Requalificaffon Training or Exemption Testing C. W Healthphysics[ chemistry >technicianswillcomplete annual requalification training or exemption testing to make them aware of and review important changes radiation j made to plant emergency and disaster, protection, security, and respirator procedures. Initial Foreman Qualifications ({and Student Engineers []) D. Foremen who meet the requirements of ANSI /ANS 18.1-197 will complete General Employee Training and on-the-job training as ~ ether the individual attends additionaT) a. Dr yn de epd inq as described in paragraph g-d a io w w s n,, J.onu a.m n ,s*f4Qy'y"\\ k *"f 'W'O

• $w ur
• w4 eMX&[tgwe.55. $6

~ ebaAs.

C.edndors wdh e.du.cdiom a.nl tricace. %+ met.fs cr e>cettds FSAR. cxwmkme,ts m $ill e [ si revike{ kbh & Ne$ ?b ies n tiNtn inh cerU$ies % [ }}se, y, h [} aa} $ g } ac,j)* n a.nN p S e+: ce exeeds +Le repu<enea &c hya,%. c Er ence VEGP-ESAR-13 / j hescribedaboveunderinitial training prior to performing independent duties. Those who do not meet the above requirements must complete initial training and progress through most of the continuing training in order to demonstrate their ability to perform courses the specific task E. Continuing Foremen Training One of the listed continuing training programs or other specific programs as requested by the health physics superintendent will be presented annually. Foremenwilll7 I normally attend these continuing training sessions l 1 unless they have already completed the offered ccurse. f and F. Health Physics @ hemistry) Supervisor Qualifications Training The health physics @ emistr@ supervisors will haverequired of hea t qualifications foremen and will normally attend a similar continuing training program. G. .c =a ::-- ~ 7 ' n 'y / A - exceed b clear 7 [ ' Personnel with experience tnat Regulatory Commission (NRC) commitments may fill a I position in the career path provided that the health physics / chemistry superintendent certifies that the -employee's experience qualifications exceed the f , position requirements. The training department may / also accept prior training or experience to fill / . specific course requirements.e-J ~ 13.f.1.I.2 @ EET. ATTACH AENT /3.M I S. L. 2.1.3 (hse.ti A~rT4cMCH'T U. L..L.I.h A. Initial Trainina Technicians who meet the education and experienc requirements of ANSI /ANS 18.1-1971 will complete generall employee training and on-the-job training as described tasks. Those below prior to being assigned independent kwhodonotmeettheaboverequirementsmust complete \\initialtraininginordertodemonstratetheirability Qo perform the specific tasks. w Amend. 7 5/84 13.2.2-4 Amend. 16 4/85

F. ATTkHMNT 13. 2. 2.. /.1 ? WS I n DRAFT i l I I' p ,1.. -. y.. 3 ~ 13.2.2.1.2 Chemistry training program i A. Initial training ~~ 3 Tech n' TechniciansviiIrunmeet the minimum education and experience .t ' ' 1 ~. requirements of ANSI 18.1-1971 prior to being considered qualified to perform all tasks independently. Prior to meeting all ANSI 18.1-1971 requirements, technicians may be trained to perform specific tasks and qualified to perform those tasks independently. Technicians will be required to complete general employee training per the requirements of section 13.2.2.1.4. 'I The numbers of technicians indicated in Table 13.2.2-1 will have completed the training indicated in the Table in order to support - preoperational testing. Following fuel load and initial criticality. replacement technicians will normally complete initial training e L, requirements within one year of assignment to the position. Initial training shall consist of pressurized water and balance of plant systems, nuclear physics fundamentals, chemistry fundamentals, mitigating core damage and on-the-job training. The initial program will have a minimum duration of 6 weeks. On-the-job training prior to fuel load and initial criticality, shall De. comprise,d of g rtJ dproceduredeview-and gagn ia preoperational program activities. l / preparationL After fuel load and initial criticality, on-the-job training shall be comprised of activities which build upon the initial classroom training. i j One of the following listed programs or.other specific programs as requested by the h::lth--physics ( Chem *,strg I superintendent will be conducted annually. Personner whc have not completed the offered course will normally attend. l 1 Approximate Curriculum outline Duration ~-~ ~ _.And &ca/ C4ees4.y _...- y /A Ahode,.>de. M.. 0.o.52.h JAI f ~~ ...:.:. s ? , n..-._. n __,, _ - - -.- -, _,, < - - -,.,,.,. -.,.. _, - ~, -, - - - - - - - - - - - - -, -. - - - - -... - -.. - - -. -

j h t I AcHREllT /3.2.2.1.2. d DRAFT C. Annual Requalification Training or Exemption Testing k emistrg technicians will complete j -:2&lth annual requalification training or exemption testing to make them aware of and review important changes y made to plant emergency and disaster, radiation protection, security, and respirator procedures. D. Initial Foreman Qualifications I Foremen vill meec the requirements of ANSI 18.1-1971. General employee training vill be completed per the requirements of section 13.2.2.1.#? Foremen vill complete training in mitigating core damage. Any other training maybe requested by the c5emistry department; S p ;wte utos8 i E. Continuing Foremen Training i. One of the listed continuing training programs or other specific programs as requested by the -heelth-physics <. eke.misTr4 i superintendent will be presented annually. Foremen will 8 normally attend these continuing training sessions-3 unless they have already completed the offered course. V F. @ alth-Physi Jeshemistry Supervisor Qualifications and Training i W The fheal-th-physics) chemistry supervisors ill have the qualifications required of Gmea+"Mhv8M r-hemistry foremen and will normally attend a similar continuing training program. G. Contractors Contractors with education and experience that meets or exceeds l FSAR commitments may fill a position provided that the p-M. n,.i Q. de_mih p Superintendent certifies that the individual's education and experience meets or enceeds the requirements for the position. ~ I l ~ -- .i a .n.. l . y d '. "y',*.p,.1 s... ^ O*<h]'.f h -. .,. * - ] l

e ecmr sw3 $~l 9g_gpy Tnald9 13.2.2.1.3fnstrumentation and Controls regram A. Initial training p i techn: Technicians wi1T'Aaseet the miniana education and experience L. requirements of ANSI 18.1-1971 prior to being considered qualified to perform all tasks independently. Prior to meeting all ANSI 18.1-1971 requirements, technicians may be trained to perform specific tasks and qual'.fied to perform those tasks independently. Technicians will be required to complete general employee training per tihe requirements of ' ' - ~ ~ section 13.2.2.1.. I The numbers of technicians indicated in Table 13.2.2-1 vill have ~ completed the training indicated in the Table in order to support preoperational testing. Following fuel load and initial criticality, replacementtechniciahwillnormallycompleteinitialtraining r quirements within one year of assignment to the position. Initial training shall consist of pressurized water and balance of plant rystems, process fundamentals, mitigating core damage and on-the-job training. The initial program will have a minimum duration of 5 t veeks. On-the-job training prior to fuel load and initial criticality, shall - g : M-I,b* h-M $ ki h tfon in Preoperational program activitie h .__ x_ _ fini After fuel load and initial .s. criticality, on-the-job training shall be comprised of activities s which build upon the initial classroom training. [" ___ 4 -l1 s ~.- i :' ~ B. Cont 1nuing Training '[. One of the following listed programs or other specific programs as requested by the maintenance superintendent will be conducted annually. Personnel who have not ' i-completed the offered course will normally attend. ~ ~ ~ - Approximate Curriculum Outline Duration i Electronics review 1 week Test equipment 2 days g Process instrumentation 1 week ~ Process control systems 1 week ~ C. Annual Requalification Training or Exemption Testing 4 i I i Instrumentation and controls technicians will complete annual requalification training or exemption testing b _. to make them aware of and review important changes made to plant emergency and disaster, radiation protection, security, and respirator procedures. ~ ~ ~ ~ ' _._.,,m,-

~ w n DRAFT ...+. D. Initial Foreman Qualifications Foresen will meet the requirements of ANSI 18.1-1971. General g, employee training will be completed per the requirements of section 13.2.2.1.ff Foremen will complete training in mitigating core damage. Any other training maybe requested by the maintenance department. .nu_ w-m.- ~ ' ' ' , ~ ' E. Continuing Foremen Training j..

i listed continuing training programs or other One of the spec'ific programs as requested by the maintenance Foremen will superintendent will be presented annually.

normally attend these sessions unless they have already N -a completed the offered course. F. Instrumentation and Controls Maintenance Supervisor Qualifications and Training The maintenance supervisors will have the qualifications required of maintenance foremen and will normally attend a similar continuing training program.__After__,ini31a LappM ntment to_ the__ position, i the new supervisor will complete the following training. Approximate Curriculum Outline Duration ---rr Electrical, pressure vessel, and 3 days piping codes and standards (including nondestructive testing review) y ~. C. _ Contractors ch; ~ .;,g., g Contractors with education and experience that meets or exceeds FSAR j ! 2 commitments may fill a position provided that the Maintenance ] Superintendent certifies that the individual's education and i experience meets or exceeds the requirements for the position. f l t

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DRAFT p T6 VEGP-FSAR-13 s-Approximate g Curriculum Outline Duration 6-10 h'** General employee badge and health / physics training 4h [ Industrial safety New employee fire training 2h 1 week / General pressurized water reactor systems 1 week General balance of plant systems Process fundamentals 1 week / Mitigating core damage (commensurate 2h l4 with responsibilities) g I week On-the-job training B. Continuing Training One of the following listed programs or other specifict j programs as requested by the maintenance superintendent {' will be conducted annually. Personnel who have not completed the offered course will normally attend. II Approximate Curriculum Outline Duration 1 week Electronics review 2 days Test equipment 1 week Process instrumentation 1 week Process control systems C. Annual Requalification Training or Exemption Testing Instrumentation and controls technicians will complete annual requalification training or exemption testing to make them aware of and review important changes made to plant emergency and disaster, radiation protection, security, and respirator procedures. D. Initial Foremen Training (and Student Engineers) \\ Foremen who meet the requirements of ANSI /ANS 18.1-1971 will complete General Employee Training Duration depends on whether the individual attends additional a. radiation worker training as described in paragraph 13.2.2.1.8.A. Amend. 4 2/84 13.2.2-5 Amend. 16 4/85

^ DELETE VEGP-ESAR-13 / s and on-the-job training as described above under initial Those training prior to performing independent duties. who do not meet the above requirements must complete / initial training and progress through most of the continuing training courses in order to demonstrate f their ability to perform the specific tasks. \\ E. Continuing Foremen Training Cne of the listed continuing training programs or other specific programs as requested by the maintenance superintendent will be presented annually. Foremen will normally attend these sessions unless they have already completed the offered course. F. Instrumentation and Controls Maintenance Supervisor Qualifications and Training l The maintenance supervisors will have the qualifications required of maintenance foremen and will normally attend a similar continuing training program. After initial appointment to the position, the new supervisor will complete the following training. Approximate ; Curriculum Outline Duration Electrical, pressure vessel, and 3 days piping codes and standards (including nondestructive testing review) G. Incumbents and New Employees Personnel with experience that exceeds NRC commitments may fill a position in the instrumentation and controls career path, provided the maintenance superintendent certifies that the employee's \\ experience qualifications exceed the position requirements. The training department may also accept / to fill specific course / \\, prior training or experience requirements. ~ 13.2.2-6 Amend. 16 4/85

s2 ud DRAFT gTs ,y o p psen VEGP-PSAR-13 S k % Mechanical Maintenance Training Program 13.2.2.1. a A. Initial Training Maintenance personnel who meet the education and experience requirements of ANSI /ANS 18.1-1971 will complete general employee training and on-the-job training as described below prior to being assigned independent tasks. Those who do not meet the above requirements must complete initial training in order to demonstrate their ability to perform the specific I f tasks. Approximate Curriculum Outline Duration General employee badge training 6-10 hea> Industrial safety 4h t New employee fire training 2h General pressurized water reactor 1 week systems General balance of plant systemc 1 week II Maintenance fundamentals 1 week ,7' Mechanical fundamentals 1 week On-the-)g B. Continuing 6 Training One of the following listed programs or other specific programs as requested by the maintenance superintendent will be conducted annually.c ^- --- ' who have not completed the offered course will normally attend. Approximate Curriculum Outline Duration 1 week Theory and maintenance of pumps and valves Power transmission devices 2 days 1 week Shop fundamentals Crane safety and operation 3 days Shaft alignment 2 days Motor-operated valves 3 days Duration depends on whether the individual attends additional a. radiation worker training as described in paragraph 13.2.2.1.8.A. 13.2.2-7 Amend. 16 4/85

p;,,._ en Jll anee! %e ceg&emed.s d AUs E 18.1 -I 971. Guenl e.mphyer inaniy, will be. en-f eM e< f4e rep %eds of sec};, l p 13 z.2..I.1. Mmen will fic "y Oe' bwmnj 'n h f/2e m d d8'W Ce efry p.FSAR-13 rs repeg C. Annual Requalification Training or Exemption Testing Mechanics will complete annual requalification training or exemption testing to make them aware of and review important changes made to plant emergency and disaster, radiation protection, security, and respirator procedures. slo thdi*'n3 p D. Initial Forem rainingM and Student Engineers) fForemen who meet the requirements of ANSI /ANS 18.1-1971 will complete General Employee Training and on-the-job ftrainingesdescribedaboveunder initial training priori to performing independent duties. Those who do not meet the above requirements must complete initial training and progress through most of the continuing training i courses in order to demonstrate their ability to perforg specifictasks[ e t E. Continuing Foremen Training One of the listed continuing training programs or other specific programs as requested by the maintenance superintendent will be presented annually. Foremen will normally attend those continuing training programs unless they have completed the offered course. F. Maintenance Supervisor Qualifications and Training The maintenance supervisors will have the qualifications required of maintenance foremen and will normally attend a similar continuing training program. After initial appointment to the position, the new supervisor will complete the following training. Approximate Curriculum Outline Duration Electrical, pressure vessels, and 3 days piping codes and standards (including nondestructive testing review) G. kcurbem ud re-Spigccs Co,derde, g Personnel with experience that exceeds NRC commitmen-., may fill a position in the mechanical career path provided that the maintenance superintendent certifies that the employee's experience qualifications excee l Co dmdo. s wih e,L J;,,, ule perkac M meds e,. eueids Frat 2. co,,w,;he,ds "[a ey/ & AW9'l$.iT **M '"MN k[df 16 h;,f(( ihl O 8 Am 4/85

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ATTACEMFAT /3 LL/ Y g U 13.2.2.1.4 Mechanical Maintenance Training Program j Qcham c. l o A. Initial training Maintenance,-._ M c5_--.__-4 vill meet the minimum education and experience ge W requirements of ANSI 18.1-1971 prior to being considered qualified to perform all tasks independently. Prior to meeting all ANSI 18.1-1971 E requirements, ;::: ' may be trained to perform specific tasks and ~ qualified to perforakhose tasks independently. h vill be required to comple e general employee training per the requirements of section13.2.2.1./ ~ The numbers of perso#nel. indicated in Table 13.2.2-1 vill have ~ completed the training indicated in the Table in order to support preoperational testing. Following fuel load and initial criticality,, ll replacement teveenner will normally complete initial training 4{ requirements withinIone year of assignment to the position. Initial training shall consist of pressurized water and balance of plant systems, maintenance fundamentals, mechanical fundamentals, and ..s, i, on-the-j ob training'. The initial program vill have a minimum duration ] of 5 weeks. ~~ On-the-job training prior to fuel load and initial criticality, shall in preoperational program activities, b,e cop g d gg g igi g,Sr.: i o g m :---- After fuel load and initial ,f criticality, on-the-job training shall be comprised of activities - which build upon the initial classroom training. w- - -

~ hh h VEGP-ESAR-13 / / the position requirements. The training department to fill IdsEtr may also accept prior training or experience specific course requirements.j ~ ~ -~~ - ~ 3 ATTAc4Q x w 13.1.2.. lf 13.2.2.lf/ flectrical Maintenance Training Program 3 1 u. W itial[ Training k b/ Eb' Maintenance personnel who meet the education and experience requirements of ANSI /ANS 18.1-1971 will' complete general employee training and on-the-job ( training as described below prior to being assigned N N independent tasks. Those who do not meet the above requirements must complete initial training in order to. demonstrate their ability to perform the specific j tasks. Approximate' { Curriculum Outline Duration j 6-10 h' General employee badge training l' Industrial safety and first aid 4h f New employee fire training 2h 1 week General pressurized water reactor systems General balance of plant systems 1 week Maintenance fundamentals 1 week Direct current fundamentals 1 week Alternating current fundamentals 2 weeks Electrical safety, drawings, and I week 10 test equipment 1 week On-the-job training B. Continuing Training One of the following listed programs or other specific programs as requested by the maintenance superintendent will be conducted annually. Personnel who have not j completed the offered course will normally attend. I \\ Duration depends on whether the individual attends additional a. radiation worker training as described in paragraph f y 13.2.2.1.8.A. Amend. 10 9/84 13.2.2-9 Amend. 16 4/85

,. rme,, wul meef he regarme, s5 d Axltr.j-n7t. %,,, [ sezg!ayee +rmnt wuI be eomple ed[er 4he 2,,e,,,4, p e ,ien i3.L2.1.'9. Fecemen will yro g,,,,f o rtyU5td by4ke.mshPR'6bhi JT'- '" D m' 4 *5 Approximate Curriculum Outline Duration Protec on devices, control devices, 3 days i and,otor control centers ac/d motors and generators 4 days Sol' state theory 3 days Ba eries, chargers, and inverters 1 day Py otronics fire detectors 1 day M tor-operated valve maintenance 1 day witchgear and breaker maintenance 3 days i Amp lugging 1 day \\ s C. Annuai aequalification Training or Exemption Testing s s Electricians will complete annual requalification s training or exemption testing to make them aware of and review important changes made to plant emergency ( and disaster, radiation protection, security, and ? \\ respirator procedures. \\ D.'\\ InitialForemenQualifications(}ar2_ Student Engineers) \\ es/ '(

1. G emen who meet the requirements of ANSI /ANS 18.1-1971

) will complete general employee training and on-the-job training as described above under initial training prior, to performing independent duties. Those who do not meet the above requirements must complete initial training and progress through most of the continuing training courses in order to demonstrate their ability to perform the specific tasks E. Continuing Foremen Training One of the listed continuing training programs or other specific programs as requested by the maintenance superintendent will be presented annually. Foremen will normally attend these continuing training programs unless they have previously completed the offered Course. E. Maintenance Supervisor Qualifications and Training The maintenance supervisors will have the qualifications required of maintenance foremen and will normally attend a similar continuing training program. After initial appointment to the position, the new supervisor will complete the following training. 13.2.2-10 Amend. 16 4/85

ATTAcusco7 :3. 2.t.f.5-DRAFT 13.2.2.1.5 Electrical Maintenance Training Program 6 r- ~ .t. Initial traininc Ej e^c;fr:cie ' o,j tc.MC8W

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g ill :ee the tintrum educa::en and experience __ : e : G r e :e. : s f.G: ' O. '. '. F '. ; r. : : :: be n:; ::nn:ers: :.:alified :: perf :: all tasks independently. Prier to =eeting all.US: 18.1-1971 requirscents,, m _..;1. =ay be trained to perform specific tasks and

r-- T will be E/eg asu 4those tasks independently. y:herequirementsof qualified to-perform requiredtocompiege general e=ployee training per section 13.2.2.1.).

g tWeh'Itlea $ The numbers of,-.....rindicated in Table 13.2.2-1 vill have 7 " *.9'q.empleted the training impicated in the Table in order to support ~ p'ISit(hes ting. Followingifuel load and initial criticality, g'. replacement E x x 51,will nor= ally complete initial training requirements within one year of assignment to the position. Initial training shall consist of pressurized water and balance of plant ~ systems, maintenance fundamentals, direct current fundamentals, alternating current fundamentals, electrical safety, drawings, test equipment and on-the-job training. The initial program vill have a minimum duration of 8 weeks. On-the-job training prior to fuel load and initial criticality, shall y P2 "Epg:,apigip8 *-*--(preoperational program activities, be compris tion in _r _ __ y_ After fuel load and initial criticality, on-the-job training shall be comprised of activities which build upon the initial classroem training. B. Centinuing TrainiAg ~ I dedetc.w One of the following listed programs or other specific programs as requested by the maintenance superintendent l n..,...cl who have not will be conducted annually. completed the of fered course will(tr:.cnns normally attend. ase ,G . l %... -. l-Approximate ~ ~ Curriculum Outline Duration ~ ~ ~ ~ Protection devices, control devices, 3 days and motor control centers ac/dc motors and generators 4 days Solid state theory 3 days Batteries, chargers, and inverters 1 day Pyrotronics fire detectors 1 day Motor-operated valve maintenance 1 day Switchgear and breaker maintenance 3 days Amp lugging 1 day .g .. = _ - ~

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Q thruchers WNl, c&icn ud opericane }$8 medS $Y ^ Cr txcet 5 F'Sht. commherds Gil 'a rsQ fQ +l,e YCdCC*Qffh7f;'4&y;fbnp≪aLa,ka %nf~' ne in VEGP-FSAR-13,b "d' /er fne far,f* g, o Approximate Curriculum Outline Duration Electrical, pressure vessel, and 3 days piping codes and standards (including g nondestructive testing review j and ':cu E=picyecy [on$taders G., 2cumbants A exceeds NRC com:nitme s ersonnel with experience that may fill a position in the electrical career path provided that the maintenance superintendent certifies that the employee's experience qualifications exceed the position requirements. The training department may also accept prior training or experience to fill specific course requirements 6 13.2.2.1.f Shift Technical Advisor Training Program ? A. Education Requirements Shift technical advisors will have a bachelor's degree 16 in a scientific or engineering discipline. B. Training Program The candidate' holds or has held an NRC senior reactor operators license for that type of reactor, or the candidate completes a Georgia Power Company (GPC) shift technical advisor training program described in table 13.2.2-1. In either case, the shift technical advisor shall receive specific training in the response and analysis of the plant for transients and accidents. C. Experience Requirements The candidate will have 1 year of power plant experience and will have performed reactor operator or senior reactor operator duties for that type of reactor, or the candidate will receive 1 month of on-the-job training as an extra shift technical advisor. A D. Requalification Training for Shift Technical Advisors Shift technical advisors will attend the same requalification program as NRC-icensed operators. Shift technical advisors Mich o not stand shift for a 4 17 period of 30 days or longer will receive on-the-job ~ instruction from the duty shift technical advisors ?. $6 feree fo ke] load STA's uislIrned'lbU,et}'""'"*'ISb y 5 i g 9siniy af feu+ if wee lcs elIdf*'W2.T-11Y *n e g c Amend. 17 7/85 C IFF j* 'fl.

VEGP-ESAR-13 concerning plant changes which have occured during their j absences. .T.A$E2.T Persons not performing the' shift technical advisor 4 ITACNHEUI function for a period of 6 months or longer shall, prior d'2 % I 7 to assuming the responsibilities of the position, undergo an individual requalification program. i 13.2.2.1.7,F Nonlicensed Operator Training Program DELETE f ~ ~ - A Initial Training h_.- m After the start of fuel load, all personnel assigned to perform independent plant equipment manipulations will either complete this initial training program, be qualified to the shift technical advisor level or certified to the senior reactor operator level, or have experience which is equivalent to the following program. Approximatg Curriculum Outline Duration General employee badge and health 6-10 h'3' l' f / physics training y \\ Industrial safety 4h \\ New employee fire training 2h / g Nuclear power plant fundamentals 1 week / Power plant components 1 week / VEGP systems 4 weeks On-the-job training 1 weelt A B. Continuing Training ,y f 4,.L doj After completing initi qualificati the /----' - n on nonlicensed operator will comp glet g th systems $on which he3was not initially $g plant $ _1 f i 4.Normally, the nonlicensed operator will be Yrdel -qualif-y on all systems outside the control room and containment during the individual's first 3 years in the plant operations department % [ghigh,afca.of re3ge,64j / q,JS Annual Requalification Training or Exemption Testing Nonlicensed operators will complete annual requalification training or exemption testing to make ,f~ ~ Duration depends on whether the individual attends additional radiation worker training as described in paragraph 13.2.2.1.8.A Amend. 4 2/84 Amend. 16 4/85 13.2.2-12 Amend. 17 7/85

3 g - \\ heat ~ removal systems, and s' radiation waste and monitoring Q fg OnenlChn S. 3' Naystem ls 'on c / / yg k, " 13.2.2-18 Amend. 16 4/85

91 ATT& rdMF 9 '

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A A n... ,g v.I y a situ run ae3 y DRAFT 13.2.2.1.11 Quality Control Training Program A. Initial Training Quality Control inspection personnel will meet the minimum education and experience requirements of ANSI ~ N45.2.6-1978 prior to being certified,in visual inspection. . g. Personnel will be required to complete general employee 9 training per the requirements of section 13.2.2.1.fl. ? The numbers of personnel indicated in Table 13.2.2-1 will have completed the training indicated in the preoperJQ Table in trder to support-plene testing. Following fuel load and initial criticality, replacement personnel will normally complete all initial training requirements within one year of assignment to the position. faitial training shall consist of pressurized water reactor systems, balance of plant systems, uality control codes $ standards [ procedures ~ visual inspection; J @.M g Jueand on-the-job training. The initial program will have a minimum duration of 4 weeks. ~ On-the-job training during preoperational and test . program activities is comprised of procedurg h a

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• DRAFT plant familiarization,and inspection activity observance.

After fuel load and criticality, on-the-job training. shall be comprised of activities which reinforce the initial classroom training and knowledge of quality control activities. B. Continuing Training After completing initial qualification, quality contr personnel will normally attendg r. 2 program /to improve their quality control skills. The program may be from electrical, mechanical or instrumentation andcontrolmaintenancecourses,orhinspection eot<J'se.r, y training af4iFiRA.e_ I C. Annual Regnalification Training or Exemption Testing 1 Quality control specialists will complete' annual requalification training or exemption testing to review important changes to plant emergency, radiation protection, security, and respirator procedures. f ~ D. Contractors Personnel with the education and experience which or exceeds meets" Nuclear Requlatory Comission commitments may' fill,a,p,osition provided the Quality Control Superintendent ce 4 //cr cert 4f4ed-that the individual's education and experience meets the requirements for the position. 3 or exceeds. =-

DRAFT DELETE VEGP-FSAR-13 h Approximate Curriculum Outline Duration ' Heat transfer and fluid flow, 1 day secondary systems, electrical systems, and accident analysis Nuclear instrumentation systems, 1 day nuclear control systems, integrated plant control, and simulator plant operations Reactor protection systems, safety 1 day injection actuation system, and / simulator plant operations s x B. Continuing Training During periodic reviews of GPC's manpower plans, training goals will be established for professional employees to fill key supervisory positions as 'e vacancies develop. C-. A If 13.2.2.2 Shift Technical Advisor Training Program The shift technical advisor training program is described in paragraph 13.2.2.1.g. 6 13.2.2.3 Mitigating Core D nage Training Program The VEGP training program tor mitigating core damage is not a separate program but is integrated into licensed personnel training, pressurized water reactor senior reactor operator certified personnel training, and shift technical advisor the training. Other personnel including the technicians, managers of the Health Physics, Chemistry, and Instrumentation and Controls Departments, as well as the plant manager will complete training in mitigating core damage commensurate with their responsibilities. Ar,nux) Kegtial$sduon Tr w m oy e v-Exemdiu Tess;y 'C. Penannel all comg/de annua! < ud/6dio,, %,,;y o<. aeys;c,, +edi3 +e make hem awe ud reviw,qcek+ eQes,mde ho fluI Cmerjer1Cf a-hk Ib&eq Yuk lkion froItckl cry, securj grik y.es itbor frocedares. 13.2.2-19 Amend. 16 4/85

i VEGP-ESAR-13 13.2.2.4 Initial Position Job Analysis The training programs described in section 13.2 are the result of the initial position job analysis for VEGP staffing. The training organisation will use a combination of plant equipment reviews by instructors, training committee reviews by plant supervisors, and instruction reviews by students to obtain feedback to update our training plans or the position job analysis. Georgia Power Company stresses the use of this feedback to meet our overall training objective to train for job proficierrey. e/m 5 M/ d[ N 13.2.2.5 Training Frogram_ Syllabus The VEGP training organization is described in subsection 13.2.1 and figure 13.2.1-1. Georgia Power Company will use the same training programs to qualify its personnel both before and after the initial fuel loadingf~~Almost all programs in tEro ? section are considered formal or " classroom" programs. A formal program consists of instruction in the classroom, laboratory, simulator, and field which is supervised by an instructor. Specifically, the shift technical advisor program (paragraph 13.2.2.1.() and the training (instructor qualification) program (paragraph 13.2.2.1.Jff use some on-the-job training before the individuals in these organisational groups are permitted to perform job tasks. 13.2.2.6 Reactor Operations Experience Training Reactor operations experience training will be provided as outlined in paragraph 13.2.1.2 by using the VEGP simulator, preoperational test program, and observation of other light-water reactors. 13.2.2.7 Differences in Training Programs The difference in the training programs for individuals based on the extent of previous nuclear power plant experience is described in paragraph 13.2.2.1. 13.2.2.8 Fire Protection Training Program A description of the fire protection training program used for fire brigade members is described in paragraph 13.2.2.1.Jf. lo 13.2.2-20 Amend. 16 4/85

DRAFT JEGP-ESAR-13 13.2.2.9 Training Proaram Effectiveness Training program effectiveness is evaluated by either. written, oral, or practiced demonstration examinations for each employee. Figure 13.2.2-1 is a schedule showing the start of each portion of the nonlicensed plant staff training program in relation to the schedule for preoperation tests, fuel load, and expected time for license examination. Since all of the training. programs in this section are used for both units before and after fuel load, after a particular program is started,.that 16 program will be available for use any time there is a need to qualify additional personnel. At the time of fuel load, sufficient VEGP personnel will be qualified in each organizational group to meet the staffing requirements of subsection 13.1.2. If fuel loading is delayed, the continuing and requalification' training programs as described in this subsection will be implemented to ensure personnel job proficiency. 13.2.2-21 Amend. 16 4/85

k' DRAFT VEGP-FSAR-13 TABLE 13.2.2-1 COMPARISON OF SHIFT TECHNICAL ADVISOft CURRICULUM WITH INPO RECOMMENDATIONS Georgia Power Topic INPO(h) Company (hl_ Education High school fundamentals 240 Note a College fundamentals 520 Note a Plant-specific applied fundamentals 120 120 Management / supervisory skills 40 40 Plant systems 200 200 Administrative controls 80 Note b 1( General operating 30 Note b precedures Transients / accident 30 Note b analysis and emergency procedures Simulator training 100 100 Mitigating core damage O Note b Incore instrumentation Excore instrumentation Vital instrumentation Primary chemistry Radiation monitoring Gas generation a. All shift technical advisors will have a bachelor's degee in scientific or engineering discipline. a b. These topics will be incorporated into the simulator training syllabus. Amend. 16 4/85 0140V b

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DRAFT MONTHS TO FUEL LOAD 54 51 48 45 42 39 36 33 30 27 24 21 18 15 12 9 6 3 Pre - License Fuel Lead operational Exams and Tests Criticality h o Types and Number of Personnel Health Physics / Radiochemistry (20) instrument and Control (20) Mechanical Maintenance (20) i Electrical Maintenance (20) Shift TO :hnical Advisor ~ and Reactor Engineer (6) Nonlicensed Operator (15) Training, instructor Qualification (15) General Employee (170) Independent Review Boards (6) r Quality Control (6) j Engineering and Technical Support (20) i l l F 8 i P TRAIT 1ING FOR lJONLICENSED vocTLE k CLE CTRIC GENER ATINdTL ANT VEGP STAFF (sCOIQlilPO WCf h g 3,uir t ANo our r 2 s FIGU PI 13.2.2-1 n t M '}}