ML24340A019
| ML24340A019 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 07/30/2023 |
| From: | James Drake NRC/NRR/DORL/LPL4 |
| To: | Entergy Operations |
| References | |
| Download: ML24340A019 (1) | |
Text
RBS USAR Revision 28 13.1-1 CHAPTER 13 CONDUCT OF OPERATIONS 13.1 ORGANIZATION AND RESPONSIBILITY Entergy Operations, Inc. (EOI) is a generating subsidiary of Entergy Corporation, a registered public utility holding company. EOI assumes sole responsibility for the operation of River Bend Station (RBS) while Entergy Gulf States Louisiana, LLC, which is also a subsidiary of Entergy Corporation, maintains ownership of RBS.
Historical data removed - To review exact wording please refer to Section 13.1 of the RBS original FSAR for information related to the organizational structure during plant construction and startup.
13.1.1 Organizational Arrangement The management organization and functional responsibilities as they relate to the operation, maintenance and technical support of the River Bend Station are discussed in the Quality Assurance Program Manual (QAPM).
EOI is committed to providing the necessary fire protection for RBS during operation.
Administrative controls and procedures exist which ensure safe, reliable activities at RBS.
Additional details regarding fire protection at RBS can be found in USAR Section 9.5.1 and Appendices 9A and 9B.
Figure 13.1-2 depicts the RBS onsite management structure. Figures 13.1-4 and 13.1-7 depict organization charts for RBS administration support groups. Figure 13.1-4 depicts an organization chart for the RBS Engineering group. Figure 13.1-5 depicts an organization chart for shift staffing during operations and Figure 13.1-6 depicts an organization chart for the Plant Operations structure.
13.1.2 DELETED 13.1.3 Qualifications of Nuclear Plant Personnel RBS personnel meet the requirements of ANSI/ANS 3.1-1978, Selection and Training of Nuclear Power Plant Personnel as discussed in the Quality Assurance Program Manual.
Notes:
FIGURE 13.1-2 A Deleted B See Figure 13.1-4 C See Figure 13.1-6 D See Figure 13.1-7 RIVER BEND STATION MANAGEMENT STRUCTURE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT Revision 25 CHIEF OPERATING OFFICER SITE VICE PRESIDENT GENERAL MANAGER DIRECTOR ENGINEERING DIRECTOR -
REGULATORY &
PERFORMANCE IMPROVEMENT MANAGER -
FINANCE MANAGER -
INFORMATION TECHNOLOGY
FIGURE 13.1-4 RIVER BEND STATION TECHNICAL SUPPORT STRUCTURE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT Revision 24 DIRECTOR ENGINEERING MANAGER -
DESIGN AND PROGRAM ENGINEERING MANAGER -
SYSTEMS AND COMPONENTS ENGINEERING
ASSISTANT OPERATIONS MANAGER SHIFT MANAGER QUALIFIED PERSONNEL NECESSARY TO STAFF THE FIRE BRIGADE MAINTENANCE I&C TECHNICIAN NUCLEAR NUCLEAR CHEMISTRY TECHNICIAN RADIATION PROTECTION TECH SHIFT TECHNICAL ADVISOR CONTROL ROOM SUPERVISOR REACTOR OPERATOR AUXILIARY OPERATOR RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 24 RIVER BEND STATION SHIFT ORGANIZATION FIGURE 13.1-5 NOTES:
A NOT ON SHIFT; SHOWN FOR CLARITY ONLY
- MAY BE TRAINED TO A LEVEL EQUIVALENT TO A SHIFT TECHNICAL ADVISOR (STA). AN STA IS ASSIGNED TO THE SHIFT IF NEITHER THE SHIFT SUPERVISOR NOR THE CONTROL ROOM SUPERVISOR IS QUALIFIED AS AN STA.
LEGEND:
SRO SENIOR REACTOR OPERATOR RO REACTOR OPERATOR NLR NO LICENSE REQUIRED
2 2
2 1
A 1
1 1
5
SITE VICE PRESIDENT GENERAL MANAGER DIRECTOR OPERATIONS DIRECTOR MAINTENANCE SENIOR MANAGER PRODUCTION ASSISTANT OPERATIONS MANAGERS SHIFT MANAGER MANAGER CHEMISTRY SENIOR MANAGER RADIATION PROTECTION OUTAGE MANAGER SUPERINTENDENT SCHEDULING ASSISTANT MAINTENANCE MANAGER RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 28 RIVER BEND STATION PLANT OPERATIONS STRUCTURE FIGURE 13.1-6
FIGURE 13.1-7 RIVER BEND STATION REGULATORY AND PERFORMANCE IMPROVEMENT RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT Revision 25 DIRECTOR REGULATORY &
PERFORMANCE IMPROVEMENT MANAGER -
REGULATORY ASSURANCE MANAGER -
PERFORMANCE IMPROVEMENT MANAGER -
EMERGENCY PLANNING MANAGER -
TRAINING MANAGER -
SECURITY
RBS USAR Revision 27 13.2-1 13.2 TRAINING 13.2.1 River Bend Station Staff Training Program The objectives of this program are to:
- 1.
Establish and maintain an organization fully qualified to be responsible for the operation, maintenance and technical aspects of the River Bend Station
- 2.
Train sufficient personnel to operate and maintain the plant in a safe and reliable manner throughout its life
- 3.
Prepare operational, technical, professional and other personnel requiring licenses for Nuclear Regulatory Commission (NRC) Examinations
- 4.
Provide the necessary training, on a continuing basis, to insure adequate numbers of qualified individuals exist to offset the impact(s) of promotions and/or attrition
- 5.
Provide requalification training to maintain a high level of proficiency throughout the plant staff.
River Bend Station is a member of the National Academy for Nuclear Training. Membership is obtained after receiving accreditation for twelve specified training programs. To obtain and maintain accreditation for a program, River Bend Station must demonstrate to the National Nuclear Accrediting Board that a program meets accreditation objectives. These objectives provide for a performance based training program which is known as the systematic approach to training.
The plant staff training matrix is presented in Fig. 13.2-1. This matrix is established to meet long-term training needs. It is the intent of RBS to provide training to each individual(s) as outlined herein unless:
- 1.
The individual(s) are already qualified on the basis of experience, academic or related technical training
- 2.
The individual(s) have received sufficient documented on-the-job training to negate the need for specific formal classroom instruction.
Any deviation between the training an individual actually receives and that identified in Fig. 13.2-1 will be documented in accordance with approved programs and this documentation retained in the training records system. Having not received all the identified training does not in itself disqualify an individual from performing duties associated with his or her job, so long as he or she is allowed to perform only those function(s) for which documented qualifications exist.
The overall training program for the plant staff is the responsibility of the Site Vice President. The details of the training program(s) and the administration thereof are the responsibility of the Manager - Training or his designee.
The Manager - Training delegates the responsibility for implementation of specific programs to individual discipline supervisors. The supervisors are responsible for the quality and adequacy of the program content, material development, presentation, examinations, performance evaluation, and documentation of each respective program.
RBS USAR Revision 28 13.2-2 Those individuals applying for a license or license renewal will have certification complete pursuant to 10CFR Sections 55.31 (a)(4) and 55.57 (a)(4) and (a)(5) signed by the Site Vice President and provided to the NRC on NRC Form 398. Form 398 will be completed in accordance with the guidance in NUREG 1021.
13.2.1.1 Program Description Professional, supervisory, and technical personnel receive training necessary to satisfy requirements for their positions. This training will consist of formal classroom presentations coupled with on-the-job training. Vendor training will be utilized, as necessary, to provide additional knowledge on specific tasks.
The overall training program for River Bend Station (RBS) is designed to provide plant staff training. The individual training programs comply with Regulatory Guide 1.8 and ANSI/ANS 3.1-1978 as discussed in the Quality Assurance Program Manual. They are designed to utilize past training and/or experience coupled with the necessary site specific training to insure each position within the plant staff is manned by a competent, well qualified individual.
SRO candidates who serve in the dual role SRO/Shift Technical Advisor (STA) capacity have as a minimum the education and training required by the Commission Policy Statement on Engineering Expertise on Shift, October 28, 1985 (FR 43621).
Individuals assigned as STA, who are not SRO licensed, will be given the training described in Section 13.2.10.5, which meets the intent of NUREG-0737, TMI Action Plan Item I.A.1.1.
RBS also complies with Reg. Guide 1.8 in that RBS will require that license candidates complete 3 months of on-shift experience as an extra person. This will be accomplished during the control room training program as the candidate assumes a trainee status with no concurrent duties.
In the following subsections, the training program elements are described to include a general course description and the approximate course length. Each course is presented by instructors qualified in accordance with applicable procedures.
13.2.2 General Employee Training (A1)
The objective of the RBS General Employee Training Program is to indoctrinate all personnel requiring unescorted access to the plant in the general procedures utilized to assure nuclear plant safety and personnel safety. Only those personnel who have completed the applicable General Employee Training Course are allowed unescorted protected area or radiation control area access. General Employee Training courses cover eight areas, as specified in ANSI/ANS 3.1-1978, 10CFR19, and Regulatory Guides 8.13 and 8.27.
- 1.
Quality assurance training
- 2.
Radiation protection training
- 3.
Station emergency procedures
- 4.
Industrial health and safety
- 5.
Access control and security
- 6.
Plant description, operating policy, organization and administration
- 7.
Fire protection
- 8.
Fitness-for duty and Supervisory Observation.
Training in specific job-related procedures and instructions will be accomplished by the responsible supervisor.
New employees and contractor personnel participate in the initial General Employee Training.
Temporary consultants, maintenance, service personnel, vendor personnel, etc, receive the General Employee Training to the extent necessary to safely execute their duties. Personnel with equivalent training from other facilities may be given only the site-specific portion of the program.
13.2.2.1 General Employee Retraining In order to maintain the knowledge acquired during the initial training, periodic retraining is provided. Retraining is accomplished by self study seminars, safety meetings, computer based training and formal classroom lectures so that retraining is provided in the areas covered by the initial training but will also include any modifications, plant changes, or other updates needed for the program.
The GET retraining program will be conducted at a frequency to meet the needs of the plant personnel such that each employee is provided retraining on a periodic basis. This retraining includes retraining for radiation workers.
13.2.2.2 Respiratory Protection Training (A2)
Training in airborne hazards and the use of respirators is provided to indoctrinate personnel in the proper methods of protecting themselves from inhaling toxic or radioactive materials. This training is provided for familiarization only and does not replace the mask fit and tests conducted by Radiation Protection or training.
13.2.3 Emergency Response Training (A3)
Personnel assigned duties associated with the Emergency Plan will complete specialized training commensurate with their job responsibilities. Emergency Response training is administered as described in the Emergency Plan Section 13.3.7.1.
13.2.4 Supervisory Skills Training (A4)
This course of study consists of training in the following areas for supervisory positions:
- 1.
Leadership
- 2.
Interpersonal Communication
- 3.
Command Responsibilities
- 4.
Motivation of Personnel
- 5.
Problem Analysis
- 6.
Decisional Analysis.
13.2.5 Fire Protection Training Fire protection training consists of training in three specific areas:
- 1.
Employees designated to be members of the station fire brigade.
- 2.
Employees assigned to the fire protection staff.
- 3.
Offsite fire departments.
Specific training requirements for each of the above categories of personnel are as described in the following sections.
13.2.5.1 Fire Brigade Training (B1)
Personnel assigned as fire brigade members receive formal training prior to assuming brigade duties. The course subject matter is selected to satisfy the requirements of Regulatory Guide 1.120 (see Section 1.8 for clarification), Branch Technical Position CMEB 9.5-1 and the NRC document "Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls, and Quality Assurance." In addition, course material selection also includes guidance from NFPA Codes 801, 802, and 803. The training includes both classroom instruction and field exercises.
Course material includes the following classroom instruction:
- 1.
Chemistry of fire
- 2.
Classification of fires and principles of extinguishment
- 3.
Fire prevention and inspection techniques
- 4.
Fire protection systems
- 5.
Radiological safety aspects of fires at nuclear facilities
- 6.
Indoctrination of plant firefighting plans with specific identification of individual responsibilities
- 7.
Identification of the type and location of fire hazards and associated types of fires that could occur in the plant
- 8.
The toxic and corrosive characteristics of expected products of combustion
- 9.
Identification of the location of firefighting equipment for each fire area and familiarization with the layout of the plant, including access and egress routes
- 10.
The proper use of available firefighting equipment and the correct method of fighting each type of fire including: fires in energized electrical equipment, fires in cables and cable trays, hydrogen fires, fires involving flammable and combustible liquids or hazardous process chemicals, fires resulting from construction or modifications (welding), and record file fires
- 11.
The proper use of communication, lighting, ventilation, and emergency breathing equipment
- 12.
The proper method for fighting fires inside buildings and confined spaces
- 13.
The direction and coordination of firefighting activities (fire brigade leaders only)
- 14.
Detailed review of firefighting strategies and procedures
- 15.
Review of the latest plant modifications and corresponding changes in firefighting plans.
Items 14 and 15 may be deleted from the training of nonoperations personnel who may be assigned to the fire brigade.
Field exercises are conducted to reinforce the classroom training and provide an opportunity to practice the skills learned. These exercises include:
- 1.
Fighting small fires with portable fire extinguishers
- 2.
Interior firefighting using breathing apparatus
- 3.
Controlling incidents involving flammable gases or pressurized liquid fuels
- 4.
Fighting large flammable liquid fires using hose lines and/or foam
- 5.
Fighting flammable liquid fires inside building.
The classroom instruction and field exercises are provided by qualified individuals who are knowledgeable, experienced, and suitably trained in fighting the types of fires that could occur and in using the types of equipment available at RBS.
13.2.5.2 Fire Protection Staff Training (B2)
The station fire protection staff receives training in:
- 1.
Design and maintenance of fire detection, suppression, and extinguishing systems
- 2.
Fire prevention techniques and procedures
- 3.
Firefighting techniques and procedures for plant personnel and the fire brigades
- 4.
Hazardous material identification and handling.
RBS USAR Revision 27 13.2-6 Specific courses to achieve the above training objectives will be provided for the System Engineers assigned to the fire protection staff if they are not fully trained when hired. These courses are available from the fire and emergency training facility operated by Louisiana State University and will be attended as necessary by these individuals. Other training organizations may be used to provide this training on a case-by-case basis.
13.2.5.3 Offsite Fire Department Training (B3)
Training for offsite fire departments that have agreed to assist RBS during a major fire onsite is provided to make members aware of the need for radiological protection of personnel, the special hazards associated with River Bend Station, and the operational precautions to be followed when fighting fires at RBS.
The course is provided annually and includes instruction in the following:
- 1.
Basic radiation protection, including the use of personal dosimetry devices
- 2.
Plant familiarization, including hazards and fire protection systems
- 3.
Firefighting procedure, including entry to and exit from the plant.
13.2.5.4 Fire Brigade Retraining
- 1.
Classroom Regular planned meetings are held at least once each calendar quarter for brigade members to review changes in the fire protection program and other subjects as necessary. Periodic refresher training sessions are held to repeat the classroom instruction program for brigade members over any 2-year period. These sessions may be concurrent with the regular planned meetings.
- 2.
Practice Practice sessions are held for each shift fire brigade on the proper method of fighting the various types of fires that could occur in a nuclear power plant. These sessions provide brigade members with experience in actual fire extinguishment and the use of emergency breathing apparatus under strenuous conditions encountered in firefighting. These practice sessions are provided at least once per year for each fire brigade member.
- 3.
Drills Fire brigade drills are performed in the plant so that the fire brigade can practice as a team. Unannounced drills shall be full dress. Regularly scheduled drills will be full dress.
Full dress includes helmet, coat, boots, gloves, and emergency breathing apparatus.
Donning of face mask and use of emergency air is not mandatory during drills.
Drills are performed at least once each calendar quarter for each shift fire brigade. The offsite local fire department is invited to participate in at least one drill per year.
Each fire brigade member should participate in each drill, but must participate in at least two drills per year.
RBS USAR Revision 27 13.2-7 13.2.5.5 Fire Brigade Records Individual records of training provided to each fire brigade member, including drill critiques, will be maintained as part of the permanent plant files for at least 3 years to ensure that each member receives training in all parts of the training program. Retraining or broadened training for fire-fighting within buildings will be scheduled for all those brigade members whose performance records show deficiencies. A system to document drills including critiques and corrective actions has been developed. Fire brigade training review and individual performance programs also have been developed.
13.2.6 River Bend Systems BWR Technology Training (C1)
This course is designed to provide the student with an understanding of the design, construction and operating characteristics of RBS. The course length, scope, and depth may vary according to the experience level of the student. The applicable training program procedures describe the specific course outlines for the various disciplines. This course will be taught by qualified instructors.
13.2.7 Maintenance Training Programs (D1) 13.2.7.1 Maintenance Training Programs The River Bend electrical, instrumentation and controls, and mechanical maintenance training programs are designed to enhance safe and reliable operation of the plant by ensuring each participant has the necessary job-related skills and knowledge needed to perform their job duties.
The program is accredited by the National Academy for Nuclear Training and is based upon a systematic approach to training. It provides for initial and continuing training as well as a task/job qualification process.
13.2.7.2 Maintenance Supervisor Training Program The River Bend maintenance supervisor training program is designed to provide maintenance supervisors with supervisory, managerial, administrative and technical knowledge to supplement their experience, training and education. The program is accredited by the National Academy for Nuclear Training. It provides for initial and continuing training as well as job familiarization sessions with selected plant personnel to provide supervisors with the perspective about organizational functions, philosophies, practices and responsibilities.
13.2.8 Quality Assurance Training Program The training program for quality assurance personnel is based upon regulatory commitments delineated in the Quality Assurance Program Manual, (Regulatory Guide 1.146 Revision 0, dated August 1980; and Regulatory Guide 1.58 Revision 1, dated September 1980). The exact content and scope of the training may change as a result of training and performance feedback. Subject areas may include and provide support for audits, inspections, and non-destructive examination.
RBS USAR Revision 27 13.2-8 13.2.9 Technical Training Programs 13.2.9.1 BWR Chemistry Training (D2)
This training program is designed to prepare the members of the plant chemistry staff to establish and maintain the chemistry program.
13.2.9.2 Radiation Protection Staff Training (D3)
This program is designed to prepare the members of the radiation protection staff to safely and efficiently carry out their position responsibilities. Radiation protection staff members will be trained in areas commensurate with their assigned responsibilities.
13.2.9.3 Engineering Support Personnel Training Programs (D4)
The training Program for engineering support personnel is developed from INPO guidelines and job performance task analysis, and are updated from post-training performance feedback. The exact content and scope for each will change as a result of the feedback.
13.2.10 Operations Training Programs The Operations Training Programs consist of the following individual programs:
- 1.
Auxiliary Operator Training
- 2.
Reactor Operator Training
- 3.
Senior Reactor Operator Training
- 4.
Requalification Training for Licensed Operators
- 5.
Shift Technical Advisor Training
- 6.
Operations Shift Manager Training All of the operations training programs have been accredited by the National Academy for Nuclear Training. Each program's content and scope is based on a systematic approach to training.
13.2.10.1 Auxiliary Operator Training (E1)
The Auxiliary Operator Training Program consists of classroom and on-the-job training. The basic training is supplemented by watchstation-specific training. This training ensures that Auxiliary Operators possess the ability to safely and efficiently execute the duties associated with a given watchstation.
13.2.10.2 Reactor Operator (RO) Training (E2)
The RO is a licensed individual responsible for control manipulation at River Bend. The RO training program is designed to ensure that individuals who operate the controls of a nuclear reactor are competent to do so.
RBS USAR Revision 27 13.2-9 13.2.10.3 Senior Reactor Operator (SRO) Training (E3)
The SRO is a senior licensed individual who typically directs the activities of licensed reactor operators. The SRO training program is designed to insure that individuals who direct the activities of licensed operators possess an understanding of the principles, systems, components, and practices associated with the operation of River Bend, as well as advanced analytical and diagnostic skills.
13.2.10.4 Requalification Training for Licensed Operators (E4)
The requalification training program has been established to provide continuing training for licensed operators. The goal of continuing training is to maintain and enhance the performance and professionalism of licensed personnel to achieve the high operations standards to ensure safety and reliability at River Bend.
13.2.10.5 Shift Technical Advisor (STA) Training (E5)
The STA is an individual assigned to evaluate plant conditions and provide engineering and accident assessment advice to the operating crew during abnormal and accident conditions. The STA training program is designed to insure individuals assigned to the STA position possess the necessary engineering and technical expertise to provide advice to the operating crew at River Bend during abnormal and accident conditions.
13.2.10.6 Operations Shift Manager (OSM) Training The OSM training program delineates initial training, continuing training, and professional development for the Operations Shift Manager (OSM), beyond that received during training for Reactor Operator (RO) and Senior Reactor Operator (SRO) at River Bend Station (RBS).
13.2.11 River Bend Simulator The simulator at the River Bend Training Center is a full-scope plant-referenced simulator that meets Regulatory Guide 1.149, including Section C.2 as it relates to plant malfunctions (see Section 1.8). The River Bend simulator is used to provide an understanding of the integrated response of the plant during normal and off-normal conditions, the bases for this response, and the appropriate operator actions to maintain the plant in a safe condition with emphasis toward procedure usage and understanding.
Each instructor who will conduct programs for licensed operators on the River Bend simulator shall be, as a minimum, SRO certified on the River Bend simulator. This certification process consists of intensive training similar in scope to that required for Senior Reactor Operators and includes a written and operating test similar in scope and content to the NRC certification examination. In addition, instructors will be qualified in accordance with applicable procedures for instructional proficiency.
RBS USAR Revision 27 13.2-10 13.2.12 Training Program Documentation Records are maintained to document each person's participation in this program. These records will be maintained in the Permanent Plant File for a minimum of 2 years or as otherwise specified in this chapter or in approved procedures. These records include:
- 1.
Attendance records
- 2.
Copies of all operator requalification examinations given with acceptable answers
- 3.
Copies of the answers to these examinations
- 4.
Results of performance evaluations of licensed operators
- 5.
Records of any additional training given to correct exhibited deficiencies of licensed operators
- 6.
On-the-job training records
- 7.
Copies of licenses of all operators
- 8.
Records for personnel other than operators as addressed in ANS 3.1-1978.
13.2.13 Applicable Documents The River Bend Station training program follows the regulations and considers the guidance listed below:
- 1.
10CFR Part 50, Domestic Licensing of Production and Utilization Facilities
- 2.
10CFR Part 55, Operators' Licenses
- 3.
10CFR Part 19, Notices, Instructions, and Reports to Workers; Inspections
- 4.
Regulatory Guide 1.8, Personnel Selection and Training
RIVER BEND STATION STAFF TRAINING PLAN CLASSIFICATION TRAINING PROGRAMS GENERAL MANAGER A1, A3 (2)
DIRECTOR - OPERATIONS A1, A3 (2)
MANAGER - SYSTEMS & COMPONENTS ENG A1, A3 (2)
ASST. OPERATIONS MANAGER A1, A3 (2), A4 SHIFT MANAGER A1, A2, A3 (2), A4, E3, E4 SUPERVISOR - CONTROL ROOM A1, A2, A3 (2), A4, E3, E4 REACTOR OPERATOR A1, A2, A3 (2), A4, E2, E4 AUXILIARY OPERATOR A1, A2, A3 (2), B1, E1 SHIFT TECHNICAL ADVISOR A1, A2, A3 (2), E5 SUPERVISOR - REACTOR ENGINEERING A1, A3 (2), C1, D4 SUPERVISOR - ENGINEERING A1, A3 (2), C1, D4 MANAGER - INFORMATION TECHNOLOGY (COMPUTER SYSTEMS)
A1, A3 (2), C1 ENGINEERING SUPPORT PERSONNEL A1, A3 (2), D4 SENIOR MANAGER - RADIATION PROTECTION A1, A3 (2), D3 (3)
SENIOR RADIATION PROTECTION STAFF A1, A3 (2), C1, D3 (3)
RADIATION PROTECTION TECHNICIANS A1, A3 (2), C1 DIRECTOR - MAINTENANCE A1, A3 (2), C1 SUPERINTENDENT - MAINTENANCE A1, A3 (2), C1 SUPERVISOR MAINTENANCE A1, A3 (2), C1 MAINTENANCE TECHNICIANS A1, A3 (2), C1, D1 MANAGER - CHEMISTRY A1, A3 (2), C1, D2 CHEMISTRY STAFF (MANAGEMENT EMPLOYEES)
A1, A3 (2), C1, D2 CHEMISTRY TECHNICIANS A1, A3 (2), C1 ADMINISTRATIVE STAFF A1, A3 (2)
NOTES FIGURE 13.2-1
- 1. DELETED
- 2. PERSONNEL ASSIGNED TO EMERGENCY RESPONSE ORGANIZATION
- 3. AS ASSIGNED BY SENIOR MANAGER - RADIATION PROTECTION RIVER BEND STATION STAFF TRAINING PLAN (SHEET 1 OF 2)
RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT Revision 28
TRAINING PROGRAMS A1 GENERAL EMPLOYEE TRAINING A2 RESPIRATORY PROTECTION TRAINING A3 EMERGENCY RESPONSE TRAINING A4 SUPERVISORY SKILLS TRAINING B1 FIRE BRIGADE TRAINING B2 FIRE PROTECTION STAFF TRAINING B3 OFFSITE FIRE DEPARTMENT TRAINING C1 RIVER BEND SYSTEMS BWR TECHNOLOGY TRAINING D1 MAINTENANCE TRAINING D2 BWR CHEMISTRY TRAINING D3 RADIATION PROTECTION STAFF TRAINING D4 ENGINEERING SUPPORT PERSONNEL TRAINING E1 NUCLEAR EQUIPMENT OPERATOR TRAINING E2 REACTOR OPERATOR TRAINING E3 SENIOR REACTOR OPERATOR TRAINING E4 REQUALIFICATION TRAINING FOR LICENSED OPERATORS E5 SHIFT TECHNICAL ADVISOR TRAINING FIGURE 13.2-1 RIVER BEND STATION STAFF TRAINING PLAN (SHEET 2 OF 2)
RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT Revision 14
RBS USAR Revision 27 13.3-1 13.3 EMERGENCY PLANNING (This section is provided in a separate binding.)
RBS USAR Revision 27 13.4-1 13.4 REVIEW AND AUDIT RBS has developed a comprehensive program for reviews and audits of operating phase activities that are safety related. This program has been developed from the guidance provided by NRC Regulatory Guide 1.33, Revision 2, which endorses ANSI N18.7-1976.
A program for reviews, including in-plant and independent reviews, is established to accomplish the following:
- 1.
Verify that activities affecting safety-related structures, systems, and components during the operational phase are performed in conformance with applicable codes and standards, company policy and rules, approved operating procedures, license provisions, and QA requirements.
- 2.
Review proposed plant changes to design, tests, and procedures that affect nuclear safety.
- 3.
Verify that all Reportable Events are promptly investigated and corrected in a manner which reduces the probability of such events recurring.
- 4.
Detect trends which may not be apparent to a day-to-day observer.
To perform these reviews, EOI has established oversight committees and assessment groups.
Reviews at the plant level are performed by the On-Site Safety Review Committee (OSRC) (see 13.4.1). Independent reviews are performed by the Safety Review Committee (SRC) (see 13.4.3), of which a majority of members are independent of direct responsibility for plant operations. In addition, assessments are performed by on-site groups or Corporate Assessment.
The audit function is described in 13.4.5 below.
13.4.1 Onsite Review The On-Site Safety Review Committee (OSRC) is responsible for in-plant reviews. This group is composed of site management personnel that independently review activities to provide additional assurance that the plant is operated and maintained in accordance with the Operating License and applicable regulations that affect nuclear safety. The OSRC reports to and advises the General Manager Plant Operations on matters related to nuclear safety.
The OSRC is responsible for all functions administratively assigned to the Facility Review Committee (FRC). Refer to the Quality Assurance Program Manual (QAPM) for specific requirements for conducting reviews and audits of operating phase activities important to safety.
13.4.2 Technical Review and Control Responsibility for technical review and approval of various procedures and programs is described below and in the RBS Technical Specifications/Technical Requirements Manual.
13.4.2.1 Procedures and Programs Written procedures are established to cover, but are not necessarily limited to, the following activities:
- 1.
The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978
- 2.
The applicable procedures required to implement the requirements of NUREG-0737
- 3.
Refueling operations
- 4.
Surveillance and test activities of safety-related equipment
- 5.
Security Plan implementation
- 6.
Emergency Plan implementation
- 7.
Fire Protection Program implementation
- 8.
Process Control Program implementation
- 9.
Offsite Dose Calculation Manual
- 10. Quality Assurance Program for effluent and environmental monitoring
- 11. Technical Requirements Manual
- 12. TS Bases Control Program Implementation 13.4.2.2 Preparation and Review Each procedure and program required by Technical Specifications 5.4 and 5.5, as well as other procedures which affect nuclear safety, and changes thereto, is prepared by a qualified individual/group. Each such procedure, and changes thereto, is reviewed by an individual/group other than the individual/group which prepared the procedures, or changes thereto, but who may be from the same organization as the individual/group which prepared the procedure. Individuals responsible for these reviews are members of the River Bend Station supervisory staff, in accordance with administrative procedures. Each such review includes a determination of whether or not additional, cross-disciplinary review is necessary and a verification that the proposed actions do not constitute an unreviewed safety question.
If deemed necessary, such review is performed by the appropriately designated review personnel.
All proposed changes to the Emergency Plan are reviewed by the On-Site Review Committee, with the exception of editorial changes.
13.4.2.3 Approval Each procedure and program required by Technical Specifications 5.4 and 5.5, as well as other procedures which affect nuclear safety, or changes thereto, is approved prior to implementation by the General Manager, one of the Managers, the Senior Manager - Radiation Protection, or by the Director/ Department Head responsible for the program or the activity described in the procedure.
RBS USAR Revision 27 13.4-3 13.4.2.4 Documentation The preparation, review, and approval of the procedures and programs required by Technical Specifications 5.4 and 5.5, as well as other procedures which affect nuclear safety, are documented; records are maintained for at least five years in the permanent plant files.
13.4.3 Independent Review The Safety Review Committee (SRC) is responsible for providing independent review of activities affecting nuclear safety. The SRC also reviews, monitors and enhances the health of the safety conscious work environment at River Bend. Refer to the Quality Assurance Program Manual (QAPM) for specific requirements for conducting reviews and audits of operating phase activities important to safety.
13.4.4 Independent Safety Engineering Function The Independent Safety Engineering Function is no longer a specific designated function for plant operating oversight and reduction of human errors. Rather, the oversight function is perfomed as part of on-going processes for assessing plant operation at RBS. Those functions include activities conducted by Nuclear Independent Oversight, Performance Improvement, Regulatory Assurance, and Engineering. Human Performance improvement has been integrated into all site functions and is a goal for all departments. The combination of these various activities meet the intent for independent safety review for the commitment to NUREG-0737,Section I.B.1.2. as follows:
- 1.
An Operating Experience group evaluates and distributes in-house and industry information to appropriate EOI personnel for review. Recommendations resulting from these reviews are implemented to improve safety and reliability.
- 2.
Engineering support for RBS is located on site, making the engineers readily available to address potential design basis issues.
- 3.
System Engineering support for RBS is located on site, responsible for optimizing system performance and reliability and for providing technical assistance to the Operations and Maintenance organizations.
- 4.
The Corrective Action Program contains the essential process elements of problem reporting, root-cause analysis, and corrective action.
- 5.
The use of assessments provides information on performance trends and improvements for EOI and RBS Management.
- 6.
Oversight committees (OSRC and SRC) review plant operations.
- 7.
Management participation in the Corrective Action Program process (e.g., review of condition reports, grading the significance of condition reports, review of root cause analysis, and determination of which conditions relate to human performance) ensures that the quality and integrity of the program is maintained and that problems are visible to RBS Management.
13.4.5 Audit Program The audit program is described in the Quality Assurance Program Manual.
RBS USAR Revision 27 13.5-1 13.5 PLANT PROCEDURES The Site, Administrative, and Entergy nuclear procedures govern the operation and maintenance of the facility in a safe and efficient manner. Written procedures and administrative policies are established, implemented, and maintained in accordance with the Quality Assurance Program described in the QAPM.
RBS USAR Revision 27 13.6-1 13.6 SECURITY (This section is provided in a separate binding.)
RBS USAR Revision 27 13A-1 APPENDIX 13A The resumes of key personnel providing technical assistance for the operation of RBS are available.