ML21307A179
| ML21307A179 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 10/28/2021 |
| From: | Energy Harbor Nuclear Corp |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML21307A174 | List:
|
| References | |
| L-21-018 | |
| Download: ML21307A179 (52) | |
Text
TABLE OF CONTENTS Section Title Page 13.0 CONDUCT OF OPERATIONS 13.1-1 13.1 ORGANIZATIONAL STRUCTURE 13.1-1 13.1.1 OFFSITE ORGANIZATION 13.1-2 13.1.2 ONSITE ORGANIZATION 13.1-2 13.2 TRAINING PROGRAM 13.2-1 13.2.1 PERRY STAFF TRAINING PROGRAM 13.2-1 13.2.2 LICENSED OPERATOR TRAINING PROGRAM 13.2-2 13.2.2.1 Initial Training 13.2-2 13.2.2.2 Retraining and Requalification Programs 13.2-7 13.2.3 TRAINING PROGRAMS FOR NON-LICENSED PERSONNEL 13.2-9 13.2.3.1 Non-Licensed Operator Training Program 13.2-10 13.2.3.2 Shift Engineer Training Program 13.2-10 13.2.3.3 Instrument and Control Technician Training Programs 13.2-11 13.2.3.4 Maintenance Personnel Training Program 13.2-11 13.2.3.5 Chemistry Training Program 13.2-11 13.2.3.6 Radiation Protection Technician Training Program 13.2-12 13.2.3.7 Engineering Support Personnel Training Program 13.2-12 13.2.3.8 Management Supervisory Training 13.2-12 Revision 22 13-i October, 2021
TABLE OF CONTENTS (Continued)
Section Title Page 13.2.4 PLANT ACCESS TRAINING 13.2-12 13.2.5 FIRE PROTECTION TRAINING 13.2-13 13.2.5.1 Fire Brigade Training (X8) 13.2-14 13.2.5.2 Fire Protection Staff Training 13.2-16 13.2.5.3 On-Shift Personnel 13.2-16 13.2.5.4 Offsite Fire Department 13.2-16 13.3 EMERGENCY PLANNING 13.3-1 13.3.1 REFERENCE FOR SECTION 13.3 13.3-2 13.4 REVIEW AND AUDIT 13.4-1 13.4.1 PLANT OPERATIONS REVIEW COMMITTEE 13.4-2 13.4.1.1 (Deleted) 13.4-2 13.4.1.2 (Deleted) 13.4-2 13.4.1.3 (Deleted) 13.4-2 13.4.1.4 (Deleted) 13.4-2 13.4.2 COMPANY NUCLEAR REVIEW BOARD 13.4-2 13.4.2.1 (Deleted) 13.4-2 13.4.2.2 (Deleted) 13.4-2 13.4.2.3 (Deleted) 13.4-2 13.4.2.4 (Deleted) 13.4-3 13.4.3 (Deleted) 13.4-3 13.4.4 OVERSIGHT DEPARTMENT 13.4-4 13.5 PLANT PROCEDURES 13.5-1 13.5.1 PROCEDURES AND INSTRUCTIONS 13.5-2 13.5.1.1 Conformance with Regulatory Guide 1.33 13.5-2 13.5.1.2 Preparation of Procedures and Instructions 13.5-2 13.5.1.3 Procedures 13.5-3 13.5.2 OPERATING AND MAINTENANCE INSTRUCTIONS 13.5-5 13.5.2.1 Operating Instructions 13.5-5 13.5.2.2 Other Plans, Manuals, Descriptions, Procedures, and Instructions 13.5-9 Revision 22 13-ii October, 2021
TABLE OF CONTENTS (Continued)
Section Title Page 13.6 INDUSTRIAL SECURITY 13.6-1 13.6.1 SECURITY PLAN 13.6-1 13.6.2 SECURITY ORGANIZATION 13.6-1 13.6.3 SECURITY PROCEDURES 13.6-2 Revision 12 13-iii January, 2003
LIST OF TABLES Table Titles Page 13.1-1 Deleted Revision 22 13-iv October, 2021
13.0 CONDUCT OF OPERATIONS 13.1 ORGANIZATIONAL STRUCTURE The Perry Nuclear Power Plant (PNPP) is owned by Energy Harbor Nuclear Generation LLC. Energy Harbor Nuclear Corp. has exclusive responsibility and control in all matters related to the facility.
Energy Harbor Nuclear Generation LLC and Energy Harbor Nuclear Corp. are wholly owned subsidiaries of Energy Harbor Corp.
The ultimate responsibility for the physical construction, operation, and maintenance of the station is maintained by Energy Harbor Nuclear Corp. The Quality Assurance Program Manual (QAPM) provides a functional description of the organizations responsible for implementation of the quality assurance program.
Plant-specific position descriptions in the Administrative Controls Section of the Technical Specifications have been replaced with generic position descriptions, avoiding the need for a future license amendment should plant-specific position descriptions change. The plant-specific position descriptions that correlate to the generic position descriptions used in the Technical Specifications are as follows:
Generic Position Description Plant Specific Description Corporate Officer Site Vice President Plant Manager General Plant Manager Operations Manager Manager, Operations Operations Middle Manager Assistant Operations Manager, Shift Radiation Protection Manager Manager, Radiation Protection and Chemistry Revision 22 13.1-1 October, 2021
13.1.1 OFFSITE ORGANIZATION The description of the corporate organization and the lines of authority and responsibility, and communication between the corporate organization and the site organization are defined and established in the Quality Assurance Program Manual (QAPM), which is incorporated by reference into this document.
13.1.2 ONSITE ORGANIZATION
<Figure 13.1-2> describes the onsite organization to operate and maintain the plant. Responsibilities associated with key positions on the figure are described below. Additional consultant and contract personnel may be required and will be utilized as workloads dictate.
The nuclear organization and key individuals responsibilities are described in Chapter 17 (the operational Quality Assurance Program).
Additionally, station personnel will meet the qualification requirements as specified in the station Technical Specifications and the operational Quality Assurance Program.
Site Vice President The Site Vice President shall have the corporate responsibility for overall plant nuclear safety at the site and shall take any measures needed to ensure acceptable performance of the site staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
General Plant Manager The General Plant Manager reports to the Site Vice President and has overall responsibility for the safe and efficient operation of the plant in accordance with the applicable regulations, operating license requirements, and station manuals.
Revision 22 13.1-2 October, 2021
Succession of Authority The General Plant Manager has overall responsibility for all plant activities during normal operations. In the event of unexpected contingencies of a temporary nature when the General Plant Manager is unavailable, responsibility will be delegated to the following positions in the order listed:
- Manager, Operations
- Assistance Operations Manager
- Shift Manager Director, Site Engineering The Director, Site Engineering, reports to the Site Vice President and is responsible for the technical and engineering activities in support of site design control, plant modifications, and system performance requirements. The Director shall utilize fleet engineering resources when necessary in support of site engineering activities and will provide assurance that all engineering activities in support of the site are accomplished in accordance with the appropriate plant, fleet, and quality assurance policies and procedures.
Director, Performance Improvement The Director, Performance Improvement, reports to the Site Vice President and has overall responsibility for site training, compliance with the plant operating license and regulations, emergency planning activities, site security, site access authorization, and monitoring the sites performance of the Corrective Action Program.
Revision 22 13.1-3 October, 2021
Manager, Operations The Manager, Operations, reports to the General Plant Manager, and is responsible for directing daily operation of the plant, fire brigades, planning and scheduling of operations and radwaste activities, and directing development and review of required procedures and instructions dealing with plant operations to assure that the plant is operated in accordance with the requirements of the operating license and applicable procedures. This position is also responsible for development, implementation, and periodic evaluation of the Fire Protection Program.
Assistant Operations Manager - Support The Assistant Operations Manager - Support, reports to the Manager of Operations. The position supports the day-to-day operation of the plant, and implementation of the Fire Protection Program to ensure compliance with station procedures and regulatory requirements.
Supervises the Operations Support Unit and coordinates activities with the operating shifts and other departments as required.
Assistant Operations Manager - Shift The Assistant Operations Manager - Shift, reports to the Manager of Operations. The position supervises activities of day-to-day operations of the plant to ensure compliance with Station procedures and regulatory requirements. Coordinates activities with other departments and between operating shifts. Directs and coordinates the activities of the Shift Managers/STAs to ensure safe and efficient plant operation. Ensures adequate engineering expertise is available on shift to diagnose, mitigate, and terminate off-normal events.
Note:
Either the Operations Manager or the Assistant Operations Manager -
Shift shall possess a Senior Reactor Operators license.
Revision 22 13.1-4 October, 2021
Shift Engineer/Shift Technical Advisor (STA)
Provides continuous management support for all station activities.
Serves as an on-shift technical advisor to support the diagnosis, mitigation and termination of off-normal events. The Shift Technical Advisor (STA) provides the advisory technical support to the unit operations shift crew as described in the Technical Specifications.
Shift Manager The Shift Manager on duty reports to the Assistant Operations Manager and is responsible for the proper startup, operation, and shutdown of station equipment in compliance with the operating license, administrative controls, and operating instructions. In the absence of direct line supervision, the Shift Manager is authorized to act as the ultimate authority with regard to nuclear safety.
Unit Supervisor The Unit Supervisor(s) on duty reports to the on duty Shift Manager and are responsible for the proper startup, operation, and shutdown of equipment, supervise the preparation of various logs and reports, direct all physical operations work, and provide on-the-job training of operating personnel.
Reactor Operator The Reactor Operator on duty reports to the Unit Supervisor and is responsible for directing the activities of the non-licensed shift employees, including plant operators and others who may be assigned for special tasks to insure proper operation and monitoring of plant systems and equipment.
Revision 22 13.1-5 October, 2021
Plant Operator The Plant Operator is the senior non-exempt operating person on each shift who performs routine inspections and operations on plant equipment outside the control room at the direction of the on-duty Reactor Operator, Unit Supervisor, or Shift Manager.
Manager, Maintenance The Manager, Maintenance, reports to the General Plant Manager, and is responsible for directing maintenance repairs, overhauls, and preventive maintenance activities on plant equipment. The scope of plant equipment includes mechanical, electrical, instrument and control systems, various micro-processor-based equipment, and control of tools and measuring and test equipment. This position is also responsible for the Fix-It-Now (FIN) process, maintenance services, and nuclear work planning.
Manager, Radiation Protection and Chemistry The Manager, Radiation Protection and Chemistry, reports to the General Plant Manager, and is responsible for providing radiation protection and chemistry functions in support of operating and maintaining the plant.
Radiological functions include radiological control coverage, implementation of ALARA and related analyses, providing direction and support for all radioactive waste shipping, radioactive waste management, maintaining the dosimetry and respiratory protection equipment, and providing radiation program technical support. Chemistry functions include administration, implementation, and maintenance of the chemistry and environmental programs ensuring compliance with state and federal requirements, control of radioactive effluents, implementation of the radiological and non-radiological environmental monitoring programs, maintaining a qualified radiochemical program, air and water permitting and reporting, and control and disposal of non-radioactive hazardous waste.
Revision 22 13.1-6 October, 2021
The Manager is designated as the Radiation Protection Manager as specified in NRC <Regulatory Guide 1.8>. If the Manager does not meet the Radiation Protection Manager qualifications specified in NRC
<Regulatory Guide 1.8>, an individual who meets the Radiation Protection Manager qualifications specified in NRC <Regulatory Guide 1.8> shall be designated as the technical specification qualified Radiation Protection Manager, who shall be responsible for all of the aforementioned radiation protection-related activities, including reviewing, approving, and signing/countersigning all associated documents.
Radiation Protection Technician Responsible for providing radiological support of unit power operations and outage activities through implementation of the Radiation Protection Program.
Manager, Nuclear Work Control The Manager, Nuclear Work Control, reports to the General Plant Manager, and is responsible for coordination, schedule development, and execution of all online work activities, maintenance, and planned and forced outages.
Manager, Design Engineering The Manager, Design Engineering, reports to the Director, Site Engineering, and is responsible for maintaining the station design basis. This includes plant modifications, plant design support, design basis and transient analysis, and technical support of plant systems and operations. The Manager shall utilize fleet engineering resources when necessary in support of design engineering activities.
Revision 22 13.1-7 October, 2021
Manager, Strategic Engineering The Manager, Strategic Engineering, reports to the Director, Site Engineering, and is responsible for the health of plant systems and components, providing technical support and engineering services, and recommending and sponsoring system improvements to optimize availability and reliability. This position is also responsible for reactor engineering and ensuring engineering programs are effective through interface with site and fleet engineering resources. The Manager shall utilize fleet engineering resources when necessary in support of strategic engineering activities.
Manager, Site Projects The Manager, Site Projects, reports to the Director, Site Engineering, and is responsible for the direction, control, and overall supervision of projects implemented at the station.
Manager, Training The Manager, Training, reports to the Director, Performance Improvement, and is responsible for providing direction, control, and overall supervision of all accredited training of personnel required by regulations.
Manager, Regulatory Compliance and Emergency Response The Manager, Regulatory Compliance and Emergency Response, reports to the Director, Performance Improvement, and is responsible for regulatory compliance activities, managing the Corrective Action Program, and maintenance of the Emergency Plan in accordance with state and federal regulations, including maintaining an effective onsite emergency response organization and effective relationships with offsite organizations that support the Emergency Plan.
Revision 22 13.1-8 October, 2021
Manager, Site Protection The Manager, Site Protection, reports to the Director, Performance Improvement, and is responsible for implementation of the Physical Security Plan and the direction and maintenance of an effective Site Protection organization.
Manager, Sourcing The Manager, Sourcing, reports to the Director, Performance Improvement, and is responsible for the procurement of goods and services, inventory management, and warehouse operations, including the receipt, storage, and issuance of materials, parts, and components to support plant operations and maintenance.
Plant Operations Review Committee (PORC)
Provides recommendations to the General Plant Manager on matters relating to nuclear safety. <Section 13.4.1> describes onsite review functions.
Revision 22 13.1-9 October, 2021
13.2 TRAINING PROGRAM 13.2.1 PERRY STAFF TRAINING PROGRAM The Perry Staff Training Program has been developed and implemented to:
- a. Ensure that personnel are effectively trained and qualified to safely operate and maintain the plant throughout its design life.
- b. Meet or exceed all regulatory requirements.
- c. Meet or exceed current INPO Training Guidelines.
Development of the training program outlined in this section will meet or exceed the requirements of <10 CFR 50>, <10 CFR 55> and other applicable industry standards. The training programs are developed using a systematic approach to training in that the specific objectives for all levels of instruction outlined in this section are derived from the job analysis for the applicable position. Additionally, student and supervisor feedback and on-the-job performance are also factored into applicable training program content.
The following training programs at Perry are accredited by INPO:
- a. Non-licensed Operator
- b. Reactor Operator
- c. Senior Reactor Operator
- d. Shift Manager
- e. Shift Engineer/Shift Technical Advisor
- f. Instrument & Control Technician and Supervisor
- g. Electrical Maintenance Personnel and Supervisor
- h. Mechanical Maintenance Personnel and Supervisor
- i. Chemistry Technician Revision 20 13.2-1 October, 2017
- j. Radiation Protection Technician
- k. Engineering Personnel
- l. Continuing Training for Licensed Personnel.
Perry maintains these training programs according to INPO Training Guidelines.
The Training Manager is responsible for the overall program. He designates qualified individuals to prepare learning objectives, instructor guides, lectures, tests, and examinations, and to provide performance evaluations for various aspects of the training program.
The detailed program description which follows is divided into three sections relating to the categories of personnel being trained: (1) Licensed Personnel, (2) Non-Licensed Technical Personnel and (3) Plant Access Training Programs.
The programs outlined below are specifically written for Perry Unit 1.
The specific arrangement or structure of the training provided may vary from this section based upon feedback and changing requirements.
Revision 20 13.2-1a October, 2017
13.2.2 LICENSED OPERATOR TRAINING PROGRAM The Licensed Operator Training Program has been developed to ensure that the individuals who operate the controls of the Perry Plant are competent to do so. The Licensed Operator Training Program is taught at the Senior Reactor Operator level and provides training in job-related knowledge requirements and skills.
Written and/or oral examinations are periodically given to students during the completion of the Licensed Operator Training Program. These examinations are given to evaluate student performance and to assess the level of comprehension of the course material.
13.2.2.1 Initial Training 13.2.2.1.1 Academic Refresher Training License candidates will receive classroom training in subjects covering science and engineering (such as heat transfer, fluid flow, thermodynamics).
13.2.2.1.2 Systems Operation Training License candidates will receive classroom instruction on Nuclear Steam Supply Systems (NSSS) and selected Balance of Plant (BOP) Systems important to safety over which the licensed control room operator has control or cognizance. This training also includes instruction on the normal operating procedures for the operation of the plant.
13.2.2.1.3 Simulator Training License candidates participate in a Simulator Training Course which prepares the individual to proficiently conduct routine evolutions and carry out abnormal/emergency actions from the control room. The Revision 12 13.2-2 January, 2003
simulator utilized in this program will have operating characteristics and control room design similar to those of the Perry Plant.
The simulator training courses prepare the student to operate Perry under normal conditions as well as provide extensive training in transients and casualty response.
Exercises involving multiple failures and/or operator error are also included. Utilization of applicable plant procedures and Technical Specifications during training exercises are emphasized.
Students are evaluated on a periodic basis and provided feedback in order to improve their performance. A final review and evaluation will be given as described in <Section 13.2.2.1.5.2>.
13.2.2.1.4 Operating Practices Training License candidates gain experience in plant operation and casualty response through a combination of in-plant, on-shift training and classroom presentations/discussions. This training includes Administrative Requirements Training, Plant Operation and Casualty Response Training.
13.2.2.1.4.1 Administrative Requirements Training License candidates receive training in the plant administrative procedures, policies, practices, and Technical Specifications which affect the licensed control room operator.
Revision 12 13.2-3 January, 2003
13.2.2.1.4.2 Plant Operation and Casualty Response Training License candidates and applicable Operations Management Staff receive classroom training on the following subjects:
- a. Abnormal and emergency operating procedures.
- b. Plant transients and accident analysis.
- c. Recognition and mitigation of the consequences of core damage.
- d. Site Emergency Plan including applicable Emergency Implementing Instructions.
13.2.2.1.4.3 On-The-Job Training License candidates spend time on shift in a training status, with no concurrent duties, under the supervision and guidance of a licensed reactor operator or senior reactor operator, as appropriate. The intent of this training period is for each candidate to gain experience in the routine operation of the nuclear power plant. During this period, the candidate will perform duties of the licensed reactor operator or senior reactor operator, as appropriate, including reactivity manipulations.
These duties will be evaluated by the licensed operator or senior operator to ensure the duties are performed correctly and in accordance with approved procedures and in other standards which may be promulgated. A Qual Card will be used to verify progress and correct performance of the duties.
13.2.2.1.5 License Examination Preparation Prior to the proposed NRC examination date, each license candidates progress in the training program is evaluated to assess the candidates Revision 12 13.2-4 January, 2003
ability to safely and competently operate the plant. The license examination preparation period includes a simulator refresher period (when required), an Audit examination and a Management Board review.
13.2.2.1.5.1 Audit Examination License candidates are administered NRC-style, comprehensive, written, oral, and performance examinations. The standards for these examinations are those in current use by the NRC at the time of the examination. The intent of these examinations is to determine the individuals ability to operate the plant in a safe and competent manner. If the candidates performance is unsatisfactory, the candidates weaknesses are evaluated, and a remedial training program may be developed to correct those weaknesses. Alternatively, the candidate will not be allowed to take the NRC license examination.
13.2.2.1.5.2 Management Board Prior to the actual NRC license examination, the candidates overall performance in the Licensed Operator Training Program is reviewed by a Management Board. The Management Board verifies that the NRC examination prerequisites are satisfied, that the operator training program has been completed, and that the candidate can safely operate the plant. If the Management Board determines that the candidates performance is satisfactory and that the candidate meets all prerequisites, the candidate will be recommended for NRC License Examination to the Site Vice President, Perry who is responsible for certifying the competency of each license candidate.
13.2.2.1.6 SRO Upgrade Candidates for Senior Operator who currently hold an Operators license on PNPP will complete an SRO Upgrade Training Program to upgrade their knowledge and skills to those required of Senior Operators.
Revision 20 13.2-5 October, 2017
13.2.2.1.7 Direct Senior Operator Training Program Direct Senior Operators (those who have not previously held an operators license) will complete a program as developed and implemented in accordance with the Training Manual.
13.2.2.1.8 Licensed Operator Training Program Instructors Instructors for the Licensed Operator Training Program who teach systems, integrated plant response, transients, and simulator courses to license candidates or NRC licensed personnel shall either complete an instructor certification program or be a guest presenter in accordance with the Training Manual.
13.2.2.1.9 Previous Nuclear Training An individuals participation in nuclear training programs at this or other facilities or previous education that satisfied the intent of the program outlined in <Section 13.2.2.1> may be substituted for portions of the training outlined for reactor operator and senior reactor operator candidates. The individuals successful completion of these other training programs will be verified prior to excusing the individual from segments of the program described in <Section 13.2.2.1>.
In cases where objective evidence is not available to document completion of other training programs, procedures have been established to verify the individuals knowledge through written or oral examinations.
Substitutions of previous training will not be authorized for special PNPP equipment operations training (e.g., Emergency Diesel Generator Operations Training) unless such training is on identical equipment.
13.2.2.1.10 Diesel Generator Training for Licensed and Non-Licensed Personnel Revision 14 13.2-6 October, 2005
13.2.2.1.10.1 Diesel Generator Operation Training All licensed and non-licensed operators responsible for the safe operation of the emergency diesel generators shall successfully complete a course covering the operation of the emergency diesel generators.
13.2.2.1.10.2 Diesel Generator Maintenance Training Maintenance personnel responsible for the performance of maintenance on the emergency diesel generator shall successfully complete a course covering the maintenance repair and troubleshooting of the emergency diesel generator.
13.2.2.2 Retraining and Requalification Programs 13.2.2.2.1 Licensed Operator Requalification Training Program A continuing requalification training program for licensed operators and senior operators has been implemented in accordance with <10 CFR 55>.
Licensed operators and senior operators are required to participate in the requalification program as described in this section. The Licensed Operator Requalification Program consists of regularly scheduled lectures, simulator training, examinations, and accelerated requalification (when necessary). Each of these elements is discussed in the paragraphs below.
13.2.2.2.1.1 Regularly Scheduled Lectures The Requalification Program includes preplanned lectures given throughout the requalification period. Emphasis shall be placed on those areas where plant operating experience, industry experience, design or procedure change, or Operator and Senior Operator written examinations indicate that an increase in scope and depth of coverage is needed.
Revision 12 13.2-7 January, 2003
13.2.2.2.1.2 Simulator Training Licensed Operators and Senior Operators will participate in a preplanned Simulator Training Program during the period of the Requalification Program.
13.2.2.2.1.3 Examinations and Evaluations Requalification examinations are given to each licensed operator and senior operator. A comprehensive written examination is administered at least every two years, while the operating test (typically consisting of a simulator evaluation and job performance measures) is given annually.
The results of each of these examinations will be determined using the NRC criteria prevailing at the time of the particular examination.
13.2.2.2.1.4 Accelerated Requalification Individuals who perform unsatisfactorily on the requalification examinations described in <Section 13.2.2.2.1.3> will not be allowed to perform licensed duties until they successfully complete an accelerated requalification program as described in the Training Manual.
Revision 14 13.2-8 October, 2005
13.2.2.2.1.5 Requalification of Inactive Operators and Senior Operators Any Licensed Operator or Licensed Senior Operator who, for any reason, has not been actively performing the functions of an Operator or Senior Operator for a calendar quarter or longer will, prior to resuming activities for which that individual is licensed, demonstrate knowledge of facility operation. This demonstration will be accomplished by having a qualified member of the station management verify that:
- a. The qualifications and status of the licensee are current and valid.
- b. The licensee has completed a minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of shift functions under the direction of a Licensed Operator or Senior Operator as appropriate. During this time, a complete tour of the plant and all required shift turnover procedures will be completed.
- c. For Senior Operators limited to fuel handling, one entire shift must be completed under the direction of a Senior Operator or Senior Operator limited to fuel handling.
13.2.3 TRAINING PROGRAMS FOR NON-LICENSED PERSONNEL Training programs for management, supervisory, professional, and technical personnel not requiring NRC licenses are provided. Trainee performance in these programs will be evaluated to ensure that the trainees have obtained an adequate knowledge of the subject matter. The individual programs are evaluated to ensure they are providing the training necessary for the personnel to fulfill their job functions.
Revision 14 13.2-9 October, 2005
Training for individuals in these categories is based upon the individuals background, experience, ability, and the position duties and responsibilities. This training is accomplished through a combination of vendor-supplied courses and courses developed and instructed by the PNPP Training Staff. In addition, Non-Licensed Technical Personnel will participate in a Continuing Training Program applicable to their job certification.
13.2.3.1 Non-Licensed Operator Training Program The Non-Licensed Operator Training Program contains training programs for the various non-licensed operator positions. The initial training program is an entry level program, and is designed to lead individuals to ultimately become Perry Plant Operators (PPO). The training typically consists of classroom presentations on power plant fundamentals, power plant theory, and systems. The program also includes on-shift training in the plant.
13.2.3.2 Shift Engineer (Shift Technical Advisor) (STA) Training Program The Shift Engineer Training Program is designed to ensure that individuals assigned to this position are prepared to make evaluations concerning plant safety and provide technical assistance to the operating shift. The Shift Engineer Training Program will be taught to the Senior Operator Level and may contain the elements described in
<Section 13.2.2.1.2>, <Section 13.2.2.1.3>, and <Section 13.2.2.1.4>.
Additionally, Shift Engineers receive training that relates to their function during power operation and outages. This typically covers the process computer, reactor behavior, thermal hydraulics, Technical Specifications, core thermal limit calculations, core reactivity, and the procedures that directly involve the functions of the Shift Engineer.
Revision 12 13.2-10 January, 2003
13.2.3.3 Instrument and Control Technician Training Programs The Instrument and Control Technician Training Program consists of classroom presentations, laboratory training and on-the-job training.
The classroom presentations include fundamentals relevant to the discipline, I&C procedures training and discussion of Technical Specifications. The Instrumentation and Control Technician Training Program is supplemented, when required, by special I&C courses (such as Diesel Generators, RCIS, Nuclear Instrumentation) presented by equipment vendors.
13.2.3.4 Maintenance Personnel Training Program Training programs for Maintenance Technicians (Mechanical and Electrical) are provided to ensure that these technicians have or acquire appropriate job-related knowledge and skills. Each training program (Mechanical and Electrical) consists of classroom presentations, laboratory training and on-the-job training. The classroom presentations include fundamentals relevant to the discipline, maintenance procedures training and discussion of Technical Specifications. The Maintenance Personnel Training Programs are supplemented, when required, by special maintenance courses (e.g.,
emergency diesel generator maintenance, control rod drive maintenance, SRVs, MSIVs, Reactor Recirc Pump Seals) presented by equipment vendors and/or Training Staff.
13.2.3.5 Chemistry Training Program The Chemistry Training Program consists of classroom lectures and on-the-job training. The classroom training typically includes theory, practical application, procedures, applicable Technical Specifications, and selected PNPP systems training. The Chemistry Training Program is supplemented, when required, by courses presented by equipment vendors.
Revision 22 13.2-11 October, 2021
13.2.3.6 Radiation Protection Technician Training Program The Radiation Protection Technician Training Program consists of classroom lectures and on-the-job training. The classroom training typically includes health physics technology, theory procedures, applicable Technical Specifications, introduction to Perry systems, and concepts of ALARA. The Radiation Protection Training Program is supplemented, when required, by courses presented by equipment vendors.
13.2.3.7 Engineering Support Personnel Training Program The Engineering Support personnel Training Program consists of classroom lectures, simulator training, and position-specific on-the-job training.
The curriculum provides both a broad-based education in nuclear fundamentals and position-specific training necessary for engineering staff enrolled in the program to be able to perform their jobs competently. The Engineering Support Personnel Training Program is supplemented, when required, with courses presented by vendors.
13.2.3.8 Management Supervisory Training Plant management will attend supervisory courses applicable for the job position assigned.
13.2.4 PLANT ACCESS TRAINING The Plant Access Training Program provides individuals with an indoctrination in the general requirements necessary to gain access to the plant. This program enhances employee effectiveness and safety by covering plant organization, security, safety regulations, radiation fundamentals, and the emergency plan. All individuals who require unescorted access to the protected area of Perry must complete Plant Access Training.
Revision 12 13.2-12 January, 2003
In addition to Plant Access Training for gate access, Radiation Worker Training is provided for employees who will work in radiation areas.
This course covers basic radiation theory, exposure controls, safe work practices, and workers rights and responsibilities. Specialized training is also provided for individuals who will wear respiratory equipment in the performance of their jobs.
13.2.5 FIRE PROTECTION TRAINING The primary purpose of fire protection training is to develop a group of plant employees knowledgeable in fire prevention, fire fighting techniques and equipment, first aid procedures, and emergency response who are trained and equipped to function as a team for the fighting of fires. The plant fire protection organization, consisting of a fire prevention staff, fire brigade and on-shift personnel, is intended to be self-sufficient with respect to fire fighting activities. A fire brigade consisting of a brigade leader with either a reactor operators license or equivalent knowledge of plant safety-related systems (simulator certification with plant systems familiarity) and four other personnel will be available on all shifts. Two of the four other personnel shall have sufficient training in or knowledge of plant safety-related systems to understand the effect of fire and fire suppressants on safe shutdown capability. Fire brigade members will have no duties during a fire except those directly related to manual fire fighting.
Prior to assignment to the fire brigade, and annually thereafter, each member will receive a physical examination that will ensure that no physical conditions exist that would prevent proper performance of strenuous fire fighting activities.
Revision 12 13.2-13 January, 2003
The fire brigade will be equipped with sufficient quantities of personal protective equipment, manual suppression equipment and other equipment necessary for effective fire fighting. Equipment will meet criteria stipulated in <10 CFR 50, Appendix R>, Section H.
13.2.5.1 Fire Brigade Training (X8)
The fire brigade training program provides for classroom training, practice sessions and drills and meets the criteria stipulated in
<10 CFR 50, Appendix R>,Section III.I.
The initial fire brigade receives classroom training in the fundamentals of fire fighting, fire prevention, fire protection equipment, fire brigade organization, hazard recognition, implementing procedures, and individual responsibilities.
A periodic training program will be conducted for all designated brigade members and replacements, on a regularly scheduled basis in conjunction with operation periodic training. The periodic training program will be repeated on a two-year cycle and includes instruction on:
- a. The plant fire brigade organization and plan of implementation, including individual responsibilities and specific response procedures.
- b. Basic fire fighting principles such as the chemistry of fire, first aid and rescue procedures, forcible entry methods and salvage techniques.
- c. Identification of the location of various fire fighting equipment throughout the plant, access and egress routes, latest plant modifications that affect fire protection, and current fire fighting procedures.
Revision 12 13.2-14 January, 2003
- d. The proper use of available fire fighting equipment including both permanent and portable systems such as deluge systems, detection and alarm systems, sprinklers, fire hoses, extinguishers, ladders, communication, lighting, ventilation, and emergency breathing equipment.
- e. Identification of the fire hazards and associated types of fires that could occur in the plant, probable locations and the correct methods of fighting each type of fire. Included are electrical fires, cable tray fires, flammable gas fires, flammable liquid fires, record file fires, and other ordinary combustible fires.
Fire brigade leaders will be provided additional training in directing and coordinating fire fighting activities. The NFPA Fire Protection Handbook, NFPA National Fire Codes and others are used as references for conducting all training activities. Classroom training is provided by qualified individuals knowledgeable and experienced in fire fighting and in using the types of equipment available in a nuclear plant. Members of the fire protection staff and fire brigade leaders are responsible for conducting this training.
Practice sessions are held for fire brigade members annually. These sessions will be utilized to provide instruction in the proper methods of fighting various types of fires and will include practical exercises in extinguishing actual fires. During these exercises, brigade members will don protective equipment including self-contained breathing apparatus.
Fire drills are conducted in the plant so that the fire brigade can practice as a team. Drills are conducted at regular intervals, that will not exceed three months for each fire brigade.
Fire brigade drills shall be performed quarterly per shift with intervening intervals no more than five months nor less than one month Revision 12 13.2-15 January, 2003
for any given shift. At least one drill per year for each fire brigade is unannounced. Drills are preplanned to provide experience for each team in fighting fires in various areas of the plant with emphasis on safety-related areas containing significant hazards.
The drills are selected to simulate as realistically as practical the size, type and location of potential fires which could occur in the plant and to provide as much experience as possible in the use of the various fire fighting equipment available. Each drill is critiqued to evaluate the entire brigade response and how well the objectives were met. Fire alarm response time, leaders direction of the effort, each individual members response, selection, placement, and use of equipment are assessed by the critique.
13.2.5.2 Fire Protection Staff Training Training for the fire protection staff members includes courses in design and maintenance of fire detection, suppression and extinguishing systems, fire prevention and manual fire fighting techniques, and procedures for plant personnel and the fire brigade.
13.2.5.3 On-Shift Personnel Sufficient on-shift personnel to meet the requirements of <10 CFR 50, Appendix R> will receive fire fighting training. These on-shift personnel will be available and trained to assist members of the fire brigade as necessary.
13.2.5.4 Offsite Fire Department Public fire department response is limited to assistance outside the restricted (protected) area or as additional manpower under the direct supervision and control of responsible plant personnel inside the restricted area.
Revision 12 13.2-16 January, 2003
Training sessions for these personnel will be available periodically to cover basic radiation principles, typical radiation hazards, precautions for fires involving radioactive materials, station layout, fire hydrant locations outside the restricted area, basic emergency plans, and plant security procedures.
Revision 12 13.2-17 January, 2003
13.3 EMERGENCY PLANNING A detailed emergency plan document describing the plans for coping with emergency situations is provided in the Emergency Plan for the Perry Nuclear Power Plant (Reference 1). The Emergency Plans conformance to applicable codes, Regulatory Guides and standards is discussed in
<Section 2.4.1> of the Plan.
The Plan has as its objectives the protection of the health and safety of the public, including Perry employees, and the limitation of damage to facilities or property in the event of an accident occurring at the Perry Nuclear Power Plant.
The Emergency Plan sets forth the objectives and the methods for achieving them. It describes the related emergency organization, including assignments of authority and responsibility. The Plan provides for the following activities: detecting and evaluating emergency conditions; establishing protective action levels and protective measures when such levels are exceeded; communications; postaccident reentry and recovery; liaison with offsite support groups, including federal, state and local governmental authorities; document review and control; periodic emergency preparedness assessment; drills and training of the participating personnel.
The Plan provides that detailed instructions be prepared for dealing with a spectrum of incidents. It also provides the bases for actions to be taken in providing for decontamination, administering of first aid and for diagnosis and treatment of persons injured as a result of a nuclear incident occurring at Perry.
Detailed implementing instructions for the Emergency Plan have been prepared for accomplishing appropriate emergency functions at Perry.
Revision 12 13.3-1 January, 2003
13.3.1 REFERENCE FOR SECTION 13.3
- 1. Emergency Plan for Perry Nuclear Power Plant.
Revision 12 13.3-2 January, 2003
13.4 REVIEW AND AUDIT A program for review, including in-plant and independent review, has been established to ensure that operation of Perry is in accordance with written procedures, instructions and license provisions which have been reviewed and approved by established authorities. This program provides for:
- a. Review of significant proposed plant changes, tests and procedures.
- b. Verification that reportable events, as defined in <10 CFR 50.73>,
are promptly investigated and corrected in a manner which reduces the probability of recurrence of such events.
- c. Detection of trends which may not be apparent to a day-to-day observer.
- d. Examination of plant operating characteristics, design and operating experience information that may indicate areas for improving plant safety.
Three organizations have been established to accomplish the review and audit function. Reviews at the plant operating level are the responsibility of the Plant Operations Review Committee (PORC).
Independent reviews are the responsibility of the Company Nuclear Review Board (CNRB) and the Oversight Department, which are independent of direct responsibility for plant operation.
A program for audits of activities affecting plant safety during the operational phase has also been established to verify that such activities are performed in accordance with company policy and rules, approved operating procedures, license provisions, and quality assurance requirements. Audits of plant operations will be administered and performed as discussed in USAR <Section 17.2>.
Revision 22 13.4-1 October, 2021
Guidance in the development of the review and audit programs was derived from <Regulatory Guide 1.33>.
13.4.1 PLANT OPERATIONS REVIEW COMMITTEE The review functions of the on-site review organization, which is known as the Plant Operations Review Committee (PORC), are described in ANSI N18.7-1976, which is committed to as delineated in the Quality Assurance Program Manual (QAPM). The specific details related to the activities of PORC are set forth in administrative procedures.
13.4.1.1 (Deleted) 13.4.1.2 (Deleted) 13.4.1.3 (Deleted) 13.4.1.4 (Deleted) 13.4.2 COMPANY NUCLEAR REVIEW BOARD The description, responsibilities, and functions of the independent review organization, which is known as the Company Nuclear Review Board (CNRB), are described in ANSI N18.7-1976, which is committed to as delineated in the Quality Assurance Program Manual (QAPM). The specific details related to the activities of CNRB are set forth in administrative procedures.
13.4.2.1 (Deleted) 13.4.2.2 (Deleted) 13.4.2.3 (Deleted)
Revision 22 13.4-2 October, 2021
13.4.2.4 (Deleted) 13.4.3 (Deleted) 13.4.4 OVERSIGHT DEPARTMENT The Oversight Department shall conduct audits of the Perry operational phase activities as described in USAR <Section 17.2>. Audit frequencies of specific safety-related activities as listed in USAR <Section 17.2>
are based on the safety significance of each activity, and are consistent with <Regulatory Guide 1.33>. Written reports of such audits shall be directed to the CNRB and appropriate management for review and assessment.
Revision 22 13.4-3 October, 2021
13.5 PLANT PROCEDURES The safe, efficient and reliable operation of the Perry Nuclear Power Plant is dependent upon the knowledge and performance of trained and qualified personnel and upon effective management and direction of these personnel. A series of documents, collectively entitled the Perry Operations Manual, clearly delineates the methods used to train, manage and direct Perry personnel. This manual is prepared to document and communicate approved methods for complying with corporate commitments to the Technical Specifications, Operational Quality Assurance Program, Updated Safety Analysis Report, and <Regulatory Guide 1.33>.
The Perry Operations Manual is established as a complete management document addressing all aspects of plant management including administrative, technical, quality, safety, personnel, and environmental.
Individual procedures and instructions shall be prepared and reviewed by plant or consultant personnel knowledgeable in the subject matter to be presented. When required by <10 CFR 50.59>, each review shall include a determination of whether or not an unreviewed safety question is involved.
All plant procedures and instructions are approved by procedurally authorized individuals.
Procedures and instructions shall be prepared, reviewed, and approved as described in the Nuclear Operating and Plant Administrative Procedures.
Revision 16 13.5-1 October, 2009
13.5.1 PROCEDURES AND INSTRUCTIONS 13.5.1.1 Conformance with <Regulatory Guide 1.33>
Plant procedures and instructions shall be prepared to address the applicable systems, activities and subjects identified in Appendix A of
<Regulatory Guide 1.33>, Quality Assurance Program Requirements (Operation), and shall be contained in the Perry Operations Manual.
Specific systems, activities and subjects identified in Appendix A may be deleted, combined or separated, as appropriate, to conform with plant configuration and the procedures for the Perry Operations Manual.
Procedures and instructions shall address all aspects of subject activities including administrative, technical and quality.
13.5.1.2 Preparation of Procedures and Instructions Safety-related procedures and instructions shall be prepared in accordance with the Perry Operations Manual. All safety-related activities performed by the Perry departments shall be performed in accordance with approved, written procedures or instructions.
Procedures and instructions required for fuel loading were written and approved for use prior to initial fuel loading. Procedures and instructions which address plant operation under normal and emergency conditions were written, to the extent practical, for use during the initial test program to familiarize plant operating and technical personnel with the operation of the plant, to verify the adequacy of content and to provide sufficient time, prior to initial fuel loading, for any necessary revisions resulting from the initial test program.
Responsibility for preparation, review, approval and implementation of the Operations Manual documents shall be addressed in applicable Plant Administrative or Nuclear Operating Procedures.
Revision 16 13.5-2 October, 2009
Nuclear Operating Procedures (NOPs), which can be administrative or technical, Plant Administrative Procedures (PAPs), and Instructions shall be independently reviewed prior to approval and implemented by plant staff personnel knowledgeable in the requirements applicable to the activity being described.
Revision 16 13.5-2a October, 2009
Interdepartmental activities are described in plant procedures and instructions. These documents define the interface responsibilities of departments involved in operational activities.
Subsequent distribution or alteration shall be controlled in accordance with Nuclear Operating and Plant Administrative Procedures. Proposed changes which conflict with the intent of the operating license shall not be made without prior review of the PORC and authorization from the Company Nuclear Review Board and the Nuclear Regulatory Commission as required by existing regulations.
13.5.1.3 Procedures PAPs and NOPs are the top level documents within the Perry Operations Manual and delineate the quality assurance policies and controls which implement the Perry Operational Quality Assurance Program. They define department, section and unit responsibilities; assign authority to the section and unit supervisors; and, in most cases, address activities which involve two or more Perry department sections and/or units.
Revision 16 13.5-3 October, 2009
PAPs and/or NOPs shall address such subjects as:
- a. Standing orders to operations Shift Managers and personnel including proper shift relief and turnover procedures.
- b. Authority and responsibilities of reactor operators and senior reactor operators including succession in the control room.
- c. Responsibility to meet licensed operator requirements as described in <10 CFR 50.54(i)>, <10 CFR 50.54(j)>, <10 CFR 50.54(k)>,
<10 CFR 50.54(l)>, and <10 CFR 50.54(m)>. The areas associated with the at the controls concept as discussed in the above articles of <10 CFR 50.54> and in the guidance in <Regulatory Guide 1.114> is shown in <Figure 13.5-1> as the Surveillance Area.
In the event of an emergency affecting the safety of operations, the operator at the controls may enter the Operations Area to verify receipt of an annunciator alarm or to initiate corrective actions depicted on <Figure 13.5-1>. In extreme emergencies, such as situations threatening the operators personal well being, or situations which require evacuation of the control room, relocation to the Remote Shutdown Panel will be allowed.
- d. Special orders of a temporary or self-canceling nature.
- e. Equipment, modification and maintenance control.
Revision 16 13.5-4 October, 2009
- f. Surveillance testing and scheduling.
- g. Logbook and signed checklist usage and control to assure staff knowledge of critical plant parameters and system status, availability and alignment.
- h. Temporary procedure issuance and control.
13.5.2 OPERATING AND MAINTENANCE INSTRUCTIONS 13.5.2.1 Operating Instructions Instructions described in this USAR Section are implemented primarily by operators or reflect operating personnel actions in the performance of their work.
Preparation and maintenance responsibilities of the following operating instructions are as follow:
Shared among the Operations, Radiation Protection, and Radwaste, Environmental, and Chemistry section heads - System Operating Instructions, Valve Lineups, and Alarm Response Instructions.
Operations section head - Electrical Lineups, Integrated Operating Instructions, Off Normal Instructions, Plant Emergency Instructions, Plant Rounds, and Perry Specific Technical Guidelines.
13.5.2.1.1 System Operating Instructions System Operating Instructions shall be written to provide guidance for operating the various plant systems. These instructions shall provide Revision 13 13.5-5 December, 2003
the operator with the steps necessary for safe startup, operation and shutdown of plant equipment and systems.
These instructions format shall provide for the instruction title, scope, precautions and limitations, prerequisites, startup, operation, shutdown, other operations, and references.
13.5.2.1.2 Electrical Lineups Electrical lineups shall be established to provide guidance in identifying the necessary electrical component positions required as prerequisite conditions for plant startup.
13.5.2.1.3 Valve Lineups Valve lineups shall be established to provide guidance in identifying the necessary valve positions required as prerequisite starting conditions for each system.
13.5.2.1.4 Integrated Operating Instructions Detailed operating instructions shall be written to provide operating personnel with step-by-step instructions for changing modes of operation. These instructions shall ensure the operator has information required to safely operate the plant from initial startup to power operation and return to a shutdown condition within the limits and conditions specified in the Technical Specifications and Operating License. These instructions shall reference other instructions or Revision 14 13.5-6 October, 2005
documents as required for changing modes. They shall contain check-off provisions for verifying various items as appropriate.
These instructions format shall provide for the instruction title, scope, precautions and limitations, prerequisites, and detailed procedural steps.
13.5.2.1.5 Off-Normal Instructions Off-Normal Instructions shall be prepared to address correction of off-normal plant conditions which, in themselves, do not constitute an actual emergency condition, but which could degenerate into an emergency condition if positive actions were not initiated.
These instructions format shall provide for the instruction title, symptoms, automatic actions, immediate operator actions, and subsequent actions.
13.5.2.1.6 Perry Specific Technical Guidelines Perry Specific Technical Guidelines (PSTG), shall be prepared as the Perry specific technical document which serves as the licensing basis for the plant Emergency Instructions. The PSTG is derived from the BWROG Emergency Procedure Guidelines (EPG) and includes plant specific deviations from the generic owners group guidance.
13.5.2.1.7 Emergency Operating Procedures Emergency Operating Procedures (EOPs) shall be prepared to ensure that the PSTGs evaluated actions are taken in response to emergency conditions or malfunctions. Revisions and changes to the EOPs are evaluated from a <10 CFR 50.59> aspect using the PSTG as their licensing basis. Changes to the EOPs that deviate from the PSTG require a 10 CFR 50.59 Review to be performed. These instructions shall provide Revision 15 13.5-7 October, 2007
symptom oriented guidance to the operators for reacting to emergency situations, as necessary, to either verify that the plant is in, or place the plant in, a safe condition with the minimum effect on the safety of the general public, site personnel or plant equipment.
These instructions format provides for the instruction title, scope, entry conditions and operator actions.
13.5.2.1.8 Plant Rounds Instructions Plant rounds shall be prepared to provide directions to monitor equipment operation, direct performance of actions in accordance with an approved procedure, or direct skill-of-the-craft tasks.
13.5.2.1.9 Startup Test Instructions These instructions have been canceled.
13.5.2.1.10 Alarm Response Instructions Alarm Response Instructions shall be prepared to provide operators with the necessary information to respond to actuation of all significant annunciator and alarm indications in the control room.
These instructions format shall provide for the instruction title, identity of the alarm, its panel location and setpoint, probable cause, automatic actions, immediate operator actions, and subsequent operator actions.
13.5.2.1.11 Temporary Instructions Temporary instructions may be issued to direct operations during testing or maintenance, to provide guidance in unusual situations not within the normal scope of operating instructions and to ensure orderly and uniform Revision 14 13.5-8 October, 2005
operation for short periods when the plant, a system or component is being operated in a manner not covered by existing documents. Temporary instructions shall also be prepared to address one time or infrequently performed tests or experiments not described in the USAR which might affect the safe operation of the plant. Each temporary instruction shall identify its period or condition of effectiveness. When appropriate, portions of temporary instructions may be included in revisions to permanent instructions before being canceled.
The format for temporary instructions shall be the same as that of an appropriate permanent instruction, depending on the use and circumstance involved.
13.5.2.2 Other Plans, Manuals, Descriptions, Procedures, and Instructions This section describes the remainder of the Perry Operations Manual, including procedures and instructions, and specific plans, manuals, descriptions, and plant data that management believes sufficiently important to address as part of the Perry Operations Manual.
13.5.2.2.1 Administrative Instructions Administrative Instructions shall be prepared to provide detailed instructions necessary to implement activities outlined in the various Plant Administrative Procedures.
13.5.2.2.2 Test Instructions Test Instructions shall be prepared to cover Technical Specification surveillances, inservice inspections and periodic test instructions. A master surveillance schedule shall identify responsibility for, and coordinate efforts for these instructions. The instructions shall Revision 13 13.5-9 December, 2003
address surveillance activities to be performed by plant personnel responsible for monitoring specific operations, instrument, maintenance, reactor engineering, chemistry and radiochemistry, radiation protection, and environmental activities or equipment. A Ten-Year Inservice Inspection Program Plan shall identify components subject to inservice inspections and establish a schedule for performance of the inspections for each 10 year inspection interval. A Pump and Valve Inservice Testing Program Plan shall identify pumps and valves subject to inservice testing and establish frequencies for performance of tests.
13.5.2.2.3 Instrument Calibration/Maintenance Instructions Instructions shall be prepared to provide guidance to plant calibration personnel in the performance of plant system, plant instrument and measuring and test equipment calibration and maintenance.
13.5.2.2.4 Maintenance Instructions Maintenance Instructions shall be prepared to provide maintenance personnel with a maintenance planning guide, as well as detailed instructions for general, preventive and corrective maintenance applicable to the electrical and mechanical activities. Preventive maintenance periodicities are established based on manufacturers recommendations, qualified personnel judgments and past experiences with similar equipment. The General Plant Manager is responsible for preparation and maintenance of this instruction type.
13.5.2.2.5 Material Control Instructions Stores and Material Control Instructions shall be prepared to address receiving, inspection, warehousing, storage, material and parts requisition and issue; including any special handling, storage or shipping requirements to be implemented.
Revision 20 13.5-10 October, 2017
13.5.2.2.6 Fuel and Technical Instructions Fuel and Technical Instructions shall be written to provide direction for performing reactor engineering activities, fuel and core analysis, application and usage of process and offline computers, special nuclear material accountability, refueling and related activities, and technical engineering activities.
13.5.2.2.7 Health Physics Instructions Plant Health Physics Instructions shall be written and included in the Perry Operations Manual. These instructions account for radioactive material and implement the radiation protection program described in
<Chapter 12>.
13.5.2.2.8 Chemistry Instructions Instructions to implement the Chemistry Program shall provide direction for laboratory techniques, reagent preparation, laboratory equipment calibration, obtaining samples, performing chemical and radiochemical analyses, and arriving at chemical and radiochemical determinations.
13.5.2.2.9 Radwaste Instructions Instructions shall be written to address liquid and solid radioactive waste management, radwaste system operation and alarm response actions.
These instructions shall provide appropriate plant personnel with details necessary to control radwaste discharge, handling, storage and shipping, and to determine the activity of packaged radwaste.
13.5.2.2.10 Training Manual Instructions shall be written to describe the training and qualification activities for the personnel described in <Section 13.2>.
Revision 14 13.5-11 October, 2005
13.5.2.2.11 Emergency Plan and Instructions The Emergency Plan and Instructions shall provide an orderly program for dealing with plant emergencies. Step-by-step methods shall be presented for evaluating emergency conditions. The individual and collective responses required to mitigate or terminate the emergency conditions will also be included. Instructions shall address actions to be taken by specific plant personnel in responding to Unusual Event, Alert, Site Area, and General Emergency situations.
The Perry Emergency Plan will be maintained as an individual document under separate cover.
13.5.2.2.12 Security Plans and Instructions The Security Plan, Security Personnel Training and Qualification Plan and Instructions shall be prepared to describe implementation and maintenance of the Security Plan discussed in <Section 13.6>. The instructions shall address routine administration, implementation, equipment inspections, maintenance and tests; and records as required to implement, maintain and document the security program.
The Security Plan, and the Security Personnel Training and Qualification Plan will be maintained under separate cover.
Revision 15 13.5-12 October, 2007
13.5.2.2.13 Fire Protection Instructions/Safety and Fire Instructions Fire Protection Instructions shall be prepared to provide plant personnel with pre-fire plans for specific types and locations of fires.
These may be based on characteristics of each specific location, including such things as type of equipment, layout, access, combustible materials, and available means of fire suppression. In addition, Safety and Fire Instructions shall be prepared to address the detailed instructions of the safety program and aspects of the Fire Protection Program which are not within the scope of <10 CFR 50, Appendix R>.
13.5.2.2.14 Plant Data Book A Plant Data Book shall be prepared and controlled to provide plant personnel with specific information and data such as tank capacity curves and equipment performance curves.
Revision 13 13.5-13 December, 2003
13.6 INDUSTRIAL SECURITY 13.6.1 SECURITY PLAN A Security Plan has been prepared which describes the comprehensive physical security program for the Perry Nuclear Power Plant. The plan was prepared in accordance with ANSI N.18.17-1973 to meet the intent of
<10 CFR 73> and <Regulatory Guide 1.17> 1973, which references ANSI N18.17 and GSA Specification W-A-00450 B(GSA-FSS).
The security plan contains a summary description of vehicle control measures that are required pursuant to <10 CFR 73.55(c)(7)> and
<10 CFR 73.55(c)(8)>.
Pursuant to provisions of <10 CFR 2.790(b)>, and <10 CFR 9.5>, this Security Plan will be filed separately and is exempt from public disclosure.
13.6.2 SECURITY ORGANIZATION The Director, Site Performance Improvement Department is responsible for the overall security at Perry. Reporting directly to the Director, Site Performance Improvement Department is the Manager, Site Protection Section who is responsible for administration of the Security Plan, including the selection and training of a security force that meets the requirements of <10 CFR 73, Appendix B> with respect to suitability, physical and mental qualification and training.
Revision 21 13.6-1 October, 2019
13.6.3 SECURITY PROCEDURES Detailed procedures have been prepared to cover implementation of the Security Plan including procedures for investigation, resolution and reporting of each security incident.
Revision 19 13.6-2 October, 2015