ML18053A739
| ML18053A739 | |
| Person / Time | |
|---|---|
| Site: | Lee  |
| Issue date: | 12/19/2017 |
| From: | Donahue J Duke Energy Carolinas |
| To: | Office of New Reactors |
| Hughes B | |
| References | |
| DUKE, DUKE.SUBMISSION.15, LEE.NP, LEE.NP.1 | |
| Download: ML18053A739 (88) | |
Text
UFSAR Table of Contents 1 Introduction and General Description of the Plant 2 Site Characteristics 3 Design of Structures, Components, Equipment and Systems 4 Reactor 5 Reactor Coolant System and Connected Systems 6 Engineered Safety Features 7 Instrumentation and Controls 8 Electric Power 9 Auxiliary Systems 10 Steam and Power Conversion 11 Radioactive Waste Management 12 Radiation Protection 13 Conduct of Operation 14 Initial Test Program 15 Accident Analyses 16 Technical Specifications 17 Quality Assurance 18 Human Factors Engineering 19 Probabilistic Risk Assessment UFSAR Formatting Legend Description Original Westinghouse AP1000 DCD Revision 19 content Departures from AP1000 DCD Revision 19 content Standard FSAR content Site-specific FSAR content Linked cross-references (chapters, appendices, sections, subsections, tables, figures, and references)
13.1 Organizational Structure ............................................................................. 13.1-1 13.1.1 Management and Technical Support Organization .................... 13.1-1 13.1.1.1 Design, Construction, and Operating Responsibilities ......................................................... 13.1-1 13.1.1.2 Provisions for Technical Support Functions .............. 13.1-2 13.1.1.3 Organizational Arrangement ..................................... 13.1-8 13.1.1.4 Qualifications of Technical Support Personnel ....... 13.1-14 13.1.2 Operating Organization ............................................................ 13.1-15 13.1.2.1 Plant Organization .................................................. 13.1-15 13.1.3 Qualifications of Nuclear Plant Personnel ................................ 13.1-25 13.1.3.1 Qualification Requirements ..................................... 13.1-25 13.1.3.2 Qualifications of Plant Personnel ............................ 13.1-25 13.1.4 Combined License Information Item ......................................... 13.1-25 13.1.5 References ............................................................................... 13.1-25 13.2 Training ....................................................................................................... 13.2-1 13.2.1 Licensed Operator Training ........................................................ 13.2-2 13.2.1.1 Licensed Operator Initial Training Program .............. 13.2-2 13.2.1.2 Continuing Training for Licensed Personnel ............. 13.2-2 13.2.2 Training for Positions Listed in 10 CFR 50.120 .......................... 13.2-3 13.2.2.1 Non-Licensed Operator (NLO) Initial Training .......... 13.2-3 13.2.2.2 Shift Manager Initial Training .................................... 13.2-3 13.2.2.3 Shift Technical Advisor Initial Training Program ....... 13.2-3 13.2.2.4 Instrumentation and Control (I&C) Technician Initial Training ............................................................ 13.2-4 13.2.2.5 Electrical Maintenance Initial Training Program ........ 13.2-4 13.2.2.6 Mechanical Maintenance Initial Training Program .... 13.2-4 13.2.2.7 Radiological Protection Technician Initial Training ... 13.2-5 13.2.2.8 Chemistry Technician Initial Training ........................ 13.2-5 13.2.2.9 Engineering Personnel Initial Training ...................... 13.2-5 13.2.2.10 Continuing Training for Personnel Listed in 10 CFR 50.120 .......................................................... 13.2-6 13.2.3 General Employee Training (GET) Program .............................. 13.2-6 13.2.3.1 Plant Access Training ............................................... 13.2-6 13.2.3.2 Radiation Worker Training Program ......................... 13.2-6 13.2.3.3 General Employee Requalification Training .............. 13.2-7 13.2.4 Selected Other Training Programs ............................................. 13.2-7 13.2.4.1 Fire Protection Training ............................................. 13.2-7 13.2.4.2 Emergency Plan Training Program ........................... 13.2-7 13.2.4.3 Physical Security Training Program .......................... 13.2-7 13.2.4.4 Station Management Training Program .................... 13.2-7 13.2.5 Training Effectiveness Evaluation Program ................................ 13.2-8 13.2.5.1 Supervisory Review for Training Effectiveness ......... 13.2-8 13.2.5.2 Trainee Review of Training Effectiveness ................. 13.2-8 13.2.5.3 Review for Effectiveness of Instructional Techniques and Materials ......................................... 13.2-8 13.2.6 Combined License Information Item ........................................... 13.2-8 13.2.7 References ................................................................................. 13.2-8 13-i Revision 1
13.2A.1 Licensed Operator Experience Requirements Prior To Commercial Operation ..............................................................13.2A-1 13.2A.2 Crew Experience Requirements during First Year of Operation ..................................................................................13.2A-2 13.2A.3 Conduct of On-the-Job Training (OJT) .....................................13.2A-3 13.2A.4 Use of Part-Task/Limited Scope Simulators .............................13.2A-3 13.2A.5 Licensed Operator Continuing Training ....................................13.2A-3 13.2A.6 Cold Licensing Process Applicability and Termination .............13.2A-3 13.2A.7 Initial Licensed Operator Examination Schedule ......................13.2A-4 13.2A.8 References ...............................................................................13.2A-4 13.3 Emergency Planning ................................................................................... 13.3-1 13.3.1 Combined License Information Item ........................................... 13.3-1 13.4 Operational Programs ................................................................................. 13.4-1 13.4.1 Combined License Information Item ........................................... 13.4-1 13.4.2 References ................................................................................. 13.4-1 13.5 Plant Procedures ......................................................................................... 13.5-1 13.5.1 Administrative Procedures .......................................................... 13.5-2 13.5.2 Operating and Maintenance Procedures .................................... 13.5-3 13.5.2.1 Operating and Emergency Operating Procedures .... 13.5-3 13.5.2.2 Maintenance and Other Operating Procedures ........ 13.5-4 13.5.3 Combined License Information Item ........................................... 13.5-6 13.5.4 References ................................................................................. 13.5-6 13.6 Security ....................................................................................................... 13.6-1 13.6.1 Combined License Information Item ........................................... 13.6-1 13.6.2 References ................................................................................. 13.6-1 13.7 Fitness for Duty ............................................................................................ 13.7-1 13.7.1 References ................................................................................. 13.7-2 PENDIX 13AA CONSTRUCTION-RELATED ORGANIZATION ................................. 13AA-1 13-ii Revision 1
1-202 Minimum On-Duty Operations Shift Organization for Two-Unit Plant ....... 13.1-30 2A-201 Comparison of Hot and Cold License Guidance ........................................13.2A-5 2A-202 Illustration of Cold Licensing Plan by Candidate Type ................................13.2A-9 2A-203 Cumulative Nuclear Power Plant Operating Crew Experience Equivalencies ............................................................................................13.2A-10 4-201 Operational Programs Required by NRC Regulations ................................ 13.4-2 5-201 Pre-COL Phase Administrative Programs and Procedures ........................ 13.5-8 13-iii Revision 1
1-202 Shift Operations Organization .................................................................... 13.1-32 1-203 Nuclear Executive Organization ................................................................. 13.1-33 1-204 Duke Energy Corporate .............................................................................. 13.1-34 A-201 Construction Management Organization .................................................... 13AA-6 A-202 Hiring Schedule for Plant Staff ................................................................... 13AA-7 13-iv Revision 1
urpose is to provide reasonable assurance that the plant will establish and maintain a staff of cient size and technical competence and that operating plans provide reasonable assurance of quate protection of the public health and safety.
1 Organizational Structure organizational structure must be consistent with the human system interface design umptions. See Section 1.8 and Chapter 18 for interface requirements pertaining to organizational cture.
section describes organizational positions of a nuclear power station and owner/applicant porations and associated functions and responsibilities. Prior to the start of construction, the ent organization may differ from what is described in this section for the construction and rating WLS organization. The QAPD as described in Section 17.5 contains the description of current Duke Energy organization including Nuclear Development. The position titles used in text are generic and describe the function of the position. Table 13.1-201, Generic Position/
Specific Position Cross Reference, provides a cross-reference to identify the corresponding
-specific position titles.
1.1 Management and Technical Support Organization e Energy has over 40 years of experience in the design, construction, and operation of nuclear erating stations. Duke Energy operates 12 nuclear units on seven sites: McGuire Units 1 and 2; awba Units 1 and 2; Oconee Units 1, 2, and 3; Harris Nuclear Plant Unit 1; Brunswick Nuclear nt Units 1 and 2; H. B. Robinson Nuclear Plant Unit 2; and Crystal River Nuclear Plant Unit 3 manent shutdown/retired). The Nuclear Generation organization includes, but is not limited to, lear engineering, nuclear operations, corporate governance and operations support, corporate anizational effectiveness, nuclear major projects, nuclear development, and nuclear oversight.
1.1.1 Design, Construction, and Operating Responsibilities responsibility for the licensing, development and construction of new nuclear generating plants Duke Energy is assigned to the Vice President of Nuclear Development. The responsibility for the ration of the new nuclear generating plants is assigned to the Chief Nuclear Officer. Each of these viduals reports directly to the President - Duke Energy Nuclear. The division of responsibilities made to allow the Chief Nuclear Officer and Nuclear Generation to remain focused on improving performance of the operating fleet and minimize the distractions associated with the construction ew nuclear generating plants. Organizational control and responsibility for the newly constructed lear generating plants transfers from Nuclear Development to the Chief Nuclear Officer following completion of construction activities and prior to loading of fuel. This transition point allows for the tinued support by the Nuclear Development organization, while the Operational Readiness (OR) anization transitions to the final structure typical of the operating fleet.
first priority and responsibility of each member of the nuclear staff throughout the life of the plant uclear safety. Decision making for station activities is performed in a conservative manner with ectations of this core value regularly communicated to appropriate personnel by management rface, training, and station directives.
s of authority, decision making, and communication are clearly and unambiguously established nable the understanding of the various project members, including contractors, that utility agement is in charge and directs the project.
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struction, and preoperational activities is addressed in Appendix 13AA.
1.1.2 Provisions for Technical Support Functions ore beginning preoperational testing, the executive - nuclear development, executive - corporate ernance and operations support, the executive - corporate organizational effectiveness, and the cutive - nuclear engineering establish the organization of managers, functional managers, ervisors, and staff sufficient to perform required functions for support of safe plant operation.
se functions include the following:
Nuclear, mechanical, structural, electrical, thermal-hydraulic, metallurgical and material, and instrumentation and controls engineering Safety review Quality assurance, audit, and surveillance Plant chemistry Radiation protection and environmental support Fueling and refueling operations support Training Maintenance support Operations support Fire protection Emergency planning organization Outside contractual assistance e event that station personnel are not qualified to deal with a specific problem, the services of lified individuals from other functions within the company or an outside consultant are engaged.
example, major contractors, such as the reactor technology vendor or turbine generator ufacturer, provide technical support when equipment modifications or special maintenance blems are considered. Special studies, such as environmental monitoring, may be contracted to lified consultants.
re 13.1-201 illustrates the management and technical support organizations supporting ration of the plant. Subsection 13.1.2 describes the responsibilities and authorities of agement positions for organizations providing technical support. Table 13.1-201 shows the mated number of positions required for each function.
tiple layers of protection are provided to preserve unit integrity, including organization.
anizationally, operators and other shift members are assigned to a specific unit. In addition, ion procedures and programs provide operating staff with methods to minimize human error, uding tagging programs, procedure adherence requirements, and training.
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grams, nuclear fuel management, and safety and engineering analysis. These groups are onsible for performing the classical design activities as well as providing engineering expertise in r areas of new plant sites and license renewal at the current plant sites. They are also onsible for probabilistic safety assessment and other safety issues, plant system reliability lysis, performance and technical support, core management and periodic reactor testing, and for grams, such as inservice inspection/inservice testing (ISI/IST), fire protection, snubbers, and es.
h of the engineering groups has a functional manager who reports to the executive - nuclear ineering (Figure 13.1-203).
nuclear engineering department is responsible for:
Support of plant operations in the engineering areas of mechanical, structural, electrical, thermal-hydraulic, metallurgy and materials, electronic, instrument and control, and fire protection. Priorities for support activities are established based on input from the plant manager with emphasis on issues affecting safe operation of the plant.
Engineering programs.
Major engineering projects for the nuclear fleet.
Support of procurement, chemical and environmental analysis, and maintenance activities in the plant as requested by the plant manager.
Performance of design engineering of plant modifications.
Maintenance of the design basis by updating the record copy of design documents as necessary to reflect the actual as-built configuration of the plant.
Accident and transient analyses.
Human Factors Engineering design process.
ctor engineering, led by the functional manager in charge of nuclear fuels and analysis ineering, provides technical assistance in the areas of core design, core operations, core thermal s, and core thermal hydraulics.
ineering work may be contracted to and performed by outside companies in accordance with the lity assurance program description (QAPD).
ineering resources are shared between units. A single management organization oversees the ineering work associated with the station units. Physical separation of units helps to minimize ng-unit activities.
1.1.2.2 Nuclear Safety Assurance nt licensing, regulatory compliance, corrective actions and performance improvement, and rgency preparedness each have a functional manager who reports to and receives direction from manager in charge of organizational effectiveness.
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Developing licensee event reports (LERs) and responding to notices of violations.
Writing/submitting operating license and technical specification amendments and updating the FSAR.
Tracking commitments and answering generic letters.
Analyzing operating experience data and monitoring industry issues.
Preparing station for special NRC inspections, interfacing with NRC inspectors, and interpreting NRC regulations.
Maintaining the licensing basis.
organizational effectiveness organization administers the corrective action program and the ions emergency preparedness program.
sonnel resources of the NSA organization are shared between units. A single management anization oversees the NSA organization for the station units.
1.1.2.3 Quality Assurance nuclear oversight organization provides independent oversight of the nuclear plant activities, ntains the Quality Assurance Program Manual, and administers the employee concerns program.
executive - nuclear oversight reports directly to the CNO. However, the executive - nuclear rsight reports to the President - Duke Energy Nuclear on matters related to the development and loyment of new nuclear generating plants.
ety-related activities associated with the operation of the plant are governed by QA direction blished in Chapter 17 and the QAPD. The requirements and commitments contained in the PD apply to activities associated with structures, systems, and components which are safety ted and are mandatory and must be implemented, enforced, and adhered to by individuals and anizations. QA requirements are implemented through the use of approved procedures, policies, ctives, instructions, or other documents which provide written guidance for the control of quality-ted activities and provide for the development of documentation to provide objective evidence of pliance. QA is a corporate function under the executive - nuclear oversight and includes:
General QA indoctrination and training for the nuclear station personnel.
Maintenance of the QAPD.
Coordination of the development of audit schedules.
Audit, surveillance, and evaluation of nuclear division suppliers.
Quality control (QC) inspection/testing activities.
rsight of safety review of station programs, procedures, and activities is performed by a plant ty review committee, a corporate safety review committee, and the QA organization. Review and it activities are addressed in Chapter 17 and the QAPD.
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uclear oversight at the Lee site reports directly to the executive - nuclear oversight.
1.1.2.4 Chemistry corporate governance and operations support organization provides the standardization and port of the chemistry program at each site. A chemistry department is established to monitor and trol the chemistry of various plant systems such that corrosion of components and piping is imized and radiation from corrosion byproducts is kept to levels that allow operations and ntenance with radiation doses as low as reasonably achievable.
functional manager in charge of environmental and chemistry is responsible to the plant general ager for maintaining chemistry programs and for monitoring and maintaining the water chemistry lant systems. The staff of the chemistry department consists of laboratory technicians, support onnel, and supervisors who report to the functional manager in charge of environmental and mistry.
sonnel resources of the chemistry organization are shared between units. A single management anization oversees the chemistry group for the station units.
1.1.2.5 Radiation Protection corporate governance and operations support organization provides the standardization and port of the radiation protection programs at each site. A radiation protection program is blished to protect the health and safety of the surrounding public and personnel working at the
- t. The radiation protection program is described in Chapter 12. The program includes:
Respiratory Protection Personnel Dosimetry Bioassay Survey Instrument Calibration and Maintenance Radioactive Source Control Effluents and Environmental Monitoring and Assessment Radioactive Waste Shipping Radiation Work Permits Job Coverage Radiation Monitoring and Surveys radiation protection department is staffed by radiation protection technicians, support personnel, supervisors who report to the functional manager in charge of radiation protection. To provide cient organizational freedom from operating pressures, the functional manager in charge of ation protection reports directly to the plant manager.
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1.1.2.6 Fueling and Refueling Support corporate governance and operations support organization provides the standardization and port of the refueling programs at each site. The function of fueling and refueling is performed by a bination of personnel from various departments including operations, maintenance, radiation ection, engineering, and reactor technology vendor or other contractor staff. Initial fueling and eling operations are a function of the work control organization. The functional manager in charge utage and scheduling is responsible for planning and scheduling outages and for refueling port and reports to the plant manager.
sonnel resources of the work control organization are shared between units. A single agement organization oversees the work control associated with both units.
1.1.2.7 Training and Development corporate organizational effectiveness support organization provides the standardization and port of the training programs at each site. The training department is responsible for providing ing programs that are established, maintained, and implemented in accordance with applicable t administrative directives, regulatory requirements, and company operating policies so that ion personnel can meet the performance requirements of their jobs in operations, maintenance, nical support, and emergency response. The objective of training programs is to provide qualified onnel to operate and maintain the plant in a safe and efficient manner and to provide compliance the license, technical specifications, and applicable regulations. The training department's onsibilities encompass operator initial license training, requalification training, and plant staff ing as well as the plant access training (general employee training) and radworker training. The tional manager in charge of training at the Lee site is independent of the operating line anization to provide for independence from operating pressures. Nuclear plant training programs described in Section 13.2.
sonnel resources of the training department are shared between units. A single management anization provides oversight of station training activities.
1.1.2.8 Maintenance Support corporate governance and operations support organization provides the standardization and port of the maintenance programs at each site. In support of maintenance activities, planners, edulers, and parts specialists prepare work packages, acquire proper parts, and develop edures that provide for the successful completion of maintenance tasks. Maintenance tasks are grated into the station schedule for evaluation of operating or safe shutdown risk elements and to ide for efficient and safe performance. Personnel of the maintenance support organization ive direction from the functional manager in charge of maintenance who reports to the plant ager.
sonnel of the maintenance support organization are shared between units. A single management anization oversees the function of maintenance support for the station units.
1.1.2.9 Operations Support corporate governance and operations support organization provides the standardization and port of the operations programs at each site. The operations support function is provided under 13.1-6 Revision 1
Operations procedures Operations surveillances Equipment tagging Fire protection testing and surveillance Radwaste system operation 1.1.2.10 Fire Protection station is committed to maintaining a fire protection program as described in Subsection 9.5.1 site executive in charge of plant management is responsible for the fire protection program.
igning the responsibilities at that level provides the authority to obtain the resources and stance necessary to meet fire protection program objectives, resolve conflicts, and delegate ropriate responsibility to fire protection staff. The relationship of the site executive in charge of t management to other staff personnel with fire protection responsibilities is shown on re 13.1-201. Fire protection for the facility is organized and administered by the engineer in rge of fire protection. The site executive in charge of plant management, through the engineer in rge of fire protection, is responsible for development and implementation of the fire protection gram including development of fire protection procedures and inspections of fire protection ems and functions. Fire brigade training, drills, and practice are organized by the functional ervisor in charge of emergency preparedness in consultation with the engineer in charge of fire ection. Fire protection trainers are qualified to perform classroom instruction or practical training iscussed in Subsection 9.5.1.8.2.2. The engineer in charge of fire protection reports to the site cutive in charge of plant management through engineering department management and rdinates operations related fire protection program activities with the manager in charge of rations. Functional descriptions of position responsibilities are included in appropriate edures. Station personnel are responsible for adhering to the fire protection/prevention uirements detailed in Subsection 9.5.1. The site executive in charge of plant management has the responsibility for the overall site fire protection during construction of new units.
sonnel resources that implement the fire protection program are shared between units. A single agement organization oversees the fire protection program for the station units.
1.1.2.11 Emergency Organization corporate organizational effectiveness support organization provides the standardization and port of the emergency response programs at each site. The emergency organization is a rixed organization composed of personnel who have the experience, training, knowledge, and ty necessary to implement actions to protect the public in the case of emergencies. Managers station personnel assigned positions in the emergency organization are responsible for porting the emergency preparedness organization and emergency plan as required. The staff mbers of the emergency planning organization orchestrate drills and training to maintain lification of personnel and develop procedures to guide and direct the emergency organization ng an emergency. The functional supervisor in charge of emergency preparedness reports to the tional manager in charge of organizational effectiveness. The site emergency plan organization escribed in the Emergency Plan.
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1.1.2.12 Outside Contractual Assistance tract assistance with vendors and suppliers of services not available from organizations blished as part of utility staff is provided by the materials, purchasing, and contracts organization.
sonnel in the materials, purchasing, and contracts organization perform the necessary functions ontract vendors of special services to perform tasks for which utility staff does not have the erience or equipment required. The functional manager in charge of Nuclear Generation - supply in reports to the vice president - supply chain.
ources of the materials, purchasing, and contracts organization are shared between units. A le management organization oversees the materials, purchasing, and contracts group for the ion units.
1.1.3 Organizational Arrangement 1.1.3.1 Executive Management Organization cutive management is ultimately responsible for execution of activities and functions for the lear generating plants owned by the utility. Executive management establishes expectations such a high level of quality, safety, and efficiency is achieved in aspects of plant operations and port activities through an effective management control system and an organization selected and ed to meet the above objectives. The nuclear executive organization is shown in re 13.1-203. A high-level chart of the Duke Energy corporate organization showing the tionship of the nuclear division to the rest of the corporate organization is illustrated in re 13.1-204. Executives and managers with direct line of authority for activities associated with ration of the plant are shown in Figure 13.1-201. Responsibilities of those executives and agers are specified below.
1.1.3.1.1 Chairman, President and CEO Duke Energy Chairman, President and CEO has the ultimate responsibility for the safe and ble operation of each nuclear station owned and/or operated by the utility. The CEO is onsible for the overall direction and management of the corporation and the execution of the pany policies, activities, and affairs. The CEO is assisted by the President - Duke Energy lear and other nuclear executive staff. Also reporting to the Chairman, President and CEO are up Executives responsible for providing support to Nuclear Generation for the following: electrical smission; electrical distribution; laboratory services; switchyard maintenance and technical port; support for the emergency response communications; information technology services; ument control and record management activities; support for contracts, engineering, and agement related to new plant construction as requested.
1.1.3.1.2 President - Duke Energy Nuclear President of Duke Energy Nuclear reports to the Chairman, President and Chief Executive cer and is responsible for the Duke nuclear fleet, enterprise project management and struction, new plant development and decommissioning activities. The President - Duke Energy lear has overall authority and responsibility for the QA Program. The President - Duke Energy lear directs the following group executives: (1) chief nuclear officer (CNO); (2) nuclear elopment; (3) project management and construction; (4) nuclear oversight; and (5) site struction. There are two additional direct reports to the President - Duke Energy Nuclear. One is 13.1-8 Revision 1
1.1.3.1.3 Group Executive Chief Nuclear Officer group executive - Nuclear Generation is the CNO. The CNO reports to the President - Duke rgy Nuclear of Duke Energy. The CNO directs the following executives for each nuclear site up in the operation of his applicable unit(s): (1) executive - nuclear engineering, (2) executive -
orate governance and operations support, (3) executive - corporate organizational effectiveness, executive - nuclear major projects, (5) executive - nuclear oversight and (6) the three executives nuclear operations. The CNO has responsibility for overall plant nuclear safety and takes the sures needed to provide acceptable performance of the staff in operating, maintaining, and iding technical support to the plant. The CNO delegates authority and responsibility for the ration and support of the sites to the executive - nuclear operations for each site group. It is the onsibility of the CNO to provide guidance and direction such that safety-related activities uding engineering, testing, modifications, preoperational testing, operations, maintenance, and ning are performed following the guidelines of the QA program. The Independent Nuclear rsight Committee reports directly to the CNO. The CNO has no ancillary responsibilities that ht detract attention from nuclear safety matters.
1.1.3.1.4 Executive - Nuclear Operations (Specified Duke Sites) executive(s) in charge of nuclear operations is responsible for oversight of operations at each of stations under his purview. Currently the sites are divided among three executives in charge of lear operations as follows: one responsible for Oconee and Robinson nuclear stations; one onsible for Catawba and McGuire nuclear stations; and one responsible for Brunswick and ris nuclear stations. With the addition of future sites, responsibilities will be redistributed among executives - nuclear operations to maintain proper focus and oversight. Reporting to each cutive - nuclear operations are the site executives for the respective nuclear stations. The cutives - nuclear operations report to the CNO.
1.1.3.1.5 Site Executive(s) - Plant Management (McGuire, Catawba, Oconee, Harris, Brunswick, Robinson, and Future Lee Site) site executive(s) in charge of plant management reports to the executive(s) in charge of nuclear rations. The site executive in charge of plant management is directly responsible for management direction of activities associated with the efficient, safe, and reliable operation of the nuclear ion, except for those functions delegated to the executive - corporate governance and the cutive - corporate organizational effectiveness. The site executive in charge of plant management ssisted in management and technical support activities by the plant manager and managers in rge of organizational effectiveness, engineering, training, security, nuclear oversight, major ects, human resources, corporate communications, and finance. The site executive in charge of t management is responsible for the site fire protection program through the engineer in charge re protection and engineering management. As Lee approaches startup, the site organization sitions to the Operating Plant Site Organization as shown in Figure 13.1-201 from the elopment focused organization shown in Figure 13AA-201.
1.1.3.1.6 Executive - Nuclear Development executive in charge of nuclear development is responsible for development of the licensing ons needed in support of new nuclear site development. Responsibilities also include engineering rsight of contractors, licensing, construction, site layout, staffing, and program development. The cutive in charge of nuclear development is assisted by a support staff and reports directly to the 13.1-9 Revision 1
1.1.3.1.7 Executive - Major Projects executive in charge of major projects provides project management, engineering, and vendor rsight for selected large projects at the nuclear sites. Providing oversight for these significant ects provides more focus and continuity for upgrades and eliminates distractions for site agement. Nuclear major projects is responsible for contracts, engineering, and management ted to fleet and nuclear site major projects. The executive in charge of major projects reports to CNO.
1.1.3.1.8 Executive - Site Construction executive for site construction reports directly to the President - Duke Energy Nuclear. This orting relationship allows the CNO and Nuclear Generation to remain focused on improving the ormance of the operating fleet and minimize the distractions associated with the construction of nuclear generating plants. This position will be filled in support of the start of construction vities for a new nuclear plant. This position is responsible for the control and oversight of all struction activities associated with a new nuclear unit. Reporting to this position will be the ager for construction; manager for site engineering; and the site plant manager as shown on re 13AA-201. This position will transfer responsibility for the constructed unit to the site executive orting to the CNO at the completion of construction activities and prior to the loading of fuel in that
. This position will retain responsibilities for other units under construction at a multi-unit site until struction activities for each unit are completed. This position is supported during these struction activities by other Duke Energy Nuclear organizations, as needed.
1.1.3.1.9 Executive - Corporate Governance and Operations Support executive for corporate governance and operations support reports to the CNO. Corporate ernance and operations support provides support to help improve overall fleet performance. This tralized organization includes protective services (security and access services); nuclear support ices; and operations support.The functional manager of nuclear operations, the functional ager of protective services, the functional manager of Fukushima responses, the functional ager of nuclear merger integration, and the functional manager of nuclear support services ort to the executive in charge of corporate governance and operations support.
1.1.3.1.10 Executive - Corporate Organizational Effectiveness executive for corporate organizational effectiveness reports to the CNO. The executive for orate organizational effectiveness will support fleet performance through improving overall fleet ctiveness. Reporting to this position will be organizational effectiveness; regulatory affairs; ing; leadership development; performance improvement and emergency preparedness.
1.1.3.1.11 Executive - Nuclear Engineering executive in charge of nuclear engineering provides support to the stations in severe accident lysis, safety analysis, nuclear design, core mechanical and thermal hydraulic analysis, fuel agement, switchyard support, metallurgical laboratory services, material aging program, steam erator maintenance, ISI program support, QC inspector training and certification, procurement ineering, welding, and radiological engineering.
executive - nuclear engineering reports to the CNO. Nuclear engineering provides broad ineering leadership and technical support to the nuclear sites, with emphasis on generic issues 13.1-10 Revision 1
agement, and reactor core mechanical and thermal hydraulic analysis; fleet electrical and urement engineering with technical support in the areas of procurement engineering, nuclear ess systems, and electrical systems and analysis; and programs and components support in the as of steam generator inspections and maintenance, engineering programs, component ineering, material failure analysis and materials science, equipment reliability, and ASME code ections and testing.
lear engineering provides record storage and document management services, technology ning, project control, and technical support for information technology applications and systems h as equipment databases, applications, infrastructure, and plant process information systems.
1.1.3.1.12 Executive - Nuclear Oversight executive in charge of nuclear oversight provides support and leadership to the general office stations with QA program audits, performance assessment, procurement quality, supplier fication, and QA, QC, NDE, and ISI, as applicable. In addition, nuclear oversight provides an isory function to senior management through the NSRB. The executive - nuclear oversight has authority and organizational freedom to identify quality problems; initiate, recommend, or provide tions to quality problems through designated channels; verify the implementation of solutions to lity problems; and ensure cost and schedule do not influence decision-making involving quality.
executive - nuclear oversight has unfettered access to the CNO to communicate QA program cerns and issues.
executive - nuclear oversight is delegated primary ownership of the department QA program cription and is responsible for day-to-day administration of the program and resolution of QA es. If significant quality problems are identified by nuclear oversight personnel, the executive -
lear oversight or designee has the responsibility and authority to stop work pending satisfactory lution of the identified problem. The executive - nuclear oversight reports directly to the CNO.
executive - nuclear oversight is responsible for providing oversight of Nuclear Generation vities; administration of the employee concerns program; and maintenance of the Quality urance Program Manual. The executive - nuclear oversight is responsible for and reports to the sident - Duke Energy Nuclear on all matters related to the independent monitoring and assessing ctivities performed by or in support of the development and deployment of new nuclear erating plants, decommissioning activities, and project management and construction activities controlled by the CNO. Assisting the executive - nuclear oversight is the functional manager in rge of corporate nuclear oversight and the functional manager(s) in charge of nuclear oversight each nuclear plant site.
1.1.3.1.13 Functional Director - Nuclear Protective Services functional director in charge of nuclear protective services is responsible for providing guidance direction to the functional manager - security at each site on the nuclear security, access orization, and fitness for duty programs. The director - nuclear protective services reports to the cutive - corporate governance and operations support.
1.1.3.2 Site Support Organization 1.1.3.2.1 The Functional Manager - Engineering functional manager in charge of engineering reports to the executive - nuclear engineering. The tional manager in charge of engineering is responsible for engineering activities related to the 13.1-11 Revision 1
functional manager in charge of engineering directs functional discipline engineers responsible ystem engineering, design engineering, and engineering programs.
ngle management organization oversees the engineering support for the station units.
1.1.3.2.1.1 Functional Manager - Plant Engineering functional manager in charge of plant engineering reports to the functional manager in charge of ineering and supervises a technical staff of engineers and other engineering specialists and rdinates their work with that of other groups. System engineering staff includes reactor ineering as discussed in Subsection 13.1.1.2.1. The functional manager in charge of plant ineering is responsible for providing direction and guidance to system engineers as follows:
Monitoring the efficiency and proper operation of balance of plant and reactor systems.
Planning programs for improving equipment performance, reliability, or work practices.
Conducting operational tests and analyzing the results.
Identification of plant spare parts for systems.
1.1.3.2.1.2 Functional Manager - Design Engineering functional manager in charge of design engineering reports to the functional manager in charge ngineering and is responsible for:
Resolution of design issues.
Onsite development of design related change packages and plant modifications.
Implementation of effective project management methods and procedures, including cost controls, for implementation of modifications and construction activities.
Management of contractors who may perform modification or construction activities.
Maintaining configuration control program.
1.1.3.2.1.3 Functional Manager - Engineering Programs functional manager in charge of engineering programs reports to the functional manager in rge of engineering and is responsible for programs such as:
Valve engineering Maintenance rule tracking and trending Fire protection Piping erosion/corrosion 13.1-12 Revision 1
1.1.3.2.2 Functional Manager - Organizational Effectiveness functional manager in charge of organizational effectiveness is responsible for those functions cribed in Subsection 13.1.1.2.2 and reports to the site executive in charge of plant management.
responsibilities of the manager in charge of nuclear safety assurance are fulfilled through the tional supervisors in charge of plant licensing and regulatory compliance, corrective actions and ormance improvement, emergency preparedness.
1.1.3.2.2.1 Functional Supervisor In Charge of Plant Licensing and Regulatory Compliance responsibility of the functional supervisor in charge of plant licensing and regulatory compliance provide a coordinated focus for interface with the NRC and technical direction and administrative ance for the licensing staff for those activities listed in Subsection 13.1.1.2.2. The functional ervisor in charge of plant licensing and regulatory compliance reports directly to the functional ager in charge of organizational effectiveness.
1.1.3.2.2.2 Functional Supervisor In Charge of Corrective Actions and Performance Improvement responsibilities of the functional supervisor in charge of corrective actions and performance rovement includes establishing processes and procedures to facilitate identification and ection of conditions adverse to quality and implement corrective actions. The functional ervisor in charge of corrective actions and performance improvement reports directly to the tional manager in charge of organizational effectiveness.
1.1.3.2.2.3 Functional Supervisor In Charge of Emergency Preparedness functional supervisor in charge of emergency preparedness is responsible for:
Coordinating and implementing the plant emergency response plan with state and local emergency plans.
Developing, planning, and executing emergency drills and exercises including coordination of fire brigade training exercises with the engineer in charge of fire protection.
Emergency action level development.
NRC reporting associated with 10CFR50.54(q).
functional supervisor in charge of emergency preparedness reports directly to the functional ager in charge of organizational effectiveness.
1.1.3.2.2.4 Additional Organizational Effectiveness Support nctional supervisor in charge of procedures develops quality site procedures and reports to the anizational effectiveness manager. In addition, a functional supervisor in charge of human ormance works with the site to improve human performance on behalf of the organizational ctiveness manager.
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ects and financial programs, and for providing oversight of accounting and payroll processes for site. The manager in charge of finance reports to the site executive in charge of plant agement.
1.1.3.2.4 Functional Manager - Training and Development functional manager in charge of training and development is responsible for training programs at site required for the safe and proper operation and maintenance of the plant including:
Operations training programs Plant staff training programs Plant access training Emergency plan training Radiation worker training functional manager in charge of training may seek assistance from other departments within the pany or outside specialists, such as educators and manufacturers. The manager in charge of ing supervises a staff of training supervisors who coordinate the development, preparation and entation of training programs for nuclear plant personnel and reports to the site executive in rge of plant management.
1.1.3.2.5 Functional Manager In Charge of Security functional manager in charge of security is responsible for:
Implementation and enforcement of security directives, procedures and instructions received from appropriate authorities.
Day-to-day supervision of the security guard force.
Administration of the security program.
functional manager in charge of security reports directly to the functional director - nuclear ective services and indirectly to the site executive - plant management.
1.1.4 Qualifications of Technical Support Personnel qualifications of managers and supervisors of the technical support organization meet the lification requirements in education and experience for those described in ANSI/ANS-3.1-1993 ference 201) as endorsed and amended by Regulatory Guide 1.8. For positions that do not have oss-reference section in ANSI/ANS-3.1 the most comparable section of ANSI/ANS-3.1 is used for ance in establishing experience and education requirements. The qualification and experience uirements of headquarters staff is established in corporate policy and procedure manuals.
13.1-14 Revision 1
plant management, technical support, and plant operating organizations are shown in re 13.1-201. The on-shift operating organization is presented in Figure 13.1-202 which shows e positions requiring NRC licenses. Additional personnel are required to augment normal staff ng outages.
lear plant employees are responsible for reporting problems with plant equipment and facilities.
y are required to identify and document equipment problems in accordance with the QA program.
program requirements, as they apply to the operating organization, are described in Chapter 17.
guidelines of Regulatory Guide 1.33, for the operating organization, onsite review, and rules of tice are implemented at the site via administrative procedure or standing order and include:
Establishment of a QA program for the operational phase.
Preparation of procedures necessary to carry out an effective QA program. See Section 13.5 for description of the station procedure program.
A program for review and audit of activities affecting plant safety. See Section 17.5 for description of station review and audit programs.
Programs and procedures for rules of practice as described in Section 5.2 of ANSI/ANS-3.2-1988 (Reference 203).
agers and supervisors within the plant operating organization are responsible for establishing ls and expectations for their organization and to reinforce behaviors that promote radiation ection. Specifically, managers and supervisors are responsible for the following, as applicable to r position within the plant organization:
Interface directly with radiation protection staff to integrate radiation protection measures into plant procedures and design documents and into the planning, scheduling, conduct, and assessment of operations and work.
Notify radiation protection personnel promptly when radiation protection problems occur or are identified, take corrective actions, and resolve deficiencies associated with operations, procedures, systems, equipment, and work practices.
Train site personnel on radiation protection, and provide periodic retraining, in accordance with 10 CFR Part 19 so that they are properly instructed and briefed for entry into restricted areas.
Periodically observe and correct, as necessary, radiation worker practices.
Support radiation protection management in implementing the radiation protection program.
Maintain exposures to site personnel ALARA.
1.2.1.1 Plant Manager plant manager reports to the site executive in charge of plant management, is responsible for rall safe operation of the plant, and has control over those onsite activities necessary for safe ration and maintenance of the plant including the following:
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Chemistry and radiochemistry Outage management Scheduling and activity coordination itionally, the plant manager has overall responsibility for occupational and public radiation safety.
iation protection responsibilities of the plant manager are consistent with the guidance in ulatory Guide 8.8 and Regulatory Guide 8.10 including the following:
Provide management radiation protection policy throughout the plant organization.
Provide an overall commitment to radiation protection by the plant organization.
Interact with and support the manager in charge of radiation protection on implementation of the radiation protection program.
Support identification and implementation of cost-effective modifications to plant equipment, facilities, procedures and processes to improve radiation protection controls and reduce exposures.
Establish plant goals and objectives for radiation protection.
Maintain exposures to site personnel ALARA.
Support timely identification, analysis and resolution of radiation protection problems (e.g.,
through the plant corrective action program).
Provide training to site personnel on radiation protection in accordance with 10 CFR Part 19.
Establish an ALARA Committee with delegated authority from the plant manager that includes, at a minimum, the managers in charge of operations, maintenance, engineering, and radiation protection to help provide for effective implementation of line organization responsibilities for maintaining worker doses ALARA.
line of succession of authority and responsibility for overall operations in the event of unexpected nts of a temporary nature is:
Manager in charge of operations Manager in charge of plant maintenance Assistant manager in charge of operations escribed in Subsection 13.1.2.1.2.4, the manager in charge on-shift is the plant managers direct esentative for the conduct of operations. The succession of authority includes the authority to e standing or special orders as required.
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rumentation and control disciplines. The functions of this department are to perform preventive corrective maintenance, equipment testing, and implement modifications as necessary.
manager in charge of maintenance is responsible for the performance of preventive and ective maintenance and modification activities required to support operations, including pliance with applicable standards, codes, specifications, and procedures. The manager in rge of maintenance reports to the plant manager and provides direction and guidance to the ntenance discipline functional managers and maintenance support staff.
1.2.1.1.2 Maintenance Discipline Functional Managers functional managers of each maintenance discipline (mechanical, electrical, and instrumentation control) are responsible for maintenance activities within their discipline including plant ifications. They provide guidance in maintenance planning and craft supervision. They establish necessary manpower levels and equipment requirements to perform both routine and emergency maintenance activities, seeking the services of others in performing work beyond the capabilities e plant maintenance group. Each discipline functional manager is responsible for liaison with r plant staff organizations to facilitate safe operation of the station. These functional managers ort to the manager in charge of plant maintenance.
1.2.1.1.3 Maintenance Discipline Supervisors maintenance discipline supervisors (mechanical, electrical, and instrumentation and control) ervise maintenance activities, assist in the planning of future maintenance efforts, and guide the rts of the craft within their discipline. The maintenance discipline supervisors report to the ropriate maintenance discipline functional managers.
1.2.1.1.4 Functional Manager - Work Control functional manager in charge of work control is responsible for planning, scheduling, and rdinating maintenance, modification, and testing activities during power operations and shutdown ods. This includes taking necessary measures to minimize risk to the plant and personnel during above activities.
functional manager in charge of work control reports to the plant manager.
1.2.1.1.5 Functional Manager - Radiation Protection functional manager in charge of radiation protection has the responsibility for providing adequate ection of the health and safety of personnel working at the plant and members of the public ng activities covered within the scope and extent of the license. Radiation protection onsibilities of the functional manager in charge of radiation protection are consistent with the ance in Regulatory Guide 8.8 and Regulatory Guide 8.10. They include:
Manage the radiation protection organization.
Establish, implement, and enforce the radiation protection program.
Provide radiation protection input to facility design and work planning.
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Support the plant emergency preparedness program and assign emergency duties and responsibilities within the radiation protection organization.
Delegate authority to appropriate radiation protection staff to stop work or order an area evacuated (in accordance with approved procedures) when, in his or her judgment, the radiation conditions warrant such an action and such actions are consistent with plant safety.
functional manager in charge of radiation protection reports to the plant manager and is assisted he supervisors in charge of radiation protection.
functional manager in charge of radiation protection reports indirectly to and receives support the corporate functional manager in charge of nuclear support.
1.2.1.1.6 Functional Supervisor(s) In Charge of Radiation Protection functional supervisors in charge of radiation protection are responsible for carrying out the
-to-day operations and programs of the radiation protection department as listed in section 13.1.1.2.5.
ervisors in charge of radiation protection report to the functional manager in charge of radiation ection.
1.2.1.1.7 Radiation Protection Technicians iation protection technicians (RPTs) directly carry out responsibilities defined in the radiation ection program and procedures. In accordance with technical specifications an RPT is on site never there is fuel in the vessel. See Table 13.1-202.
following are some of the duties and responsibilities of the RPTs:
As delegated authority by the functional manager in charge of radiation protection, stop work or order an area evacuated (in accordance with approved procedures) when, in his or her judgment, the radiation conditions warrant such an action and such actions are consistent with plant safety.
Provide coverage and monitor radiation conditions for jobs potentially involving significant radiation exposure.
Conduct surveys, assess radiation conditions and establish radiation protection requirements for access to and work within restricted, radiation, high radiation, very high radiation, airborne radioactivity areas, and areas containing radioactive materials.
Provide control over the receipt, storage, movement, use, and shipment of licensed radioactive materials.
Review work packages, proposed design modifications, and operations and maintenance procedures to facilitate integration of adequate radiation protection controls and dose-reduction measures.
Review and oversee implementation of plans for the use of process or other engineering controls to limit the concentrations of radioactive materials in the air.
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Perform assigned emergency response duties.
1.2.1.1.8 Functional Manager - Chemistry functional manager in charge of chemistry is responsible for development, implementation, and ction and coordination of the chemistry, radiochemistry and nonradiological environmental itoring programs. The chemistry department has charge of overall operation of the hot lab, cold emergency offsite facility lab, and non-radiological environmental monitoring. The functional ager in charge of chemistry is responsible for the development, administration, and lementation of procedures and programs which provide for effective compliance with ironmental regulations. The functional manager in charge of chemistry reports to the plant ager and directly supervises the chemistry supervisors and chemistry technicians as assigned.
functional manager in charge of chemistry reports indirectly to and receives support from the orate located functional manager in charge of nuclear support services. Three functional ervisors over chemistry disciplines assist the functional manager in charge of chemistry.
1.2.1.2 Operations Department perations activities are conducted with safety of personnel, the public, and equipment as the rriding priority. The operations department is responsible for:
Operation of station equipment.
Monitoring and surveillance of safety and non-safety related equipment.
Fuel handling.
Providing the nucleus of emergency and fire-fighting teams.
operations department maintains sufficient licensed and senior licensed operators to staff the trol room continuously using a crew rotation system. The operations department is under the ction of the manager in charge of operations, who through the assistant manager in charge of rations directs the day-to-day operation of the plant.
cific duties, functions, and responsibilities of key shift members are discussed in sections 13.1.2.1.2.4 through 13.1.2.1.2.8 and in plant administrative procedures and the nical specifications. The minimum shift manning requirements are shown in Table 13.1-202.
e resources of the operations organization are shared between units. Administrative and support onnel perform their duties on either unit. Additional operations staff is required to fill the on-shift fing requirements of the additional units. To operate, or supervise the operation of more than one
, a senior reactor operator (SRO) or reactor operator (RO) must hold an appropriate, current nse for each unit. A single management organization oversees the operations group for the ion units. See Table 13.1-201 for estimated number of staff in the operations department for a le unit. Positions required for operation of the second unit are also shown.
operations support section is staffed with sufficient personnel to provide support activities for the rating shifts and overall operations department. The following is an overview of the operations anization.
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e plant. The functional manager in charge of operations reports to the plant manager and is sted by the assistant functional manager in charge of operations and assistant functional ager in charge of operations support. The functional manager in charge of operations receives port from the engineer in charge of fire protection for coordination of operations related fire ection activities. The functional manager in charge of operations or the assistant functional ager of operations is SRO licensed.
1.2.1.2.2 Assistant Functional Manager - Operations assistant functional manager in charge of operations, under the direction of the functional ager in charge of operations, is responsible for:
Shift plant operations in accordance with the operating license, technical specifications, and written procedures.
Providing supervision of operating shift personnel for operational shift activities including those of emergency and firefighting teams.
Coordinating with the assistant functional manager in charge of operations support and other plant staff sections.
Verifying that nuclear plant operating records and logs are properly prepared, reviewed, evaluated and turned over to the assistant functional manager in charge of operations support.
assistant functional manager in charge of operations is assisted in these areas by the managers harge on-shift who direct the operating shift personnel. The assistant functional manager in rge of operations reports to the functional manager in charge of operations and in the absence of manager in charge of operations or assistant functional manager in charge of operations support assume the duties and responsibilities of either of these positions.
1.2.1.2.3 Assistant Functional Manager In Charge of Operations Support assistant functional manager in charge of operations support, under the direction of the tional manager in charge of operations, is responsible for:
Directing and guiding plant operations support activities in accordance with the operating license, technical specifications, and written procedures.
Providing supervision of operating support personnel, for operations support activities, and coordination of support activities.
Providing for nuclear plant operating records and logs to be turned over to the nuclear records group for maintenance as QA records.
assistant functional manager in charge of operations support is assisted by the supervisors of k management, operations procedures group, and other support personnel. In the absence of the tional manager in charge of operations or assistant functional manager in charge of operations, assistant functional manager in charge of operations support may assume the duties and onsibilities of either of these positions.
13.1-20 Revision 1
tion, and is the plant managers direct management representative for the conduct of operations.
uch, the manager in charge on-shift has the responsibility and authority to direct the activities personnel onsite as required to:
Protect the health and safety of the public, the environment, and personnel on the plant site.
Protect the physical security of the plant.
Prevent damage to site equipment and structures.
Comply with the operating license.
manager in charge on-shift retains this responsibility and authority until formally relieved of rating responsibilities by a licensed SRO. Additional responsibilities of the manager in charge hift include:
Directing nuclear plant employees to report to the plant for response to potential and real emergencies.
Seeking the advice and guidance of the shift technical advisor and others in executing the duties of the manager in charge on-shift whenever in doubt as to the proper course of action.
Promptly informing responsible supervisors of significant actions affecting their responsibilities.
Participating in operator training, retraining, and requalification activities from the standpoint of providing guidance, direction, and instruction to shift personnel.
manager in charge on-shift is assisted in carrying out the above duties by the supervisors in rge on-shift and the operating shift personnel. The manager in charge on-shift reports to the stant functional manager in charge of operations.
1.2.1.2.5 Supervisor in Charge On-Shift supervisor in charge on-shift is a licensed SRO. The primary function of the supervisor in charge hift is to administratively support the manager in charge on-shift such that the command tion is not overburdened with administrative duties and to supervise the licensed and non-nsed operators in carrying out the activities directed by the manager in charge on-shift. Other es include:
Being aware of maintenance and testing performed during the shift.
Shutting down the reactor if conditions warrant this action.
Informing the manager in charge on-shift and other station management in a timely manner of conditions which may affect public safety, plant personnel safety, plant capacity or reliability, or cause a hazard to equipment.
Initiating immediate corrective action as directed by the manager in charge on-shift in any upset situation until assistance, if required, arrives.
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supervisor in charge on-shift reports directly to the manager in charge on-shift.
1.2.1.2.6 Reactor Operator ROs are licensed reactor operators and normally report to the supervisor in charge on-shift or ager in charge on-shift. They are responsible for routine plant operations and performance of or evolutions at the direction of the manager/supervisor in charge on-shift. The RO duties include:
Monitoring control room instrumentation.
Responding to plant or equipment abnormalities in accordance with approved plant procedures.
Directing the activities of non-licensed operators.
Documenting operational activities, plant events, and plant data in shift logs.
Initiating plant shutdowns or scrams or other compensatory actions when observation of plant conditions indicates a nuclear safety hazard exists or when approved procedures so direct.
enever there is fuel in the reactor vessel, at least one reactor operator is in the control room itoring the status of the unit at the main control panel. The RO assigned to the main control panel esignated the operator at the controls and conducts monitoring and operating activities in ordance with the guidance set forth in Regulatory Guide 1.114, which is further described in section 13.1.2.1.3, Conduct of Operations.
1.2.1.2.7 Non-Licensed Operator non-licensed operators perform routine duties outside the control room as necessary for tinuous, safe plant operation including:
Assisting in plant startup, shutdown, surveillance, and emergency response by manually or remotely changing equipment operating conditions, placing equipment in service, or securing equipment from service at the direction of the reactor operator.
Performing assigned tasks in procedures and checklists such as valve manipulations for plant startup or data sheets on routine equipment checks, and making accurate entries according to the applicable procedure, data sheet, or checklist.
Assisting in training of new employees and for improvement and upgrading of their own performance by participating in the applicable sections of the training program.
-licensed operators include auxiliary operators as shown in Figure 13.1-202.
1.2.1.2.8 Shift Technical Advisor station is committed to meeting NUREG-0737 TMI Action Plan item I.A.1.1 for shift technical isors. The shift technical advisor (STA) reports directly to the manager in charge on-shift and ides advanced technical assistance to the operating shift complement during normal and ormal operating conditions. The STAs responsibilities are detailed in plant administrative 13.1-22 Revision 1
Activities to monitor core power distribution and critical parameters.
Activities to assist the operating shift with technical expertise during normal and emergency conditions.
Evaluation of technical specifications, special reports, and procedural issues.
STA is to primarily contribute to maximizing safety of operations by independently observing t status and advising shift supervision of conditions that could compromise plant safety. During sients or accident situations the STA independently assesses plant conditions and provides nical assistance and advice to mitigate the incident and minimize the effect on personnel, the ironment, and plant equipment.
RO on shift who meets the qualifications for the combined SRO/STA position specified for ion 1 of Generic Letter 86-04 (Reference 202) may also serve as the STA. If this option is used for ift, then the separate STA position may be eliminated for that shift.
1.2.1.2.9 Engineer - Fire Protection engineer in charge of fire protection and the fire protection program staff are responsible for the wing:
Fire protection program requirements, including consideration of potential hazards associated with postulated fires, knowledge of building layout, and system design.
Post-fire shutdown capability.
Design, maintenance, surveillance, and QA of fire protection features (e.g., detection systems, suppression systems, barriers, dampers, doors, penetration seals and fire brigade equipment).
Fire prevention activities (administrative controls and training).
Fire brigade organization and oversight of fire brigade training.
Pre-fire planning including review and updating of pre-fire plans at least every two years.
engineer in charge of fire protection reports through engineering department management to the executive in charge of plant management who has ultimate responsibility for fire protection of the
- t. Additionally, the engineer in charge of fire protection works with the manager in charge of rations to coordinate activities and program requirements with the operations department. In ordance with Regulatory Guide 1.189 the engineer in charge of fire protection is a graduate of an ineering curriculum of accepted standing and has completed not less than six years of ineering experience, three of which were in a responsible position in charge of fire protection ineering work. The engineer in charge of fire protection is trained and experienced in nuclear t safety or has available personnel who are trained and experienced in nuclear plant safety.
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rdination of radwaste activities. The Radwaste Operations Lead reports to the operations ager in charge on-shift.
Radwaste Operations lead supervises radwaste operators assigned to the radwaste area.
1.2.1.3 Conduct of Operations ion operations are controlled and/or coordinated through the control room. Maintenance vities, surveillances, and removal from/return to service of SSCs affecting the operation of the t may not commence without the approval of senior control room personnel. The rules of practice ontrol room activities, as described by administrative procedures, which are based on Regulatory de 1.114, address the following:
Position/placement of operator at the controls workstation and the expected area of the control room where the majority of the supervisor/manager in charge on-shifts time should be spent.
Definition and outline of surveillance area and requirement for continuous surveillance by the operator at the controls.
Relief requirements for operator at the controls and the supervisor/manager in charge on-shift.
ccordance with 10 CFR 50.54:
Reactivity controls may be manipulated only by licensed reactor operators and senior reactor operators except as allowed for training under 10 CFR Part 55.
Apparatus and mechanisms other than controls which may affect reactivity or power level of the reactor shall be operated only with the consent of the operator at the controls or the manager/supervisor in charge on-shift.
During operation of the facility in modes other than cold shutdown or refueling a senior operator shall be in the control room and a licensed reactor operator or senior reactor operator shall be present at the controls.
1.2.1.4 Operating Shift Crews nt administrative procedures implement the required shift staffing. These procedures establish ws with sufficient qualified plant personnel to staff the operational shifts and be readily available in event of an abnormal or emergency situation. The objective is to operate the plant with the uired staff and to develop work schedules that minimize overtime for plant staff members who orm safety-related functions. Work hour limitations and shift staffing requirements defined by TMI on Plan I.A.1.3 are retained in station procedures. When overtime is necessary the provisions in technical specifications and the plant administrative procedures apply. Shift crew staffing plans be modified during refueling outages to accommodate safe and efficient completion of outage k in accordance with the proceduralized work hour limitations.
minimum composition of the operating shift crew is contingent upon the unit operating status.
ition titles, license requirements and minimum shift manning for various modes of operation are 13.1-24 Revision 1
1.2.1.5 Fire Brigade station is designed and the fire brigade organized to be self-sufficient with respect to firefighting vities. The fire brigade is organized to deal with fires and related emergencies that could occur. It sists of a fire brigade leader and a sufficient number of team members to be consistent with the ipment that must be put in service during a fire emergency. A sufficient number of trained and sically qualified fire brigade members are available on site during each shift. The fire brigade sists of at least five members on each shift. Members of the fire brigade are knowledgeable of ding layout and system design. The assigned fire brigade members for any shift does not include manager in charge on-shift nor any other members of the minimum shift operating crew essary for safe shutdown of the unit. Nor does it include any other personnel required for other ential functions during a fire emergency. Fire brigade members for a shift are designated in ordance with established procedures at the beginning of the shift.
1.3 Qualifications of Nuclear Plant Personnel 1.3.1 Qualification Requirements lifications of managers, supervisors, operators, and technicians of the operating organization t the qualification requirements in education and experience for those described in SI/ANS-3.1-1993 (Reference 201), as endorsed and amended by Regulatory Guide 1.8. For itions that do not have a cross-reference section in ANSI/ANS-3.1 the most comparable section NSI/ANS-3.1 is used for guidance in establishing experience and education requirements.
1.3.2 Qualifications of Plant Personnel umes and/or other documentation of qualification and experience of initial appointees to ropriate management and supervisory positions are available for review by regulators upon uest after position vacancies are filled.
1.4 Combined License Information Item organizational structure is addressed in Subsections 13.1, 13.1.1.2.11, 13.1.2, 13.1.2.1.3,
.3, and Appendix 13AA.
1.5 References
. American Nuclear Society, American National Standard for Selection, Qualification, and Training of Personnel for Nuclear Power Plant, ANSI/ANS -3.1-1993.
. U.S. Nuclear Regulatory Commission, Generic Letter 86-04, Policy Letter, Engineering Expertise on Shift.
. American Nuclear Society, American National Standard for Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants, ANSI/ANS-3.2-1988.
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Expected Function Position - Expected additional ANSI/ANS-3.1-1993 Nuclear Plant Position Positions positions Nuclear Function section reference (Site-Specific) 1st unit 2nd unit cutive management chief executive officer n/a President and Chief Executive Officer, Duke Energy 1 -
n/a President, Duke Energy Nuclear 1 -
chief nuclear officer n/a Group Executive, Chief Nuclear Officer 1 -
executive, nuclear operations n/a Executive, Nuclear Operations 1 -
executive, nuclear generation n/a Executive, Nuclear Plant Development 1 0 and development lear support executive, nuclear support n/a Executive, Corporate Governance and Operations 1 -
Support
n/a Executive, Corporate Organizational Effectiveness 1 -
manager 4.2.4 Manager, Nuclear Plant Support 1 -
nt management executive n/a Site Executive, Plant Management 1 -
plant manager 4.2.1 Nuclear Station Plant Manager 1 -
ineering executive n/a Executive, Nuclear Engineering 1 -
executive n/a Executive, Major Projects 1 -
manager 4.2.4 Functional Manager, Engineering 1 -
manager 4.2.4 Manager, Nuclear Support Services 1 -
system engineering functional manager 4.3.9 Functional Manager, Plant Engineering 1 -
system engineer 4.6.1 System Engineer 16 4 design engineering functional manager 4.3.9 Functional Manager, Design Engineering 1 -
design engineer 4.6 - staff Design Engineer 23 7 engineer safety and functional manager 4.3.9 Manager, Safety and Engineering Analysis 1 -
engineering analysis programs engineer 4.6 - staff Analysis Engineer 4 -
engineer 13.1-26 Revision 1
Expected Function Position - Expected additional ANSI/ANS-3.1-1993 Nuclear Plant Position Positions positions Nuclear Function section reference (Site-Specific) 1st unit 2nd unit engineering programs functional manager 4.3.9 Functional Manager, Engineering Programs 1 -
programs engineer 4.6 - staff Programs Engineer 20 5 engineer reactor engineering functional manager 4.3.9 Functional Supervisor, Reactor Engineering 1 -
reactor engineer 4.6 - staff Reactor Engineer 3 1 engineer ntenance manager 4.2.3 Manager, Maintenance 1 -
instrumentation and functional manager 4.3.4 Functional Manager, Instrumentation and Control 1 -
control supervisor 4.4.7 Supervisor, Instrumentation and Control 7 -
technician 4.5.3.3 Instrumentation and Control Technician 30 17 mechanical functional manager 4.3.6 Manager, Mechanical 1 -
supervisor 4.4.9 Supervisor, Mechanical 9 -
technician 4.5.7.2 Mechanic 30 14 electrical functional manager 4.3.5 Manager, Electrical 1 -
supervisor 4.4.8 Supervisor, Electrical 6 4 technician 4.5.7.1 Electrician 18 3 support functional manager 4.3 Manager, Maintenance Support 1 -
rations manager 4.2.2 Manager, Operations 1 -
operations, plant functional manager 4.3.8 Assistant Operations Manager 1 -
operations, admin functional manager 4.3.8 Assistant Operations Manager Support 1 -
operations, radwaste supervisor 4.4 Lead - Radwaste Operations 1 1 13.1-27 Revision 1
Expected Function Position - Expected additional ANSI/ANS-3.1-1993 Nuclear Plant Position Positions positions Nuclear Function section reference (Site-Specific) 1st unit 2nd unit operations, (on-shift) functional manager 4.4.1 Shift Manager 5 5 supervisor 4.4.2 Shift Supervisor 5 5 licensed operator 4.5.1 Control Room Operator 10 10 non-licensed operator 4.5.2 Plant Equipment Operator 30 30 shift technical advisor 4.6.2 Shift Technical Advisor 5 5 protection supervisor 4.4 Engineer, Fire Protection Program 1 -
iation protection functional manager 4.3.3 Functional Manager, Radiation Protection 1 -
supervisor 4.4.6 Radiation Protection Functional Supervisor 3 -
technician 4.5.3.2 Radiation Protection Technician 20 10 ALARA specialist n/a ALARA Specialist 2 -
mistry functional manager 4.3.2 Functional Manager, Chemistry and Environmental 1 -
supervisor 4.4.5 Chemistry Functional Supervisor 3 -
technician 4.5.3.1 Chemistry Technician 14 12 radwaste operator 4.5.2 Radwaste Operator 5 4 lear safety assurance manager 4.2 Functional Manager, Organizational Effectiveness 1 -
licensing functional manager 4.3 Manager, Plant Licensing and Regulatory - -
Compliance supervisor n/a Functional Supervisor, Licensing and Regulatory 1 0 Programs licensing engineer n/a Licensing Engineer 5 -
corrective action functional manager 4.3 Functional Supervisor, Corrective Action and 1 -
Performance Improvement corrective action engineer n/a corrective action engineer 2 -
emergency functional manager 4.3 Functional Supervisor, Emergency Preparedness 1 -
preparedness 13.1-28 Revision 1
Expected Function Position - Expected additional ANSI/ANS-3.1-1993 Nuclear Plant Position Positions positions Nuclear Function section reference (Site-Specific) 1st unit 2nd unit EP planner n/a EP Planner 2 -
ning functional manager 4.3.1 Functional Manager, Training and Development 1 -
supervisor ops trng 4.4.4 Training Supervisor, Operations 1 -
ops training instructor n/a Ops Training Instructor 6 6 supervisor tech staff/maint trng 4.5.4 Supervisor Tech Staff/Maint Trng 1 -
tech staff/maint instructors 4.4.4 Tech Staff/Maint Instructor 8 -
chasing, and contracts functional manager 4.3 Functional Manager, Purchasing and Contracts 1 -
urity functional manager 4.3 Functional Manager, Security 1 -
nning and scheduling functional manager 4.3 Functional Manager, Planning and Scheduling 1 -
functional manager 4.3 Functional Manager, Outages 1 -
lity assurance functional manager 4.3.7 Functional Manager, Nuclear Oversight 1 -
supervisor 4.4.13 Quality Assurance Supervisor 1 -
QA auditor 4.5.6 QA Auditor 6 -
supervisor 4.4.13 Quality Control Supervisor 1 -
QC inspector 4.5.5 QC Inspector 4 2 tup testing supervisor 4.4.11 Startup Testing Supervisor 1 -
startup test engineer 4.4.1 Startup Test Engineer 6 -
supervisor 4.4.12 Preop Testing Supervisor 1 -
preop test engineer 4.4.1 Preop Test Engineer 20 -
13.1-29 Revision 1
Units Operating Two Units Two Control Rooms All Units Shutdown 1 SM (SRO) 2 RO 3 NLO One Unit Operating(a) 1 SM (SRO) 1 SRO 3 RO 3 NLO Two Units Operating(a) 1 SM (SRO) 2 SRO 4 RO 4 NLO SM - shift manager RO - Licensed Reactor Operator SRO - Licensed Senior Reactor Operator NLO - non-licensed operator a) Operating modes other than cold shutdown or refueling.
s:
In addition, one Shift Technical Advisor (STA) is assigned per shift during plant operation. A shift manager or another SRO on shift, who meets the qualifications for the combined Senior Reactor Operator/Shift Technical Advisor position, as specified for option 1 of Generic Letter 86-04 (Reference 202), the commissions policy statement on engineering expertise on shift, may also serve as the STA. If this option is used for a shift, then the separate STA position may be eliminated for that shift.
In addition to the minimum shift organization above, during refueling a licensed senior reactor operator or senior reactor operator limited (fuel handling only) is required to directly supervise any core alteration activity.
A shift manager/supervisor (SRO licensed for each unit that is fueled), shall be on site at all times when at least one unit is loaded with fuel.
A radiation protection technician shall be on site at all times when there is fuel in a reactor.
A chemistry technician shall be on site during plant operation in modes other than cold shutdown or refueling.
To operate, or supervise the operation of more than one unit, an operator (SRO or RO) must hold an appropriate, current license for each unit.
13.1-30 Revision 1
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ning programs incorporate instructional requirements to qualify personnel to operate and ntain the facility in a safe manner in all modes of operation (Reference 202). The programs are eloped and maintained in compliance with the facility license and applicable regulations. The ing programs are periodically evaluated and revised to reflect industry experience and to rporate changes to the facility, procedures, regulations, and quality assurance requirements, and periodically reviewed by management for effectiveness. These training programs are described te and/or corporate procedures, as appropriate. Sufficient records are maintained and kept ilable for NRC inspection to verify adequacy of the programs.
Training Department provides the required training based on individual employee experience, intended position, and previous training and education. Training Department personnel may be plemented by other personnel such as subject matter experts, contract staff, and vendor esentatives. Formal instruction may be presented through a combination of classroom lectures, arning, assigned reading, simulator training and evaluations, and other delivery techniques.
reactor operators, senior reactor operators, fuel handlers, fire protection personnel, and positions cified in 10 CFR 50.120 (Reference 13.2-4), programs are developed, established, implemented maintained using a systems (or systematic) approach to training (SAT) as defined by CFR 55.4 (Reference 13.2-8) and ANSI/ANS-3.1-1993 (Reference 13.2-14), as endorsed by ulatory Guide 1.8 (Reference 13.2-16).
al and continuing training programs accredited by the National Academy for Nuclear Training NT) provide personnel with the skills and knowledge to perform assigned tasks. Accredited ing programs include the following:
Non-licensed operator Reactor operator Senior reactor operator Shift manager Shift technical advisor Continuing training for licensed personnel Instrument and control technician and supervisor Electrical maintenance personnel and supervisor Mechanical maintenance personnel and supervisor Chemistry technician Radiological protection technician Engineering personnel results of reviews of operating experience are incorporated into training and retraining programs ccordance with the provisions of TMI Action Item I.C.5, Appendix 1A. Training programs ompass all phases of plant operation including preoperational testing and low-power operation in ordance with the provisions of TMI Action Item I.G.1 (Reference 13.2-19). Before initial fuel ing, sufficient plant staff will be trained to provide for safe plant operations. Table 13.4-201 ides milestones for training implementation.
rators involved in the Human Factors Engineering Verification and Validation (V&V) Program ive additional training specific to the task of performing V&V. A systematic approach to training is rporated in developing this training program along with input from WCAP-14655, Designers 13.2-1 Revision 1
pter 18, Section 18.10 references WCAP 14655. This document describes input from the igner on the training of the operations personnel who participate as subjects in the human factors ineering (HFE) verification and validation. The WCAP also describes how training insights are sed from the designer.
2.1 Licensed Operator Training Reactor Operator (RO) and Senior Reactor Operator (SRO) training programs, including initial requalification training, provide the means to train individuals in the knowledge, skills, and ties needed to perform licensed operator duties. The licensed operator training program includes requalification program as required by 10 CFR 55.59 (Reference 13.2-13). Collectively, ROs and Os are referred to as Licensed Operators. Before initial fuel loading, the number of persons ed in preparation for RO and SRO licensing examinations will be sufficient to meet regulatory uirements, with allowances for examination contingencies and without the need for planned rtime.
site employs a simulator in accordance with 10 CFR 55.46. This simulator is used for training nsed personnel, and for the administration of the operating test.
2.1.1 Licensed Operator Initial Training Program Licensed Operator Initial Training Program prepares RO and SRO candidates for the NRC nse exam. This program is implemented in accordance with administrative procedures.
2.1.1.1 Reactor Operator ctor Operator candidates receive training in the topics listed in 10 CFR 55.41 (Reference 13.2-9) candidates receive plant simulator training to demonstrate understanding and the ability to orm the actions listed in 10 CFR 55.45 (Reference 13.2-11).
2.1.1.2 Senior Reactor Operator ddition to the Reactor Operator topics listed in 10 CFR 55.41 (Reference 13.2-9), candidates for Senior Reactor Operator license receive training in the topics listed in 10 CFR 55.43 ference 13.2-10). SRO candidates receive plant simulator training to demonstrate understanding the ability to perform the actions listed in 10 CFR 55.45 (Reference 13.2-11).
2.1.2 Continuing Training for Licensed Personnel tinuing training for licensed personnel consists of regularly scheduled formal instruction, luation, and on-the-job training. Training material is developed using the SAT process, and udes Operational Experience (OE). Licensed operators participate in continuing training.
gram content, course schedules and examination schedules comply with 10 CFR 55.59 ference 13.2-13). Continuing training for licensed personnel is conducted in accordance with inistrative procedures.
13.2-2 Revision 1
ference 13.2-4). The systematic approach to training (SAT) process is used to establish and ntain training programs. Course duration and content are determined by the SAT process and by inistrative procedure. This program will commence no later than eighteen months prior to initial loading.
2.2.1 Non-Licensed Operator (NLO) Initial Training sonnel employed as NLOs receive instruction on operation of plant equipment and components er normal and emergency conditions. This program is a combination of formal instruction and he-job training. Training is given in:
Fundamentals of mechanical and electrical components Operation of equipment and systems Operating procedures Surveillance requirements Operation of systems important to plant safety lant training includes system walk downs, which emphasize the use of procedures, the proper ration of equipment, and safe operating practices.
2.2.2 Shift Manager Initial Training t managers have been trained as Senior Reactor Operators and receive additional training that resses higher-level management skills and behaviors, and provides a broader perspective of t operations. Initial training includes such topics as:
Application of Operating Experience Problem-solving skills Planning and managing evolutions Maintaining a broad view of plant operations Application of observation skills Operating philosophy Shift team management Application of design bases to plant operations Emergency Plan Transient and Accident Analysis Systematic Approach to Training Work controls 2.2.3 Shift Technical Advisor Initial Training Program t technical advisors provide engineering expertise on-shift. Training provides them with the skill knowledge to monitor equipment and system operation, and assess plant conditions during ormal and emergency events. Initial training for individuals who fill the position of shift technical isor includes instruction in the following areas:
Responses to accidents and analyses of plant transients Application of engineering principles to protection of the core Mitigation of plant accidents Basis of plant and systems design 10 CFR 52.78 (Reference 13.2-6) requires that Combined License applicants demonstrate compliance with 10 CFR 50.120.
13.2-3 Revision 1
Simulator training, including exercises in the following situations:
Plant or reactor startups to include a range such that reactivity feedback from nuclear heat addition is noticeable and heatup rate is established Plant shutdown Manual control of feedwater during startup or shutdown.
Significant (10 percent) power changes due to manual changes in control rod position.
Accident response training 2.2.4 Instrumentation and Control (I&C) Technician Initial Training al training for I&C technicians includes instruction in the following areas:
Fundamentals of instrumentation and control Pneumatic systems and equipment Electronics Fundamental systems training I&C and other job related procedures Surveillance requirements Mitigating core damage training commensurate with their responsibilities during accidents that involve severe core damage On-the-job training the-job training allows I&C technicians to practice the skills learned in the classroom under the ance of experienced and qualified I&C personnel.
2.2.5 Electrical Maintenance Initial Training Program al training for electrical maintenance technicians includes instruction in the following areas:
Print reading Use of electrical tools and test equipment Fundamental systems training Electrical components and equipment Electrical maintenance practices Maintenance procedures On-the-job training the-job training allows Electricians to practice the skills learned in the classroom under the ance of experienced and qualified electrical maintenance personnel.
2.2.6 Mechanical Maintenance Initial Training Program al training for mechanical maintenance technicians includes instruction in the following areas:
Print reading Use of hand tools, power tools, and measurement devices Fundamental systems training Mechanical components and equipment Mechanical maintenance practices Maintenance procedures On-the-job training 13.2-4 Revision 1
2.2.7 Radiological Protection Technician Initial Training al training for radiological protection technicians includes instruction in the following areas:
Principles of radiation Radiation protection and safety Use of survey instruments Use of analytical equipment Radiation Protection procedures Emergency Plan procedures ALARA practices and procedures Fundamental systems training Mitigating core damage training commensurate with their responsibilities during accidents that involve severe core damage the-job training provides the trainee opportunities to practice actual operation of radiation ection equipment and use of procedures under the guidance of experienced technicians. Further rmation on training for radiological protection technicians can be found in Section 12.5.
2.2.8 Chemistry Technician Initial Training al training for chemistry technicians includes instruction in the following areas:
Chemistry procedures Laboratory practices Conduct of analytical tests Operation of laboratory equipment Fundamental systems training On-the-job training to include actual operation of analytical equipment and the use of procedures Mitigating core damage training commensurate with their responsibilities during accidents that involve severe core damage Power plant chemistry the-job training provides the trainee opportunities to practice actual operation of analytical ipment and use of procedures under the guidance of experienced technicians.
2.2.9 Engineering Personnel Initial Training ineering personnel complete orientation training on topics such as those listed below. The topics chosen to familiarize engineering support personnel with various aspects of nuclear technology in perating plant environment. Training topics include:
Records management and document control Applicable industrial and nuclear regulations, codes, and standards Procedures and drawings Applicable programs such as corrective action, configuration management, work control, and the QA program Technical Specifications Fundamentals such as reactor theory, heat transfer, fluid flow, properties of materials, and chemistry Plant systems, instrumentation, and components 13.2-5 Revision 1
2.2.10 Continuing Training for Personnel Listed in 10 CFR 50.120
-licensed plant personnel specified in Subsection 13.2.2 [i.e., personnel listed in 10 CFR 50.120 ference 13.2-4)] receive continuing training to maintain qualifications and enhance proficiency.
tinuing training reinforces initial training by reiterating selected portions of the material.
tinuing training also addresses new and modified procedures and plant design changes.
rating Experience (OE) is included in continuing training, providing personnel with actual mples of good practices and lessons learned. OE topics are selected from Licensee Event orts, corrective action databases, industry groups, and other sources.
tinuing training material is developed in accordance with the systematic approach to training and onducted in accordance with administrative procedures.
qualifications are maintained by participation in continuing training for licensed personnel.
2.3 General Employee Training (GET) Program 2.3.1 Plant Access Training art of the GET program, members of the station staff, contractor workers, and unescorted visitors icipate in Plant Access Training, which consists of the following topics, prior to being granted scorted access to the plant:
Station organization Station facilities and layout Station administration Nuclear plant overview Industrial safety Fire protection Quality assurance and quality control Plant security Emergency planning Radiological orientation Appropriate portions of 10 CFR 26 (Reference 13.2-2)
Appropriate portions of 10 CFR 19 (Reference 13.2-1) 2.3.2 Radiation Worker Training Program sonnel whose job duties require them to have unescorted access to radiologically controlled as of the plant receive instruction in the applicable aspects of radiation protection. Topics include following:
Sources of radiation Types and measurement of radiation Biological effects Limits and guidelines, including Reg. Guide 8.13 (Reference 13.2-18)
Concept of As Low As Reasonably Achievable (ALARA)
Radiation dosimetry Contamination Internal exposure 13.2-6 Revision 1
Radioactive waste Rights and responsibilities Protective clothing 2.3.3 General Employee Requalification Training sonnel with unescorted access to the plant participate in annual requalification training.
ualification training includes those topics in Subsections 13.2.3.1 and 13.2.3.2, as applicable to ess requirements. Emphasis is placed on significant changes to the plant, plant procedures, ernment regulations regarding the operation of the plant, and quality assurance requirements. As licable, training is conducted on industry operating experiences, Licensee Event Reports, and onnel errors.
2.4 Selected Other Training Programs subsection addresses training for positions not specified by 10 CFR 55 (Reference 13.2-7) or CFR 50.120 (Reference 13.2-4).
2.4.1 Fire Protection Training al fire protection training is completed prior to receipt of fuel at the site. Personnel assigned as fire ade members receive formal training prior to assuming brigade duties, and regularly scheduled aining. Fire brigade training complies with NFPA Standard 600 (Reference 13.2-15).
ning appropriate to the assigned work is also provided for the fire protection staff, fire watch onnel, and the general employee. Subsection 9.5.1 includes additional information regarding fire ection training.
2.4.2 Emergency Plan Training Program ergency Plan training meets the requirements of 10 CFR 50 Appendix E Section IV.F ference 13.2-5) and the standards of 10 CFR 50.47(b)(15) (Reference 13.2-3). Further details of Emergency Plan training program can be found in the Emergency Plan, which is a separate ument.
2.4.3 Physical Security Training Program ning of security personnel is discussed in Section 13.6 and in the Physical Security Plan, which separate document.
2.4.4 Station Management Training Program ion supervisors receive Fitness for Duty (FFD) supervisory training in accordance with CFR 26.22. The remaining definitions and recommendations in this subsection are taken from SI/ANS-3.1-1993 (Reference 13.2-14) as endorsed by Regulatory Guide 1.8 (Reference 13.2-16).
qualification requirements for managers and middle managers include training or experience in ervision or management. Training for supervisors develops their skills in the following areas:
Leadership Interpersonal communications Management responsibilities and limits 13.2-7 Revision 1
Observation skills Coaching 2.5 Training Effectiveness Evaluation Program program to evaluate the effectiveness of training programs is based on three independent inputs erspectives: the supervisor of the trainee, the trainee, and an educational content evaluation.
h of these reviews is discussed below.
2.5.1 Supervisory Review for Training Effectiveness purpose of this review is to monitor the content and effectiveness of training programs as related e duties and job responsibilities of the trainees. Reviews may be performed by supervisors of loyees meeting with appropriate Training personnel, by designated oversight personnel, or by erving subsequent job performance. Observations are discussed to determine topics that may uire additional training or subjects that may be removed from the training program.
2.5.2 Trainee Review of Training Effectiveness owing selected courses, or training cycles, trainees have the opportunity to provide comments arding the effectiveness of the instructional methods and content relevancy to their jobs. These ments are used in the evaluation of both instruction and content of the training program.
2.5.3 Review for Effectiveness of Instructional Techniques and Materials ning material and instructional aids are assessed for clarity and applicability. Observations of ructors in the teaching environment are conducted by this qualified individual to monitor sroom performance. Full time instructors receive basic indoctrination in instructional techniques oon as practicable after assuming instructional duties. The educational specialist conducts odic seminars in instructional techniques, discussing areas where group performance could be roved and recommends innovative techniques observed at this or other power stations.
2.6 Combined License Information Item training programs for plant personnel, including the training program for the operations onnel who participate as subjects in the human factors engineering verification and validation the scope of licensing examinations, as well as new training requirements, are addressed in tion 13.2.
2.7 References 2-1. 10 CFR 19, "Notices, Instructions, and Reports to Workers; Inspection and Investigations" 2-2. 10 CFR 26, "Fitness for Duty" 2-3. 10 CFR 50.47, "Emergency Plans" 2-4. 10 CFR 50.120, "Training and Qualification of Nuclear Power Plant Personnel" 2-5. 10 CFR 50 Appendix E, "Emergency Planning and Preparedness for Production and Utilization Facilities" 13.2-8 Revision 1
2-7. 10 CFR 55, "Operator's Licenses" 2-8. 10 CFR 55.4, "Definitions" 2-9. 10 CFR 55.41, "Written Examinations: Operators" 2-10. 10 CFR 55.43, "Written Examinations, Senior Operators" 2-11. 10 CFR 55.45, "Operating Tests" 2-12. 10 CFR 55.46(c), "Plant-Referenced Simulators" 2-13. 10 CFR 55.59, "Requalification" 2-14. American National Standards Institute, "Selection, Qualification, and Training of Personnel for Nuclear Power Plants," ANSI/ANS-3.1-1993 2-15. National Fire Protection Association, "Standard on Industrial Fire Brigade," NFPA Standard 600, 2005 Edition 2-16. U.S. Nuclear Regulatory Commission, "Qualification and Training of Personnel for Nuclear Power Plants," Regulatory Guide 1.8, Revision 3, May 2000 2-17. U.S. Nuclear Regulatory Commission, "Nuclear Power Plant Simulation Facilities for Use in Operator Training and License Examinations," Regulatory Guide 1.149, Revision 3, October 2001 2-18. U.S. Nuclear Regulatory Commission, "Instruction Concerning Prenatal Radiation Exposure," Regulatory Guide 8.13, November, 1980.
2-19. U.S. Nuclear Regulatory Commission, "Clarification of TMI Action Plan Requirements", NUREG-0737, Revision 3, June 1999 2-20. U.S. Nuclear Regulatory Commission, "Policy Statement on Engineering Expertise on Shift", GL 86-04
. Westinghouse, "Designer's Input to the Training of the Human Factors Engineering Verification and Validation Personnel," WCAP-14655, Revision 1, August 1996.
. NEI 06-13A, Template for an Industry Training Program Description, Nuclear Energy Institute, Revision 2, March 2009.
13.2-9 Revision 1
UELING OUTAGE r to operation, plant experience requirements specified in Regulatory Guide 1.8 (Revision 3) and SI/ANS 3.1-1993 cannot be met. Additionally, other standard guidance for operator selection, ing, and qualification cannot be met.
d licensing of operators provides the method for operations personnel to acquire the knowledge experience required for licensed operator duties during the unique conditions of new plant struction and initial operation.
sons eligible for the cold license process shall meet the following requirements:
Candidates for a Reactor Operator license shall have a High School Diploma or equivalent as required by R.G. 1.8 Revision 3.
Candidates for a Senior Reactor Operator license shall have at least one of the following qualifications:
- Previously held a Senior Reactor Operator license for an operating nuclear power plant.
- Previously held a Reactor Operator license for an operating nuclear power plant.
- Bachelor's Degree in engineering or science as defined by R.G. 1.8 Revision 3.
- Experience as a licensed operator training instructor with an SRO certification. This experience will be evaluated and approved on a case by case basis by the NRC.
- Two years military experience in a position equivalent to a reactor operator.
provisions in this section are applicable to each unit of a multiple unit site separately.
cold licensing process for the selection, training and licensing of Operations personnel for the nuclear plants adheres to current industry guidance for operating plants with exemptions and rnatives in the following areas.
2A.1 Licensed Operator Experience Requirements Prior To Commercial Operation nsed operator candidates need not satisfy the experience requirements prior to entering a nsed operator training program. Experience and plant evolution requirements that have not been at the time the licensed operator examination is administered shall be met prior to issuing the vidual's NRC operator license. In such a case, the Licensee will notify the NRC when the didate meets the experience and plant evolution requirements.
methods listed below provide the licensed operator candidate with meaningful experience on the tor for which the license is sought. Methods for gaining meaningful experience include pleting systematically designed training courses, and participating in practical work assignments h as preoperational testing, procedure development and validation, human factors engineering vities, task analysis verification, or conducting licensed operator classroom or simulator training.
itionally, for these activities to be considered meaningful, they must be associated with safety ificant, defense-in-depth, or other major plant components or systems. All cold licensed operator didates will:
13.2A-1 Revision 1
licensed operator tasks. The selected non-licensed operator tasks are those tasks that are important to plant operation with regard to nuclear safety, defense-in-depth, or that are risk significant.
Participate in practical work assignments for a minimum of six months that includes preoperational testing, and one or more of the following:
- Procedure development and validation
- Human factors engineering activities
- Task analysis verification
- Licensed operator classroom presentations or simulator training implementation ior reactor operator cold license candidates will complete a site-specific reactor operator and ior reactor operator training course.
ior reactor operator cold license candidates without "hot" plant experience will complete a plant rational excellence course that is conducted in a plant simulator or they will observe control room vities at an operating nuclear plant for at least six weeks. The course and the observation activity designed to familiarize the candidate with the operational interfaces encountered by decision ers in a nuclear plant control room.
plant experience is defined as performance of senior reactor operator duties for at least six ths including:
At least 6 weeks of operation above 20 percent power A startup from subcritical to 20 percent power A shutdown from above 20 percent power to cold (less than 212°F) and subcritical Startup preparations following a fueling or refueling outage startup, shutdown, and startup preparations may have been performed at an operating plant or a t simulator.
le 13.2A-201, Comparison of Hot and Cold License Guidance, shows the current experience uirement and the associated cold license experience method. Table 13.2A-202, Illustration of Cold nsing Plan by Candidate Type, shows education and experience methods for each licensed rator candidate type.
2A.2 Crew Experience Requirements during First Year of Operation h operating crew's cumulative nuclear power plant experience shall be > 6 years; and the crew's ulative power plant experience shall be > 13 years.
crew's cumulative nuclear power plant experience is gained by working at nuclear power plants military nuclear propulsion plants, conducting licensed operator training, participating in new lear plant construction and testing, and completing academic degree requirements. The 13.2A-2 Revision 1
en determining cumulative nuclear power plant experience, all 6 years shall not be attributed from crew member.
crew's cumulative power plant experience is the sum of each individual's power plant erience. Power plant experience, for example, is experience gained by working at nuclear power ts, conventional power plants, and military propulsion plants. Cumulative power plant experience s not involve weighting factors or maximum credit limits.
ddition to the experience requirement mentioned above, each operating crew shall be staffed with nior reactor operator with hot plant experience (previously defined in 1.1, Licensed Operator erience Requirements Prior to Commercial Operation). If a senior reactor operator with hot plant erience is not available, then a shift advisor may be substituted. The shift advisor will have at t one year of on-shift licensed senior reactor operator experience at a similar type (PWR/BWR) rating plant, and will have completed a training program on the design for which they are ising. While observing crew performance, the shift advisor will make recommendations to the shift ager only, and will not interfere with the licensed responsibilities of the operating crew. The shift isor will have direct access to plant senior management to resolve issues. Shift advisor duties ude, but are not limited to the following:
Monitor procedure adherence Observe the conduct of prejob briefs, shift turnover, plant evolutions, non- licensed operator rounds, plant tours, and post job debriefs Monitor overall station risk ghting factors and maximum credit limits for determining cumulative nuclear power plant rating crew experience are shown in Table 13.2A-203, Cumulative Nuclear Power Plant rating Crew Experience Equivalencies.
2A.3 Conduct of On-the-Job Training (OJT) l plant construction is completed, acceptable methods for the conduct of on-the-job training ude discussion, simulation, and use of mockup equipment and virtual reality technology.
2A.4 Use of Part-Task/Limited Scope Simulators
-task or limited scope simulators may be used during licensed operator training.
2A.5 Licensed Operator Continuing Training nsed operator continuing training begins within 90 days following the issuance of the first rator license. Continuing training content is systematically determined to maintain operator wledge of plant operation.
2A.6 Cold Licensing Process Applicability and Termination cold licensing process described in this document may be applied to each unit of a multi-unit site.
13.2A-3 Revision 1
d license guidance items 3 through 9 on Table 13.2A-201 will apply to any licensed operator ing class started after initial fuel load and before completion of the first refueling outage. Items 1 2 cold license guidance are no longer allowable after initial fuel load.
cold licensing process will terminate after completion of the first refueling outage.
plant systems, components, and structures are completed, and as integrated plant operations in, the systematic approach to training process will be used to adjust cold license class training hods and settings used to implement the guidance in Table 13.2A-201 items 1 through 9. The pose is to optimize student learning using actual in-plant training and experience opportunities as become available.
2A.7 Initial Licensed Operator Examination Schedule inistration of licensed operator examinations begins approximately 18 months prior to fuel load.
2A.8 References 2-201. Nuclear Energy Institute (NEI), "Technical Report on a Template for an Industry Training Program Description," NEI 06-13A 13.2A-4 Revision 1
Current Hot License Guidance Applicable Position References Cold License Guidance ANSI 3.1-1993; 4.4.1 4.4.2 Six months practical work assignments Six months on-site at reactor for 4.5.1.
All and which license is sought.
Regulatory Guide 1.8 Rev 3:
Complete a site layout course 2.8 2.10.
NUREG 1021 Rev 9 ES-202 Six months practical work assignments ANSI 3.1-1993:
and 4.5.1. Complete a site layout course and One year on-site at the reactor for Regulatory Guide 1.8 Rev 3: Complete a site-specific non-licensed which the license is sought with Reactor operator operator training program for selected six months as a nonlicensed 2.10. nonlicensed operator tasks operator.
NUREG 1021 Rev 9 ES-202 13.2A-5 Revision 1
Current Hot License Guidance Applicable Position References Cold License Guidance Pre-requisite experience NUREG 1021 Rev 9 ES-202 Applicable experience requirements shall requirements must be met to All be met prior to NRC license issuance.
enter training program.
Section D.
ANSI 3.1-1993:
Six months practical work assignments Three years power plant 4.5.1 experience at least one of which and Reactor operator should have been at the plant for Regulatory Guide 1.8 Rev 3:
which the license is sought. Cumulative operating crew experience 2.10 requirements apply NUREG 1021 Rev 9 ES-202 Complete a site layout course and Regulatory Guide 1.8 Rev 3:
Reactor operator license Complete a site-specific non-licensed Senior reactor operator actively involved in the operator training program for selected 2.8 performance of licensed duties nonlicensed operator tasks (Non-degreed) for at least one year.
NUREG 1021 Rev 9 ES-202 and Complete a reactor operator and senior reactor operator training course 13.2A-6 Revision 1
Current Hot License Guidance Applicable Position References Cold License Guidance Complete a site layout course and Regulatory Guide 1.8 Rev 3:
Complete a site-specific non-licensed At least three years of Senior reactor operator operator training program for selected responsible nuclear power plant 1.3 nonlicensed operator tasks experience. (Degreed) 2.8 and Complete a reactor operator and senior reactor operator training course At least six weeks of operation Cumulative Operating Crew Experience above 20% power, and startup requirements apply from subcritical to 20% power, Shift Supervisor ANSI 3.1-1993:
and shutdown from above 20%
and power to cold (less than 212°F)
(Shift Manager) 4.4.1 and subcritical, and startup Complete a Plant Operational Excellence preparations following a fueling Course or plant observation activity or refueling outage.
13.2A-7 Revision 1
Current Hot License Guidance Applicable Position References Cold License Guidance Cumulative Operating Crew Experience requirements apply ANSI 3.1-1993:
At least six weeks of operation Senior reactor operator and above 20% power.
4.4.2 Complete a Plant Operational Excellence Course or plant observation activity ANSI 3.1-1993 Six months practical work assignments 4.4.1 Three years power plant and experience and three years Senior reactor operator 4.4.2 nuclear power plant experience Regulatory Guide 1.8 Rev 3:
Cumulative Operating Crew Experience requirements apply 2.8 NUREG 1021 Rev 9 ES-202 13.2A-8 Revision 1
Plant Operational Six Months Site Layout NLO Task SRO Excellence Course License Candidate Education RO Training Practical Work Course Training Training or Observation Assignments (1)
Activity actor operator High school diploma Yes Yes Yes N/A N/A Yes nior reactor operator Bachelor of Science or degreed manager or equivalent in engineering, Yes Yes Yes Yes Yes Yes degreed nonlicensed engineering technology, or operator or technical staff physical science nior reactor operator High school diploma Yes Yes Yes Yes Yes (2) Yes previous license or military equivalent nior reactor operator High school diploma Yes Yes Yes Yes Yes Yes certified instructor practical work assignments includes activities such as participating in preoperational testing, procedure development and validation, human factors engineering activities, and task analysis verification, or conducting licensed operator classroom or simulator training No, if candidate has hot license experience 13.2A-9 Revision 1
Type of Experience Weighting Factor Max Credit Justification
- 1. Commercial Nuclear Plant RO/SRO on same type plant Task Analysis for same type plant are 1.00 No Limit (PWR/BWR) essentially the same
- 2. Commercial Nuclear Plant RO/SRO from different type plant Task Analysis demonstrates that 75% of 0.75 No Limit (PWR/BWR) PWR/BWR tasks are similar
- 3. Military Nuclear Propulsion Plant Experience (Propulsion For these military nuclear propulsion Plant Watch Officer, Engineering Watch Supervisor, Reactor plant watch qualifications, 0.5 36 months Operator, Engineering Officer of the Watch, Propulsion Plant approximately 50% of the job tasks are Watch Supervisor) similar
- 4. Military Nuclear Propulsion Plant Experience (Other than For these (other) watch qualifications, a watch qualifications in 3 above such as Machinist Mate, range of similarities between job tasks 0.25 36 months Electricians Mate, Engineering Laboratory Technician, or (25-75%) exists, so a conservative Electronics Technician) value of 25% is credited 13.2A-10 Revision 1
Type of Experience Weighting Factor Max Credit Justification Industry analysis demonstrated that activities completed in a simulator,
- 5. Reference Plant Simulator 5.00 12 months compare to an operating Control Room, occur in a ratio of approx. 400/1
- 6. Limited Scope Simulator 3.00 9 months Similar to Reference Plant Approximately 25% of the tasks during construction testing in preparation for
- 7. Actual nuclear plant experience during construction 0.25 12 months system turnover to operations is similar to an operating facility 75% of tasks during pre- operational
- 8. Actual nuclear plant experience during pre-operational 0.75 12 months testing are similar to an operating testing facility
- 9. Actual nuclear plant experience during fuel load and startup Tasks during initial startup are similar to 1.00 12 months testing operating facility 13.2A-11 Revision 1
Type of Experience Weighting Factor Max Credit Justification Theory of ops and specific plant design
- 10. License Classroom training 0.25 9 months knowledge is critical to an operators success
- 11. Participation in operator duties at another commercial 0.75 12 months Task similarities nuclear facility. This includes nonlicensed operator duties Procedure writing, facility operation
- 12. Other Nuclear Plant experience 0.25 12 months (water plant and other support facilities, etc)
Instructors will have participated in a
- 13. Licensed operator instructor 0.50 12 months train-the- trainer program that includes simulator, classroom (systems, theory).
College work (in these fields) gives
- 14. Bachelors Degree in an Engineering, Science or Technical n/a 24 months student an understanding of the field fundamentals of plant operations 13.2A-12 Revision 1
Type of Experience Weighting Factor Max Credit Justification Student gains knowledge of
- 15. Associates Degree (technical) n/a 6 months fundamentals (1): Weighting factors and max credit values based on those in Industry Evaluation of Operating Shift Experience Requirements By: J.H. Miller Jr. 2/24/1984, and endorsed by Generic Letter number 84-16, Adequacy of On-Shift Operating Experience For Near Term Operating License Applicants, except for shaded rows which are added experience types based on new technology or additional analysis.
13.2A-13 Revision 1
the decontamination facilities. See Section 9.4 for a description of the HVAC systems for the n control room/control support area and the annex building. See Section 18.8 for the high level uirements for the technical support center and the operations support center. See Section 7.5 for tification of plant variables that are provided for interface to the emergency planning areas.
munication interfaces among the main control room, the technical support center and the rgency planning centers are discussed below.
fing of the emergency operations facility occurs consistent with current operating practice and revision 1 of NUREG-0654/FEMA-REP-1.
emergency planning information is submitted to the Nuclear Regulatory Commission as a arate licensing document.
t-72 hour support actions, as discussed in Subsections 1.9.5.4 and 6.3.4, are addressed in sections 6.2.2, 8.3, and 9.1.3. Provisions for establishing post-72 hour ventilation for the main trol room, instrumentation and control rooms, and dc equipment rooms are established in rating procedures.
emergency plan describes the plans for coping with emergency situations, including munications interfaces and staffing of the emergency operations facility.
le 13.4-201 provides milestones for emergency planning implementation.
3.1 Combined License Information Item ergency planning including post-72 hour actions and its communication interface are addressed ection 13.3.
vation of the emergency operations facility consistent with current operating practice and REG-0654/FEMA-REP-1 is addressed in Section 13.3 and in the Emergency Plan.
13.3-1 Revision 1
rational programs are specific programs that are required by regulations. Table 13.4-201 lists h operational program, the regulatory source for the program, the section of the FSAR in which operational program is described, and the associated implementation milestone(s).
4.1 Combined License Information Item rational programs are addressed in Section 13.4.
4.2 References
. ASME Boiler and Pressure Vessel Code (B&PVC),Section XI - Rules for Inservice Inspection of Nuclear Power Plant Components.
. ASME OM Code for the Operation and Maintenance of Nuclear Power Plants.
13.4-1 Revision 1
Implementation Program Source m Program Title (Required by) FSAR Section Milestone Requirement
. Inservice Inspection Program 10 CFR 50.55a(g) 5.2.4, Prior to Commercial service 10 CFR 50.55a(g),
5.4.2.5, ASME XI IWA-2430(b) 6.6 (Reference 201)
. Inservice Testing Program 10 CFR 50.55a(f); 3.9.6, After generator online on nuclear 10 CFR 50.55a(f),
10 CFR Part 50, 5.2.4 heat(a) ASME OM Code Appendix A (Reference 202)
. Environmental Qualification Program 10 CFR 50.49(a) 3.11 Prior to initial fuel load License Condition
. Preservice Inspection Program 10 CFR 50.55a(g) 5.2.4, Completion prior to initial plant 10 CFR 50.55a(g);
5.4.2.5, start-up ASME XI IWB-2200(a) 6.6 (Reference 201)
. Reactor Vessel Material Surveillance 10 CFR 50.60; 5.3.2.6 Prior to initial criticality License Condition Program 10 CFR 50.61; 10 CFR Part 50, Appendix H
. Preservice Testing Program 10 CFR 50.55a(f) 3.9.6 Prior to initial fuel load License Condition
. Containment Leakage Rate Testing Program 10 CFR 50.54(o); 6.2.5.1 Prior to initial fuel load License Condition 10 CFR 50, Appendix A (GDC 52);
. Fire Protection Program 10 CFR 50.48 9.5.1.8 Prior to receipt of fuel onsite License Condition Prior to initial fuel load (portions applicable to radioactive material) 10 CFR 30.32 Prior to initial receipt of byproduct, 10 CFR 30.32(a) 10 CFR 40.31 source, or special nuclear 10 CFR 40.31(a) 10 CFR 70.22 materials (excluding Exempt 10 CFR 70.22(a)
Quantities as described in 10 CFR 30.18) 13.4-2 Revision 1
Implementation Program Source m Program Title (Required by) FSAR Section Milestone Requirement
. Process and Effluent Monitoring and Sampling Program:
Radiological Effluent Technical 10 CFR 20.1301 and 11.5 Prior to initial fuel load License Condition Specifications/Standard Radiological 20.1302; Effluent Controls 10 CFR 50.34a; 10 CFR 50.36a; 10 CFR 50, Appendix I, Section II and IV Offsite Dose Calculation Manual Same as above 11.5 Prior to initial fuel load License Condition Radiological Environmental Monitoring Same as above 11.5 Prior to initial fuel load License Condition Program Process Control Program Same as above 11.4 Prior to initial fuel load License Condition 13.4-3 Revision 1
Implementation Program Source m Program Title (Required by) FSAR Section Milestone Requirement
- 0. Radiation Protection Program 10 CFR 20.1101 12.1 License Condition (including ALARA principle) 10 CFR 20.1406 12.5
- Radioactive Source Control 1. Prior to initial receipt of by-(assignment of RP Supervisor) product, source, or special nuclear materials (excluding
- Assignment of RP Supervisor Exempt Quantities as
- Minimization of Contamination described in 10 CFR 30.18)
- Personnel Dosimetry 2. Prior to receipt of fuel onsite
- Radiation Monitoring and Surveys
- Radiation Work Permits
- Assignment of RP Manager 3. Prior to initial fuel load
- Respiratory Protection
- Bioassay
- Effluents and Environmental Monitoring and Assessment
- Job Coverage
- Radioactive Waste Shipping 4. Prior to first shipment of radioactive waste
. Non Licensed Plant Staff Training Program 10 CFR 50.120 13.2 18 months prior to scheduled date 10 CFR 50.120(b) of initial fuel load (portions applicable to radioactive material) 10 CFR 30.32 Prior to initial receipt of byproduct, 10 CFR 30.32(a) 10 CFR 40.31 source, or special nuclear 10 CFR 40.31(a) 10 CFR 70.22 materials (excluding Exempt 10 CFR 70.22(a)
Quantities as described in 10 CFR 30.18) 13.4-4 Revision 1
Implementation Program Source m Program Title (Required by) FSAR Section Milestone Requirement
- 2. Reactor Operator Training Program 10 CFR 55.13; 13.2 18 months prior to scheduled date License Condition 10 CFR 55.31; of initial fuel load 10 CFR 55.41; 10 CFR 55.43; 10 CFR 55.45
- 3. Reactor Operator Requalification Program 10 CFR 50.34(b); 13.2 Within 3 months after the date the 10 CFR 50.54 (i-1) 10 CFR 50.54(i); Commission makes the finding 10 CFR 55.59 under 10 CFR 52.103(g)
- 4. Emergency Planning 10 CFR 50.47; 13.3 Full participation exercise 10 CFR Part 50, 10 CFR 50, conducted within 2 years of Appendix E, Appendix E scheduled date for initial loading of Section IV.F.2.a(ii) fuel.
Onsite exercise conducted within 10 CFR Part 50, 1 year before the scheduled date Appendix E, for initial loading of fuel Section IV.F.2.a(ii)
Applicants detailed implementing 10 CFR Part 50, procedures for its emergency plan Appendix E,Section V submitted at least 180 days prior to scheduled date for initial loading of fuel EPZ population change review 10 CFR Part 50, conducted at least 365 days before Appendix E,Section IV.7 scheduled date for initial loading of fuel
- 5. Security Program:
Physical Protection Program (applicable to 10 CFR 73.1 13.5.2.2.8 Prior to initial receipt of special 10 CFR 73.1(a) protection of special nuclear material prior to 10 CFR 73.67 13.6 nuclear material 10 CFR 73.67 the protected area being declared operational) 13.4-5 Revision 1
Implementation Program Source m Program Title (Required by) FSAR Section Milestone Requirement Physical Security Program 10 CFR 73.55(b); 13.6 Prior to receipt of fuel onsite 10 CFR 73.55(a)(4) 10 CFR 73.55(c)(3); (protected area) 10 CFR 73.56; 10 CFR 73.57; Safeguards Contingency Program 10 CFR 73.55(c)(5); 13.6 Prior to receipt of fuel onsite 10 CFR 73.55(a)(4) 10 CFR 73.55(k); (protected area) 10 CFR Part 73, Appendix C Training and Qualification Program 10 CFR 73.55(c)(4); 13.6 Prior to receipt of fuel onsite 10 CFR 73.55(a)(4) 10 CFR 73.55(d)(3); (protected area) 10 CFR Part 73, Appendix B
- 6. Quality Assurance Program - Operation 10 CFR 50.54(a); 17.5 COL issuance 10 CFR 50.54(a)(1) 10 CFR Part 50, Appendix A (GDC 1);
- 7. Maintenance Rule 10 CFR 50.65 17.6 Prior to fuel load authorization per 10 CFR 50.65(a)(1) 10 CFR 52.103(g)
- 8. Motor-Operated Valve Testing 10 CFR 50.55a(b)(3)(ii) 3.9.6.2.2 Prior to initial fuel load License Condition
- 9. Initial Test Program 10 CFR 50.34; 14.2 Prior to the first construction test License Condition 10 CFR 52.79(a)(28) being conducted for the Construction Test Program Prior to the first preoperational test for the Preoperational Test Program Prior to initial fuel load for the Startup Test Program 13.4-6 Revision 1
Implementation Program Source m Program Title (Required by) FSAR Section Milestone Requirement
- 0. Fitness for Duty (FFD) Program for 10 CFR 26.4(f) 13.7 Prior to initiating 10 CFR Part 26 10 CFR Part 26, Construction (workers and first-line construction activities Subpart K supervisors)
FFD Program for Construction 10 CFR 26.4(e) 13.7 Prior to initiating 10 CFR Part 26 10 CFR Part 26, (management and oversight personnel) construction activities Subparts A - H, N, and O FFD Program for Security Personnel 10 CFR 26.4(e)(1) 13.7 Prior to initiating 10 CFR Part 26 10 CFR Part 26, construction activities Subparts A - H, N, and O 10 CFR 26.4(a)(5) or Prior to the earlier of: 10 CFR Part 26, 26.4(e)(1) A. Licensees receipt of SNM in Subparts A - I, N, and O the form of fuel assemblies, or B. Establishment of a protected area, or C. The 10 CFR 52.103(g) finding FFD Program for FFD Program personnel 10 CFR 26.4(g) 13.7 Prior to initiating 10 CFR Part 26 10 CFR Part 26, construction activities Subparts A, B, D - H, N, O, and C per licensees discretion FFD Program for persons required to 10 CFR 26.4(c) 13.7 Prior to the conduct of the first 10 CFR Part 26, physically report to the Technical Support full-participation emergency Subparts A - I, N, and O, Center (TSC) or Emergency Operations preparedness exercise under except for §§ 26.205 -
Facility (EOF) 10 CFR Part 50, App. E, 209 Section F.2.a FFD Program for Operation 10 CFR 26.4(a) and (b) 13.7 Prior to the earlier of: 10 CFR Part 26, A. Establishment of a protected Subparts A - I, N, and O, area, or except for individuals B. The 10 CFR 52.103(g) finding listed in § 26.4(b), who are not subject to
§§ 26.205 - 209 13.4-7 Revision 1
Implementation Program Source m Program Title (Required by) FSAR Section Milestone Requirement
- 1. Cyber Security Program 10 CFR 73.54(b); 13.6 Prior to receipt of fuel onsite 10 CFR 73.55(a)(4) 10 CFR 73.55(b)(8); (protected area) 10 CFR 73.55(c)(6)
- 2. SNM Material Control and Accounting 10 CFR 74, Subpart B 13.5.2.2.9 Prior to receipt of special nuclear License Condition Program (§§ 74.11 - 74.19, excl. material
§ 74.17)
Inservice Testing Program will be fully implemented by generator on line on nuclear heat. Appropriate portions of the program are implemented as necessary to support the system operability requirements of the technical specifications.
13.4-8 Revision 1
f) uses to conduct the routine operating, abnormal, and emergency activities in a safe manner.
Quality Assurance Program Description (QAPD), as discussed in Section 17.5, describes edural document control, record retention, adherence, assignment of responsibilities, and nges.
cedures are identified in this section by topic, type, or classification in lieu of the specific title and esent general areas of procedural coverage.
cedures are issued prior to fuel load to allow sufficient time for plant staff familiarization and to elop operator licensing examinations.
format and content of procedures are controlled by the applicable AP1000 Writers Guideline.
h procedure is sufficiently detailed for an individual to perform the required function without direct ervision, but does not provide a complete description of the system or plant process. The level of il contained in the procedure is commensurate with the qualifications of the individual normally orming the function.
cedures are developed consistent with guidance described in Section 18.9, Procedure elopment and with input from the human factors engineering process and evaluations.
erences to applicable combined license information are included in Section 1.8. This includes, for mple, reference to guidelines on inservice inspection in Chapters 3 and 6, and initial testing in pter 14. Operational experience and the resolution of generic issues to be considered in the paration of plant procedures are outlined in Section 1.9. Procedures to perform rod control system eillance tests specified in WCAP-13864, Revision 1 (Reference 7), at the beginning of each fuel e will be provided as discussed in Subsection 13.5.2.1. All portions of the safety-related logic uitry will be adequately covered in the surveillance procedures as described in Generic er 96-01 (Reference 8).
acceptability of the computerized procedure system, and its backup, for application to the 000 design will be determined as outlined in Section 18.8.
development of plant specific refueling plans (Appendix 19E provides input for refueling plans) is iscussed in Subsection 13.5.2.1.
age plans are discussed in Subsection 13.5.2.1 and should as a minimum address the following ments:
An outage philosophy, which includes safety as a primary consideration in outage planning and implementation, Separate organizations responsible for scheduling and overseeing the outage; provisions for an independent safety review team that would be assigned to perform final review and grant approval for outage activities, Control procedures, which address both the initial outage plan and all safety-significant changes to schedule, Provisions to ensure that all activities receive adequate resources, 13.5-1 Revision 1
Provisions to ensure that all personnel involved in outage activities are adequately trained; this should include operator simulator training to the extent practicable; other plant personnel, including temporary personnel, should receive training commensurate with the outage tasks they will be performing.
eeze seals are to be used, plant-specific guidelines will be developed to reduce the potential oss of RCS boundary and inventory when they are in use.
5.1 Administrative Procedures section describes administrative procedures that provide administrative control over activities are important to safety for the operation of the facility.
cedures outline the essential elements of the administrative programs and controls as described NSI/ANS 3.2-1988 (Reference 201) and in Section 17.5. These procedures are organized such the program elements are prescribed in documents normally referred to as administrative edures. Regulatory and industry guidance for the appropriate format, content and typical vities delineated in written procedures is implemented as appropriate.
inistrative procedures contain adequate programmatic controls to provide effective interface ween organizational elements. This includes contractor and owner organizations providing port to the station operating organization.
riters Guideline promotes the standardization and application of human factors engineering ciples to procedures. The Writers Guideline establishes the process for developing procedures are complete, accurate, consistent, and easy to understand and follow. The Writers Guideline ides objective criteria so that procedures are consistent in organization, style, and content. The ers Guideline includes criteria for procedure content and format including the writing of action s and the specification of acceptable acronym lists and acceptable terms to be used.
cedure maintenance and control of procedure updates are performed in accordance with the PD, as discussed in Section 17.5.
administrative programs and associated procedures developed in the pre-COL phase are cribed in Table 13.5-201 (for future designation as historical information).
plant administrative procedures provide procedural instructions for the following:
Procedures review and approval.
Equipment control procedures - These procedures provide for control of equipment, as necessary, to maintain personnel and reactor safety, and to avoid unauthorized operation of equipment.
Control of maintenance and modifications.
Crane Operation Procedures - Crane operators who operate cranes over fuel pools are qualified and conduct themselves in accordance with ANSI B30.2 (Chapter 2-3), Overhead and Gantry Cranes (Reference 202).
13.5-2 Revision 1
Special orders of a temporary or self-canceling nature.
Standing orders to shift personnel including the authority and responsibility of the shift manager, licensed senior reactor operator in the control room, control room operator and shift technical advisor.
Manipulation of controls and assignment of shift personnel to duty stations per the requirements of 10 CFR 50.54 (i), (j), (k), (l), and (m) including delineation of the space designated for the At the Controls area of the control room.
Shift relief and turnover procedures.
Control Room access.
Working hour limitations.
Feedback of design, construction, and applicable important industry and operating experience.
Shift Manager administrative duties.
Verification of correct performance of operational activities.
A vendor interface program that provides vendor information for safety related components is incorporated into plant documentation.
Fire protection program implementation.
A process for implementing the safety/security interface requirements of 10 CFR 73.58.
A process is in effect at the time of issuance of the combined license and was developed using NRC endorsed industry guidance. This process is used to manage safety/security interface while the security procedures and emergency plan implementing procedures are being developed and implemented.
5.2 Operating and Maintenance Procedures 5.2.1 Operating and Emergency Operating Procedures process to manage the development, review, and approval of AP1000 Normal Operating, ormal Operating, Emergency Operating, Refueling and Outage Planning, Alarm Response, inistrative, Maintenance, Inspection, Test, and Surveillance Procedures, as well as the edures which address the operation of post-72 hour equipment, is delineated in
-GW-GLR-040 (Reference 10). In addition, APP-GW-GLR-040 provided to the NRC the Writers delines for Normal Operating and Two-Column Format Procedures, APP-GW-GJP-100 and
-GW-GJP-200, respectively.
13.5-3 Revision 1
industry guidance for the appropriate format, content, and typical activities delineated in written edures is implemented as appropriate.
5.2.2.1 Plant Radiation Protection Procedures plant radiation protection program is contained in procedures. Procedures are developed and lemented for such things as: maintaining personnel exposures, plant contamination levels, and t effluents ALARA; monitoring both external and internal exposures of workers, considering stry-accepted techniques; routine radiation surveys; environmental monitoring in the vicinity of plant; radiation monitoring of maintenance and special work activities; evaluation of radiation ection implications of proposed modifications; establishing quality assurance requirements licable to the radiation protection program; and maintaining radiation exposure records of workers others.
5.2.2.2 Emergency Preparedness Procedures scussion of emergency preparedness procedures can be found in the Emergency Plan.
5.2.2.3 Instrument Calibration and Test Procedures QAPD, as discussed in Section 17.5, provides a description of procedural requirements for rumentation calibration and testing.
5.2.2.4 Chemistry Procedures cedures provided for chemical and radiochemical control activities include the nature and uency of sampling and analyses; instructions for maintaining fluid quality within prescribed limits; use of control and diagnostic parameters; and limitations on concentrations of agents that could se corrosive attack, foul heat transfer surfaces or become sources of radiation hazards due to vation.
cedures are also provided for the control, treatment, and management of radioactive wastes and trol of radioactive calibration sources.
5.2.2.5 Radioactive Waste Management Procedures cedures for the operation of the radwaste processing systems provide for the control, treatment, management of on-site radioactive wastes. Procedural controls are in place for radiological ases.
equired by License Condition, operating procedures that include provisions to assure that uantities for radionuclides specified in Appendix A to 10 CFR Part 71 are not exceeded will be eloped, implemented and maintained prior to initial fuel load. Procedural controls limit the onuclide inventory to less than the A2 limit in each of the three (3) monitor tanks, and in each of o three (3) mobile radwaste processing systems. Procedures also ensure that any additional ipment to be located in the Radwaste Building is limited to A2 quantities. Spent media transfer a mobile radwaste processing system located in the Radwaste Building is procedurally trolled such that spent media transfer and packaging for offsite shipment must be complete prior lacing the mobile radwaste processing system back into service. The procedures also ensure that total cumulative source term of unpackaged wastes, including liquid waste, wet waste, solid te, gaseous waste, activated or contaminated metals and components, and contaminated waste ent at any time in the Radwaste Building is limited consistent with RG 1.143, Revision 2, 13.5-4 Revision 1
5 rem to site personnel located 10 feet from the total cumulative radioactive inventory. The itigated, unshielded worker dose is calculated at 10 feet from the source. Unlimited worker upancy workstations and low dose rate waiting areas are located no closer than 10 feet from a ile radwaste processing system or a Waste Monitor Tank. The liquid radwaste system is ussed in Section 11.2.
5.2.2.6 Maintenance, Inspection, Surveillance, and Modification Procedures 5.2.2.6.1 Maintenance Procedures ntenance procedures describe maintenance planning and preparation activities. Maintenance edures are developed considering the potential impact on the safety of the plant, license limits, ilability of equipment required to be operable, and possible safety consequences of concurrent or uential maintenance, testing or operating activities.
ntenance procedures contain sufficient detail to permit the maintenance work to be performed ectly and safely. Procedures include provisions for conducting and recording results of required s and inspections, if not performed and documented under separate test and inspection edures. References are made to vendor manuals, plant procedures, drawings, and other rces as applicable.
ructions are included, or referenced, for returning the equipment to its normal operating status.
ing is commensurate with the maintenance that has been performed. Testing may be included in maintenance procedure or be covered in a separate procedure.
preventive maintenance program, including preventive and predictive procedures, as ropriate for structures, systems and components, prescribes the frequency and type of ntenance to be performed. An initial program based on service conditions, experience with parable equipment and vendor recommendations is developed prior to fuel loading. The program vised and updated as experience is gained with the equipment. To facilitate this, equipment ory files are created and kept current. The files are organized to provide complete and easily evable equipment history.
5.2.2.6.2 Inspection Procedures QAPD, as discussed in Section 17.5, provides a description of procedural requirements for ections.
5.2.2.6.3 Modification Procedures nt modifications and changes to setpoints are developed in accordance with approved edures. These procedures control necessary activities associated with the modifications such they are carried out in a planned, controlled, and orderly manner. For each modification, design uments such as drawings, equipment and material specifications, and appropriate design lyses are developed or the as-built design documents are utilized. Separate reviews are ducted by individuals knowledgeable in both technical and QA requirements to verify the quacy of the design effort.
posed modification(s) which involve a license amendment or a change to Technical Specifications processed as proposed license amendment request(s).
13.5-5 Revision 1
5.2.2.7 Material Control Procedures QAPD, as discussed in Section 17.5, provides a description of procedural requirements for erial control.
5.2.2.8 Security Procedures scussion of security procedures is provided in the Security Plan.
Special Nuclear Material (SNM) Physical Protection Program describes the 10 CFR Part 70 uired protection program in effect for the period of time during which new fuel as SNM or non-fuel M is received and stored in a controlled access area (CAA), in accordance with the requirements 0 CFR 73.67.
New Fuel Shipping Plan addresses the applicable 10 CFR 73.67 requirements in the event that radiated new fuel assemblies or components are returned to the supplying fuel manufacturer(s) ity.
5.2.2.9 Special Nuclear Material Material Control and Accounting Procedures aterial control and accounting system consisting of special nuclear material accounting edures is utilized to delineate the requirements, responsibilities, and methods of special nuclear erial control from the time special nuclear material is received until it is shipped from the plant.
se procedures provide detailed steps for SNM shipping and receiving, inventory, accounting, and paring records and reports. The Special Nuclear Material (SNM) Material Control and Accounting
&A) Program description is submitted to the Nuclear Regulatory Commission as a separate nsing basis document.
5.3 Combined License Information Item plant procedures are addressed in APP-GW-GLR-040 (Reference 10), and in Section 13.5.
5.4 References Not used.
Not used.
Not used.
Not used.
Not used.
Not used.
WCAP-13864, Rod Control System Evaluation Program, Revision 1-A, November 1994.
USNRC Generic Letter 96-01, Testing of Safety-Related Logic Circuits, January 10, 1996.
13.5-6 Revision 1
Westinghouse Electric Company LLC.
. ANSI/ANS 3.2-1988, Administrative Control and Quality Assurance for the Operational Phase of Nuclear Power Plants.
. ANSI B30.2 (Chapter 2-3), Overhead and Gantry Cranes.
13.5-7 Revision 1
(This table is included for future designation as historical information.)
- Design/Construction Quality Assurance Program
- Reporting of Defects and Noncompliance, 10 CFR Part 21 Program
- Design Reliability Assurance Program 13.5-8 Revision 1
Safeguards Contingency Plan. The Security Plan will be submitted to the Nuclear Regulatory mission as a separate licensing document in order to fulfill the requirements for CFR 52.79(a)(35) and 10 CFR 52.79(a)(36). The Security Plan will meet the requirements of CFR 52.98(c). The plan is classified as Security Safeguards Information and is withheld from lic disclosure pursuant to 10 CFR 73.21. Additionally, the AP1000 Interim Compensatory sures Report (Reference 2), the AP1000 Enhancement Report (Reference 3), and the 1000 Safeguards Assessment Report (Reference 4) are submitted to the Nuclear Regulatory mission as separate licensing documents to establish the design of the AP1000 Security tems. Each document is classified as Security Safeguards information and is withheld from public losure pursuant to 10 CFR 73.21.
Security Plan consists of the Physical Security Plan, the Training and Qualification Plan, and the eguards Contingency Plan. The Security Plan is submitted to the Nuclear Regulatory Commission separate licensing document in order to fulfill the requirements of 10 CFR 52.79(a)(35) and 9(a)(36). The Security Plan meets the requirements contained in 10 CFR Part 73 and will be ntained in accordance with the requirements of 10 CFR 52.98. The Plan is categorized as urity Safeguards Information and is withheld from public disclosure pursuant to 10 CFR 73.21.
Cyber Security Plan is submitted to the Nuclear Regulatory Commission as a separate licensing ument to fulfill the requirements contained in 10 CFR 52.79(a)(36) and 10 CFR 73.54. The Cyber urity Plan will be maintained in accordance with the requirements of 10 CFR 52.98. The Plan is held from public disclosure pursuant to 10 CFR 2.390.
le 13.4-201 provides milestones for security program implementation.
6.1 Combined License Information Item rmation for the Security Plan is addressed in Section 13.6.
rmation for the Physical Security ITAAC is addressed in Subsection 14.3.2.3.2.
rmation for the cyber security program is addressed in Section 13.6.
6.2 References Not used.
APP-GW-GLR-067, AP1000 Interim Compensatory Measures Report, Westinghouse Electric Company LLC.
APP-GW-GLR-062, AP1000 Enhancement Report, Westinghouse Electric Company LLC.
APP-GW-GLR-066, AP1000 Safeguards Assessment Report, Westinghouse Electric Company LLC.
. Not used.
. Not used.
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Fitness for Duty (FFD) Program is implemented and maintained in multiple and progressive ses dependent on the activities, duties, or access afforded to certain individuals at the struction site. In general, two different FFD programs will be implemented: a construction FFD gram and an operations FFD program. The construction and operations phase programs are ined in Table 13.4-201.
construction FFD program is consistent with NEI 06-06 (Reference 201). NEI 06-06 applies to ons constructing or directing the construction of safety- and security-related structures, systems, omponents performed onsite where the new reactor will be installed and operated. Management oversight personnel, as further described in NEI 06-06, and security personnel prior to the ipt of special nuclear material in the form of fuel assemblies (with certain exceptions) will be ject to the operations FFD program that meets the requirements of 10 CFR Part 26, Subparts A ugh H, N, and O. At the establishment of a protected area, all persons who are granted scorted access will meet the requirements of an operations FFD program. Prior to issuance of a bined License, the Duke-approved construction FFD program (elements Subpart K) will be ewed and revised, as necessary, should substantial revisions occur to NEI 06-06 following NRC orsement of the requirements of 10 CFR Part 26.
following site-specific information is provided:
The construction site is defined in the Physical Security Plan, Appendix E, and is under control of the Primary Site Contractor. The 10 CFR Part 26 requirements are implemented for the construction site area based on the description provided in Table 13.4-201.
Construction Workers and First Line Supervisors (Primary Site Contractor employees and subcontractors) are covered by a Duke-approved Construction FFD Program (elements Subpart K).
Duke employees and Duke subcontractor's construction management and oversight personnel are covered by a Duke Operations FFD Program and the Primary Site Contractor's employees and the Primary Site Contractor's subcontractors, construction management, and oversight personnel are covered by a Duke-approved FFD Program (elements Subpart A-H, N, and O).
Duke security personnel are covered by a Duke Operations FFD Program and the Primary Site Contractor's security personnel are covered by a Duke-approved FFD Program (elements Subpart A-H, N, and O). This coverage is applicable from the start of construction activities to the earlier of (1) the receipt of SNM in the form of fuel assemblies, (2) the establishment of a protected area, or (3) the 10 CFR 52.103(g) finding.
The Duke FFD Program personnel are covered by a Duke Operations FFD program and the Primary Site Contractor's FFD Program personnel are covered by a Duke-approved FFD Program (elements Subpart A, B, D-H, N, O, and C per licensee's discretion).
Duke security personnel protecting fuel assemblies are covered by a Duke Operations FFD Program (Elements Subpart A-I, N, and O).
Personnel required to physically report to the Technical Support Center (TSC) or Emergency Operations Facility (EOF), when that requirement is in effect, are covered by a Duke Operations FFD program (elements Subpart A-I, N, and O, except for §§ 26.205 - 209).
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7.1 References
. Nuclear Energy Institute Fitness for Duty Program Guidance for New Nuclear Power Plant Construction Sites, NEI 06-06, Revision 5, August 2009 (ML092430016).
13.7-2 Revision 1
agraphs are numbered to be subsequent to Subsection 13.1.1.1.
A.1.1.1.1 Design and Construction Activities Westinghouse Electric Company (WEC) was selected to design, fabricate, deliver, and install the 000 advanced light water pressurized water reactors (PWR) and to provide technical direction for allation and startup of this equipment. Subsection 1.4.1 provides detailed information regarding C past experience in design, development, and manufacturing of nuclear power facilities.
rating experience from design, construction, and operation of earlier WEC PWRs is applied in design, construction, and operation of the AP1000 as described in numerous locations ughout (e.g., Subsections 3.6.4.4, 3.9.4.2.1, 4.2.3.1.3).
nstruction architect engineer (AE) provides the construction of the plant and additional design ineering for selected site specific portions of the plant. The AE is selected based on experience proven technical capability in nuclear construction projects or projects of similar scope and plexity.
er design and construction activities are generally contracted to qualified suppliers of such ices. Implementation or delegation of design and construction responsibilities is described in the sections below. QA aspects of these activities are described in Chapter 17.
A.1.1.1.1.1 Principal Site-Related Engineering Work principal site engineering activities accomplished towards the construction and operation of the t are:
Meteorology rmation concerning local (site) meteorological parameters is developed and applied by station contract personnel to assess the impact of the station on local meteorological conditions. Onsite eorological measurements are obtained by station personnel to produce data for the purpose of ing atmospheric dispersion estimates for postulated accidental and expected routine airborne ases of effluents. Maintenance procedures are established for surveillance, calibration, and repair struments. Meteorological information is summarized in Section 2.3.
Geology rmation relating to site and regional geotechnical conditions is developed and evaluated by utility contract personnel to determine if geologic conditions could present a challenge to the safety of plant. Items of interest include geologic structure, seismicity, geological history, and groundwater ditions. During construction, foundations within the power block area are mapped or visually ected and photographed. Section 2.5 provides details of these investigations.
Seismology rmation relating to seismological conditions is developed and evaluated by utility and contract onnel to determine if the site location and area surrounding the site is appropriate from a safety dpoint for the construction and operation of a nuclear power plant. Information regarding onics, seismicity, correlation of seismicity with tectonic structure, characterization of seismic rces, and ground motion are assessed to estimate the potential for strong earthquake ground ions or surface deformation at the site. Section 2.5 provides details of these investigations.
13AA-1 Revision 1
evaluated by utility and contract personnel. The study includes hydrologic characteristics of ams, lakes, shore regions, the regional and local groundwater environments, and existing or posed water control structures that could influence flood control and plant safety. Section 2.4 udes more detailed information regarding this subject.
Demography rmation relating to local and surrounding area population distribution is developed and evaluated tility and contract personnel. The data is used to determine if requirements are met for blishment of exclusion area, low population zone, and population center distance. Section 2.1 udes more detailed information regarding population around the plant site.
Environmental Effects itoring procedures are developed to enable the collection of data necessary to determine sible impact on the environment due to construction, startup, and operational activities and to blish a baseline from which to evaluate future environmental monitoring.
A.1.1.1.1.2 Design of Plant and Ancillary Systems ponsibility for design and construction of systems outside the power block such as circulating er, service water, switchyard, and secondary fire protection systems is delegated to qualified tractors.
A.1.1.1.1.3 Review and Approval of Plant Design Features ign engineering review and approval is performed in accordance with the reactor technology dor QA program and Section 17.1. The reactor technology vendor is responsible for design trol of the power block. Verification is performed by competent individuals or groups other than e who performed the original design. Design issues arising during construction are addressed implemented with notification and communication of changes to the manager in charge of ineering for review. As systems are tested and approved for turnover and operation, control of ign is turned over to plant staff. The manager in charge of engineering, along with functional agers and staff, assumes responsibility for review and approval of modifications, additions, or tions in plant design features, as well as control of design documentation, in accordance with the rational QA program. Design control becomes the responsibility of the manager in charge of ineering prior to loading fuel. During construction, startup, and operation, changes to human-em interfaces of control room design are approved using a human factors engineering (HFE) luation addressed within Chapter 18. See organization charts, Figure 13.1-201 and 13AA-201 for orting relationships.
A.1.1.1.1.4 Site Layout with Respect to Environmental Effects and Security Provisions layout was considered when determining the expected environmental effects from construction.
Physical Security Plan is designed with provisions that meet the applicable NRC regulations.
layout was considered when developing the Physical Security Plan.
13AA-2 Revision 1
A.1.1.1.1.6 Review and Approval of Material and Component Specifications ety-related material and component specifications of structures, systems, and components igned by the reactor technology vendor are reviewed and approved in accordance with the tor technology vendor QA program and Section 17.1. Review and approval of items not designed he reactor technology vendor are controlled for review and approval by Section 17.5 and the PD.
A.1.1.1.1.7 Procurement of Materials and Equipment curement of materials during construction phase is the responsibility of the reactor technology dor and constructor. The process is controlled by the construction QA programs of these anizations under the flowdown requirements established by the Duke Energy QA program in ct. Oversight of the inspection and receipt of materials process is the responsibility of the ager in charge of nuclear QA and oversight.
A.1.1.1.1.8 Management and Review of Construction Activities rall management and responsibility for construction activities is assigned to the site executive in rge of plant management. The project director of the engineering, procurement, and construction C) contractor is accountable to the site executive in charge of plant management for construction vities. See organization chart Figure 13AA-201. Construction management personnel are cient in number to provide effective oversight in the areas of cost, schedule, and other functions eemed necessary by the manager in charge of construction. Table 13.1-201 provides additional rmation regarding the number of station personnel. Monitoring and review of construction vities by utility personnel is a continuous process at the plant site. Contractor performance is itored to provide objective data to utility management in order to identify problems early and elop solutions. Monitoring of construction activities verifies that contractors are in compliance with tractual obligations for quality, schedule, and cost. Monitoring and review of construction activities vided functionally across the various disciplines of the utility construction staff, e.g., electrical, hanical, instrument and control, etc., and tracked by schedule based on system and major plant ponents/areas.
r each system is turned over to plant staff the construction organization relinquishes onsibility for that system. At that time they will be responsible for completion of construction vities as directed by plant staff and available to provide support for preoperational and start-up ing as necessary.
odic assessment involving both the construction and operations organizations continues to tify SSCs that could reasonably be expected to be impacted by scheduled construction activities.
ropriate administrative and managerial controls are then established as necessary. Specific ards, impacted SSCs, and managerial and administrative controls are reviewed on a recurring is and, if necessary, controls are revised/developed and implemented and maintained current as k progresses on site. For example, prior to construction activities that involve the use of large struction equipment such as cranes, managerial and administrative controls are in place to ent adverse impacts on any operating unit(s) overhead power lines, switchyard, security ndary, etc., by providing the necessary restrictions on the use of large construction equipment.
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the aid of those managers that report directly to the plant manager, is responsible for the vities required to transition the unit from the construction phase to the operational phase. These vities include turnover of systems from construction, preoperational testing, schedule agement, procedure development for tests, fuel load, integrated startup testing, and turnover of ems to plant staff.
A.1.1.1.2.1 Development of Human Factors Engineering Design Objectives and Design Phase Review of Proposed Control Room Layouts design objectives are initially developed by the reactor technology vendor in accordance with pter 18. As a collaborative team, personnel from the reactor technology vendor design staff and onnel, including, licensed operators, engineers, and instrumentation and control technicians owner and other organizations in the nuclear industry assess the design of the control room and
-machine interfaces to attain safe and efficient operation of the plant. See Section 18.2 for itional details of HFE program management.
ifications to the certified design of the control room or man-machine interface are reviewed per ineering procedures, as required by Section 18.2, to evaluate the impact to plant safety. The ager in charge of engineering is responsible for the HFE design process and for the design mitment to HFE during construction and throughout the life of the plant as noted in section 13.1.1.2.1. The HFE program is established in accordance with the description and mitments in Chapter 18.
A.1.1.1.2.2 Preoperational Testing Organization operational and startup testing is conducted by the plant test and operations (PT&O) anization. The PT&O organization functions and responsibilities are addressed in Section 14.2.
icient numbers of personnel are assigned to perform preoperational and startup testing to itate safe and efficient implementation of the testing program. Plant specific training provides ruction on the administrative controls of the test program. To improve operational experience, rations and technical staff are used as support in conducting the test program and in reviewing results.
Figure 13AA-201 for organization chart for preoperational and startup testing.
A.1.1.1.3 Development and Implementation of Staff Recruiting and Training Programs fing plans are developed based on operating plant experience with input from the reactor nology vendor as determined by HFE. See Section 18.6. These plans are developed under the ction and guidance of the site executive in charge of plant management. Staffing plans are pleted and manager level positions are filled prior to start of preoperational testing. Personnel cted to be licensed reactor operators and senior reactor operators along with other staff essary to support the safe operation of the plant are hired with sufficient time available to plete appropriate training programs, and become qualified, and licensed, if required, prior to fuel g loaded in the reactor vessel. See Figure 13AA-202 for an estimated timeline of hiring uirements for operator and technical staff relative to fuel load.
ause of the dynamic nature of the staffing plans and changes that occur over time, it is expected specific numbers of personnel on site will change; however, Table 13.1-201 includes the initial mated number of staff for selected positions and the estimated number of additional positions 13AA-4 Revision 1
training program is described in Section 13.2.
A.1.1.1.4 Development of Plant Maintenance Programs nsure equipment operability and reliability, plant maintenance programs such as preventive and ective maintenance are developed and made effective during the preoperation/startup phase with roved administrative procedures under the direction of the managers in charge of maintenance, ineering, and work control.
A.1.1.1.5 Qualification lification and experience requirements for personnel of the PT&O organization are addressed in section 14.2.2.2. Station management and supervisory personnel in the design and construction agement organization meet the qualification requirements in education and experience for those cribed in ANSI/ANS-3.1-1993 (Section 13.1.5 Reference 201) as endorsed and amended by ulatory Guide 1.8. For positions listed in Table 13.1-201 that do not have a cross-reference ion in ANSI/ANS-3.1 the most comparable section of ANSI/ANS-3.1 is used for guidance in blishing experience and education requirements.
13AA-5 Revision 1
Executive President Nuclear Duke Energy Nuclear Oversight Project Director Executive Site Construction EPC Contractor AP1000 Design / Plant Site Manager Engineering Construction Manager, Manager Manager Manager Engineering Functional Functional Craft Schedule Manager, Engineering Oversight Manager Superintendent Operations Functional Design Functional Manager, Manager Plant Test &
Operations (PT&O)
Technical Functional Cost / Scheduling Cost Oversight Oversight Manager, Design Superintendent Functional Maintenance Manager Functional Manager Startup QA / QC Human Factors Superintendent Engineering Functional Manager PT&O Support Construction Engineering Procurement Superintendent Component & Owner / Licensee Module Module Program Note:
Inspection &
Manager Dashed borders around functional areas indicate matrixed Testing Superintendent organizations providing support to the nuclear sites.
Subcontract Manager Engineering, Procurement
& Construction (EPC)
Figure 13AA-201 Construction Management Organization 13AA-6 Revision 1
Figure 13AA-202 Hiring Schedule for Plant Staff 13AA-7 Revision 1