ML21055A079
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FERMI 2 UFSAR 13.1-1 REV 23 02/21 CHAPTER 13:
CONDUCT OF OPERATIONS This chapter describes the framework within which Fermi 2 will be operated. It summarizes the organizational structure, the training program, review and audit procedures, plant procedures, plant records, and industrial security.
13.1 ORGANIZATIONAL STRUCTURE The DTE Electric Company (DTE) is providing the operational organization for operating Fermi 2. This chapter describes the DTE organization as it pertains to testing and operation of the plant.
DTE Energy is an investor-owned public utility, incorporated and engaged in the generation, transmission, and sale of electrical energy in the State of Michigan.
DTE has had considerable experience in designing, constructing, and operating fossil-fueled facilities for generating electricity. Normally, the design engineering effort and the construction management for such facilities have been performed by DTE personnel with the assistance of design and construction contractors. Such contractors are guided and directed in their work by the responsible divisions that report through the DTE Corporate Organization. The corporate functions, responsibilities, and authorities related to Fermi 2 are described in this section. Figures 13.1-1 through 13.1-4 show the Corporate Organization; the Nuclear Generation Organization; and the Executive Director - Nuclear Production's Organization, including the Operations organization.
NOTE:
The titles of Plant Manager and Executive Director - Nuclear Production have the same functional responsibility.
NOTE:
When a position is not filled, reporting order will be to the next higher position.
13.1.1 Corporate Organization See Figure 13.1-1 for reporting relationship.
13.1.1.1 Not Used
FERMI 2 UFSAR 13.1-2 REV 23 02/21 13.1.1.2 President and Chief Executive Officer - DTE Energy The President and Chief Executive Officer, DTE Energy is subject to the control of the Board of Directors. This individual has responsibility for the companys DTE Electric subsidiary and other DTE Energy subsidiaries.
13.1.1.3 Senior Vice President and Chief Nuclear Officer (CNO)
The Senior Vice President and Chief Nuclear Officer reports to the President and Chief Executive Officer, DTE Energy. This individual has responsibility for the overall administration of DTE nuclear power. The CNO is the ultimate management authority for establishing QA policy and responsibility for the Quality Assurance function. Reporting to the CNO are the Director - Nuclear Oversight, the Site Vice President - Nuclear Generation, Vice President - Engineering and Technical Support, Director - Strategic Business Operations, and the Nuclear Safety Review Group (NSRG) Chairman.
13.1.1.3.1 Director - Nuclear Oversight The Director - Nuclear Oversight is responsible for establishing a sustainable oversight model for Fermi. This includes responsibility for Quality Assurance and Employee Concerns. Reporting to the Director - Nuclear Oversight is the Manager - Nuclear Quality Assurance.
13.1.1.3.1.1 Manager - Nuclear Quality Assurance The responsibilities of the Manager - Nuclear Quality Assurance are discussed in Section 17.2.
13.1.1.3.2 Corporate Support Corporate Support groups provide several functions to DTE nuclear organizations such as Information Technology Services, Supply Chain, Human Resources, Business Performance, Facilities, Communications and Controller Services.
When corporate support groups perform quality-related activities for Fermi 2, such activities are performed under the Fermi 2 Quality Assurance Program.
13.1.1.3.3 Director - Strategic Business Operations The Director - Strategic Business Operations is responsible for strategic planning and business support, including information and procedure management. The Director -
Strategic Business Operations is also responsible for managing budgets for site projects and contracts providing services. In the absence of a Director, the role and responsibilities may be filled by a Manager - Strategic Business Operations.
13.1.1.4 Site Vice President - Nuclear Generation The Site Vice President - Nuclear Generation reports to the Senior Vice President and Chief Nuclear Officer and also has access to the President and Chief Executive Officer, DTE
FERMI 2 UFSAR 13.1-3 REV 23 02/21 Energy for the reporting of nuclear safety problems. This individual has responsibility for the administration of the Fermi 2 plant, overall plant safety including operation, maintenance, modification, training, security, outage management, and the fire protection program, with the exception of engineering aspects of the program (see Section 13.1.1.5). Refer to section 13.1.2 for the detailed description of the Nuclear Generation Organization including those organizations reporting to the Site Vice President - Nuclear Generation.
13.1.1.5 Vice President - Engineering and Technical Support The Vice President - Engineering and Technical Support reports to the Senior Vice President and Chief Nuclear Officer and also has access to the President and Chief Exectuve Officer, DTE Energy for the reporting of nuclear safety problems. This individual has responsibility for the administration of engineering, including engineering aspects of the fire protection program, and technical support organizations. Supply Chain has a functional relationship to the Vice President - Engineering and Technical Support. Refer to section 13.1.2 for the detailed description of the Nuclear Generation Organization, including those organizations reporting to the Vice President - Engineering and Technical Support.
13.1.2 Nuclear Generation Nuclear Generation refers collectively to all organizations reporting to the Site Vice President - Nuclear Generation and the Vice President - Engineering and Technical Support.
See Figure 13.1-2.
Reporting to the Site Vice President - Nuclear Generation are the Executive Director -
Nuclear Production, Manager - Nuclear Security, Manager - Nuclear Performance Improvement, and Director - Nuclear Training.
Reporting to the Vice President - Engineering and Technical Support are the Director -
Nuclear Engineering, the Director - Nuclear Technical Support - Project Management, the Manager - Nuclear Licensing, and the Manager - Radiological Emergency Response Preparedness.
13.1.2.1 Director - Nuclear Training The Director - Nuclear Training is responsible for developing and implementing training programs in support of safe and efficient operation of the plant. The training program is described in Section 13.2. The Director - Nuclear Training also provides the support for licensed operator medical issues.
13.1.2.2 Executive Director - Nuclear Production The Executive Director - Nuclear Production is responsible for the operation, maintenance, radiation protection, chemistry, industrial health and safety, plant administration, human performance, and implementation of the fire protection program of Fermi 2. The Executive Director - Nuclear Production shall delegate in writing the succession to this responsibility during any absence.
FERMI 2 UFSAR 13.1-4 REV 23 02/21 Reporting to the Executive Director - Nuclear Production are the Director - Nuclear Operations, the Director - Nuclear Maintenance, the Director - Outage and Work Management, the Manager - Radiation Protection, and the Manager - Chemistry. The Radiation Protection Manager reports directly to the Executive Director - Nuclear Production regarding radiological control.
Figures 13.1-3 and 13.1-4 are the organization charts for the sections reporting to the Executive Director - Nuclear Production; each classification in the figures represents a job position for one or more individuals. The functions, responsibilities, and authorities of plant personnel are described below.
13.1.2.2.1 Director - Nuclear Operations The Operations Section is responsible for the operation of plant equipment and systems, and implementation of the fire protection program. The Director - Nuclear Operations is responsible for the activities of this section.
The Director - Nuclear Operations exercises overall managerial and supervisory responsibility for the startup testing and safe, reliable, and efficient operation of the plant and all associated equipment. It is the Director's responsibility to have a staff of trained and properly licensed personnel to accomplish the various plant responsibilities and to ensure that qualified personnel are available to fill the plant complement positions. Prior to operation, the Director - Nuclear Operations was responsible for the Fermi 2 startup and testing activities. The Operations Section is shown in Figure 13.1-4.
All operations, testing, or maintenance work must be approved either by the Director or by an assigned delegate, as established in procedures.
In the absence of the Director, the succession to the Director's responsibilities is documented in the form of organizational charts, functional descriptions, job descriptions for key personnel or in equivalent forms of documentation.
Reporting to the Director are the Operations Engineer and other support personnel as necessary. The Director - Nuclear Operations may also assume the functions and responsibilities of the Operations Engineer. When assuming these responsibilities, the Director - Nuclear Operations shall hold a senior reactor operators license.
The Operations Engineer is responsible for the overall operation of the plant equipment and systems. The Operations Engineer shall have a senior reactor operator's (SRO) license. As designated in procedures, the Operations Engineer or a delegate approves written work requests for equipment operation, maintenance, or tests. During the Operations Engineer's absence, a licensed SRO may be appointed to assume the duties and responsibilities of that position. Reporting to the Operations Engineer are the Shift Manager(s) and shift organization.
The Shift Manager(s) is responsible for and exercises supervisory control over the operating personnel on shift. The Shift Manager (or a designated individual during the Shift Managers absence from the control room) has control room command function. The Shift Manager is
FERMI 2 UFSAR 13.1-5 REV 23 02/21 responsible for the overall operation of the plant during the absence of the Director - Nuclear Operations, and the Operations Engineer. Each Shift Manager shall have an SRO license.
Reporting to the Shift Manager is the Control Room Supervisor and Shift Technical Advisors.
The Control Room Supervisor assists the Shift Manager in duties as directed. Each Control Room Supervisor shall have an SRO license. Reporting to the Control Room Supervisor are the Licensed Nuclear Operators.
The Licensed Nuclear Operators manipulate the reactor controls and other controls and direct the activities of the Nuclear Operators. Normally, three Licensed Nuclear Operators are assigned to each operating shift. Each Licensed Nuclear Operator shall have a reactor operator's (RO) license.
The Nuclear Operators are responsible, under the direction of the Shift Manager, the Control Room Supervisor, or the Licensed Nuclear Operators, for operating auxiliary systems and for assisting in the refueling of the plant as directed. Among their regular duties are the operation of such plant equipment as pumps, turbine generator auxiliaries, blowers, radwaste systems, compressors, and auxiliary service equipment. Additional duties include radiation monitoring, recordkeeping, and general housekeeping.
Operations is responsible for implementing and coordinating the Fire Protection Program, including coordinating fire protection surveillances.
13.1.2.2.2 Director - Nuclear Maintenance The Director - Nuclear Maintenance is responsible for the maintenance of the plant and all associated systems and equipment. Reporting to the Director - Nuclear Maintenance are the Maintenance Superintendents.
The Director - Nuclear Maintenance is responsible for the maintenance of plant structures, systems, and equipment. In this capacity, compliance with the Technical Specifications related to maintenance, written procedures, and work practices is ensured; and duties include the instrument spare parts, routine calibration, instrument and control troubleshooting, and the standards calibration program.
13.1.2.2.3 Manager - Radiation Protection The Manager - Radiation Protection is responsible for the administration and supervision of the Radiation Protection Department. This department is responsible for radiological engineering, health physics, radiation protection, radiological effluents, ALARA programs, radwaste (radwaste shipping, decontamination, and Onsite Storage Facility), and medical programs. Reporting to the Manager - Radiation Protection are the Radiation Protection Manager, and the General Supervisor - RP Technical Services and Support. The Manager may also assume the functions and responsibilities of the Radiation Protection Manager as described in subsection 13.1.2.2.3.1.
FERMI 2 UFSAR 13.1-6 REV 23 02/21 The Manager - Radiation Protection assists the Fermi 1 Custodian. On the average, this activity will not require more than 100 work hours of effort each year.
13.1.2.2.3.1 Radiation Protection Manager The Radiation Protection Manager, as described in NRC Regulatory Guides 1.8, 8.8 and 8.10, has the responsibility and authority to formulate and administer plant programs and procedures which ensure radiation protection for plant personnel, members of the public, and the environment. This position receives delegated authority from the Executive Director -
Nuclear Production in the area of radiological control, which includes radiation protection, radioactive effluents, radioactive waste transportation and disposal, and radiological health.
The Radiation Protection Manager has direct access to the Site Vice President - Nuclear Generation to resolve questions related to the conduct of the radiation protection program.
In the event the Radiation Protection Manager function is assigned to the Manager -
Radiation Protection, an Assistant Radiation Protection Manager may be assigned to supervise the Radiation Protection Staff.
13.1.2.2.3.2 General Supervisor - RP Technical Services and Support The General Supervisor - RP Technical Services and Support is responsible for maintaining the site within local, state, and federal environmental regulations, radiological health, radiological instrumentation matters, and reporting Fermi 2 compliance with established site procedures, company policies, and governing regulations.
13.1.2.2.4 Manager - Chemistry The Manager - Chemistry is responsible for maintaining the chemical parameters of the plant within the requirements of the Technical Specifications; UFSAR; fuel warranty and industry guidelines. The Manager - Chemistry evaluates results, reports, and laboratory techniques and is responsible for the following:
- a.
Overseeing the operation, maintenance, and calibration of, and providing technical support for, the plant chemical processing and water treatment equipment,
- b.
Directing the sampling of plant fluid systems, for the chemical laboratory, and for prescribing the procedures to be followed for sample preparation and analysis, and results reports.
13.1.2.2.5 Director - Outage and Work Management The Director - Outage and Work Management is responsible for the on-line work control, outage management, and reactor services at Fermi 2.
Reporting to the Director - Outage and Work Management are the Manager - On Line Work Management, Manager - Outage, and Manager - Reactor Services.
The functions, responsibilities, and authorities of these job positions are described below.
FERMI 2 UFSAR 13.1-7 REV 23 02/21 13.1.2.2.5.1 Manager - Online Work Management NOTE:
The positions of Manager - Online Work Management and Manager - Outage may be combined.
The Manager - Online Work Management is responsible for plant work management and planning services. Reporting to the Manager - Online Work Management are individuals responsible for assigning priority and planning, coordinating, and tracking all evaluation, design, and testing activities in support of plant operations. Also reporting to the Manager -
Online Work Management are individuals responsible for reviewing and prioritizing all work requests, ensuring that work requests are completed as scheduled, and reviewing completed work requests. Also included are managing the 30-day, 7-day, and 48-hr schedules and coordinating near-term outage support.
Individuals reporting to the Manager - Online Work Management are also responsible for plant cost engineering, engineering planning, maintenance planning, developing work request packages, preparing management tracking reports, and for the day-to-day operation of the surveillance and performance scheduling and tracking.
13.1.2.2.5.2 Manager - Outage NOTE:
The positions of Manager - Online Work Management and Manager - Outage may be combined.
The Manager - Outage is responsible for outage management including outage programs and schedules, cost engineering, engineering planning, estimating plant modifications and generating outage reports. Reporting to the Manager - Outage are individuals responsible for developing and maintaining outage programs and schedules and assuming the lead role during outages. Also included is work scheduling and database input. Other support staff is responsible for the remainder of the Managers outage responsibilities.
13.1.2.2.5.3 Manager - Reactor Services The Manager - Reactor Services is responsible for all activities related to reactor vessel refueling and maintenance, and dry storage loading campaigns.
13.1.2.3 Director - Nuclear Technical Support - Project Management The Director - Nuclear Technical Support - Project Management is responsible for the project management and engineering support functions of large nuclear related projects.
Reporting to the Director - Nuclear Technical Support - Project Management is the Manager
- Engineering Projects and Modifications.
13.1.2.3.1 Manager - Engineering Projects and Modifications The Manager - Engineering Projects and Modifications may be delegated the responsibility for the project management of large plant modifications and engineering support functions associated with modifications of plant structures, systems and equipment. This responsibility
FERMI 2 UFSAR 13.1-8 REV 23 02/21 includes the planning and management of the engineering scope and specifications, detailed design, procurement, installation and testing phases of the project. In this capacity, the Manager - Engineering Projects and Modifications has the responsibility and authority to utilize DTE personnel or retain qualified contract architects/engineers or consultants to implement the design development and control procedures under the jurisdiction of the Manager - Nuclear Design Engineering.
13.1.2.4 Director - Nuclear Engineering The Director - Nuclear Engineering is responsible for design engineering, nuclear fuel design and management, strategic engineering, performance engineering, inservice inspection, modifications and configuration management, and procurement engineering. The Director - Nuclear Engineering is responsible for the formulation and effectiveness of the fire protection program. Reporting to the Director - Nuclear Engineering are Manager -
Nuclear Design Engineering, Manager - Nuclear Strategic Engineering, Manager - Nuclear Performance Engineering, and Manager - Nuclear Tactical Engineering.
13.1.2.4.1 Manager - Nuclear Design Engineering The Manager - Nuclear Design Engineering has the overall responsibility for the Fermi 2 plant configuration management program. The Manager - Nuclear Design Engineering is responsible for Engineering Projects and Modifications, and engineering support functions associated with modifications to plant structures, systems and equipment. This responsibility includes the planning and management of the engineering scope and specification, detailed design, procurement, installation and testing phases of the modification.
Within the context of Section 4.6.1 of ANSI N18.1-1971 (Selection and Training of Nuclear Power Plant Personnel), the Manager - Nuclear Design Engineering is equivalent to the "Engineer in Charge." In this capacity, the Manager - Nuclear Design Engineering has the responsibility and authority to assign DTE personnel or to retain qualified consultants to perform necessary design work, design reviews, incident evaluations, or safety analyses.
13.1.2.4.2 Manager - Nuclear Strategic Engineering The Manager - Nuclear Strategic Engineering is responsible for the engineering functions related to the operation of the plant, including strategic engineering, preventive maintenance program, and technical and administrative procedures.
13.1.2.4.3 Manager - Nuclear Performance Engineering The Manager - Nuclear Performance Engineering is responsible for the Inservice Inspection Program, equipment performance evaluation, equipment qualification program, fire protection program, and performance and inservice testing.
The Manager - Nuclear Performance Engineering is also responsible for nuclear fuel, including fuel cycle analysis, nuclear fuel accountability, uranium and enrichment accounting, core analysis, reactor dynamics, fuel design, fuel fabrication contract administration, fuel storage and shipment, fuel performance, and fuel burn-up.
FERMI 2 UFSAR 13.1-9 REV 23 02/21 The Manager - Nuclear Performance Engineering is also responsible for safe operating procedures as related to reactor core operating limits, fuel management, including maintaining records and specifying plant operations for maximum economic performance within the limits of the operating license, and procedures and documentation for fuel handling.
The Manager - Nuclear Performance Engineering is also responsible for all aspects of the Probabilistic Safety Assessment program including ownership and maintenance of the PSA model and the plant operating and plant shutdown risk assessment activities.
13.1.2.4.4 Manager - Nuclear Tactical Engineering The Manager - Nuclear Tactical Engineering is responsible for Procurement Engineering and the Engineering Response Team.
13.1.2.5 Other Managers in Figure 13.1-2 13.1.2.5.1 Manager - Nuclear Security The Manager - Nuclear Security is responsible for the physical security of DTE nuclear power plants and the facilities, material, equipment, and construction associated with them.
The physical security responsibility includes developing and implementing the Physical Security Plan, the Safeguards Contingency Plan, the Security Personnel Training and Qualifications Plan, the Safeguards Information Protection Program, and security policy; conducting personnel screening for all personnel requiring unescorted access into the protected area; and implementing the access authorization and fitness for duty programs.
The Manager - Nuclear Security also conducts investigations or initiates investigations of attempts to breach nuclear security, whether committed by a person employed at Fermi or a member of the public.
13.1.2.5.2 Manager - Nuclear Performance Improvement The Manager - Nuclear Performance Improvement is responsible for administration of the plant Corrective Action Program, including trending and tracking of corrective action documents, administration of root cause analysis program and administration of operating experience, self-assessment and benchmarking programs.
13.1.2.5.3 Manager - Nuclear Licensing The Manager - Nuclear Licensing is responsible for licensing activities, including regulatory and compliance support, and nonradiological environmental monitoring. The Manager -
Nuclear Licensing provides the interface and communications with the NRC and other outside agencies, as assigned.
13.1.2.5.4 Manager - Radiological Emergency Response Preparedness The Manager - Radiological Emergency Response Preparedness is responsible for coordinating the activities of Emergency Planning.
FERMI 2 UFSAR 13.1-10 REV 23 02/21 13.1.2.6 Shift Crew Composition NOTE:
The titles Nuclear Shift Supervisor (NSS), Nuclear Assistant Shift Supervisor (NASS), and Nuclear Power Plant Operator (NPPO) have the same functional responsibilities as the titles Shift Manager (SM), Control Room Supervisor (CRS) and Nuclear Operator (NO), respectively.
During routine operations, the shift complement consists of one Shift Manager, one Control Room Supervisor, one Shift Technical Advisor/Operations Shift Engineer (OSE), three Licensed Nuclear Operators, five Nuclear Operators, and one Radiation Protection Technician. The Shift Manager, Control Room Supervisor, and Operations Shift Engineer must hold SRO licenses, and the Licensed Nuclear Operators must hold RO or SRO licenses.
The Nuclear Operators are not licensed because they do not perform activities for which an RO license is required.
All core alterations shall be observed and directly supervised by either a licensed Senior Reactor Operator or licensed Senior Reactor Operator limited to fuel handling who has no other concurrent responsibilities during the operation. This is in addition to the normal Shift Crew Compliment during Mode 5.
The minimum crew composition of operators for normal routine operations consists of the following:
Position Number of Personnel per shift NRC License Requirements Shift Manager (SM) 1 SRO Control Room Supervisor (CRS) 1 SRO Licensed Nuclear Operators (LNO) 3 RO or SRO Nuclear Operators (NO) 5 None The minimum shift crew requirements for the various modes is as follows:
Positions Number of individuals required to fill position Mode 1, 2 or 3 Mode 4 or 5 SM 1
1*
CRS 1
None LNO 3
1 NO 5
1 STA/OSE 1
1 Does not include the supervision of core alterations by the licensed SRO or the SRO limited to fuel handling.
FERMI 2 UFSAR 13.1-11 REV 23 02/21 Except for the Shift Manager, the shift crew composition may be one less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
The operating modes are the following:
Mode Title Reactor Mode Switch Position Average Reactor Coolant Temperature (°F) 1 Power operation Run N/A 2
Startup Refuela or Startup/Hot Standby N/A 3
Hot shutdowna Shutdown
> 200 4
Cold shutdowna Shutdown 200 5
Refuelingb Shutdown or Refuel N/A a
All reactor vessel head closure bolts fully tensioned.
b One or more reactor vessel head closure bolts less than fully tensioned The Shift Technical Advisors are required to have a Bachelor's Degree or equivalent in a scientific or engineering discipline from an accredited institution and 2 years of related nuclear experience. They complete an INPO-accredited Shift Technical Advisor training program. This program contains all of the SRO training materials and practical skills training that has been identified on a job task listing that is Fermi 2 specific. The Shift Technical Advisors are normally assigned to a shift and participate in the training cycle for licensed operator requalification.
The Operations Shift Engineers are required to meet the same qualifications as a Shift Technical Advisor and hold an SRO license.
The Operations Shift Engineer may be designated as the Control Room Supervisor on some shifts. This is in accordance with the NRC Policy Statement on Engineering Expertise on Shift (Reference 1).
The Shift Managers, Control Room Supervisors, Licensed Nuclear Operators, and Nuclear Operators are trained in the following areas of radiation protection:
- a. Use of portable radiation detectors
- b. Limits of exposure rates and accumulated doses
- c. Use of protective barriers and signs
- d. Use of protective clothing and breathing apparatus
- e. Limiting contamination
- f. Pertinent plant and federal regulations.
FERMI 2 UFSAR 13.1-12 REV 23 02/21 Shift chemistry technicians perform technical quantitative functions in chemistry, radiochemistry, and other areas. These technicians are qualified to meet the requirements of ANSI N18.1.
13.1.2.7 Qualification Requirements for Nuclear Plant Personnel Regulatory Guide 1.8, Revision 1, September 1975, and ANSI N18.1 (1971) provide the regulatory criteria for the selection and training of Fermi 2 plant personnel. Regulatory Guide 1.8 endorses the criteria of ANSI N18.1 (1971), with the exception of the Radiation Protection Manager whose requirements are defined in the Regulatory Guide. Training and retraining for NRC-licensed operators is in compliance with 10 CFR 55.
For the purposes of complying with these requirements, the Technical Specifications, and 10 CFR 55, the following definitions apply to Fermi 2 personnel:
Plant Staff All personnel reporting to the Site Vice President -
Nuclear Generation or the Vice President -
Engineering and Technical Support Unit Staff All personnel reporting to the Executive Director -
Nuclear Production, including the Executive Director -
Nuclear Production Operations Staff All personnel reporting to the Operations Engineer Technical Staff All personnel reporting to the Director - Nuclear Engineering A Regulatory Qualifications List (RQL) is maintained and revised as required for changes in the regulatory requirements and plant staff personnel and titles. Using this list, qualified personnel can be selected for positions and the correct training and retraining programs can be maintained.
The qualification summaries, as required for plant staff affected by the RQL are maintained onsite and are available for review.
The resumes of the initial appointees to the managerial and supervising technical positions for Fermi 2 were included in the original FSAR.
FERMI 2 UFSAR 13.1 ORGANIZATIONAL STRUCTURE REFERENCES 13.1-13 REV 23 02/21
- 1. U.S. Nuclear Regulatory Commission, Policy Statement on Engineering Expertise on Shift, Generic Letter 86-04, February 13, 1986.
Fermi 2 UFSAR PRESIDENT AND CHIEF EXECUTIVE OFFICER DTE ENERGY SENIOR VICE PRESIDENT AND CHIEF NUCLEAR OFFICER SITE VICE PRESIDENT NUCLEAR GENERATION Signifies direct access Fermi 2 UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 13.1-1 DTE ENERGY CORPORATE ORGANIZATION REV 23 02/21 VICE PRESIDENT ENGINEERING AND TECHNICAL SUPPORT
Signifies Functional Relationship
(*)
When corporate support organizations perform quality-related activities for Fermi 2, such activities are performed under the Fermi 2 Quality Assurance Program.
NOTE:
When a position is not filled, reporting order will be the next higher position.
Fermi 2 UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 13.1-2 NUCLEAR GENERATION SENIOR VICE PRESIDENT AND CHIEF NUCLEAR OFFICER SITE VICE PRESIDENT NUCLEAR GENERATION DIRECTOR NUCLEAR ENGINEERING DIRECTOR NUCLEAR TRAINING MANAGER NUCLEAR SECURITY MANAGER NUCLEAR LICENSING MANAGER NUCLEAR PERFORMANCE IMPROVEMENT MANAGER NUCLEAR STRATEGIC ENGINEERING MANAGER NUCLEAR PERFORMANCE ENGINEERING MANAGER NUCLEAR DESIGN ENGINEERING MANAGER NUCLEAR TACTICAL ENGINEERING EXECUTIVE DIRECTOR NUCLEAR PRODUCTION DIRECTOR NUCLEAR OPERATIONS DIRECTOR NUCLEAR MAINTENANCE MANAGER RADIATION PROTECTION MANAGER CHEMISTRY DIRECTOR NUCLEAR OVERSIGHT DIRECTOR NUCLEAR TECHNICAL SUPPORT PROJECT MANAGEMENT MANAGER RADIOLOGICAL EMERGENCY
RESPONSE
PREPAREDNESS MANAGER ENGINEERING PROJECTS AND MODIFICATIONS CHAIRMAN NUCLEAR SAFETY REVIEW GROUP FERMI 2 UFSAR DIRECTOR STRATEGIC BUSINESS OPERATIONS DIRECTOR OUTAGE AND WORK MANAGEMENT REV 23 02/21 MANAGER NUCLEAR QUALITY ASSURANCE CORPORATE SUPPORT (*)
VICE PRESIDENT ENGINEERING AND TECHNICAL SUPPORT CORPORATE SUPPORT (*)
EXECUTIVE DIRECTOR NUCLEAR PRODUCTION DIRECTOR NUCLEAR OPERATIONS MANAGER RADIATION PROTECTION (*)
DIRECTOR NUCLEAR MAINTENANCE GENERAL SUPERVISOR(S)
RADIATION PROTECTION MANAGER (*) (**)
INDUSTRIAL HEALTH, AND SAFETY MAINTENANCE SUPERINTENDENT(S)
Fermi 2 UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 13.1-3 PLANT MANAGERS ORANIZATION SIGNIFIES DIRECT ACCESS
(*)
MANAGER - RADIATION PROTECTION AND THE RADIATION PROTECTION MANAGER POSITIONS MAY BE COMBINED. SHOULD THIS OCCUR, AN ASSISTANT RADIATION PROTECTION MANAGER MAY BE ASSIGNED.
(**)
THE RADIATION PROTECTION MANAGER HAS DIRECT ACCESS TO THE SITE VICE PRESIDENT -
NUCLEAR GENERATION TO RESOLVE QUESTIONS RELATED TO THE CONDUCT OF THE RADIATION PROTECTION PROGRAM. THE RADIATION PROTECTION MANAGER REPORTS DIRECTLY TO THE EXECUTIVE DIRECTOR - NUCLEAR PRODUCTION REGARDING RADIOLOGICAL CONTROL.
(***)
MANAGER - OUTAGE AND MANAGER - ONLINE WORK MANAGEMENT MAY BE COMBINED.
FERMI 2 UFSAR MANAGER CHEMISTRY SITE VICE PRESIDENT NUCLEAR GENERATION DIRECTOR OUTAGE AND WORK MANAGEMENT MANAGER ONLINE WORK MANAGEMENT (***)
MANAGER REACTOR SERVICES MANAGER OUTAGE (***)
REV 23 02/21
FERMI 2 UFSAR REV 23 02/21 SRO SRO SRO Fermi 2 UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 13.1-4 OPERATIONS ORGANIZATION
- DIRECTOR - NUCLEAR OPERATIONS AND OPERATIONS ENGINEER POSITION MAY BE COMBINED.
- CONTROL ROOM SUPERVISOR AND OPERATIONS SHIFT ENGINEER POSITION MAY BE COMBINED.
DIRECTOR NUCLEAR OPERATIONS OPERATIONS ENGINEER*
SHIFT MANAGER CONTROL ROOM SUPERVISOR**
NUCLEAR OPERATOR SHIFT TECHNICAL ADVISOR/OPERATIONS SHIFT ENGINEER RO LICENSED NUCLEAR OPERATOR
FERMI 2 UFSAR 13.2-1 REV 23 02/21 13.2 TRAINING PROGRAM 13.2.1 Program Description 13.2.1.1 General The objective of the training program for Fermi 2 is to provide fully trained operating, maintenance, and technical personnel. To accomplish this objective, the nuclear training program for Fermi 2 has been designed, and is being implemented, to meet the needs of the individual staff members. Each person receives training on the basis of background, previous training, and staff assignment.
Training for the following positions is derived from a systems approach to training and satisfies 10 CFR 50.120 requirements:
- a.
Non-licensed Operator
- b.
Shift Manager
- c.
Shift Technical Advisor/Operations Shift Engineer
- d.
Instrument and Control Technician
- e.
Electrical Maintenance Personnel
- f.
Mechanical Maintenance Personnel
- g.
Radiological Protection Technician
- h.
Chemistry Technician
- i.
Engineering Support Personnel The overall training program for the plant staff is divided into the following four areas:
- a.
Training programs for reactor operator and senior reactor operator license candidates, as described in Subsection 13.2.1.2
- b.
Training programs for nonlicensed personnel, as described in Subsection 13.2.1.3
- c.
General employee training (Fermi 2 orientation), as described in Subsection 13.2.1.4
- d.
Fire-protection training, as described in Subsection 13.2.4.
The Director - Nuclear Training has overall responsibility for the training program and is also in charge of simulator activities and simulator training.
13.2.1.2 Training Program for Operator License Candidates The training program for operator license candidates has been implemented in accordance with 10 CFR 55. The licensed operator training program was initially accredited by the Institute of Nuclear Power Operations (INPO) on December 18, 1985. This training program was developed using a systems approach to training.
FERMI 2 UFSAR 13.2-2 REV 23 02/21 13.2.1.3 Training Programs for Nonlicensed Personnel 13.2.1.3.1 General Training suited to individual needs and backgrounds is given to nonlicensed personnel, such as supervisors, engineers, operators, technicians, and repairmen. Each course is described in more detail in the sections that follow. In all cases, various sections of the training for nonlicensed personnel may be omitted for those who have applicable experience.
13.2.1.3.2 Training of Chemistry Personnel Selected chemical or chemical engineering personnel obtain specialized training presented by qualified personnel. In classroom and laboratory sessions, students receive instruction and practical experience that enable them to complete both radiochemical and chemical analyses for process control, waste disposal, effluent monitoring, and process and laboratory instrument calibrations and evaluations. The course work also covers material on interpreting and complying with the chemical and radiochemical aspects of the Technical Specifications, procedures, licenses, and plant warranties.
13.2.1.3.3 Training of Instrumentation and Control Personnel Training for instrumentation and control personnel is divided into two portions: (1) classroom and (2) practical exercises. Classroom courses include instrumentation theory, procedures, and plant specific systems training. During the practical exercises portion, the trainee receives specific hands-on training that is most beneficial to his/her position on the staff. In addition, personnel will demonstrate the ability to use plant and maintenance administrative procedures.
13.2.1.3.4 Training for Mechanical and Electrical Maintenance Personnel Mechanical and electrical journeymen for the plant are selected from other DTE facilities or from outside the company and have a minimum of 3 years of experience in one or more crafts. Their dexterity and ability in the basic skills of mechanical and electrical maintenance repair are shown by their previous experience.
As needed, personnel receive training in those skills required for the performance of work in radiological areas, the use of respiratory protection equipment, the use and/or maintenance of specific equipment, plant systems, and general employee training. In addition, personnel will demonstrate the ability to use plant and maintenance administrative procedures.
13.2.1.3.5 Training for Shift Technical Advisors Training for shift technical advisors is designed to provide the knowledge to effectively perform assigned duties. Included is theoretical training in the sciences related to nuclear power plant operations and practical training in the design and procedures used at Fermi 2.
In addition, simulator training is used to develop experience in transient responses.
FERMI 2 UFSAR 13.2-3 REV 23 02/21 13.2.1.3.6 Training for Radiation Protection Personnel The Radiation Protection Technician Program provides training and qualification in the duty areas of dosimetry, instrument calibration, effluent monitoring, and radiation protection operations. Trainees receive training as needed in general employee training, position-required training, and continuing training. Personnel will also demonstrate the use of plant and/or Radiation Protection administrative procedures, as applicable.
13.2.1.3.7 Training for Quality Assurance Personnel Quality assurance personnel must be certified in accordance with the applicable codes, regulations, and standards for the positions they hold.
As needed, personnel receive training in those skills required for the performance of work in radiological areas, the use of respiratory protection equipment, the use and/or maintenance of specific equipment, plant systems, and general employee training. In addition, personnel will demonstrate the ability to use plant and quality assurance administrative procedures.
13.2.1.3.8 Training for Nonlicensed Operators The training program for nonlicensed operators provides the necessary knowledge and skills for the operators to perform their jobs. Included in the program are systems training course(s) and area qualifications. This training facilitates ensuring the reliability of plant systems and equipment. The training program consists of two phases as described below.
System Training. System training increases the nonlicensed operator's knowledge of the function and operation of plant systems. It ensures the safety and reliability of plant operation as a result of the integrated activities performed by licensed and nonlicensed operators. The objective of system training, which is provided in addition to area qualifications, is to give the non-licensed operator a concept of the overall operation of the system, the purpose of systems, the interrelationships of systems, and the operator's responsibilities relative to each system. Emphasis is placed on systems that can affect the safe operation or the safe shutdown of the plant. System training uses examinations to verify qualifications in each system. Examinations are used for requalification purposes to ensure that an optimum level of proficiency is maintained by the nonlicensed operator.
Area Qualifications. Checklists are developed and established by plant area and by job classification to familiarize the operators with the specific job tasks expected to be performed as part of the normal shift functions. Area qualifications are based on the following plant areas:
- a.
Turbine building
- b.
Reactor building
- c.
Radwaste building
- d.
Outside areas, consisting of:
- 1.
Residual heat removal building
- 2.
General service water and circulating water pump houses
FERMI 2 UFSAR 13.2-4 REV 23 02/21
- 3.
Auxiliary boiler house
- 4.
120 KV and 345 KV switchyards Satisfactory completion of each checklist item by each operator is documented by a fully qualified nuclear operator, a licensed nuclear operator, a control room supervisor, or a shift manager. Final completion of each area qualification checklist is approved by the Operations Engineer or his/her designee.
13.2.1.3.9 Training for Engineer Support Personnel Technical personnel receive training to improve their overall knowledge of Fermi 2. This includes fundamental science topics, plant systems, and plant operations. They also receive general employee training. As needed, engineer support personal receive training on job-specific tasks and demonstrate a knowledge of organization specific procedures.
13.2.1.4 General Employee Training 13.2.1.4.1 Permanent Plant Personnel Training All DTE employees permanently assigned (those assigned on a day-to-day basis) to the plant are trained as necessary in the following areas.
- a.
Appropriate plans and procedures, including plant procedures for security, radiological emergency, and reporting fires
- b.
Radiological health and safety, including applicable portions of 10 CFR 19 and 10 CFR 20
- c.
Industrial safety
- d.
Use of protective clothing and equipment
- e.
Quality assurance
- f.
Evacuation signals and routes
- g.
Fitness for duty 13.2.1.4.2 Temporary Plant Personnel Training Temporary maintenance and service personnel (those who are not assigned to the plant on a day-to-day basis) are trained in the areas listed in Subsection 13.2.1.4.1 to the extent necessary to ensure the safe execution of their duties, or they are escorted by properly trained personnel as required.
13.2.1.4.3 Consultant, Vendor, and Contract Personnel Consultant, vendor, and contract personnel who are required to perform duties at the plant receive indoctrination training in the areas listed in Subsection 13.2.1.4.1 to the extent necessary for the safe execution of their normal duties, or they are escorted by properly trained personnel as required.
FERMI 2 UFSAR 13.2-5 REV 23 02/21 13.2.1.4.4 Deleted 13.2.1.5 Responsible Individual The Site Vice President - Nuclear Generation is responsible for ensuring that all plant staff members are trained appropriately to do their jobs. Authority is delegated to the individual managers of Nuclear Generation, who are responsible for specifically defining training requirements and for ensuring that their personnel have been trained according to said requirements.
The Director - Nuclear Training is responsible for administering, designing, developing, and implementing all training that has been determined to be required by the Site Vice President -
Nuclear Generation or his/her delegate.
13.2.2 Retraining Program A continuing requalification program for licensed operators and senior operators has been implemented in accordance with 10 CFR 55. The licensed operator requalification program was initially accredited by the Institute of Nuclear Power Operations (INPO) on December 18, 1985. This requalification program was developed using a systems approach to training.
13.2.3 Replacement Training The purpose of the plant replacement training program is to ensure that replacement personnel satisfy the training requirements stipulated in ANSI N18.1-1971 for the various plant positions.
13.2.3.1 Licensed Personnel Replacement Personnel selected to be in training for a reactor operator's or senior reactor operator's license are given formal technical training and practical on-the-job training. Subsection 13.2.1.2 identifies replacement training requirements.
13.2.3.2 Nonlicensed Personnel Replacement Personnel filling positions not requiring an NRC reactor operator's or senior reactor operator's license receive training as outlined in Subsection 13.2.1.3.8.
13.2.3.3 Program Administration The program is administered as described in Subsection 13.2.1.5.
13.2.4 Fire-Protection Training 13.2.4.1 Fire Brigade Training
FERMI 2 UFSAR 13.2-6 REV 23 02/21 13.2.4.1.1 General The fire brigade (five 5-member teams) is trained in accordance with the NRC staff supplemental guidance, "Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls and Quality Assurance," dated August 29, 1977. Fire brigade members will receive instruction in the following topics:
- a.
Identification of the fire hazards and associated types of fires that could occur in the plant and an identification of the location of the hazards, including areas where breathing apparatuses are required, regardless of the size of the fire
- b.
Identification of the location of installed and portable fire-fighting equipment in each area and familiarization with plant layout, including access and egress routes to each area
- c.
Proper use of available equipment and the correct method of fighting each type of fire (electrical fires, fires in cables and cable trays, hydrogen fires, flammable liquids, waste debris fires, and record file fires)
- d.
Indoctrination in the plant fire-fighting plan, with coverage of each employee's responsibilities, including changes thereto
- e.
Proper use of breathing equipment, and communication, lighting, and ventilation equipment
- f.
Detailed review of the procedures, with particular emphasis on what equipment must be used in particular areas
- g.
Review of the latest modifications, additions, or changes to the plant, procedures, fire-fighting equipment, and the fire-fighting plan
- h.
Proper method of fighting fires inside buildings and tunnels.
Special instruction in directing and coordinating fire-fighting activities will be provided for fire brigade leaders.
Qualified personnel, experienced in fighting the types of fires that could occur in the plant and in using the types of equipment available in the plant, provide the instruction. Classroom training is repeated at a frequency of at least every 2 years.
13.2.4.1.2 Practice Sessions Practice sessions are held at regular intervals not to exceed 1 year (Subsection 13.2.4.1.4).
These sessions are held at a location sufficiently remote from the plant so as not to endanger safety-related equipment. These sessions provide practice in extinguishing actual fires and are conducted by DTE or other qualified personnel.
Practice sessions are also conducted that require fire brigade members to use protective equipment, including emergency breathing apparatus. These sessions need not include fire fighting. They are provided at regular intervals not to exceed 1 year (Subsection 13.2.4.1.4).
FERMI 2 UFSAR 13.2-7 REV 23 02/21 13.2.4.1.3 Fire Drills Fire brigade drills are performed at the plant so that the fire brigade can practice as a team.
Drills include the following.
- a.
The simulated use of equipment for the various situations and types of fires that could reasonably occur in each safety-related area
- b.
Conformance, where possible, to the established plant fire-fighting plans
- c.
Operating fire-fighting equipment where practical; this also includes self-contained breathing apparatus, communication equipment, and portable or installed ventilation equipment, when applicable.
The drills are performed at regular intervals not to exceed 90 days, with a grace period of 25 percent, for each fire brigade. The minimum number of fire brigade drills conducted within a period shall be equal to the number of operating shifts at the station. At least one drill per year will be performed on a backshift for each brigade. At least one drill per year for each fire brigade will be unannounced.
The drills are preplanned, evaluated, and critiqued to assess the effectiveness, the response time, the selection, the placement, and the use of equipment. An assessment is also made of the leaders' direction of the effort and each member's response.
At 3-year intervals, a randomly selected unannounced drill must be critiqued by qualified individuals independent of the Fermi 2 staff.
13.2.4.1.4 Periodicity of Fire Brigade Training All training shall be performed within the time interval specified with
- a.
A maximum allowable extension not to exceed 25 percent of the training interval, but
- b.
The combined time interval for three consecutive training intervals shall not exceed 3.25 times the specified training interval.
13.2.4.1.5 Periodicity of Fire Drills Including the Offsite Fire Department Periodically (once per calendar year) these drills will include offsite fire department personnel and will conform with the Fermi 2 plan for coordination with offsite fire departments.
13.2.4.1.6 Offsite Fire Departments Training for the offsite fire departments is made available and includes training in basic radiation principles and practices, typical radiation hazards that may be encountered when fighting fires, and related plant procedures.
FERMI 2 UFSAR 13.3-1 REV 16 10/09 13.3 EMERGENCY PLANNING Information for this section is contained in the Fermi 2 Radiological Emergency Response Preparedness Plan, submitted separately to the NRC on the Fermi 2 docket. This plan is periodically updated and current revisions are submitted to the NRC.
FERMI 2 UFSAR 13.4-1 REV 23 02/21 13.4 REVIEW AND AUDIT 13.4.1 General During the construction of Fermi 2, the Edison quality assurance (QA) review and audit program complied with and exceeded the requirements of 10 CFR 50, Appendix B, QA Criteria for Nuclear Power Plants. The review and audit functions that Edison performed during construction are briefly addressed in Subsection 13.4.2 and more completely described in Section 17.1.
DTE uses a formal committee method to review testing and operation at Fermi 2. The review functions are carried out at two levels: one at the plant operations level and the second at the corporate level. The organizations responsible for reviews at these two levels are the Onsite Review Organization (OSRO) and the Nuclear Safety Review Group (NSRG),
respectively. The OSRO reviews plant operations, administrative procedures that could affect nuclear safety, and tests and plans for future activities to assist and advise the Executive Director - Nuclear Production on the safe operation of the plant. The NSRG functions to provide an independent review of plant activities and reports to and advises the Senior Vice President and Chief Nuclear Officer as described in Subsection 13.4.3.2. In developing the essential elements of DTE's review program for tests and operations, which is discussed more fully in Subsection 13.4.3, DTE was guided by ANSI N18.7-1976, Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants.
13.4.2 Review and Audit - Construction Reviews and audits during the construction of Fermi 2 were part of the QA program described in Section 17.1. This program used a designated organizational unit to provide review and audit, the Project Management Organization, which met at least monthly for a review of construction work in progress. The Assistant Project Manager - Engineering was specifically assigned responsibility for design review. The Edison administrative and technical staffs reviewed design documentation (e.g., specifications, drawings, and design changes) for compliance with applicable codes, standards, good engineering practice, and overall design intent. Quality assurance for the project was the responsibility of the Director-Project Quality Assurance, who reported functionally to the Manager - Enrico Fermi 2 Project and administratively to the Manager - Quality Assurance. Quality Assurance performed vendor surveillance and review by witnessing significant check-points and overall vendor performance. Edison QA also systematically audited activities at the plant site to ensure that the required standards of quality were attained in all construction and installation work performed at the job site. These owner activities complied with the requirements of 10 CFR 50, Appendix B. The review and audit functions during the construction phase are more fully described in Section 17.1.
13.4.3 Review - Test and Operation A review program has been established to ensure that the operation of the plant is in conformance with established requirements. Independent reviews by the Nuclear Safety
FERMI 2 UFSAR 13.4-2 REV 23 02/21 Review Group (NSRG) and reviews by the Onsite Review Organization (OSRO) are described in detail in Subsection 17.2.1.7.
13.4.3.1 Administration of the Onsite Review Organization The OSRO is responsible for advising the Executive Director - Nuclear Production on all matters related to nuclear safety.
Onsite Review Organization membership, meeting frequency, meeting minutes, and subjects requiring OSRO review are described in Section 17.2 and covered in a written charter.
Procedure - The chairman of the OSRO has the authority to approve or disapprove proposals by the OSRO for nuclear-related matters that do not have safety implications. The OSRO Chairman, or designated alternate, may make a temporary change or authorize interim remedial action involving matters related to nuclear safety, as deemed necessary, provided the intent of the operating license or the Technical Specifications is not altered and the provisions of Subsection 13.5.2 are met.
In the review process, the item for review by the OSRO is placed on the agenda by the staff member initiating the item, who has seen that all necessary preliminary actions, such as the design review, and all necessary 10 CFR 50.59 reviews have been completed. The OSRO considers the item and votes approval or disapproval. The action taken by the OSRO is recorded in the minutes of the meeting. Should the proposed change require a license amendment prior to implementation, it is then forwarded to the NSRG for review, together with a report from the OSRO giving the basis for the findings.
Subjects that require the use of special technical skills may be handled by a subcommittee or task force composed of specialists in that field. When necessary, consultants are obtained to assist the subcommittee or task force in its deliberation. The members of the subcommittee or task force and the consultants are appointed by the OSRO Chairman.
13.4.3.2 Administration of the Nuclear Safety Review Group The purpose of the NSRG is to provide independent review of facility operations as specified in Section 17.2. The NSRG reports to the Senior Vice President and Chief Nuclear Officer and acts for him in the review of the safety aspects of nuclear power plant operation.
Details concerning the membership requirements, areas of expertise, quorum requirements, review responsibilities and other administrative functions of the NSRG are given in Section 17.2.
13.4.3.3 Review of Operating Experience Internal and external operating experience is reviewed and assessed to ensure that information pertinent to plant safety is supplied continually to operators and other appropriate personnel and is used for effecting design and procedural changes to correct generic or specific deficiencies and to enhance plant safety when warranted.
The review of externally generated operating experience shall be coordinated primarily by individuals in Nuclear Performance Improvement and Nuclear Design Engineering. These reviews include, but are not limited to, GE nuclear steam supply system (NSSS) reports;
FERMI 2 UFSAR 13.4-3 REV 23 02/21 INPO Significant Event Evaluation Information Network (SEEIN) reports such as SOERs and SERs, and NRC Bulletins, and Generic Letters.
The operating experience that is considered as warranting further evaluation is evaluated through the Corrective Action Program. The conclusions and recommendations are reviewed and documented. Recommendations, hardware and software modifications, procedures revisions, design changes, etc., resulting from the reviews are then implemented by the responsible groups within Nuclear Generation. Procedural changes are reviewed and approved by OSRO as applicable.
The Executive Director - Nuclear Production is responsible for ensuring that evaluations are performed for internally generated operating experience events. LERs are reviewed by OSRO and are distributed to appropriate groups for implementation or for information and to the NRC.
FERMI 2 UFSAR 13.5-1 REV 23 02/21 13.5 PROCEDURES 13.5.1 General All safety-related operations at Fermi 2 are conducted in accordance with detailed written procedures. These procedures include the topics specified by Regulatory Guide 1.33 for compliance with the quality assurance (QA) requirements of 10 CFR 50, Appendix B and the applicable procedures required to implement the Fermi 2 commitments made in response to requirements of NUREG-0737. The procedures are implemented following the guidance provided in ANSI N18.7. The procedures related to nuclear safety are reviewed and approved prior to the initial use and periodically thereafter as described in Section 17.2.
The types of procedures used include the following:
- a.
Administrative Procedures
- b.
Technical Procedures, including:
- 1.
Operating Procedures
- 2.
Maintenance Procedures
- 3.
Reactor Engineering Procedures
- 4.
Radiation Protection
- 5.
Radiochemistry Procedures
- 6.
Fuel-Handling and Special Nuclear Materials Control and Accountability Procedures
- 7.
Fire Protection Implementing Procedures
- 8.
Radioactive-Materials-Handling Radwaste Procedures
- 9.
Environmental Procedures.
- 10. Maintenance, Calibration, and Testing Procedures
- 11. Surveillance Procedures
- c.
Radiological Emergency Response Preparedness Plan Procedures
- d.
Security Plan Procedures Contract personnel were used to prepare the initial Fermi 2 procedures. Available plant personnel assisted with this work when training and preoperational testing workload permitted. The ultimate responsibility for the content and accuracy of the final operation procedures and any updating that becomes necessary is as shown below for the various documents. The Director - Strategic Business Operations is responsible for the distribution and upkeep of procedures.
The format varies with the different procedures, but each procedure generally contains the following.
- a.
Purpose
FERMI 2 UFSAR 13.5-2 REV 23 02/21
- b.
References
- c.
Description of the equipment involved
- d.
Prerequisites
- e.
Safety precautions
- f.
Valve status and checkoff
- g.
Step-by-step actions
- h.
Normal reactions
- i.
Monitoring requirements
- j.
Emergency actions or hold instructions.
A complete list of titles of all procedures is included in a procedure control system.
13.5.2 Temporary Changes A temporary change to a procedure may be made provided that
- a.
The intent or format of the original procedure is not altered
- b.
The change is approved by two members of the plant management staff, at least one of whom holds a senior reactor operator's license
- c.
The change is documented, reviewed by the OSRO when required, and approved by the Executive Director - Nuclear Production or delegate within 14 days of implementation.
13.5.3 Conduct Manuals (Administrative Procedures)
The conduct manuals establish rules and instructions pertaining to the following:
- a.
Procedure adherence
- b.
Plant responsibilities and authorities
- c.
Review and audit programs
- d.
Reports and records
- e.
Equipment control and work permit procedures
- f.
Procurement and warehousing
- g.
Surveillance program
- h.
Plant security and visitor control
- i.
Standing or special orders (plant orders)
- j.
Radiation control standards procedures
- k.
Chemical-radiochemical procedures.
- l.
Shift and relief turnover procedure
FERMI 2 UFSAR 13.5-3 REV 23 02/21 Administrative Procedures are prepared under the direction of the appropriate director, or manager, who has the responsibility for their content and implementation. These procedures apply to all site activities and to all personnel at the site.
The procedure for shift and relief turnover consists in part of a checklist that is completed and signed by the oncoming and off-going Shift Managers and control room licensed nuclear operators.
The shift relief checklist is maintained in the control room by the control room operators.
13.5.4 Technical Procedures Technical procedures shall be used to provide step-by-step sequences for performing technical work activities. The following subsections describe various types of technical procedures used at Fermi 2.
13.5.4.1 Operating Procedures The preparation of the Operating Procedures is under the direction of the Director - Nuclear Operations. The implementation of these procedures mainly falls to the operating group and is performed under the direction of a licensed senior reactor operator or reactor operator.
Procedures that are prepared include, but are not limited to, those in Regulatory Guide 1.33, Appendix A.
13.5.4.1.1 General Operating Procedures The General Operating Procedures provide the necessary instructions for the integrated operation of all plant systems. Sign-offs are provided to ensure that necessary operating instructions, tests, and calibrations have been completed and are also used for confirming the completion of major steps in the proper sequence. General Operating Procedures are prepared under the direction of the Director - Nuclear Operations and implemented by Operations personnel.
13.5.4.1.2 System Operating Procedures System Operating Procedures provide the necessary sequence of steps to properly operate a particular system, including the following, as necessary:
- a.
Normal operation
- b.
Startup operation
- c.
Shutdown operation
- d.
Standby operation
- e.
Automatic initiation
- f.
Manual initiation.
FERMI 2 UFSAR 13.5-4 REV 23 02/21 13.5.4.1.3 Alarm Response Procedures Alarm Response Procedures provide guidance on actions to be taken by the control room operator when the alarm annunciators actuate. Each procedure contains the following:
- a.
The title of the annunciator
- b.
The actuating device
- c.
The setpoint(s) of the actuating device
- d.
The possible causes of the actuation
- e.
The immediate action to be taken by the operator and those actions which occur automatically
- f.
The subsequent action to be taken to return the system to its normal mode of operation, if necessary.
13.5.4.1.4 Abnormal Operating Procedures Abnormal Operating Procedures provide operator guidance for stabilizing the plant or for restoring normal operating conditions following a perturbation.
13.5.4.1.5 Emergency Operating Procedures Emergency Operating Procedures provide operator guidance to mitigate, reduce, or eliminate the consequence of an accident or potentially hazardous condition that has already occurred, to implement the emergency plan, or to prepare for possible hazardous natural occurrences.
13.5.4.2 Maintenance Procedures Maintenance activities that affect the performance of safety-related equipment are preplanned and performed in accordance with written procedures, documented instructions, and drawings appropriate to the activity. Procedures for performing various categories of maintenance are prepared following the guidelines contained in Regulatory Guide 1.33, Appendix A. The Director - Nuclear Maintenance is responsible for these procedures.
Maintenance receives permission from the Shift Manager before performing maintenance on plant equipment. This ensures that the operability of redundant safety-related systems is maintained as required by the Technical Specifications.
13.5.4.3 Maintenance, Calibration, and Testing Procedures Technical Procedures include the procedures necessary to provide periodic maintenance, calibration, and testing of plant instrumentation and components. These procedures have provisions for meeting surveillance schedules and for ensuring that measurement accuracies are adequate to keep parameters within operational and safety limits. Procedures for these tests and the control of measuring and test equipment used in conducting these tests are prepared in accordance with Regulatory Guide 1.33, Appendix A. The Manager - Nuclear Strategic Engineering, Manager - Nuclear Performance Engineering, and the Director -
Nuclear Maintenance are responsible for these procedures.
FERMI 2 UFSAR 13.5-5 REV 23 02/21 13.5.4.4 Reactor Engineering Procedures Reactor Engineering Procedures provide guidance for activities associated with fuel and core management and nuclear performance evaluation. The Manager - Nuclear Performance Engineering is responsible for these procedures.
13.5.4.5 Radiation Protection Procedures Procedures for personnel Radiation Protection are consistent with the requirements of 10 CFR Part 20 and are approved, maintained, and adhered to for all operations involving personnel radiation exposure. Radiation Protection Procedures describe the methods for personnel exposure control and monitoring; area radiation surveys; portable radiation surveys; portable radiation-monitoring equipment operation and calibration; emergency plan implementation; receipt, storage, and shipment of radioactive materials; and Radiation Protection training. The Manager - Radiation Protection is responsible for these procedures.
13.5.4.6 Radiochemistry Procedures Radiochemistry Procedures describe the plant chemistry and radiochemistry program, the calibration and operation of plant chemistry and radiochemistry equipment, and the methods of analysis to implement this program. The Manager - Chemistry is responsible for these procedures.
13.5.4.7 Fuel-Handling and Special Nuclear Material Control and Accountability Procedures Fuel-Handling Procedures specify all actions for core alterations and partial or complete refueling operations. Special Nuclear Material Control and Accountability Procedures define the methods for the control, accountability, and inventory of special nuclear material. The Manager - Nuclear Performance Engineering is responsible for ensuring that the requirements of the special nuclear material accountability program are implemented including the procedures governing special nuclear material greater than one gram. The Director - Nuclear Operations is also responsible fuel handling procedures.
13.5.4.8 Fire Protection Implementing Procedures Fire Protection Implementing Procedures are developed to control the activities associated with the Fire Protection Program. These procedures include fire prevention, fire detection, confinement, suppression, extinguishment, and administrative controls. Procedures are available for fire brigade organization and training, fire inspection procedures, maintenance, and testing. The Director - Nuclear Operations is responsible for the implementation of the Fire Protection Program and ensures that the requirements for the Fire Protection Program are met.
FERMI 2 UFSAR 13.5-6 REV 23 02/21 13.5.4.9 Radioactive-Materials-Handling Radwaste Procedures The Radioactive-Materials-Handling Radwaste Procedures describe the methods of operation and handling of liquid and solid radioactive waste. Radioactive waste from the floor, equipment, and chemical drains is included, plus the processing of sludges and liquids that result. The handling of dry compactible and noncompactible wastes is also included.
Procedures for the implementation of the Process Control Program are also included in this group. The Director - Nuclear Operations and Manager - Radiation Protection are responsible for these procedures.
13.5.4.10 Environmental Procedures The Environmental Procedures describe the environmental control programs, including whom to notify and what actions to take in the event of environmental incidents. Permits for the National Pollutant Discharge Elimination System are discussed, as are oil and chemical spills. The Manager - Nuclear Licensing is responsible for these procedures.
13.5.4.11 Surveillance Procedures Surveillance Procedures provide the necessary steps to perform the required periodic testing of safety-related structures, systems, and components in accordance with Technical Specification requirements and/or the ASME Boiler and Pressure Vessel (B&PV) Code Section XI. Surveillance procedures require the Shift Managers approval before performance of the surveillance. After completion of operability tests, the Shift Manager also reviews tests to verify that they have been successfully performed and meet the acceptance criteria cited in the surveillance procedure.
13.5.5 Radiological Emergency Response Preparedness Implementing Procedures The Radiological Emergency Response Preparedness (RERP) Plan and Implementing Procedures are the responsibility of the Supervisor - RERP. The RERP Plan establishes and defines the criteria and concepts that are necessary to respond to and mitigate the consequences of radiological emergencies to safeguard plant personnel and protect the health and safety of the public. The RERP Implementing Procedures establish the organization, direction and control, overall response, and protective actions for an emergency at Fermi 2.
RERP Implementing Procedures may be either administrative or technical procedures, depending upon content. The RERP Plan and Implementing Procedures are on file with the NRC.
13.5.6 Security Plan Procedures Security Plan Procedures are the responsibility of the Manager -Nuclear Security working in conjunction with the Director - Nuclear Operations. Security procedures may be either administrative or technical, depending upon content. The implementation of the Security Plan Procedures is performed by Nuclear Security personnel under the direction of the Manager - Nuclear Security.
FERMI 2 UFSAR 13.6-1 REV 23 02/21 13.6 PLANT RECORDS 13.6.1 Plant History The Director - Strategic Business Operations has overall responsibility for documents.
Specific individuals within the Fermi Organization are assigned responsibility for the generation and control of documents within their purview. The preparation of written procedures and revisions thereto, and of other administrative records, is also included in the responsibilities of these individuals.
A recorded history of Fermi 2 documenting the design, engineering, construction, testing, operation, maintenance, and modification of the plant is maintained in accordance with 10 CFR 50, Appendix B, Section XVII, Quality Assurance Records.
13.6.2 Operating Records Operating records and documents include appropriate log books, log sheets, data log output, and recorder charts covering the operation of the plant. These records are to include data sufficient to prepare operational information reports as required.
13.6.3 Events Records In addition to the operating records that are maintained on a continuing basis, records of other occurrences that may be required to reconstruct significant events or satisfy statutory requirements are maintained for the life of the plant.
FERMI 2 UFSAR 13.7 INDUSTRIAL SECURITY 13.7.1 Personnel and Plant Design The Manager - Nuclear Security is directly responsible for the security at Fermi 2. This section describes, in general terms, the security measures that are in effect at Fermi 2 for protection against radiological sabotage. A detailed security plan, not for public disclosure, is made available to the NRC. The Fermi 2 Security Plan conforms to the requirements of 10 CFR 73.55, Requirements for Physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage.
The security program is generally outlined in the Fermi 2 Physical Security Plan and is administered by the Manager - Nuclear Security. The security program at the plant is implemented by compliance with the criteria outlined in the Physical Security Plan.
The consequences of acts of radiological sabotage are minimized by the plant protective systems, including the nuclear safety features and engineered safety feature (ESF) systems incorporated in the plant design. The redundant protective systems and redundant ESF systems are described in detail in Chapters 6, 7, and 8. Also, fire protection equipment is located throughout the plant to minimize the effects of fire or explosion.
Plant operating, security, and staff personnel are screened to minimize potential security risks and to help ensure that reliable and emotionally stable personnel are selected for assignment in the plant. A background investigation, fitness for duty testing, and a psychological evaluation are performed for each employee who requires unescorted access to the Fermi 2 protected area. In addition, other DTE personnel and certain vendors or contractors, who have a need to be at the plant on a frequent basis, and whose personnel require unescorted access, are subject to the same pre-access screening. These people are issued photo-identification badges that permit unescorted access into the protected area. All other persons infrequently entering the protected area, such as certain subcontractors, vendor personnel, or visitors, are issued special badges that will provide limited and escorted access during their authorized visits.
Plant personnel in a management or supervisory capacity are advised of the necessity to recognize emotionally unstable personnel and to report abnormal behavior. A behavior observation program is established as required by 10 CFR 26.
A security training and qualification program is established for the purpose of developing and maintaining maximum proficiency of the Security Force personnel. In general, the guidelines in 10 CFR 73, Appendix B, are followed by the program. Security Force personnel are to be thoroughly familiar with all plant security procedures and are responsible for their implementation.
13.7.2 Security Plan A detailed Physical Security Plan, Safeguards Contingency Plan, and Security Training and Qualification Plan are on file with the NRC.
13.7-1 REV 19 10/14
FERMI 2 UFSAR Security procedures are issued to provide additional information for use by both the plant operating personnel and the plant security personnel in implementing the Physical Security Plan.
13.7.2.1 Access Control The control of access into the protected area is accomplished with perimeter barriers and intrusion detection/assessment devices. An industrial-type security fence, properly lighted and cleared on both sides and contiguous with certain site buildings, forms the boundary of the protected area. The protected area barrier serves as a physical and psychological deterrent to entry. In addition, the protected area has intrusion detection alarms to detect entry into this area. Electronic equipment is used for the surveillance of the protected area perimeter fence. A vehicle barrier system is also in place to protect the plant from malevolent use of vehicles. A description of the vehicle barrier system is included in the Physical Security Plan.
Manned alarm stations are established to control and monitor alarms, personnel, vehicles, and materials entering and leaving the protected area. Specific responsibilities are assigned in the Physical Security Plan and by written procedures for the operation of these manned stations.
The control of materials into the protected area is covered by written procedures, which provide controls for articles carried by personnel as well as loads carried by vehicles.
Personnel access to vital buildings, rooms, and spaces, including the main control room, is controlled by a computer-based access control system. Access is granted by the need to enter specific areas. Portal protection of vital rooms, buildings, and structures is provided by locking devices and alarms. All alarms are self-checking and tamper-indicating.
The surveillance of vital areas is accomplished by periodic security patrols and by authorized operating personnel.
13.7.2.2 Control of Personnel by Categories The control of authorized entry and movement is accomplished by a color-coded, conspicuously worn, photo-identification badge system. For permanent plant personnel and DTE employees who enter the plant frequently, a current access list is maintained and given to the Central Alarm Station and Secondary Alarm Station operators. Admission is granted to those persons who are positively identified and whose names appear on the approved access list. Access lists are reviewed and approved by a cognizant DTE manager or supervisor to ensure personnel on the list have a continued need for access.
For contractor, vendor, service personnel, or other authorized personnel not on the access authorization list, a visitor's badge is issued and an escort required. A visitor's log is maintained to show the name, date, time, purpose of visit, employment affiliation, citizenship, and name of individual to be visited.
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FERMI 2 UFSAR 13.7.2.3 Access Control During Emergencies Requests for emergency aid are made either by site security personnel or by authorized plant operating personnel with such requests coordinated with security personnel to permit the required rapid access needed in emergency conditions. Procedures covering emergency access are referred to in the Physical Security or Safeguards Contingency Plans and are compatible with the Fermi 2 Radiological Plan.
13.7.2.4 Surveillance and Monitoring Surveillance and monitoring of vital equipment, components, and areas are accomplished in accordance with administrative procedures and controls by the use of electronic equipment and remote-reading instruments to detect changes in ESF equipment. The inspection of nuclear fuel and radioactive materials upon receipt is in accordance with administrative controls and procedures.
13.7.2.5 Potential Security Threats Nuclear security officers are armed and trained to respond as necessary as outlined in the site's Safeguards Contingency Plan in the event of situations affecting the security of the Fermi 2 plant. Fermi 2 security personnel have two independent means of communicating with local law enforcement agencies in order to summon aid. In addition, all on duty members of the security force are equipped with two-way portable radios if other means of communication are not available.
For any civil disorder, bomb threat, or other type of security threat, the Monroe County Sheriff's office and/or the Michigan State Police are notified and provide the necessary assistance. Any incidents involving attempted or actual breach of security controls or attempted acts of sabotage are reported to the NRC, in accordance with 10 CFR 73.71.
The Nuclear Security Organization evaluates all security incidents to determine if they are reportable to the NRC in accordance with 10 CFR 73.71. Those incidents found to be reportable are investigated and a report is developed. The report is reviewed by the Manager
- Nuclear Security and the Site Vice President - Nuclear Generation before it is submitted to the NRC.
13.7.2.6 Administrative Procedures The Physical Security Plan and implementing procedures are reviewed and approved and periodic reviews are performed according to the Physical Security Plan.
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