ML23304A363
| ML23304A363 | |
| Person / Time | |
|---|---|
| Site: | 05200050 |
| Issue date: | 10/31/2023 |
| From: | NuScale |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML23306A033 | List:
|
| References | |
| LO-151262 | |
| Download: ML23304A363 (1) | |
Text
NuScale US460 Plant Standard Design Approval Application
Chapter Thirteen Conduct of Operations
Final Safety Analysis Report
Revision 1
©2023, NuScale Power LLC. All Rights Reserved COPYRIGHT NOTICE This document bears a NuScale Power, LLC, copyright notice. No right to disclose, use, or copy any of the information in this document, other than by the U.S. Nuclear Regulatory Commission (NRC), is authorized without the express, written permission of NuScale Power, LLC.
The NRC is permitted to make the number of copi es of the information contained in these reports needed for its internal use in connection with gen eric and plant-specific reviews and approvals, as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, or der, or regulation subject to the requirements of 10 CFR 2.390 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by NuScale Power, LLC, copyright protection notwithstanding.
Regarding nonproprietary versions of these reports, the NRC is permitted to make the number of additional copies necessary to provide copies for public viewing in appropriate docket files in public document rooms in Washington, DC, and elsewhere as may be required by NRC regulations. Copies made by the NRC must include this copyright notice in all instances and the proprietary notice if the original was identified as proprietary.
NuScale Final Safety Analysis Report Table of Contents
TABLE OF CONTENTS
CHAPTER 13 CONDUCT OF OPERATIONS............................. 13.1-1 13.1 Organizational Structure......................................... 13.1-1 13.1.1 Management and Technical Support Organization................ 13.1-1 13.1.2 Operating Organization..................................... 13.1-1 13.1.3 Qualifications of Nuclear Plant Personnel....................... 13.1-1 13.2 Training....................................................... 13.2-1 13.3 Emergency Planning............................................ 13.3-1 13.4 Operational Programs........................................... 13.4-1 13.5 Plant Procedures............................................... 13.5-1 13.5.1 Administrative Procedures................................... 13.5-1 13.5.2 Operating and Maintenance Procedures........................ 13.5-1 13.6 Security....................................................... 13.6-1 13.6.1 Physical Security.......................................... 13.6-1 13.6.2 Access Authorization - Operational Program..................... 13.6-2 13.6.3 Cyber Security Plan........................................ 13.6-2 13.6.4 References............................................... 13.6-2 13.7 Fitness for Duty................................................ 13.7-1
NuScale US460 SDAA i Revision 1 NuScale Final Safety Analysis Report Organizational Structure
CHAPTER 13 CONDUCT OF OPERATIONS
13.1 Organizational Structure
13.1.1 Management and Technical Support Organization
COL Item 13.1-1: An applicant that references the NuScale Power Plant US460 standard design will provide a description of the corporate or home office management and technical support organization, including a description of the qualification requirements for (1) each identified position or class of positions that provide technical support to the on-site operating organization, and (2) individuals holding management and supervisory pos itions in organizational units providing technical support to the on-site operating organization.
13.1.2 Operating Organization
COL Item 13.1-2: An applicant that references the NuScale Power Plant US460 standard design will provide a description of the proposed structure, functions, and responsibilities of the on-site organization necessary to operate and maintain the plant. The proposed operating staff shall be consistent with the minimum licensed operator staffing requirements in Section 18.5.
13.1.3 Qualifications of Nuclear Plant Personnel
COL Item 13.1-3: An applicant that references the NuScale Power Plant US460 standard design will provide a description of the qualification requirements for each management, operating, technical, and maintenance position described in the operating organization.
NuScale US460 SDAA 13.1-1 Revision 1 NuScale Final Safety Analysis Report Training
13.2 Training
COL Item 13.2-1: An applicant that references the NuScale Power Plant US460 standard design will provide a description and schedule of the Initial Training and Qualification as well as Requalification Programs for reactor operators and senior reactor operators.
COL Item 13.2-2: An applicant that references the NuScale Power Plant US460 standard design will provide a description and schedule of the Non-Licensed Plant Staff Training Programs including initial training, periodic retraining, and qualification requirements.
NuScale US460 SDAA 13.2-1 Revision 1 NuScale Final Safety Analysis Report Emergency Planning
13.3 Emergency Planning
The NuScale Power Plant design includes design features, facilities, and equipment that are usable for up to six NuScale Power Modules to support Emergency Response functions.
A Technical Support Center (TSC) is provided, compliant with the design requirements of NUREG-0696, Functional Criteria for Emergency Response Facilities. The TSC is located in the Control Building. A description of the Control Building is provided in Section 1.2.2, General Arrangement of Major Structures and Equipment. When using the shortest designed direct route, the walking time between the entrance of the control room and the entrance of the TSC does not exceed two minutes. The TSC can accommodate staffing levels of at least 25 persons, including 20 licensee and 5 NRC personnel at 75 square feet per person. The TSC includes a technical evaluation room and additional space for storage, offices, and conference rooms. The design ensures that personnel are protected from radiological hazards, including direct radiation and airborne radioactivity from in-plant sources under accident conditions (i.e., maximum of 5 rem total effective dose equivalent for the duration of the accident). In the event of a loss of ventilation, or if the TSC becomes otherwise uninhabitable, personnel are evacuated and the TSC functions are transferred to a location de signated by the Emergency Plan. Heating, ventilation and air conditioning for the TSC is provided by the control room area ventilation system and is discussed further in Section 9.4.1, Control Room Area Ventilation System.
The TSC is equipped with voice communications systems that provide communications between the TSC and plant, local, and off-si te Emergency Response facilities, the NRC, and local and state operations centers. Section 9.5.2, Communication System, provides additional information regarding commun ications equipment and power sources.
The TSC includes engineering workstations and non-operator workstation displays, as described in Section 7.2.13, Displays and Monitoring.
An Emergency Response data system compliant with Section VI of 10 CFR 50 Appendix E provides a direct near-real-time electronic data link of selected parameters between the on-site computer system and the NRC Operations Center in the event of an emergency.
Radiation Protection support facilities, includi ng personnel decontamination facilities, are described in Section 12.1.2, Design Considerations.
COL Item 13.3-1: An applicant that references the NuScale Power Plant US460 standard design will provide a description of the Emergency Response facilities for management of overall licensee Emergency Response. The facility will meet the requirements of 10 CFR 52.79.
COL Item 13.3-2: An applicant that references the NuScale Power Plant US460 standard design will provide a comprehensive Emergency Plan in accordance with 10 CFR 50 and 10 CFR 52.79(a)(21).
NuScale US460 SDAA 13.3-1 Revision 1 NuScale Final Safety Analysis Report Operational Programs
13.4 Operational Programs
COL Item 13.4-1: An applicant that references the NuScale Power Plant US460 standard design will provide site-specific information, including implementation milestones, for Operational Programs:
- Inservice Inspection Programs (Section 5.2, Section 5.4, and Section 6.6)
- Inservice Testing Programs (Section 3.9 and Section 5.2)
- Environmental Qualification Program (Section 3.11)
- Preservice Inspection Program (Section 5.2 and Section 5.4)
- Preservice Testing Program (Section 3.9.6 and Section 5.2)
- Containment Leakage Rate Testing Program (Section 6.2)
- Fire Protection Program (Section 9.5.1)
- Process and Effluent Monitoring and Sampling Program (Section 11.5)
- Radiation Protection Program (Section 12.5)
- Non-Licensed Plant Staff Training Program (Section 13.2)
- Reactor Operator Training Program (Section 13.2)
- Reactor Operator Requalification Program (Section 13.2)
- Emergency Planning (Section 13.3)
- Process Control Program (Section 11.4)
- Security (Section 13.6)
- Quality Assurance Program (Section 17.5)
- Maintenance Rule (Section 17.6)
- Initial Test Program (Section 14.2)
NuScale US460 SDAA 13.4-1 Revision 1 NuScale Final Safety Analysis Report Plant Procedures
13.5 Plant Procedures
Administrative and operating procedures are ut ilized by the operating organization to ensure that routine operating, off-normal, and emergency activities are conducted in a safe manner.
13.5.1 Administrative Procedures
COL Item 13.5-1: An applicant that references the NuScale Power Plant US460 standard design will describe the site-specific procedures that provide administrative control for activities that are important for the safe operation of the facility consistent with the guidance provided in Regulatory Guide 1.33, Quality Assurance Program Requirements (Operation), Revision 3.
COL Item 13.5-2: An applicant that references the NuScale Power Plant US460 standard design will provide a plan for the development, implementation, and control of administrative procedures, including preliminary schedules for preparation and target dates for completion. Additionally, the applicant will identify the group within the operating organization responsible for maintaining these procedures.
13.5.2 Operating and Maintenance Procedures
13.5.2.1 Operating and Emergency Operating Procedures
COL Item 13.5-3: An applicant that references the NuScale Power Plant US460 standard design will describe the process to manage the development, review and approval of the site-specific procedures that operators use in the main control room and locally in the plant, including normal operating procedures, abnormal operating procedures, and emergency operating procedures. The applicant will describe the classification system for these procedures, and the general format and content of the different classifications.
COL Item 13.5-4: An applicant that references the NuScale Power Plant US460 standard design will provide a plan for the development, implementation, and control of operating procedures, including preliminary schedules for preparation and target dates for completion. Additionally, the applicant will identify the group within the operating organization re sponsible for maintaining these procedures.
COL Item 13.5-5: An applicant that references the NuScale Power Plant US460 standard design will provide a plan for the development, implementation, and control of emergency operating procedures, including preliminary schedules for preparation and target dates for completion.
Additionally, the applicant will identify the group within the operating organization responsible for maintaining these procedures.
NuScale US460 SDAA 13.5-1 Revision 1 NuScale Final Safety Analysis Report Plant Procedures
13.5.2.2 Maintenance and Other Operating Procedures
COL Item 13.5-6: An applicant that references the NuScale Power Plant US460 standard design will describe the site-specific maintenance and other operating procedures, including how these procedures are classified, and the general format and content of the different classifications. The categories of procedures listed below will be included:
- plant radiation protection procedures
- emergency preparedness procedures
- calibration and test procedures
- chemical-radiochemical control procedures
- radioactive waste management procedures
- maintenance and modification procedures
- material control procedures
- plant security procedures
COL Item 13.5-7: An applicant that references the NuScale Power Plant US460 standard design will provide a plan for the development, implementation, and control of maintenance and other operating procedures, including preliminary schedules for preparation and target dates for completion. Additionally, the applicant will identify what group or groups within the operating organization have the responsibility for maintaining and following these procedures.
NuScale US460 SDAA 13.5-2 Revision 1 NuScale Final Safety Analysis Report Security
13.6 Security
13.6.1 Physical Security
The NuScale Power Plant physical security design provides the capabilities to detect, assess, impede, and delay threats up to and including the design basis threat, and to provide defense-in-depth through the integration of systems, technologies, and equipment. The design of physical security systems within the nuclear island and structures is described in the technical report TR-118318, NuScale Design of Physical Security Systems, (Reference 13.6-1), which is incorporated by reference to this Final Safety Analysis Report.
COL Item 13.6-1: An applicant that references the NuScale Power Plant US460 standard design will provide the following:
- Security Plans (Physical Security, Security Training and Qualification, and Safeguards Contingency Plans)
- proposed site security provisions to be implemented during construction and as modules are completed and become operational
- elements of the physical security system not located within the nuclear island and structures
COL Item 13.6-2: An applicant that references the NuScale Power Plant US460 standard design will be responsible for the requirements described in Table 5-1 of TR-118318, NuScale Design of Physical Security Systems (Reference 13.6-1).
The central alarm station provides
- continuous communications with on-site and off-site resources via two-way voice communication.
- two-way voice communication between local law enforcement authorities and the site.
- a system for continuous communication with the control room.
COL Item 13.6-3: An applicant that references the NuScale Power Plant US460 standard design will provide a secondary alarm station that is equal and redundant to the central alarm station.
Independent power sources for alarm annunciation equipment and non-portable communication equipment are provided. Reference 13.6-1 provides additional information on communications systems associated with physical security.
The methodology for Inspections, Tests, Analyses, and Acceptance Criteria is described in Section 14.3. The applicant addresses site-specific Inspections, Tests, Analyses, and Acceptance Criteria for physical security structures, systems, and components.
NuScale US460 SDAA 13.6-1 Revision 1 NuScale Final Safety Analysis Report Security
13.6.2 Access Authorization - Operational Program
COL Item 13.6-4: An applicant that references the NuScale Power Plant US460 standard design will provide a description of the Access Authorization Program.
13.6.3 Cyber Security Plan
COL Item 13.6-5: An applicant that references the NuScale Power Plant US460 standard design will provide a Cyber Security Plan.
13.6.4 References
13.6-1 NuScale Power, LLC, NuScale Design of Physical Security Systems, TR-118318, Revision 1.
NuScale US460 SDAA 13.6-2 Revision 1 NuScale Final Safety Analysis Report Fitness for Duty
13.7 Fitness for Duty
This section addresses an operational program that is the responsibility of an applicant and is not applicable to new plant designs.
NuScale US460 SDAA 13.7-1 Revision 1