ML17264B172
| ML17264B172 | |
| Person / Time | |
|---|---|
| Site: | NuScale |
| Issue date: | 09/21/2017 |
| From: | Rad Z NuScale |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| RAIO-0917-56125 | |
| Download: ML17264B172 (15) | |
Text
RAIO-0917-56125 September 21, 2017 Docket No.52-048 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738
SUBJECT:
NuScale Power, LLC Response to NRC Request for Additional Information No.
102 (eRAI No. 8925) on the NuScale Design Certification Application
REFERENCE:
U.S. Nuclear Regulatory Commission, "Request for Additional Information No.
102 (eRAI No. 8925)," dated July 25, 2017 The purpose of this letter is to provide the NuScale Power, LLC (NuScale) response to the referenced NRC Request for Additional Information (RAI).
The Enclosure to this letter contains NuScale's response to the following RAI Questions from NRC eRAI No. 8925:
13.03-1 13.03-2 13.03-3 13.03-4 This letter and the enclosed response make no new regulatory commitments and no revisions to any existing regulatory commitments.
If you have any questions on this response, please contact Steven Mirsky at 240-833-3001 or at smirsky@nuscalepower.com.
Sincerely, Zackary W. Rad Director, Regulatory Affairs NuScale Power, LLC Distribution: Gregory Cranston, NRC, OWFN-8G9A Samuel Lee, NRC, OWFN-8G9A Prosanta Chowdhury NRC, OWFN-8G9A (QFORVXUH 1X6FDOH5HVSRQVHWR15&5HTXHVWIRU$GGLWLRQDO,QIRUPDWLRQH5$,1R
NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com
NuScale Response to NRC Request for Additional Information eRAI No. 8925 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com
Response to Request for Additional Information Docket No.52-048 eRAI No.: 8925 Date of RAI Issue: 07/25/2017 NRC Question No.: 13.03-1 In accordance with 10 CFR 50.47(b)(8) and paragraph IV.E.8 to Appendix E of 10 CFR Part 50, respectively, adequate emergency facilities and equipment to support the emergency response shall be provided and maintained, and adequate provisions shall be made and described for emergency facilities and equipment. In the Design Certification Application (DCA), Final Safety Analysis Report (FSAR) Tier 2, Chapter 13, Conduct of Operations, Section 13.3, Emergency Planning, the applicant stated that the NuScale design includes, design features, facilities, and equipment that are usable for multiple NuScale Power Modules to support emergency response functions.
The staff requests that NuScale explain what is implied by the term multiple, and if the design features are only usable for a certain number of modules or pertain to an entire site.
NuScale Response:
The NuScale Power Plant design includes design features, facilities, and equipment that are usable for up to twelve (12) NuScale Power Modules to support emergency response functions.
FSAR Tier 2 Section 13.3 has been updated to replace "multiple" with the number of NuScale Power Modules.
Impact on DCA:
FSAR Section 13.3 has been revised as described in the response above and as shown in the markup provided in this response.
NuScale Nonproprietary
Response to Request for Additional Information Docket No.52-048 eRAI No.: 8925 Date of RAI Issue: 07/25/2017 NRC Question No.: 13.03-2 The regulatory requirements for a Technical Support Center (TSC) are found in 10 CFR 50.47(b)(8), Subsection IV.E.8 in Appendix E to 10 CFR Part 50, and 10 CFR 50.34(f)(2)(xxv).
Associated guidance is described in NUREG-0696, Functional Criteria for Emergency Response Facilities, Section 2, and in Supplement 1 to NUREG-0737, Clarification of TMI Action Plan Requirements, Section 8.2.
- i. Structure Section 2.5 of NUREG-0696 states that the TSC should be able to withstand the most adverse conditions (100-yearrecurrence frequency wind and flood) and well-engineered to withstand earthquakes. Supplement 1 to NUREG-0737, Section 8.2.1.d, notes that it should be structurally built in accordance with the Uniform Building Code. However, FSAR Tier 2, Section 13.3 appears to be silent on the structural features of the TSC.
The staff requests that NuScale describe the structural features of the TSC as they relate to Section 2.5 of NUREG-0696 and Supplement 1 to NUREG-0737, Section 8.2.
ii. Habitability and Comparability to MCR Section 2.6 of NUREG-0696 states that the TSC shall have the same radiological habitability as the main control room (MCR) under accident conditions. In addition, NUREG-0737 states, in part, that the TSC shall meet the requirements of General Design Criteria 19 (5 rem whole body) for the duration of the accident and have radiation monitoring equipment available to measure those radiation levels. However, FSAR Tier 2, Section 13.3, does not specifically state whether the TSC can protect personnel from direct, airborne, in-plant radiological hazards under accident conditions in a manner that is equivalent to the MCR.
NuScale Nonproprietary
The staff requests that NuScale clarify if the TSC will be able to protect personnel from direct, airborne, in-plant radiological hazards under accident conditions in a manner that is equivalent to the MCR, as specified in Section 2.6 of NUREG-0696. If yes, then NuScale is to explain how those design features are met for the TSC facility and either reference the pertinent discussion in the FSAR, or provide revisions to FSAR text, to clearly document the basis for TSC radiological habitability. If no, then NuScale is to explain why those design features do not need to be met for the TSC facility.
iii. Relocating function if TSC is evacuated FSAR Tier 2, Section 13.3 states, in part: In the event of a loss of ventilation, or if the TSC becomes otherwise uninhabitable, personnel are evacuated and the TSC function is transferred to an alternate location.
The staff requests that NuScale describe where the TSC function will be transferred to if the TSC is evacuated, and the capabilities of this alternate location to perform TSC functions.
iv. Diagram of location FSAR Tier 2, Section 13.3 states, in part, that the TSC is located on the 100-ft elevation of the control building. The FSAR also states that the walking time between the entrance of the MCR and the entrance of the TSC does not exceed 2 minutes.
The staff requests that NuScale identify where, if any, a diagram exists that displays this plant layout for the technical staffs review to ensure consistency with Section 2.2 of NUREG-0696.
NuScale Response:
Part i:
The technical support center (TSC) is located in the portion of the Control Building (CRB) that is designed to Seismic Category I criteria to withstand seismic loads associated with the safe shutdown earthquake (refer to FSAR Tier 2 Section 3.8.4.1.2). The portion of the CRB containing the TSC complies with General Design Criterion (GDC) 2 and GDC 4 and is designed to withstand the most severe effects of wind, hurricane, tornadoes, and floods (refer to Section 3.3 and Section 3.4). These design criteria meet the requirements of NUREG-0696 Section 2.5 and NUREG-0737 Supplement 1 Section 8.2.1.d. FSAR Tier 2 Section 13.3 has been updated to identify the seismic classification of the CRB.
Part ii:
The TSC and the main control room (MCR) share the control room ventilation system (CRVS),
as described in FSAR Tier 2 Section 9.4.1. Upon detection of a high radiation level in the NuScale Nonproprietary
outside air intake, the normal outside air flow path is isolated and 100 percent of the outside air is bypassed through the air filtration unit to filter outside air and minimize radiation exposure to personnel within the MCR and TSC. This mode of operation allows the CRVS to continue providing breathable air to MCR and TSC personnel and maintain the MCR and TSC at positive pressure with respect to the outside environment. This design meets the requirement of NUREG-0696 Section 2.6.
Part iii:
If the TSC becomes uninhabitable, the plant management function is transferred to a location designated by the emergency plan (COL Item 13.3-3). FSAR Tier 2 Section 13.3 has been updated to refer to the emergency plan.
Part iv:
The TSC is located directly above the MCR in the CRB, as shown in FSAR Tier 2 Figure 1.2-24 and Figure 1.2-27. Using either stairwell in the CRB, the transit time between the TSC and the MCR is less than two minutes, meeting the requirement in NUREG-0696 Section 2.2.
Impact on DCA:
FSAR Section 13.3 has been revised as described in the response above and as shown in the markup provided in this response.
NuScale Nonproprietary
Response to Request for Additional Information Docket No.52-048 eRAI No.: 8925 Date of RAI Issue: 07/25/2017 NRC Question No.: 13.03-3 Relevant regulations pertaining to emergency preparedness instrumentation, data system equipment, and power supplies include 10 CFR 50.47(b)(8), Subsection IV.E.9 in Appendix E to 10 CFR Part 50, and Subsection VI in Appendix E to 10 CFR Part 50. Instrumentation, data system equipment, and power supplies must be in place to provide data retrieval capabilities of safety parameters during accident conditions and the communication of emergency response data system (ERDS) parameters to the NRC as identified in Sections 2.8 and 2.9 of NUREG-0696 and Supplement 1 to NUREG 0737, Section 8.2.1.h.
- i. FSAR Tier 2, Section 13.3 states, in part: The TSC includes a safety display and indication system as discussed in Section 7.2.14. However, neither Section 13.3 nor 7.2.14 provides a clear indication or description regarding how the safety display indication system (SDIS) relates to applicable EP functions and how these functions are achieved.
The staff requests that NuScale describe the data retrieval capabilities of the SDIS for the NuScale design, as compared to the traditional Safety Parameter Display System (SPDS) and Emergency Response Data System (ERDS) for traditional light water reactors. The staff also requests that NuScale explain the design features and characteristics of those system(s) as related to ensuring that appropriate displays and instrumentation are in place to display and receive parameters during accident conditions (e.g. meteorological data, radiation monitors-stationary and/or designated portable monitoring) within the TSC.
ii. Section 2.8 of NUREG-0696 states that the TSC must contain primary and backup power in order to maintain continuity of TSC functions and to immediately resume data acquisition, storage, and display of TSC data in the event of a loss of power and/or if the TSC becomes uninhabitable.
The staff requests that NuScale describe the backup power capabilities of the NuScale design as they pertain to instrumentation and data system equipment associated with the TSC.
NuScale Nonproprietary
iii. FSAR Tier 2, Section 13.3 states, in part: 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 onsite computer system and the NRC Operations Center in the event of an emergency.
Table 7.1-7, Summary of Type A, B, C, D, and E Variables, in FSAR Tier 2, Section 7.2.15 appears to contain the variables monitored by the Module Protection System (MPS) and the Plant Protection System (PPS). However, neither FSAR Section 13.3 nor 7.2.15 provides a clear discussion on ERDS data variables.
The staff requests that NuScale provide discussions to confirm that the capability exists for the data variables identified in FSAR Table 7.1-7 to be communicated to the NRC as specified in Sections 2.8 and 2.9 of NUREG-0696 and Supplement 1 to NUREG-0737, Section 8.2.1.
NuScale Response:
Part i:
The reference to the safety display and indication system (SDIS) in Section 13.3 is being changed to refer to the technical support center (TSC) engineering workstations, which are part of the module control system (MCS) and plant control system (PCS). The post-accident monitoring (PAM) variables displayed on SDIS in the main control room are also displayed on MCS or PCS and are available to the TSC engineering workstations. The PAM instrumentation includes the required functions, range, and accuracy for each variable monitored. Variables and their type classification are based on their accident management function as identified in abnormal operating procedures, emergency operating procedures, and emergency procedure guidelines. The PAM Type B, C, D, and E variables are summarized in FSAR Tier 2 Table 7.1-7.
The engineering workstation PCS displays in the technical support center (TSC) provide monitoring functionality to plant processes and equipment.
There is a unidirectional communication interface between the MCS and PCS networks and the plant network. The MCS and PCS systems provide monitoring data via one-way communication interfaces to the plant network which provides data recording, trending, and historical retention that can be called up on the TSC engineering workstations.
Additionally, there is a link from the plant network to the NRC emergency response data system (ERDS) via dedicated communication servers that connect to the plant network and provide data communication of required plant data to offsite emergency response facilities as shown in FSAR Tier 2 Figure 7.0-1.
This design addresses the requirements of NUREG-0696 Section 2.8 and Section 2.9 and NuScale Nonproprietary
NUREG-0737 Supplement 1 Section 8.2.1.
Part ii:
TSC equipment, such as engineering workstations and communications equipment, are components of the MCS, PCS, and communications system (COMS). Power is supplied to these systems from the normal DC power system (EDNS).
As described in FSAR Tier 2 Section 8.3.2.1.2, the EDNS consists of batteries, battery chargers, and inverters. The EDNS battery chargers are normally supplied from the low voltage AC electrical distribution system (ELVS). Following a loss of AC electrical power supply to the EDNS battery chargers, the batteries automatically assume the loads for a minimum duration of 40 minutes.
Additionally, in the event of a loss of normal onsite AC power, backup power to the ELVS can be provided by the backup power supply system (BPSS). Spare battery and charger terminal connection points are also provided for connection to mobile battery and charging units if necessary. The BPSS design is described in FSAR Tier 2 Section 8.3.1.1.2.
Part iii:
As described in the response to Part i, the capability exists for the data variables identified in FSAR Table 7.1-7 to be communicated to the NRC ERDS. The specific data to be transmitted via ERDS will be identified as part of emergency planning (COL Item 13.3-3).
Impact on DCA:
FSAR Section 13.3 has been revised as described in the response above and as shown in the markup provided in this response.
NuScale Nonproprietary
Response to Request for Additional Information Docket No.52-048 eRAI No.: 8925 Date of RAI Issue: 07/25/2017 NRC Question No.: 13.03.4 In accordance with 10 CFR 50.47(b)(8) and subsection IV.E.8 in Appendix E to 10 CFR Part 50, respectively, adequate emergency facilities and equipment to support the emergency response shall be provided and maintained, and adequate provisions shall be made and described for emergency facilities and equipment, including a licensee emergency operations facility (EOF) from which effective direction can be given and effective control can be exercised during an emergency.
COL Item 13.3-2 in FSAR Tier 2, Section 13.3 states: A COL applicant that references the NuScale Power Plant design certification will provide a description of a near-site emergency operations facility for management of overall licensee emergency response and which complies with the guidance in NUREG-0696, Functional Criteria for Emergency Response Facilities.
However, this COL Item does not include a provision for conformance to the updated performance-based EOF guidance in NSIR/DPR/ISG-01,Section VI.I, which supplemented NUREG-0696, or Supplement 1 to NUREG-0737, Section 8.4.
The staff requests that NuScale consider revision of COL Item 13.2-2 to include a provision for conforming to the guidance in NSIR/DPR/ISG-01, in addition to NUREG-0696 and Supplement 1 to NUREG-0737, or explain why this conformance is not necessary.
It should also be noted that the 2011 final rule, Enhancements to Emergency Preparedness Regulations (76 FR 72598; November 23, 2011), removed the reference to the EOF as a near site facility and provided, instead, performance-based criteria for EOFs.
NuScale Response:
COL Item 13.3-2 will be changed to state:
A COL applicant that references the NuScale Power Plant design certification will provide a description of an emergency operations facility for management of overall licensee emergency response and which complies with the guidance in NUREG-0696, 'Functional Criteria for Emergency Response Facilities,' NUREG-0737 Supplement 1, 'Clarification of TMI Action Plan NuScale Nonproprietary
Requirements - Requirements for Emergency Response Capability,' and NSIR/DPR-ISG-01,
'Interim Staff Guidance - Emergency Planning for Nuclear Power Plants.'
Impact on DCA:
FSAR Section 13.3 and FSAR Table 1.8-2 have been revised as described in the response above and as shown in the markup provided in this response.
NuScale Nonproprietary
NuScale Final Safety Analysis Report Interfaces with Certified Design RAI 02.04.13-1, RAI 03.05.01.04-1, RAI 03.05.02-2, RAI-03.06.02-15, RAI 03.07.01-2, RAI 03.07.01-3, RAI 03.07.02-12, RAI 03.11-14, RAI 03.11-8, RAI 10.02-1, RAI 10.02-2, RAI 10.04.10-2, RAI 13.01.01-1, RAI 13.02.02-1, RAI 13.03-4, RAI 13.05.02.01-2, RAI 13.05.02.01-3, RAI 13.05.02.01-4 Table 1.8-2: Combined License Information Items Item No. Description of COL Information Item Section COL Item 1.1-1: A COL Applicantapplicant that references the NuScale Power Plant design certification will 1.1 identify the site-specific plant location.
COL Item 1.1-2: A COL Applicantapplicant that references the NuScale Power Plant design certification will 1.1 provide the schedules for completion of construction and commercial operation of each power module.
COL Item 1.4-1: A COL Applicantapplicant that references the NuScale Power Plant design certification will 1.4 identify the prime agents or contractors for the construction and operation of the nuclear power plant.
COL Item 1.7-1: A COL Applicantapplicant that references the NuScale Power Plant design certification will 1.7 provide site-specific diagrams and legends, as applicable.
COL Item 1.7-2: A COL Applicantapplicant that references the NuScale Power Plant design certification will list 1.7 additional site-specific P&IDs and legends as applicable.
COL Item 1.8-1: A COL Applicantapplicant that references the NuScale Power Plant design certification will 1.8 provide a list of departures from the certified design.
COL Item 1.9-1: A COL Applicantapplicant that references the NuScale Power Plant design certification will 1.9 review and address the conformance with regulatory criteria in effect six months before the docket date of the COL application for the site-specific portions and operational aspects of the facility design.
COL Item 1.10-1: A COL Applicantapplicant that references the NuScale Power Plant design certification will 1.10 evaluate the potential hazards resulting from construction activities of the new NuScale facility to the safety-related and risk significant structures, systems, and components of existing operating unit(s) and newly constructed operating unit(s) at the co-located site per 10 CFR 52.79(a)(31). The evaluation will include identification of any management and administrative controls necessary to eliminate or mitigate the consequences of potential hazards and demonstration that the limiting conditions for operation of an operating unit would not be exceeded. This COL item is not applicable for construction activities (build-out of the facility) at an individual NuScale Power Plant with operating NuScale Power Modules.
COL Item 2.0-1: A COL Applicantapplicant that references the NuScale Power Plant design certification will 2.0 demonstrate that site-specific characteristics are bounded by the design parameters specified in Table 2.0-1. If site-specific values are not bounded by the values in Table 2.0-1, the COL applicant will demonstrate the acceptability of the site-specific values in the appropriate sections of its combined license application.
COL Item 2.1-1: A COL Applicantapplicant that references the NuScale Power Plant design certification will 2.1 describe the site geographic and demographic characteristics.
COL Item 2.2-1: A COL Applicantapplicant that references the NuScale Power Plant design certification will 2.2 describe nearby industrial, transportation, and military facilities. The COL applicant will demonstrate that the design is acceptable for each potential accident, or provide site-specific design alternatives.
COL Item 2.3-1: A COL Applicantapplicant that references the NuScale Power Plant design certification will 2.3 describe the site-specific meteorological characteristics for Section 2.3.1 through Section 2.3.5, as applicable.
COL Item 2.4-1: A COL Applicantapplicant that references the NuScale Power Plant design certification will 2.4 investigate and describe the site-specific hydrologic characteristics for Section 2.4.1 through Section 2.4.14, as applicable.
COL Item 2.5-1: A COL Applicantapplicant that references the NuScale Power Plant design certification will 2.5 describe the site-specific geology, seismology, and geotechnical characteristics for Section 2.5.1 through Section 2.5.5, below.
COL Item 3.2-1: A COL Applicantapplicant that references the NuScale Power Plant design certification will 3.2 update Table 3.2-1 to identify the classification of site-specific SSC.
Tier 2 1.8-3 Draft Revision 1
NuScale Final Safety Analysis Report Interfaces with Certified Design Table 1.8-2: Combined License Information Items (Continued)
Item No. Description of COL Information Item Section COL Item 13.1-1: A COL Applicantapplicant that references the NuScale Power Plant design certification will 13.1 provide a description of the corporate or home office management and technical support organization, including a description of the qualification requirements for each identified position or class of positions, including management and supervisory positions, in organizational units providing technical support for plant operations.
COL Item 13.1-2: A COL Applicantapplicant that references the NuScale Power Plant design certification will 13.1 provide a description of the proposed structure, functions, and responsibilities of the onsite 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.
COL Item 13.1-3: A COL Applicantapplicant that references the NuScale Power Plant design certification will 13.1 provide a description of the qualification requirements for each management, operating, technical, and maintenance position described in the operating organization.
COL Item 13.2-1: A COL Applicantapplicant that references the NuScale Power Plant design certification will 13.2 provide a description and schedule of the initial training and qualification as well as requalification programs for reactor operators, and senior reactor operators, and non-licensed plant staff (plant management, supervisory personnel, technicians and general employees).
COL Item 13.2-2: A COL applicant that references the NuScale Power Plant design certification will provide a 13.2 description and schedule of the non-licensed plant staff training programs including initial training, periodic retraining and qualification requirements.
COL Item 13.3-1: A COL Applicantapplicant that references the NuScale Power Plant design certification will 13.3 provide a description of the onsite operational support center (OSC) including the direct communication system or systems between the OSC and the control room.
COL Item 13.3-2: A COL Applicantapplicant that references the NuScale Power Plant design certification will 13.3 provide a description of a near-sitean emergency operations facility for management of overall licensee emergency response and which complies with the guidance in NUREG-0696, Functional Criteria for Emergency Response Facilities," NUREG-0737 Supplement 1, "Clarification of TMI Action Plan Requirements - Requirements for Emergency Response Capability," and NSIR/DPR-ISG-01, "Interim Staff Guidance - Emergency Planning for Nuclear Power Plants.
COL Item 13.3-3: A COL Applicantapplicant that references the NuScale Power Plant design certification will 13.3 provide a comprehensive emergency plan in accordance with 10 CFR 50.47, 10 CFR 50, Appendix E, 10 CFR 52.48, and 10 CFR 52.79(a)(21).
Tier 2 1.8-14 Draft Revision 1
NuScale Final Safety Analysis Report Emergency Planning 13.3 Emergency Planning RAI 13.03-1 The NuScale Power Plant design includes design features, facilities, and equipment that are usable for multipleup to twelve (12) NuScale Power Modules to support emergency response functions.
RAI 13.03-2 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 on the 100-ft elevation of the control building, which is a Seismic Category I structure below the 120-ft elevation as discussed in Section 3.8.4.1.2. 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 2 minutes. The TSC can accommodate staffing levels of at least 25 persons (20 utility and 5 NRC) at 75 ft2 per person. The TSC includes 2500 ft2 for a technical evaluation room, and an additional 1000 ft2 for storage, three offices, and two 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 TEDE 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 function is transferred to an alternate locationa location designated by the emergency plan (COL Item 13.3-3). Heating, ventilation and air conditioning (HVAC) for the TSC is provided by the control room HVAC system and discussed further in Section 9.4.1.
The TSC is equipped with voice communications systems, which provide communications between the TSC and plant, local, and offsite emergency response facilities, the NRC, and local and state operations centers. Additional information is provided in Section 9.5.2.2.
RAI 13.03-3 The TSC includes a safety display and indication system as discussed in Section 7.2.14.The TSC includes engineering workstations as described in Section 7.2.13.7.
RAI 13.03-3 TSC engineering workstations and communications equipment are supplied with power from the normal DC power system (EDNS). As discussed in Section 8.3.2.1.2, the EDNS includes battery backup power sources and the EDNS may also be provided backup power from the backup power supply system (BPSS).
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 onsite computer system and the NRC Operations Center in the event of an emergency.
COL Item 13.3-1: A COL applicant that references the NuScale Power Plant design certification will provide a description of the onsite operational support center (OSC) including the direct communication system or systems between the OSC and the control room.
Tier 2 13.3-1 Draft Revision 1
NuScale Final Safety Analysis Report Emergency Planning RAI 13.03-4 COL Item 13.3-2: A COL applicant that references the NuScale Power Plant design certification will provide a description of a near-sitean emergency operations facility for management of overall licensee emergency response and which complies with the guidance in NUREG-0696, Functional Criteria for Emergency Response Facilities,"
NUREG-0737 Supplement 1, "Clarification of TMI Action Plan Requirements -
Requirements for Emergency Response Capability," and NSIR/DPR-ISG-01, "Interim Staff Guidance - Emergency Planning for Nuclear Power Plants.
COL Item 13.3-3: A COL applicant that references the NuScale Power Plant design certification will provide a comprehensive emergency plan in accordance with 10 CFR 50.47, 10 CFR 50, Appendix E, 10 CFR 52.48, and 10 CFR 52.79(a)(21).
Tier 2 13.3-2 Draft Revision 1