ML24346A132
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Response to SDAA Audit Question Question Number: A-1.6-1 Receipt Date: 04/14/2023 Question:
Tables 1.6-1 and 1.6-2 are missing numerous topical and technical reports that must be incorporated by reference, otherwise all of this information would be considered missing by the associated SDAA sections. Missing topical and technical reports include, but are not limited to:
LOCA LTR, non-LOCA LTR, XPC LTR, Nuclear codes and methods LTR, Fuel methods applicability LTR, stability LTR, CHF LTR, Subchannel LTR, Rod Ejection LTR, Fluence TeR, EDAS TeR, nuclear fuel and control rod design TeR, AREVA fuel structural response applicability LTR and the Framatome fuel structural applicability LTR. The items identified above are considered missing in their entirety. They are topical reports that are a methodology in their entirety, or they are technical reports where all sections are necessary and applicable to the design whose information would otherwise be considered a gap.
Response
NuScale maintains the position that additional topical and technical reports are beyond the application content requirements of 10 CFR 52.137 and are therefore not required in the Final Safety Analysis Report (FSAR).
However, to prevent delays to the US460 SDAA review, NuScale incorporates the NRC staffs proposed list of technical and topical reports for incorporation by reference in the FSAR revision as shown below. Because NuScale has incorporated the incorporated by reference (IBR) list proposed by the NRC, NuScale believes this action resolves the IBR High Impact Technical Issue, recognizing minor changes to the IBR tables will be needed in the future (e.g., to refer to approved versions of topical reports).
Markups of the affected changes, as described in the response, are provided below:
NuScale Nonproprietary NuScale Nonproprietary
NuScale Final Safety Analysis Report Material Referenced NuScale US460 SDAA 1.6-2 Draft Revision 2 Audit Item A-1.6-1 Table 1.6-1: NuScale Referenced Topical Reports Topical Report Number Topical Report Title Report Sections Incorporated by Reference Where Referenced (FSAR Section)
MN-122626-A, Revision 1 NuScale Power, LLC Quality Assurance Program Description All 17.5 TR-1015-18653-P-A, Revision 2 Design of the Highly Integrated Protection System Platform All 7.0, 7.1, 7.2, 15.8, SDAA Part 7, Exemption 3 Chapter 7, Chapter 15 TR-131981-P, Revision 1 Methodology for the Determination of the Onset of Density Wave Oscillations (DWO)
All 3.9, 5.4 TR-0516-49422-P, Revision 3 Loss-of-Coolant Accident Evaluation Model All 4.4, 5.2, 6.2, 6.3, 15.0, 15.6 TR-124587-P, Revision 0 Extended Passive Cooling and Reactivity Control Methodology All 5.4, 6.2, 15.0, 15.6, SDAA Part 4 TR-0920-71621-P, Revision 1 Building Design and Analysis Methodology for Safety-Related Structures Section B, Sections 3.0 - 7.0 3.5, 3.7, 3.8, 3B TR-0118-58005-P-A, Revision 2 Improvements in Frequency Domain Soil-Structure-Fluid Interaction Analysis Section B, Sections 3.0 - 8.0 3.7, 3A TR-0716-50351-P-A, Revision 1 NuScale Applicability of AREVA Method for the Evaluation of Fuel Assembly Structural Response to Externally Applied Forces Section B, Sections 3.0 - 5.0 4.2 TR-0616-48793-P-A, Revision 1 Nuclear Analysis Codes and Methods Qualification Section B, Sections 2.0 - 8.0 4.3, SDAA Part 4 TR-0116-20825-P-A, Revision 1 Applicability of AREVA Fuel Methodology for the NuScale Design All 4.2, 4.3, 4.4, SDAA Part 7, Exemption 14 TR-108553, Revision 0 Framatome Fuel and Structural Response Methodologies Applicability to NuScale (Supplement 1 to TR-0116-20825-P-A, Revision 1; Supplement 1 to TR-0716-50351-P-A, Revision 1)
All 4.2, 4.3, 4.4, SDAA Part 7, Exemption 14 TR-0116-21012-P-A, Revision 1 NuScale Power Critical Heat Flux Correlations All 4.4, 15.0, 15.6 TR-107522-A, Revision 1 Applicability Range Extension of NSP4 Critical Heat Flux Correlation (Supplement 1 to TR-0116-21012-P-A, Revision 1)
All 4.4, 15.0, SDAA Part 4 TR-0915-17564-P-A, Revision 2 Subchannel Analysis Methodology All 4.3, 4.4, 15.0, 15.4, 15.6, SDAA Part 4
NuScale Final Safety Analysis Report Material Referenced NuScale US460 SDAA 1.6-3 Draft Revision 2 TR-108601-A, Revision 4 Statistical Subchannel Analysis Methodology (Supplement 1 to TR-0915-17564-P-A, Revision 2)
All 4.3, 4.4, 15.0, 15.4, 15.6, SDAA Part 4 TR-0915-17565-P-A, Revision 4 Accident Source Term Methodology Section B, Sections 3.0 - 5.0 2.3, 3.11, 3C, 12.2, 15.0, SDAA Part 4 TR-0516-49416-P, Revision 4 Non-Loss-of-Coolant Accident Analysis Methodology All 5.2, 6.2, 7.1, 15.0, SDAA Part 4 TR-0716-50350-P, Revision 3 Rod Ejection Accident Methodology All 4.3, 15.0, 15.4 TR-0516-49417-P-A, Revision 1 Evaluation Methodology for Stability Analysis of the NuScale Power Module Section B, Sections 3.0 -
10.0 4.4, 15.4, 15.0, 15.9 TR-0420-69456, Revision 1 NuScale Control Room Staffing Plan None 18.5, SDAA Part 4 TR-0515-13952-NP-A, Revision 0 Risk Significance Determination Section D, Section 3.0 17.4, 18.6, 19.1, 19.3 Table 1.6-1: NuScale Referenced Topical Reports (Continued)
Topical Report Number Topical Report Title Report Sections Incorporated by Reference Where Referenced (FSAR Section)
NuScale Final Safety Analysis Report Material Referenced NuScale US460 SDAA 1.6-4 Draft Revision 2 Audit Item A-1.6-1, Audit Question A-4.4-1, Audit Question 5.3.1.5-1, Audit Question A-5.3.2.3-1, Audit Question A-5.3.2.4-1 Table 1.6-2: NuScale Referenced Technical Reports Technical Report Number Title Specific Report Sections Incorporated by Reference Where Referenced (FSAR Section)
TR-118318, Revision 1 NuScale Design of Physical Security Systems All 9.5, 13.6, 14.2 TR-122844-P, Revision 0 NuScale Instrument Setpoint Methodology Technical Report All 7.0, 7.2 TR-121353-P, Revision 0 NuScale Comprehensive Vibration Assessment Program Analysis Technical Report All 3.9, 5.4 14.2 TR-121515-P, Revision 0 NuScale Power Module Seismic Analysis All 3.7, 3.12 TR-130877-P, Revision 0 Pressure and Temperature Limits Methodology All 5.2, 5.3 TR-121517-P, Revision 10 NuScale Power Module Short-Term Transient Analysis All 3.9 TR-130721-P, Revision 0 Use of Austenitic Stainless Steel for NPM LowerUS460 Standard Design Reactor Pressure Vessel All 5.2, 5.3 TR-121354-P, Revision 10 NuScale Comprehensive Vibration Assessment Program Measurement and Inspection Plan Technical Report All 3.9, 14.2 TR-121507-P, Revision 0 Pipe Rupture Hazards Analysis All 3.6 TR-118976-P, Revision 0 Fluence Calculation Methodology and Results All 4.3, 5.3 TR-117605-P, Revision 0 NuFuel-HTP2TM Fuel and Control Rod Assembly Designs All 4.2, 4.3 TR-121516-P, Revision 1 Containment Vessel Ultimate Pressure Integrity All 3.8.2 TR-123242-P, Revision 1 Effluent Release (GALE Replacement) Methodology and Results All 11.1, 11.2, 11.3 TR-130418-NP, Revision 0 Human Factors Engineering Design Implementation Plan None 18.11 TR-124333-NP, Revision 0 Human Factors Engineering Functional Requirements Analysis and Function Allocation Implementation Plan None 18.3 TR-130417-NP, Revision 0 Human Factors Engineering Human-System Interface Design Implementation Plan None 18.7 TR-130409-P, Revision 0 Human Factors Engineering Operating Experience Review Implementation Plan None 18.1, 18.2 TR-130414-NP, Revision 0 Human Factors Engineering Program Management Plan None 18.1, 18.2 TR-130412-P, Revision 0 Human Factors Engineering Staffing and Qualification Results Summary Report None 18.5 TR-130413-P, Revision 0 Human Factors Engineering Task Analysis Implementation Plan None 18.4 TR-130416-NP, Revision 0 Human Factors Engineering Treatment of Important Human Actions Results Summary Report None 18.6 TR-130415-NP, Revision 0 Human Factors Engineering Verification and Validation Implementation Plan None 18.10 TR-123952-P, Revision 0 NuScale Containment Leakage Integrity Assurance None 3.8, 3.9, 6.2, Exemption 7 TR-101310-NP, Revision 0 US460 Standard Design Approval Technical Specifications Development None 16.1 TR-169856-P, Revision 0 NuScale US460 Statistical Subchannel Critical Heat Flux Analysis Probabilistic Uncertainties All 4.4