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Category:Response to Request for Additional Information (RAI)
MONTHYEARML23361A0992023-12-27027 December 2023 LLC, Response to NRC Request for Additional Information (RAI 10083) on the NuScale Standard Design Approval Application ML23304A4942023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 16, Section 16.5.5.09-1, Information Related to Generic Technical Specification 5.5.9, Containment Leakage Rate Testing Program ML23304A4952023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 16, Section 16.5.5.09-2, Information Related to Containment Leakage Rate Testing Program ML23304A4932023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 16, Section 16.1.1-1, Information Related to FSAR Section 16.1.1, Introduction to Technical Specifications ML23304A4922023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 16, Response to Sdaa Question 16-1, Re Information Related to FSAR Chapter 16, Information Related to Technical Specifications ML23304A4902023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 15, Response to Sdaa Question 15.6.3-1, Re Information Related to Steam Generator Tube Failure (Thermal Hydraulic) ML23304A4962023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 16, Section 16.5.5.09-3, Information Related to Generic Technical Specification 5.5.9, Containment Leakage Rate Testing Program ML23304A5162023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 19, Section 19.1-20, Information Related to FSAR Section 19.1, Probabilistic Risk Assessment ML23304A4892023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 15, Section 15.5.1-1, Information Related to Chemical and Volume Control System Malfunction ML23304A4882023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 12, Response to Sdaa Question 12.4.1.9-1, Re Information Related to Construction Activities ML23304A4872023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 12, Section 12.4.1.9-1 (Follow-up), Information Related to FSAR Section 12.4.1.9, Construction Activities ML23304A4862023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 12, Response to Sdaa Question 12.3.2.2-1, Re Design Considerations ML23304A5172023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 19, Response to Sdaa Question 19.1-25, Re Information Related to FSAR Section 19.1, Probabilistic Risk Assessment (Non-Prop) ML23304A4852023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 12, Section 12.3.1.1-2, Information Related to FSAR Section 12.3.1.1, Equipment Design ML23304A5192023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 19, Section 19.1-27, Information Related to Probabilistic Risk Assessment ML23304A5212023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 19, Section 19.1-40, Information Related to FSAR Section 19.1, Probabilistic Risk Assessment ML23304A5222023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 19, Section 19.3-1, Information Related to Regulatory Treatment of Nonsafety Systems ML23304A4832023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 12, Section 12.2-5, Information Related to Radiation Sources ML23304A5242023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 19, Section 19.5-12, Information Related to Adequacy of Design Features and Functional Capabilities Identified and Described for Withstanding Aircraft Impacts ML23304A4822023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 12, Response to Sdaa Question 12.2-3, Re Information Related to FSAR Section 12.2, Radiation Sources ML23304A4802023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 12, Response to Sdaa Question 12.2-1, Re Information Related to Radiation Sources ML23304A4792023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 12, Section 12.2.1.8-1, Information Related to Reactor Pool Water ML23304A4782023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 11, Response to Sdaa Question 11.5-4, Re Information Related to Process and Effluent Radiation Monitoring Instrumentation and Sampling System ML23304A4772023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 11, Section 11.5-4, Information Related to Process and Effluent Radiation Monitoring Instrumentation and Sampling System - Follow-Up ML23304A4762023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 3, Response to Sdaa Question 11.5-3, Re Information Related to Process and Effluent Radiation Monitoring Instrumentation and Sampling System ML23304A4752023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 11, Response to Sdaa Question 11.5-2, Re Information Related to FSAR Section 11.5, Process and Effluent Radiation Monitoring Instrumentation and Sampling. ML23304A4742023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 11, Section 11.5-1, Information Related to Process and Effluent Radiation Monitoring Instrumentation and Sampling System ML23304A4692023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 11, Section 11.4-2, Information Related to Solid Waste Management System Follow-Up ML23304A4642023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 11, Response to Sdaa Question 11.1-2, Re Information Related to Source Terms ML23304A4652023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 11, Response to Sdaa Question 11.1-3, Re Information Related to Source Terms ML23304A4722023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 11, Section 11.4-4, Information Related to FSAR Section 11.4, Solid Waste Management System ML23304A4712023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 11, Section 11.4-3, Information Related to Solid Waste Management System ML23304A4702023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 11, Response to Sdaa Question 11.4-2, Re Information Related to Solid Waste Management System ML23304A4672023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 11, Response to Sdaa Question 11.4-1, Re Information Related to FSAR Section 11.4, Solid Waste Management System (Follow-Up) ML23304A4662023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 11, Response to Sdaa Question 11.3.2, Re Information Related to Gaseous Waste Management System ML23304A4682023-10-31031 October 2023 LLC Response to NRCs Request for Docketing of Resolved Audit Responses, Chapter 11, Response to Sdaa Question 11.4-1, Re Information Related to FSAR Section 11.4, Solid Waste Management System 2023-12-27
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NuScale Nonproprietary Response to SDAA Audit Question Question Number: A-5.2.1.1-5 Receipt Date: 06/30/2023 Question:
Section 5.2.1.1 states that The ASME BPVC of record for the US460 standard design for the NPM is the ASME BPVC, 2017 Edition. However, Section 3.5.1.1.1 states that Missiles from piping or valves designed in accordance with American Society of Mechanical Engineers (ASME)Section III, (Reference 3.5-1) and maintained in accordance with an ASME Section XI (Reference 3.5-2) inspection program. Section 3.5.1.2 states that The control rod drive mechanism housing is a Class 1 appurtenance per Reference 3.5-1.The staff notes that References 3.5-1 and 3.5-2 refer to 2013 Code edition. Please clarify the inconsistency of the Code Edition.
Response
Reference 3.5-1 and Reference 3.5-2 refer to incorrect American Society of Mechanical Engineers (ASME) Boiler Pressure Vessel Code (BPVC) editions for Section III and Section XI.
The ASME BPVC 2017 edition is applicable to the entire standard design approval application.
The attached markup corrects Reference 3.5-1 and Reference 3.5-2 to the 2017 edition of the ASME BPVC for Section III and Section XI, respectively.
Markups of the affected changes, as described in the response, are provided below:
NuScale Nonproprietary
NuScale Final Safety Analysis Report Missile Protection In determining an appropriate equivalent static load, elasto-plastic behavior can be assumed with permissible ductility ratios as long as deflections do not result in loss of function of safety-related systems.
Section 3.8 provides additional information on loading combinations and analysis methods for the RXB and CRB.
3.5.4 References Audit Question A-5.2.1.1-5 3.5-1 American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, 20173 edition with no Addenda (subject to the conditions specified in paragraph (b)(1) of section 50.55a),Section III, "Rules for Construction of Nuclear Facility Components," New York, NY.
Audit Question A-5.2.1.1-5 3.5-2 American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, 20173 edition with no Addenda (subject to the conditions specified in paragraph (b)(2) of section 50.55a),Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," New York, NY.
3.5-3 Kennedy, R.P., "A Review of Procedures for the Analysis and Design of Concrete Structures to Resist Missile Impact Effects," Nuclear Engineering and Designs, (1976) 37(2), 183-203.
3.5-4 American Concrete Institute, "Code Requirements for Nuclear Safety-Related Concrete Structures and Commentary," ACI 349-06, Farmington Hills, MI.
3.5-5 Bechtel Power Corporation, "Design of Structures for Missile Impact,"
BC-TOP-9A, Revision 2, San Francisco, CA, September 1974.
3.5-6 Nuclear Engineering and Design, Full-Scale Tornado-Missile Impact Tests, Volume 45, Issue 1, March 1978, Pages 123-143.
3.5-7 Design of composite SC walls to prevent perforation from missile impact, Bruhl, J. C., et al., International Journal of Impact Engineering, 75 (2015) 75-87.
3.5-8 U.S. Reactor Containment Technology, Chapter 6, Volume 1, W.B. Cottrell and A.W. Savolainen, ORNL-NSIC-5, Oak Ridge National Laboratory, Oak Ridge, TN, 1965.
3.5-9 American Institute of Steel Construction, Specification for the Design, Fabrication and Erection of Steel Safety-Related Structures for Nuclear Facilities, ANSI/AISC N690, 2018.
3.5-10 Williamson, R.A., and R.R. Alvy, Impact Effect of Fragments Striking Structural Elements, Holmes and Narver, Inc., Orange, CA, 1973.
NuScale US460 SDAA 3.5-16 Draft Revision 2