ML24215A090
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Response to SDAA Audit Question Question Number: A-4.5.1-4 Receipt Date: 12/04/2023 Question:
Provide the schemiatics (in FSAR and/or confirming in existing drawings in FSAR) for each of the CRDM component line items from the proposed Table 4.5-1 of response to Audit Question A-04.05.01-3.
Response
The components in FSAR Table 4.5-1 correspond to a component listed in FSAR Figure 4.6-1 through Figure 4.6-6.
Updated Response Figure 4.6-1 through Figure 4.6-5 are updated as shown in the attached FSAR markup. The items listed in FSAR Table 4.5-1 that are not shown in Figure 4.6-1 through Figure 4.6-6 are shown in Figure 1 below.
ASME Boiler and Pressure Vessel Code Section III NB-2331 applies to pressure retaining materials, and the control rod drive shafts are not pressure retaining; thus, FSAR Section 3.9 is updated as shown in the FSAR markup.
NuScale Nonproprietary NuScale Nonproprietary
((2(a),(c) Markups of the affected changes, as described in the response, are provided below: NuScale Nonproprietary NuScale Nonproprietary
NuScale Final Safety Analysis Report Introduction NuScale US460 SDAA 1.1-5 Draft Revision 2 Audit Question A-3.9.4-7, Audit Question A-4.5.1-4 Table 1.1-1: Acronyms and Abbreviations Acronym or Abbreviation Description ABS auxiliary boiler system ABVS Annex Building HVAC system ABWR advanced boiling water reactor AC alternating current ACCS air cooled condenser system ACI American Concrete Institute ACM Availability Controls Manual ACRS Advisory Committee on Reactor Safeguards AEA Atomic Energy Act AFU air filtration unit AFWS auxiliary feedwater system AHJ authority having jurisdiction AHU air handling unit AIA Authorized Inspection Agency AISC American Institute of Steel Construction AISI American Iron and Steel Institute ALARA as low as reasonably achievable ALU actuation logic unit ALWR advanced light water reactor AMCA Air Movement and Control Association International, Inc. ANB Annex Building ANS American Nuclear Society ANSI American National Standards Institute AO axial offset AOA axial offset anomaly AOO anticipated operational occurrence AOV air-operated valve API American Petroleum Institute APL actuation and priority logic APWR advanced pressurized water reactor AQ augmented quality ARM area radiation monitor ARO all rods out ARS acceleration response spectra ASAI application specific action item ASCE American Society of Civil Engineers ASD adjustable speed drive ASHRAE American Society of Heating, Refrigerating and Air-Conditioning Engineers ASM American Society for Metals International ASME American Society of Mechanical Engineers ASTM American Society for Testing and Materials ATB Administration and Training Building ATJC articulating traveling jib crane ATWS anticipated transient without scram AVT all-volatile treatment AWH auxiliary wet hoist AWS American Welding Society AWWA American Water Works Association BAS boron addition system
NuScale Final Safety Analysis Report Introduction NuScale US460 SDAA 1.1-13 Draft Revision 2 MIR module inspection rack MIT Massachusetts Institute of Technology MJA magnetic jack assembly MLD master logic diagram MM multiple, multi-module MMAF multi-module adjustment factor MMI multi-module issue MMPSF multi-module performance shaping factor MMS moment magnitude scale MOC middle of cycle MOV motor-operated valve MPS module protection system MPT main power transformer MPU magnetic speed pickup MS main steam MSI main steam isolation MSIBV main steam isolation bypass valves MSIV main steam isolation valve MSLB main steam line break MSO multiple spurious operations MSPB main steam pipe break MSPI mitigating system performance index MSS main steam system MSSV main steam safety valve MTC moderator temperature coefficient MTU metric tons, uranium MWe megawatt electric MWS maintenance workstation MWt megawatt thermal N/A Not Applicable NDE non-destructive examination NDRC National Defense Research Council NDS nitrogen distribution system NDT non-destructive testing NEI Nuclear Energy Institute NERC North American Electric Reliability Corporation NFA new fuel assembly NFE new fuel elevator NFJC new fuel jib crane NFPA National Fire Protection Association NIC network interface controller NIST National Institute of Standards and Technology NIST NuScale Integral System Test Facility NMS neutron monitoring system NOG nuclear overhead and gantry NPM NuScale Power Module NPP NuScale Power Plant NPS nominal pipe size NPSH net positive suction head NRC Nuclear Regulatory Commission Table 1.1-1: Acronyms and Abbreviations (Continued) Acronym or Abbreviation Description
NuScale Final Safety Analysis Report Mechanical Systems and Components NuScale US460 SDAA 3.9-34 Draft Revision 2 The CRDM is capable of a continuous full-height withdrawal and insertion and holding a position during normal operating conditions. The CRDM components in contact with the primary coolant are designed to operate for a 60-year design life. The CRDMs are designed to be replaceable and freely interchangeable without limitations in function and connections. Control Rod Drive Shaft The control rod drive shaft is the link and the method of transferring force between the CRDM and the CRA. The control rod drive shaft passes through the upper region of the reactor vessel to allow the CRDM to raise, lower, or hold the CRA. The control rod drive shaft also interacts with the rod position indication sensor coils that communicate the elevation of the control rods. The control rod drive shaft allows for the remote release of the CRA for refueling purposes. The control rod drive shaft is analyzed to the guidance of ASME, Section III, Nonmandatory Appendix F for linear type supports and is evaluated to not adversely affect the integrity of the core support structures in accordance with NG-1122(c). Audit Question A-4.5.1-4 Martensitic stainless steel materials used in the control rod drive shafts are Cv tested in accordance with NB-2331. Drive Coil Assembly The drive coil assembly has four main coils: the lift coil, the upper gripper coil, the lower gripper coil, and the load transfer coil. The drive coil assembly is a part of the external assembly that slides over the pressure housing and sits on a ledge at the base of the pressure housing. The drive coil assembly is depicted by Figure 4.6-3.The direct current generated by the control cabinets is sent through a coil that generates a magnetic field; this magnetic field engages the flat-face plunger magnet of the latch arm assembly, which moves the latch arm to engage the control rod drive shaft. The rate at which the upper gripper coil, the load transfer coil, the lower gripper coil, and the lift coil are energized determines the speed of the control rod drive shaft. The motive power supply from the alternating current distribution system to the CRDM control cabinet is interrupted when the reactor trip breakers open, causing the control rods to be inserted via gravity. The CRDS safety function of rapid insertion of the control rods is accomplished when power is removed from the CRDM. Rod movement logic tracks the speed of the control rods, which utilizes direct rod position indication. Audit Question A-3.9.4-7 The remote disconnect mechanism coils together with the magnets and internal components of the control rod drive shaft are capable of remotely
NuScale Final Safety Analysis Report Reactor Materials NuScale US460 SDAA 4.5-6 Draft Revision 2 Audit Question A-4.5.1-3, Audit Question A-4.5.1-4 Table 4.5-1: Acceptable Control Rod Drive Mechanism Materials Item Material Designation (Grade, Class, or Type) Latch Mechanism (contained within RCPB) Magnetic parts: poles, supports, and spacers Type 410 (annealed or tempered) Springs Alloy X-750 (UNS N07750) AMS 5698 or AMS 5699 Wear parts: pins Haynes Alloy 25 (AMS 5759) Wear parts: grip arms and links Stellite 6 or 6B (AMS 5894) Guide tube, shims (gap spacers) Type 304 or Inconel Alloy 625 (UNS N06625) Locking nut and locking cup, grip arm housing Type 304 Magnetic jack assembly (MJA) support items UNS N07718 (AMS 5662 or AMS 5663), Type 304 Fasteners Grade B6 Anti-rotation key Type 440C Items External to Reactor Coolant Pressure Boundary (RCPB) Support rings, coil housing spacers, power cable tube, RPI bobbin, cooling jacket and piping, lateral seismic support plates, RPI outer housing tube Type 304 Coil housings: drive coils, RDM, RHO Type 410 Fasteners Grade B8 and B8M, Type 630 H1100 Miscellaneous items UNS N07718 (AMS 5662 or AMS 5663), Type 630 H1100, Type 304, Type 316 CRD Shaft Assembly (contained within RCPB) Tube connector, coupling retainer and connector, dowel pins, manual operating rod Type 304 Magnetic parts: poles and supports CRD shaft lobed section, taper key, connecting rod pieces, retaining ring, extension tubes, protective sleeve Type 410 (annealed or tempered) Springs Alloy X-750 (UNS N07750) AMS 5698 or AMS 5699 CRD shaft coupling UNS N06625 Push button, button ring, extension tube adapter, connector tube UNS N07718 (AMS 5662 or AMS 5663) Coupling nut, spring bushing Type 440C Shims (gap spacers) Type 304 or Inconel Alloy 625 (UNS N06625) Fasteners Grade B8 RHO Ball Grip Assembly (contained within RCPB) Magnetic parts: poles and grips Type 410 (annealed or tempered) Springs Alloy X-750 (UNS N07750) AMS 5698 or AMS 5699 Ball grip inner, steel ball Type 440C Fasteners Grade 8 or B8 Dowel pin Type 304 Weld Filler Metals for Non-RCPB Items (may be used for items both external to or contained within the RCPB) Ferritic stainless steel weld filler metals E410, E430 ER410, ER430 Austenitic stainless steel weld filler metals1 E308, E308L, E309, E309L, E316, E316L ER308, ER308L, ER309, ER309L, ER316, ER316L
NuScale Final Safety Analysis Report Reactor Materials NuScale US460 SDAA 4.5-7 Draft Revision 2 CRDM RCPB Items Table 5.2-3 Notes: (1) 0.03 percent maximum carbon for unstabilized AISI Type 3XX weld filler metals with ferrite number in the range of 5FN to 20FN, except 5FN to 16FN for Type 316 and Type 316L. Table 4.5-1: Acceptable Control Rod Drive Mechanism Materials (Continued) Item Material Designation (Grade, Class, or Type)
NuScale Final Safety Analysis Report Functional Design of Control Rod Drive System NuScale US460 SDAA 4.6-6 Draft Revision 2 Audit Question A-4.5.1-4 Figure 4.6-1: Representative Overview of Control Rod Drive Mechanism Locations in Relation to the Reactor Pressure Vessel and Containment Vessel CRDM SUPPORT FRAME CRDM CRDM SUPPORT STRUCTURE CNV TYPICAL CONTROL ROD DRIVE (CRD) SHAFT PRESSURIZER RPV TYPICAL CRD SHAFT SUPPORT TYPICAL CONTROL ROD ASSEMBLY GUIDE TUBE TYPICAL FUEL ASSEMBLY
NuScale Final Safety Analysis Report Functional Design of Control Rod Drive System NuScale US460 SDAA 4.6-7 Draft Revision 2 Audit Question A-4.5.1-4 Figure 4.6-2: Representative Control Rod Drive Mechanism Coils and HousingsRepresentative Control Rod Drive Mechanism with Interfaces to Reactor Pressure Vessel Upper Head and Lateral Seismic Supports TIE ROD COOLING WATER SUPPLY/RETURN RPI CONNECTORS (TRAIN A/B) CRDM COIL POWER CONNECTORS (DRIVE/RDM & RHO) TOP VIEW TOP PLUG ASSEMBLY ROD HOLDOUT (RHO) COIL ASSEMBLY ROD POSITION INDICATION (RHO) BALL GRIP ASSEMBLY REMOTE DISCONNECT MECHANISM (RDM) COIL ASSEMBLY LATCH (MAGNETIC JACK) ASSEMBLY MECHANISM MJA SUPPORT PRESSURE HOUSING DRIVE SHAFT ASSEMBLY LATERAL SEISMIC SUPPORT PLATES RDM SUPPORT RING DRIVE COILS AND COOLING JACKET COOLING WATER PIPING POWER CABLE TUBE UPPER CRDM SEISMIC SUPPORT FRAME LOWER CRDM SEISMIC SUPPORT FRAME RPV UPPER HEAD CNV UPPER HEAD
NuScale Final Safety Analysis Report Functional Design of Control Rod Drive System NuScale US460 SDAA 4.6-8 Draft Revision 2 Audit Question A-4.5.1-4 Figure 4.6-3: Representative Control Rod Drive Mechanism Drive Coil and Cooling Jacket Assembly POWER CABLES COOLING WATER TUBES COOLING JACKET LIFT COIL UPPER GRIPPER COIL LOAD TRANSFER COIL LOWER GRIPPER COIL (COOLING JACKET REMOVED) COIL HOUSING SPACER
NuScale Final Safety Analysis Report Functional Design of Control Rod Drive System NuScale US460 SDAA 4.6-9 Draft Revision 2 Audit Question A-4.5.1-4 Figure 4.6-4: Representative Rod Position Indication Assembly TOP PLUG ASSEMBLY RHO STATIONARY POLE RHO COIL ASSEMBLY RHO BALL GRIP ASSEMBLY RHO MOVABLE POLE RHO OUTER BALL GRIP RHO INNER BALL GRIP RHO STEEL BALL RPI COIL (CHANNEL B) RPI COIL (CHANNEL A) RPI COIL (CHANNEL B) RPI COIL (CHANNEL A) RPI COIL (CHANNEL B) RPI COIL (CHANNEL A) RPI COIL (CHANNEL B) RPI COIL (CHANNEL A) RPI COIL (CHANNEL B) RPI COIL (CHANNEL A) RPI COIL (CHANNEL B) RPI COIL (CHANNEL A) RPI COIL (CHANNEL B) RPI COIL (CHANNEL A) RPI COIL (CHANNEL B) RPI COIL (CHANNEL A) RPI COIL (CHANNEL B) RPI COIL (CHANNEL A) RPI COIL (CHANNEL B) RPI COIL (CHANNEL A) RPI SUPPORT RING RDM UPPER (UNLOCKING) COIL ASSEMBLY UPPER SEISMIC SUPPORT PLATE RPI BOBBIN RPI OUTER TUBE CRDM PRESSURE HOUSING LOWER SEISMIC SUPPORT PLATE INTERMEDIATE SEISMIC SUPPORT PLATE (MOVED UP FOR VISIBILITY) RDM LOWER (LIFT) COIL ASSEMBLY
NuScale Final Safety Analysis Report Functional Design of Control Rod Drive System NuScale US460 SDAA 4.6-10 Draft Revision 2 Audit Question A-4.5.1-4 Figure 4.6-5: Representative Overview of Latch Mechanism Assembly LOCKING NUT LIFT POLE GUIDE TUBE SPRING (TYP) STATIONARY GRIP POLE MOVEABLE GRIP POLE LOWER RING SUPPORT ANTI-ROTATION KEY SHIMS (GAP SPACERS) LOCKING CUP AND LOCK SCREW (TYP) UPPER GRIPPER ASSEMBLY LOWER GRIPPER ASSEMBLY LOAD TRANSFER POLE GRIP ARM LINK (CRANK) PINS (TYP) GRIP ARM HOUSING}}