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PM-0219-64475-NP, Revision 0, Reactor Vessel Flange Tool (Rft) Design Plan and Schedule
	ML19045A306
Person / Time
Site:	NuScale
Issue date:	02/12/2019
From:	Addison D, Linik L; NuScale
To:	; Office of New Reactors
References
	LO-0219-64495 PM-0219-64475-NP, Rev 0
	Download: ML19045A306 (31)
	v • d • e

Enclosure 2:

"Reactor Vessel Flange Tool (RFT) Design Plan and Schedule," PM-0219-64475-NP, Revision 0, Nonproprietary version NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com L0-0219-64495

PM-0219-64475-NP Revision: 0 NuScale Nonproprietary Reactor Vessel Flange Tool (RFT) Design Plan and I

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RFT Design Plan and Schedule - Agenda

Discuss RFT Design Plan, and Schedule for Transmitta~s

Expected Changes to_ the NuScale FSAR and Associated Reports

Proposed COL Item 3.8-5

Core Plate Motion Generation, and Comparison of In-Structure Response Spectra (ISRS), and

Scope of Follow-up Analysis

Description of RFT and RFT Support Models, and Results 2

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RFT (RAI 8838 and RAI 9225) Closure Schedule

[ __ ~JPlanned_Action ______________

________, _______________ ----------~----------. _---

__________ ]bched~le __. _1 1 Transmittal of documentation (on docket) providing high-level results from the preliminary Framatome results based on draft (non-QA) core plate motions for RFT and operating bay locations Feb-122019 2 Transmittal of documentation describing planned FSAR and Technical Report mark-ups.

3.Transmittal on the docket of core plate motions (RFT and operating bay) for staff confirmatory analyses 4 Completion of FSAR mark-ups for Chapter 3, per RAI 8838 closure plan.

Feb-12 2019 I

Feb-12 2019

.Mar-8 2019 5 !ransmittal of documentation providing high-level results from the full Framatome results based on draft (non-

.:Jul-31 2019

QA) core plate motions 6 Transmittal of mark-ups for RAI 9225 Items 1, 2, and 3 - To be addressed during this meeting.

Item 4 - To be addressed with submittal of NuScale response to RAI 8838 Items 5 and 6 - To be addressed with submittal of NuScale response to RAI 9225 3

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Scope of FSAR Related Changes Planned Changes to FSAR Chapter 3 & TR-0916-51502 (RAI 8838)

Update and expand description of the RFT design and analysis (including description of anchor plates, SSC classification, and weight). Add COL Item 3.8-5.

FSAR Impacts:

Sectio=n ___ _]secti9n Title----

3.8.4.1.15 Reactor Flange Tool Revise RFT description for consistency. Add description of anchoring plates, and attachments to these plates.

3.8.4.3.1.12 3.8A.3.2 3.8.4.5 Table 3.2-1

RfT Weig_ht

... -~Jl.dful?TRFT weight ~Q ~CCOl.!nt_for c_ur~~~t_ des1g_n.

_ '.,Liquid Loads

Consistency changes, and clarify the flow of analysis.

Structural Acceptance Criteria

. - *Revise R{T accept~nce cri_teria

'dassiticatfon ot sfructu.res,- systems,".anc:f -

components

Consistency change to match 3.8.4.5 (RFT to B2)

Table 3.8.4-21

.... RFT structural Member-Derria.nd to *capacity -

.. :update Design to Capacity Ratios

,Ratios for SSE Table 3.8.4-22

. i'Ri=T Eml:ied Plates Demand to Capacity Ratios* *u-d****t*.D..... t C.. - 't. R t.---

for SSE p a e es1gn o apac1 y a 10s Table 3.8.4-23

Ri=T Stru_dural K,lernber -Cpad C_o~tiin_~ti9~~-- _. _**DE:fine st_ructu.raf i,_ier:r,ber load _9c:,rn_bin_ati_o~s. ___. -......

Conforming chan!;Je~ in 9:1, COL _Item Ta!Jle 1 :8-2 iconforn,ing c_hanges for RF~ de~_cription,_.,m9 ne\\AI C()L __ lter:ri_

TR-0916-51502 "NuScale Power Module Seismic Analysis" Impacts:

§ection-=:==!§ection Title

_________ _,lbescriP-tion of Potential Change 5.2 Three-Dimensional ANSYS model of Lower NPM and Reactor Flange Tool Update discussion of the ANSYS model for the RFT design, provide new figures of the 4-armed refueling configuration for seismic analysis 8.4.3 Appendix B 4

PM-0219-64475-NP Revision: O NuScale Power Module Seismic Analysis Results Representative In-Structure Response Spectra Update maximum seismic reactions at RPV Upper Supports and Fuel Assembly Supports Update existing and add new ISRS plots for RFT analysis.

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Scope of FSAR Related Changes Planned Changes to FSAR Chapter 4 & TR-0816-51127 (RAI 9225)

Expand the discussions of fuel design to include the RFT location, define applicable requirements, and provide conclusions.

FSAR Impacts:

~ecti9n

_]sectiohTitle

~ ----

4.2.1.5.3 4.2.3.5.1 Infrequent Events and Postulated Accidents Fuel Assembly Structural Design Evaluation

]Description of'Potential Chang~----

Define ASME Service Level for fuel in added RFT location (Service Level D, consistent with 4.2.3.5.1)

Add discussion for RFT location, define NPM and RFT locations.

4.2.3.5.9 New Section, addressing RFT Location Add section to discuss results for RFT location.

Potential conforming changes for 4.2, 4.2.1, 4.2.3, and 4.2.3.5 Conforming changes to account for addition of RFT location, as needed TR-0816-51127 "NuFuel-HTP2' Fuel and Control Rod Assembly Designs" Impacts:

Section* *

]Section.Tj,.,,tl=e~. -"---~------'----.::...--

4.1, 1 Stress and Loading Limits 4.4.4 New Section, addressing RFT Location Potential conforming changes for 1.0, 2.0, 4.0.

]bescriP-ticm of.Potential Chan_g=e_-'--'--------"--------.....

Define ASME Service Level for fuel in added RFT location (Service Level D, consistent with FSAR 4.2.3.5.1)

Add section to discuss evaluation and results for RFT location.

Conforming changes to account for addition of RFT location, as needed TR-0716-50351 "NuScale Applicability of Areva Method for the Evaluation of Fuel Assem*bly Structural Response to Externally Applied Forces" Impacts:

Section **.

l§!lc=t=io"""n""'T:..:.it=le,,_*~-_,;;,_-....,....:......;;._... _______

_..,,. DescriRtion of Potential Chang,"'"e_,_. ----'----'-_:_:_, ---.............J*j 3.0 5

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Current Proposed COL Item COL Item 3.8-5:

A COL applicant that references the NuScale Power Plant design certification will verify that the reactor flange tool (RFT) and embedded plate structures are evaluated using site-specific parameters, and generate input to the reactor pressure vessel and fuel assemblies that are bounded by the certified design.

The design of the structural members will be confirmed by assessing demand-to-capacity ratios for the load combinations in Table 3.8.4-23. The design of the embed plates will be confirmed by assessing demand-to-capacity ratios for the load combinations in Table 3.8.4-1 and Table 3.8.4-2, and applicable design codes in Table 3.8.4-12.

In addition, the core plate motions of the RFT shown in Figures 8-34 through 8-39 of TR-0916-51502 (NuScale Power Module Seismic Analysis) shall be confirmed against the site-specific values.

If either the demands on the structural members or the embed plates exceed their capacity, or core plate motions are not bounded by the certified design, the COL applicant will design an alternate reactor flange tool and associated embedded plate structures per the criteria specified in FSAR Section 3.8.4, and the fuel assembly-imposed load limitations.

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7 ISRS Comparisons - Preliminary vs Final Results

Preliminary core plate time histories have been analyzed by Framatome over the past two months

The preliminary analysis has given high confidence that margin to limit exists

Final core plate time histories have now been transmitted to Framatome and the final analysis is underway

The slides following compare the ISRS of the preliminary (dq!t~9.!i.~~~) time histories and the final (solid lines) time histories, showing good agreement

Confidence that margin to limit exists for the fuel when analyzed using the final core plate time histories is high PM-0219-644 7 5-N P Revision: 0 Copyright 2019 by Nu Scale Power, LLC.

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Operating Bay-Lower Core Plate 8

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Fuel Design Considerations

FSAR Chapter 4.2, "Fuel System Design" The RFT location will be described Requirements for the RFT location will be identified Evaluations based on the RFT location will be added No changes required for the Operating Bay results
TR-0816-51127, "NuFuel-HTP2TM and Control Rod Assembly Designs" The RFT location will be described Requirements for the RFT location will be identified The RFT location results will be evaluated, and tables reporting margins to limits will be added The Operating Bay tables reporting margins to limits will be updated
TR-0716-50351, "NuScale Applicability of AREVA Method for the Evaluation of Fuel Assembly Structural Response to Externally Applied Forces" The applicability of ANP-10337, "PWR Fuel Assembly Structural Response to Externally Applied Dynamic Excitations" to the RFT location will be evaluated 21 PM-0219-64475-NP Revision: 0 Copyright 2019 by NuScale Power, LLC.

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