|
---|
Category:Slides and Viewgraphs
MONTHYEARML20184A2872020-07-0101 July 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and General Design Criterion 33, PM-0720-70785, Revision 0 ML20150C8812020-05-29029 May 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and Associated Design and DCA Changes, PM-0620-70244, Revision 0 ML20150C5172020-05-29029 May 2020 LLC Submittal of Presentation Materials Entitled NRC Public Meeting Presentation: Boron Redistribution and Associated Design and DCA Changes, PM-0620-70336, Revision 0 ML20133J9142020-05-11011 May 2020 LLC Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution, PM-0420-69511, Revision 0 ML20099H0802020-04-0808 April 2020 LLC - Submittal of Presentation Materials Entitled NRC Public Meeting: Revisions to Nuscale'S EPZ Sizing Methodology Topical Report, PM-0420-69598, Revision 0 ML20097F1922020-04-0606 April 2020 Nuscale Power, LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: Nuscale Topic - Hydrogen/Oxygen Monitoring, PM-0420-69518, Revision 0 ML20094H6742020-04-0303 April 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation NuScale Topic-Probabilistic Risk Assessment with a Focus on Emergency Core Cooling System Analysis PM-0420-69559, Revision 0 ML20072H3272020-03-0909 March 2020 LLC - Public Meeting Presentation: Topic - Emergency Core Cooling System Boron (ECCS) Distribution, PM-0320-69218, Revision 0 ML20069A1632020-03-0505 March 2020 ACRS Full Committee Presentation: NuScale Topical Report-Rod Ejection Accident Methodology, PM-0320-69146, Revision 0 ML20069A9692020-03-0505 March 2020 ACRS Full Committee Presentation: NuScale Topical Report, Loss-of-Coolant Accident Evaluation Model, PM-0320-69138, Revision O ML20069A1542020-03-0404 March 2020 ACRS Full Committee Presentation: NuScale Topical Report- Non-Loss-of-Coolant Accident, PM-0320-69141, Revision 0 ML20066G2802020-03-0303 March 2020 LLC, Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale Topic - Hydrogen Monitoring, PM-0220-69071, Revision 0 ML20066F4672020-02-28028 February 2020 Enclosure 1: ACRS Subcommittee Presentation: NuScale FSAR Topic- Resolution of Chapter 15 Phase 2 Open Items, PM-0220-69062, Revision 0 ML20066G2772020-02-28028 February 2020 ACRS Full Committee Presentation: NuScale - Steam Generator Design, PM-0220-69051, Revision 0 ML20054A9622020-02-19019 February 2020 ACRS Subcommittee Presentation: NuScale Topical Report - Non-Loss-of-Coolant Accident, PM-0220-68852, Revision 0 ML20054A4062020-02-17017 February 2020 ACRS Subcommittee Presentation: NuScale Topical Report- Loss-of-Coolant Accident Evaluation Model, PM-0220-68917, Revision 0 ML20054B6342020-02-17017 February 2020 Nuscale - ACRS Subcommittee Presentation: NuScale Topical Report - Rod Ejection Accident Methodology, PM-1019-67365, Revision 0 ML20035C7892020-02-0404 February 2020 Nuscale - ACRS Subcommittee Presentation, FSAR, Steam Generator Design ML19340B5912019-12-0606 December 2019 Public Meeting - NuScale Incorporated by Reference (Ibr) Slides ML19324C8362019-11-13013 November 2019 LLC Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale Source Term Methodology Application, PM-1119-67928, Revision 0 ML19192A1662019-07-10010 July 2019 Presentation Entitled, Evaluation Methodology for Stability Analysis of the NuScale Power Module. ML19169A1662019-06-14014 June 2019 Mitigation of Beyond-Design-Basis-Events, NuScale FSAR Chapter 20, PM-0619-65964, Revision 0 ML19135A0642019-05-0909 May 2019 LLC - Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale FSAR Chapter 21, Multi-Module Design Considerations, PM-0519-65533, Revision 0 ML19105A1352019-04-11011 April 2019 ACRS Presentation: NuScale Chapter 5, Reactor Coolant System and Connecting Systems Overview, PM-0419-65159, Revision 0 ML19105A1312019-04-10010 April 2019 Enclosuacrs Presentation: Chapter 4, Reactor Overview, PM-0419-65096, Revision 0 ML19098A7802019-04-0202 April 2019 LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Chapter 9, Auxiliary Systems, PM-0319-64807, Revision 0 ML19073A0482019-03-11011 March 2019 LLC - ACRS Presentation Chapter 10 - Steam and Power Conversion System, PM-0219-64501, Revision 1 ML19073A0512019-03-11011 March 2019 ACRS Presentation Chapter 11 - Radioactive Waste Management, PM-0219-64543, Revision 1 ML19073A0532019-03-11011 March 2019 Enclosure 1: ACRS Presentation Chapter 12 - Radiation Protection, PM-0219-64534, Revision 1 ML19050A1632019-02-20020 February 2019 Enclosure 1: ACRS Presentation Chapter 11 - Radioactive Waste Management, PM-0219-64543, Revision 0 ML19053A5182019-02-19019 February 2019 Nuscale - Dhrs and ECCS Logic Changes, PM-0219-64563, Revision 0 ML19050A3982019-02-13013 February 2019 Enclosure 1: ACRS Presentation Chapter 10 - Steam and Power Conversion System, PM-0219-64501, Revision 0 ML19045A3062019-02-12012 February 2019 PM-0219-64475-NP, Revision 0, Reactor Vessel Flange Tool (Rft) Design Plan and Schedule. ML19042A0732019-02-0505 February 2019 Nuscale - Chapters 2 and 17 ACRS Full Committee, PM-0219-64333, Revision 0 ML19024A2042019-01-23023 January 2019 ECCS Valve DCA Demonstration Testing, PM-0119-64160-NP, Revision 0 ML18360A1782018-12-19019 December 2018 Enclosure 2: Presentation Titled, Addressing Component Fatigue for NuScale Dca. ML18362A1422018-12-19019 December 2018 Enclosure 2: Absorption Coefficient for Pool Water and Reactor Building Floor Interaction, PM-1218-63882, Revision 0 ML18347A2032018-12-18018 December 2018 Enclosure 1: ACRS Presentation Chapter 17 - Quality Assurance and Reliability Assurance, PM-1218-63732, Revision 0 ML18347A2072018-12-18018 December 2018 ACRS Presentation Chapter 2 - Site Characteristics and Site Parameters, PM-1218-63753, Revision 0 ML19025A2212018-12-18018 December 2018 Enclosure 2: Slides Titled, Basis for an Rft Stand COL Item, PM-1218-63892-NP, Revision 0, Non-Proprietary Version ML18331A1602018-11-20020 November 2018 Enclosure 2: Addressing Component Fatigue for NuScale DCA, November 20, 2018 ML18338A1032018-11-14014 November 2018 Nuscale - LTC RAI Closure Plan, PM-1118-63594-NP, Revision 0, Nonproprietary Version ML18235A3152018-08-23023 August 2018 LLC - Presentation Materials Entitled ACRS Presentation: NuScale Instrumentation and Controls Design Overview, PM-0618-60212, Revision 0 ML18222A1932018-08-0808 August 2018 Enclosure 1: NuScale Accident Source Terms Methodology Options PM-0818-61166, Revision 0 ML18213A1572018-08-0101 August 2018 Risk-Informed Review of NuScale Initial Test Program, PM-0718-61123, Revision 0 ML18220A8742018-07-25025 July 2018 Enclosunuscale CIRLT-RAI 9474 ML18156A1262018-06-0101 June 2018 LLC Submittal of Presentation Materials Entitled, ACRS Presentation Chapter 8 Overview, for Use During a Public Meeting on June 6, 2018 ML18156A1272018-05-31031 May 2018 LLC Submittal of Presentation Materials Entitled NuScale Power Containment Leak Rate Test Program, PM-0518-59978, Revision 1 ML18116A4422018-04-24024 April 2018 Enclosure 2: NuScale Power Comprehensive Vibration Assessment Program - Audit Report Summary Discussion, Revision 0, PM-0218-58803-NP (Non-Proprietary Version) ML18037A6732018-02-0808 February 2018 PM-0218-58480, Revision 0, Shutdown Capability of the NuScale Power Module. 2020-07-01
[Table view] |
Text
L0-1218-63893 :
"Basis for an RFTStand COL Item," PM-1218-63892-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
NuScale Nonproprietary Basis for and RFT Stand COL Steven Shaw Supervisor, Refueling and Remote Handling December 18, 2018 PM-1218-63892-NP Copyright 2018 by NuScale Power, LLC.
Revision:. O T t:111µ1c1Lt: +1-. uuuu-L , 1L 1-ru , Kq
Acknowledgement & Disclaimer This material is based upon work supported by the Department of Energy under Award Number DE-NE000063~.
This report was prepared as an account of work sponsored by an agency of the United States (U.S.) Government. N~ither the U.S.
Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein
- to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S.
Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect t,hose of the U.S.
Government or any agency thereof.
2 PM-1218-63892-NP Copyright 2018 by NuScale Power, LLC.
Revision: O Ttm1µ1c11~ 11-, uuuu-L 1 1 L 1 -ru 1 ~q
RAI 8838_, 8911, a.nd 9225
- Agenda: To provide a basis for reclassifying the completion of final design of the reactor flange tool stand (RFT stand) as a COL item.
- Review of fuel locations where qualification is required.
- Review of fuel design inputs, core plate motions, and fuel analysis performed by Framatome.
- Potential RFT stand design capable of meeting seismic requirements: * * *
- Description* of bounding seismic analysis performed on the RFT design. *
- Core Plate motions for conceptual RFT designs and bay locations ISRS. *
- COL Implementation 3
PM-1218-63892-NP Copyright 2018 by NuScale Power, LLC.
Revision: O Ttimµ1a1ti tt. uuuu-L 1, L 1-ru 1 r<.<+
Fuel Locations 4
PM-1218-63892-N P Copyrig ht 2018 by Nu Scale Power, LLC .
" Sowo, lo
- ull hcmod;,.a Revision : 0 Tt::111JJ 1c1tt:: tt . uuuu-.::, 1.::1-ru, "'+
Fuel Design Inputs
((2(a ),(c )
5 PM-1218-63892-NP Copyrig ht 2018 by NuScale Power, LLC.
Revision : 0 Te111f.JlcHe It . uuuu-L 11L1-ru, ""
RFT Redesign Concept - Upper Support
- Upper Support shown in blue. (Note near wall removed to illustrate concept, all 4 corners anchor to the wall.)
- Braces upper flange of lower RPV to the walls of the refueling pool.
6 PM-1218-63892-NP Copyri ght 2018 by NuScale Power, LLC .
Revision : 0 Te, 11µ1c11e tt . uuuu-L, 1 L 1 -r u , rv+
Core Plate Motions for RFT and Operating Bays
((
}}2(a),(c) 7 PM-1218°63892-NP Copyright 2018 by NuScale Power, LLC.
Revision: 0 Tt:llll!)li:ILt:l tt-. uuuu-,: 1 , ,: , -ru I r-<+
((
}}2(a),(c)
PM-1218-63892-NP
((
g --------------------------------------------,,,----}~}2:(a~),(~c)
- -!:,',~3892-NP Copyright2018 by NuScale Power, LLC. M~\:l.?.f.~b,r
((
- - - - - - - - - - - - - - - - - - - ~ ~ - - - - - - - - - - - - - - - - - - - - - - - - _ _ ; _ . . . . . . , ._ __J}}~2(::a)~,(c:'..)
10
- -~:::~3892-NP Copyright 2018 by NuScale Power, LLC. ~ M~!J,~.~-~-~~
- T~111µ1c11t:: tt. uuuu-L 1 1 L 1-ru I rv+
((
- ---------------- ---------------- --------------., ,....---.!!}}:'.2 (:a)~,(c~)
11
- ~;;:~::~3892-NP Copyright2018 by NuScale Power, LLC. M~!,1,~f-~.~r Ttm1µ1c11~ 11-. uuuu-.<: 11 L 1-ru , K'+
((
\
- ----------------------:------------ -----...;...-----------::,,....---~}} ~2(~a)~,(c~)
12
- ,~3892-NP Copyright 2018 by NuScale Power, LLC. M~!!.?.f~b~
- Tt:ll!IJ.llcllt:l 11-. uuuu-.: 11 .:1-ru I l"i.'f
((
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _..:....__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _...:....__ _ _ _ _ _ _ _ _~}}~2(~a)~,(c~)
13
- -
- 3892-NP Copyright2018 by NuScale Power, LLC. M~!:J.~.f.~bf T~mµ1c11~ 11-. uuuu-, 1 1, 1-ru I r-1.q
. Remaining Design Activities
- Refueling Pool
- Maintenance and Repair
. - Hose & Cable Philosophy Development Management
- Crane (wet hook) access
- Operations personnel access
- Potential design/technology upgrades.
14 PM-1218-63892-NP Copyright 2018 by NuScale Power, LLC.
Revision: 0 Tt:Hllf.lli:IL~ if. uuuu-L 1 1L 1-ru I rv+
COL Implementation -_Applicant Actions
- Complete design
- Perform a site specific analysis that demonstrates during.
an SSE:
- The s~ismic category 1 RFT stand is retained in position in the refueling pool.
- The lower RPV is retained* in the RFT stand.
- The RFT stand is structurally qualified in accordance with SC 1 criteria.
(continued next slide) 15 PM-1218-63892-NP Copyright 2018 by NuScale Power, LLC. .
*~! NUSCALE'"
eowo, lo, all h,mankh,d Revision: 0 T~111µ1aL~ tt. uuuu-L 1, L 1-ru I rv+
COL Implementation -Applicant Actions (cont)
- Fuel margins to limits are established using the more demanding of the following two scenarios:
*- site specific core plate motions in the RFT are enveloped by the design basis core plate motions for the RPV in the RFT stand, OR
- the core plate motions for the assembled NPM in the operating bays at the site are enveloped by the design basis core plate motions with the assembled NPM installed .in the operating bays 16 PM-1218-63892-NP Copyright 2018 by NuScale Power, LLC.
Revision: O Ttm1µ1c11e ff-. uuuu-L 11 Lt-ru I r-"+
Portland Office Richland Office 6650 SW Redwood Lane, 1933 Jadwin Ave., Suite 130 Suite 210 Richland, WA 99354
. Porlland, OR 97224 541. 360. 0500 971.371.1592 Arlington Office Corvallis Office 2300 Clarendon Blvd., Suite 1110 1100 NE Circle Blvd., Suite 200 Arlington, VA 22201 Corvallis, OR 97330 541. 360. 0500 London Office 1st Floor Porlland House Rockville Office Bressenden Place 11333 Woodglen Ave., Suite 205 London SW1 E 5BH Rockville, MD 20852 United Kingdom 301.770.0472 +44 (OJ 2079 321700 Charlotte Office 2815 Coliseum Centre Drive, Suite 230 Charlotte, NC 28217
/ 980.349.4804 http://www. nuscalepower. com W Twitter: @NuScale_Power NUSCALETM
- Power for all humankind 17 PM-1218-63892-N P Copyright 2018 by NuScale Power, LLC.
Revision:* O Te111µ1c1te 11-. uuuu-, , , , , -ru , r;.q}}