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Category:Meeting Briefing Package/Handouts
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 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 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 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 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 ML20069A9692020-03-0505 March 2020 ACRS Full Committee Presentation: NuScale Topical Report, Loss-of-Coolant Accident Evaluation Model, PM-0320-69138, Revision O ML20069A1632020-03-0505 March 2020 ACRS Full Committee Presentation: NuScale Topical Report-Rod Ejection Accident Methodology, PM-0320-69146, Revision 0 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 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 ML20054B6342020-02-17017 February 2020 Nuscale - ACRS Subcommittee Presentation: NuScale Topical Report - Rod Ejection Accident Methodology, PM-1019-67365, Revision 0 ML20054A4062020-02-17017 February 2020 ACRS Subcommittee Presentation: NuScale Topical Report- Loss-of-Coolant Accident Evaluation Model, PM-0220-68917, 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 ML19204A2772019-07-22022 July 2019 Discussion Topic July 22, 2019 Public Meeting to Discuss Interface Requirement Associated with the NuScale Design Certification Application ML19190A0882019-07-0303 July 2019 LLC Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation, NuScale FSAR Chapter 20, Mitigation of Beyond-Design-Basis Events, PM-0719-66189, Revision 0 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 ML19134A0742019-05-0909 May 2019 LLC Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale FSAR Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation, PM-0519-65372, Revision 0 ML19105A1352019-04-11011 April 2019 ACRS Presentation: NuScale Chapter 5, Reactor Coolant System and Connecting Systems Overview, PM-0419-65159, 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 ML19079A2382019-03-20020 March 2019 Enclosure 1: ACRS 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 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 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 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 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 ML18205A3182018-07-24024 July 2018 NRC Staff Questions for the August 1, 2018 Public Meeting with NuScale on ITP 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) ML18090A0032018-04-0202 April 2018 Handout for the April 2, 2018 Public Meeting to Discuss NuScale Plans to Respond to the NRC Staff RAIs Related to Sections 3.7 and 3.8 ML18085A0722018-03-26026 March 2018 NRC Staff Questions for April 9, 2018 Public Meeting with NuScale on DCA Chapter 20 ML18037A6732018-02-0808 February 2018 PM-0218-58480, Revision 0, Shutdown Capability of the NuScale Power Module. ML18019A1612018-01-23023 January 2018 LLC - Shutdown Capability of the NuScale Power Module ML18019A1632018-01-23023 January 2018 Source Term Revision, Revision 0, PM-0118-58201 2020-07-01
[Table view] 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
NuScale Nonproprietary Incorporated by Reference (IBR)
Public Meeting December 9, 2019 1
PM-MMYY-XXXX-P Revision: Copyright 2019 by NuScale Power, LLC.
Template #: 0000-21727-F01 R5
Purpose To achieve alignment on implementation of Incorporated by Reference in NuScale FSAR.
2 PM-MMYY-XXXX-P Revision: Copyright 2019 by NuScale Power, LLC.
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Introduction
- NuScale believes it will also benefit the Rulemaking process and burden.
- Two separate but related concepts at issue:
- Reducing amount of reports incorporated by reference in the DCD* (DCD-IBR), and
- Reducing the amount of reports approved for incorporation by reference by the Office of Federal Register (OFR-IBR).
- Note: For simplicity, use of term DCD herein refers to the Generic DCD as traditionally defined (Tier 1, Tier 2, and Generic Tech Specs) 3 PM-MMYY-XXXX-P Revision: Copyright 2019 by NuScale Power, LLC.
Template #: 0000-21727-F01 R5
Scope of IBR
- DCD-IBR:
- Used by applicants to incorporate reports into the DCD; equivalent to including directly in the DCD. For NuScale listed in Tier 2 Tables 1.6-1 and 1.6-2.
- Traditionally used in Part 50 applications to adopt approved Topical Reports.
Additional function is to incorporate SUNSI and SGI that cannot be included in the DCD directly.
- Afforded issue resolution and finality by the DC Rule. Becomes necessary for a COL applicant to include or IBR the same reports.
- OFR-IBR:
- A subset of DCD-IBR: public reports that are DCD-IBR.
- Formally approved for IBR by the OFR. Directly included in the scope the DC rule in the same manner as the DCD itself.
- First used in the ESBWR DC:
>> ESBWR DCD Rev. 10 includes 70 reports that are DCD-IBR (Tables 1.6-1 and 1.6-2) and 48 reports that are additional references (Table 1.6-3).
>> 20 of the DCD-IBR reports are public documents and were approved for IBR by the OFR, in addition to the DCD itself.
4 PM-MMYY-XXXX-P Revision: Copyright 2019 by NuScale Power, LLC.
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Reducing IBR
- DCD-IBR:
- Primarily SUNSI/SGI reports (including nonprop versions of proprietary reports).
- Problem: may expand licensing basis beyond what is intended or necessary; potential burden on NuScale and COL applicants/licensees.
- OFR-IBR:
- Subset of DCD-IBR: Fully public documents that are IBRd for expediency.
- Problem: for clarity to NRC and third parties, these reports should be references only (pre-ESBWR approach).
- First flowchart shared with NRC (Slide 6) aimed at what could be done to reduce DCD-IBR. Included some implicit assumptions that reflected that purpose.
- New flowchart (Slide 7) attempts to simplify DCD-IBR and OFR-IBR issues, and recognizes feasibility of DCA/SER changes at this stage.
5 PM-MMYY-XXXX-P Revision: Copyright 2019 by NuScale Power, LLC.
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Original IBR logic 6
PM-MMYY-XXXX-P Revision: Copyright 2019 by NuScale Power, LLC.
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Simplified IBR logic Is information in the report Are the requirements intended as a requirement? severable from the report?
- Can be readily distinguished required information AND from non-requirement
- Forward-looking: necessary for a information COL applicant to comply with Potential SDA improvements YES Can the requirements be NO captured in the DCD* directly?
Are the requirements
- Information intended as requirements is not SUNSI/SGI, already captured in DCD?
and
- I.e., the information intended
- Its practical to reproduce directly as requirements is in DCD.
NO redundant to equivalent Is the full report public?
information in the DCD
- E.g., there arent separate Prop and Nonprop versions YES Incorporate requirements in DCD, corresponding NO YES changes to SER.
Report becomes a reference only.
Report is incorporated by Report is a reference Report IBRd in the reference in the DCD only (additional DCD and will be (Prop and NP versions); *DCD isnt a term applicable to the information that approved for IBR by SDA, but it is used for simplicity here.
accorded issue resolution supports DCD) the OFR and finality by DC Rule 7
PM-MMYY-XXXX-P Revision: Copyright 2019 by NuScale Power, LLC.
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Simplifying Table 1.6-1-Topical Reports Topical Report FSAR FSAR Changes Topical Report Title IBR disposition Notes SER Ref.
Number Section (beyond §1.6 tables)
NP-TR-1010-859- NuScale Topical Report: Maintain as DCD-IBR; Nonproprietary document. Includes forward-looking requirements for None.
NP, Rev 4 Quality Assurance 17 Will be OFR-IBR. future QA.
Program Description for the NuScale Power Plant TR-0515-13952- Risk Significance 17, 19 Delete from IBR; Nonproprietary document. Provides methodology that is required for None. Ch. 17 A, Rev 0 Determination FSAR but no forward-looking requirements.
Maintain as reference.
§17.4 uses as methodology reference.
Table 19.1-19: Criteria for Risk Significance provides the criteria. TR-0515-13952-A is a reference.
TR-0815-16497- Safety Classification of 8, 15 Delete from IBR; Proprietary report with necessary information for safety evaluation in None. Ch. 5, P-A, Rev 1 Passive Nuclear Power FSAR Maintain as reference. Ch. 6, Plant Electrical Systems
§8.3 references the methodology provided in the TR.
Ch. 8, Part 7 and SER reference to support GDC 17, 18 exemptions.
Ch. 13, Ch. 15 TR-1015-18653- Design of the Highly 7, 15 Maintain as DCD-IBR; Proprietary report (nonproprietary version provided). The TR provides None Ch. 7, P-A, Rev 2 Integrated Protection non-severable requirements for system design:
Will not be OFR-IBR. Ch. 16 System Platform Topical §7.0.4.1 points to the TR for design detail (The MPS is built on Report the highly integrated protection system platform (See TR-1015-18653-P-A),
§7.1.1 states The safety-related module protection system (MPS) uses the highly integrated protection system (HIPS) platform described in topical report NuScale Power, LLC, TR-1015-18653-P-A,
§7.2.15.3 states More detail on the MPS diagnostics functions are provided in TR-1015-18653-P-A.
Other uses:
§15.8 lists as a reference Part 4 (B.3.3) lists as validation source Part 7 reference to support 10 CFR 50.62(c)(1) ATWS exemption.
8 PM-MMYY-XXXX-P Revision: Copyright 2019 by NuScale Power, LLC.
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Simplifying Table 1.6-2-Technical Reports Report Technical Report FSAR IBR disposition Notes FSAR Changes SER Ref.
Number Title Section TR-0716- Comprehensive 3.9, 14.2 Maintain as DCD-IBR; Proprietary report. The TR provides forward-looking requirements, e.g., None Ch. 3, 50439 Vibration Assessment Ch. 4, Will not be OFR-IBR. §14.2.3.3 The program is implemented consistent with the requirements of TR-0716-50439, Program (CVAP)
Ch. 5 Technical Report TR- §14.2.11 Vibration testing is performed in accordance to the requirements of the NuScale CVAP as described 0716-50439 in TR-0716-50439 Also: §13.9 COL Item 3.9-10: The methodology contained in.TR-0716-50439 is acceptable.
TR-0816- Fuel Storage Rack 3.7, 3.8, Maintain as DCD-IBR; Proprietary report. The TR provides forward-looking requirements specified in §9.1.2: A COL applicant will provide a None Ch. 9 49833 Analysis 9.1 neutron absorber material qualification report which demonstrates that the neutron absorber material can meet the Will not be OFR-IBR.
neutron attenuation and environmental compatibility design functions described in Technical Report TR-0816-49833.
Also:
- §3.7.3: The design of the racks is discussed in Section 9.1.2 and the details of the seismic analysis are provided in technical report"§3.8.4: The fuel storage racks are described in Section 9.1 and Technical Report.
- §9.1.5: Uses as a validation source (i.e., RH margin)
- §9.1.3: The maximum keff remains below the applicable limits in the regulations and no abnormal condition would cause an inadvertent criticality
- Table 3.7.2-35 uses as reference TR-0816- Loss of Large Areas 20.2 Delete from IBR; None Proprietary report. LOLA requirements defined by regulation and design features described in FSAR. Report provides 50796 Due to Explosions and Maintain as reference. details of evaluation that was performed but doesnt contain forward-looking requirements.
Fires Assessment
§20.2: TR-0816-50796documentsresponse to a LOLA event using the guidance in.NEI 06-12 defines LOLA criteria and identifies the design features that meet those criteria and COL applicant requirements COL Item 20.2-1: A COL applicant that references the NuScale Power Plant design certification will develop enhanced firefighting capabilities in accordance with 10 CFR 50.155(b)(2). The enhanced firefighting capabilities should address the expectation elements listed in Section 4.1.3 of the Technical Report TR-0816-50796 (Reference 20.2-1).
COL Item 20.2-2: A COL applicant that references the NuScale Power Plant design certification will provide a means for water spray scrubbing using fog nozzles and the availability of water sources, and address runoff water containment issues (sandbags, portable dikes, etc.) as an attenuation measure for mitigating radiation releases outside containment.
RP-0914- Human Factors 18.11 Maintain as DCD-IBR; Non-proprietary report: None Ch. 18 8544 Engineering Design Will be OFR-IBR.
- Contains the requirements that a COL must meet to verify conformance of the as-built design to the planned design.
Implementation Implementation Plan
- Describes how ownership of the HFE program is transferred from NuScale to a licensee and what actions a licensee must complete in order to close the HFE ITAAC.
RP-1215- Control Room Staffing 18.5 Delete from IBR; Proprietary report: None Ch. 18 20253 Plan Validation Maintain as reference.
- Provides a systematic method to perform staffing validations and testing with focus on high workload situations Methodology
- Describes the methodology used to evaluate licensed operator workload in a control room environment
- A workload assessment will verify the physical and cognitive demands associated with operating a 12-unit facility with the staffing plan to ensure that the staff workload is within limits.
ES-0304- Human-System 18.10 Maintain as DCD-IBR; Proprietary report: None Ch. 18 9
1381 Interface Style Guide Will not be in OFR-IBR. Ensures the implementation of human factors engineering and human system interface principles in the PM-MMYY-XXXX-P development of user interface display pages, work locations, and work stations.
Revision: Copyright 2019 by NuScale Power, LLC.
Documents all of the information, requirements, and functional specifications of the human system interface.Template #: 0000-21727-F01 R5
Interpretations of Tables 1.6-1, 1.6-2
- Is use in a DCA part other than Part 2 a reason for IBR?
- Yes, e.g., Part 4 (Tech Specs); Part 7 (Exemptions) cannot be.
- Is reference in RAI response, by itself, a reason for IBR?
- No. Only reports with information intended as requirements will be IBR.
- Does SER statement referencing report as supporting a safety finding require in FSAR 1.6 tables?
- No. Only reports with information intended as requirements will be IBR.
- Does an SER statement that report is IBR require inclusion in FSAR 1.6 tables?
- No, although SER wording may need to be revised.
10 PM-MMYY-XXXX-P Revision: Copyright 2019 by NuScale Power, LLC.
Template #: 0000-21727-F01 R5
Implementation
- Actions to get to agreement on what can be removed from NuScale FSAR IBR content
- Implications for SER updates
- Other thoughts or questions?
11 PM-MMYY-XXXX-P Revision: Copyright 2019 by NuScale Power, LLC.
Template #: 0000-21727-F01 R5
Portland Office Richland Office 6650 SW Redwood Lane, 1933 Jadwin Ave., Suite 130 Suite 210 Richland, WA 99354 Portland, 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 Portland House Rockville Office Bressenden Place 11333 Woodglen Ave., Suite 205 London SW1E 5BH Rockville, MD 20852 United Kingdom 301.770.0472 +44 (0) 2079 321700 Charlotte Office 2815 Coliseum Centre Drive, Suite 230 Charlotte, NC 28217 980.349.4804 http://www.nuscalepower.com Twitter: @NuScale_Power 12 PM-MMYY-XXXX-P Revision: Copyright 2019 by NuScale Power, LLC.
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