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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
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Text
NuScale Nonproprietary NuScale Source Term Revision Mark Shaver Radiological Engineering Supervisor Gary Becker Regulatory Affairs Counsel Darrell Gardner Licensing Project Manager January 23, 2018 PM-0118-58201 -NP *. NUSCALE Revision : 0 Copyright 2018 by NuScale Power, LLC. .:* POWER-Template # : 0000-21727-F0 1 R1
Acknowledgement and Disclaimer This material is based upon work supported by the Department of Energy under Award Number DE-NE0000633.
This presentation was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States 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 United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.
2 PM-0118-58201-NP *~ _NUSCALE Revision : 0 Copyright 2018 by NuScale Power, LLC . : POWER-Template # : 0000-21727-F01 R1
Outline
- Source Term Changes Rationale
- AST LTR Iodine Spike MHA
- AST LTR Core Damage MHA
- Regulatory Considerations
PM-0118-58201-NP aats*** NUSCA LE Revis ion : 0 Copyright 2018 by NuScale Power, LLC. ... Pow eR-Temp1a1e #: 0000-21727-F01 R1
Purpose
- Inform NRC of forthcoming changes to NuScale Accident Source Term Methodology Topical Report (AST LTR) and the DCA source term associated with the maximum hypothetical accident (MHA)
Note: "MHA" is shorthand for the scenario described in 10 CFR 52 .4 7(a)(2)(iv)
- technical approach
- regu latory interpretations
- schedules 4
PM-011 8-58201 -NP
- '; NUSCALE Revision
- O Copyright 2018 by NuScale Power, LLC. *. ,: POW l: R-Temp1ate #: 0000-21727-F01 R1
Current DCA Source Terms Various source terms are used in various design-basis analyses. Only the underlined text below will change.
Technica l 0.0028% Failed 0.028% Failed Specification 1% Failed Fuel Contents of 1 Core Damage Fuel Fraction Fuel Fraction Limit Primary Fraction Fuel Assembly Coo lant 5
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Template#: 0000-21727-F01 R1
Current AST LTR Approach
- MHA source term is derived from <1E-10/year PRA core damage sequences
- core damage leads to fiss ion product release into containment 6
PM-0118-58201-N P c e a';* NUSCALE Revision : O Copyright 2018 by NuScale Power, LLC. .=* POWE:RN Template#: 0000-21727-F01 R1
DCA Source Term Changes
- Incredible source terms (CDF<1 E-6/year) Technical involving core damage Specification Limit Core Darnage will only be used for Prirnary Coolant EPZ and SAMOA 7
PM-0118-58201-NP
..*. NUSCALE Revision : O Copyright 2018 by NuScale Power, LLC . : POWER-Temp1ate#: 0000-21727-F01 R1
Source Term Changes Rationale
- NuScale has elected to make these changes because the current MHA approach is overly conservative given the low probability of internal events core damage (<1 E-9/year)
- existing analyses using the current methodology result in overly conservative design requirements for
- control room habitability design
- Additionally, for defense-in-depth, the NuScale containment's primary purpose is to facilitate emergency core cooling, with a secondary function of retaining fission products
- both prevention and mitigation functions 8
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Source Term Changes Rationale Steam escapes Condenses on Re-enters RPV Returns to core RPV CNV wall at RRV from RRV 9
PM-0118-58201 -N P \ NUSCALE Revis ion : 0 Copyright 2018 by NuScale Power, LLC . mwa..** POWE::RN Template#: 0000-2 1727-F01 R1
Source Term Changes Rationale
- IAEA defense-in-depth report (INSAG-10)
NuScale's containment provides both Level 4 and Level 3 TABLE I. LEVELS OF DEFENCE lN DEPTH Levels of defcncx Objective &sential means in depth Prevention of abnonnal opcralion Conservative design and high and failures quality in conslruction and operation Lcvc12 Control of abno.mtal operation and Corttrot limiting and protection detection of failures systems and other surveillance features Level 3 Control of accidents wid1in the Engineered safety features an.d OC!iign basis accident p rocedmcs Level 4 Control of severe plant conditions, Complementary* measures and incl.,.,ling prevention of accident accwent manageinent progression and mitigation of the consequences of severe accidents 1..c..*et 5 Mil:igsticm of radiological Off-sile emergency te_*pon~e:
consequ:cncxs of significant rclea~~s of radioactive material~
10 PM-0118-582 01 -NP *; NUSCALE Revision : O Copyright 2018 by NuScale Power, LLC. : POWER~
Template#: 0000-21727-F01 R1
AST LTR Changes
- Logic gate added near beginning of AST LTR
/ >1E-6(year intact
/ containment core damage event?
L---J Yes No 11 PM-0118-58201-NP ce:a*, NUSCALE Revision : 0 Copyright 2018 by NuScale Power, LLC .
- POWER-Template # : 0000-21727-F01 R1
AST LTR Iodine Spike MHA
- Surrogate MHA event derived from sequences
>1 E-6/year not resulting in core damage
- LOeA in containment initiating event (e.g., eves break in containment) is used, as it is representative of a spectrum of events that result in primary coolant in the containment
- Radionuclides in primary coolant at technical specification limits released from core into containment
- assume Iodine spiking
- Significantly less technically complex to analyze than the core damage MHA and significantly smaller source term 12 PM-0118-58201-NP
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- O Copyright 2018 by NuScale Power, LLC . *.: . .:* POWl:R~
Template#: 0000-21727-F01 R1
AST LTR Core Damage MHA
- Alternative path of logic gate is essentially the current MHA approach shown in AST LTR Rev. 2 that NRC already reviewed
- two changes to how dose is calculated from the MHA source term in AST LTR Rev. 3
- leak rate assumptions 13 PM-0118-58201-NP Revision : 0 Copyright 2018 by NuScale Power, LLC .
Regulatory Considerations
" .. . The following power reactor design characteristics will be taken into consideration by the Commission: ...
(iii) The extent to which the reactor incorporates unique, unusual or enhanced safety features having a significant bearing on the probability or consequences of accidental release of radioactive materials; and (iv) ...design features intended to mitigate the radiological consequences of accidents. In performing this assessment, an applicant shall assume a fission product release 3 from the core into the containment. .. The applicant shall perform an evaluation and analysis of the postulated fission product release ... to evaluate the offsite radiological consequences. "
14 PM-0118-58201-NP -; NUSCALE Revision : 0 Copyright 2018 by NuScale Power, LLC . **EaHla:* POWE::R-Temp1 ate # : 0000-21727-F01 R1
Regulatory Considerations
- 10 CFR 52.47, Footnote 3 "The fission product release assumed for this evaluation should be based upon a major accident, hypothesized for purposes of site analysis or postulated from considerations of possible accidental events. These accidents have generally been assumed to result in substantial meltdown of the core with subsequent release into the containment of appreciable quantities of fission products. "
15 PM-0118-58201-NP - *:* NUSCALE Revision : O Copyright 2018 by NuScale Power, LLC. .=* PowER-Template #: 0000-21727-F01 R 1
Regulatory Considerations
- included phrase: "that would result in potential hazards not exceeded by those from any accident considered credible" and explicit reference to TID-14844 (see current 10 CFR 100.11)
- Part 100 rulemaking to "decouple siting from accident source term and dose calculations" modified to be compatible with "revised accident source terms" (63 FR 65159)
- 10 CFR 50.67 AST rulemaking , "There is no regulatory requirement for a specific source term for reactors to be licensed in the future" (64 FR 71995)
Regulatory Considerations
- Containment leakage integrity remains applicable
- GDC 16, Containment design: " ... an essentially leak-tight barrier against the uncontrolled release of radioactivity to the environment. .. "
- Containment's function in accident prevention and mitigation is addressed by other requirements
- 10 CFR 52.47(a)(4 ): assess "adequacy of structures, systems, and components provided for the prevention of accidents and the mitigation of the consequences of accidents."
- 10 CFR 50.46 ECCS acceptance criteria, GDC 34 residual heat removal, GDC 35 emergency core cooling 17 PM-0 118-5820 1-NP '; NUSCALE Revision : 0 Copyright 2018 by NuScale Power, LLC . .**PoweR-r emplate # : 0000-21727-F01 R1
Regulatory Considerations
- Consistent with other source term requirements
- GDC 19, Control room: "A control room shall be provided from which actions can be taken to operate the nuclear power unit safely under normal conditions and to maintain it in a safe condition under accident conditions, including loss-of-coolant accidents. Adequate radiation protection shall be provided to permit access and occupancy of the control room under accident conditions without personnel receiving radiation exposures in excess of 5 rem whole body, or its equivalent to any part of the body, for the duration of the accident."
- 10 CFR 52.79(a)(1 )(vi): Comparable requirement for COL applications, using actual site characteristics. COL would be expected to use same approach 18 PM-0118-58201-NP *. NUSCALE Revision : 0 Copyright 2018 by NuScale Power, LLC . ~.* POWER-Temp1ate # : 0000-21727-F01 R1
DCA Impacts
- Referenced AST LTR Rev. 3 methodology change
- option of core damage or iodine spike MHA source term based on whether >1 E-6/year core damage event exists
- change to aerosol modeling
- change to leak rate assumptions
- 3.11 and 3.C Environmental Qualification Methodology
- 12.2 Radiation Sources
- 15.0.3 Radiological Consequence Analyses 19 PM-0118-58201-NP Revision : O Copyright 2018 by NuScale Power, LLC .
Schedule
- July 2018
- July 2018
- DCA update unilateral letter
- July 2018 20 PM-0 11 8-58201 -NP :* ': NUSCALE Revision : O Copyright 2018 by NuScale Power, LLC . *:. ,:* POWE:R~
Template#: 0000-21727-F01 R1
Summary
- Core damage MHA source term is overly conservative as a design basis for the NuScale Power Module
- RAI 9224 response, AST LTR Rev. 3, and associated DCA markups to be submitted July 2018 21 PM-0118-58201-NP :* *: NUSCALE Revision : 0 Copyright 2018 by NuScale Power, LLC. :. ,;* POWE:R-Temp1ate#: 0000-21727-F01 R1
- NUSCALE POWER' 6650 SW Redwood Lane, Suite 210 Portland, OR 97224 971 .371 .1592 1100 NE Circle Blvd. , Suite 200 Corvallis, OR 97330 541 .360.0500 11333 Woodglen Ave., Suite 205 Rockville, MO 20852 301 . 770.0472 2815 Coliseum Centre Dr. , Suite 230 Charlotte, NC 28217 980. 349.4804 1933 Jadwin Ave., Suite 130 Richland, WA 99354 1st Floor Portland House Bressenden Place London SW1 E 5BH United Kingdom
+44 (0) 2079 321700 http://www.nuscalepower.com 22 PM-0 11 8-58201-NP *. NUSCALE Revision : O Copyright 20 18 by NuScale Power, LLC . ** POWER-Temp1ate #: 0000-2 1727-F0 1 R1