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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 NuScales 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 NuScales 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
L0-0619-65966
Enclosure:
"Mitigation of Beyond-Design-Basis-Events, NuScale FSAR Chapter 20," PM-0619-65964, Revision 0.
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 Mitigation of Beyond-Design-Basis Events NuScale FSAR Chapter 20 Nadja Joergen sen Licensing Specialist Elizabeth English Licensing Specialist Chris Maxwell Senior Reactor Operator June 17, 2019 PM-0619-65964 Revision: O Copyright 2019 by NuScale Power, LLC.
N!t!,l,?f~.~r Template#: 0000-21727-F01 R5
Objective of MBDBE Rule
- Establish coping capabilities to prevent damage to fuel in any NPM and the SFP, and to maintain containment function by using plant and mitigating equipment during an extended loss of AC power (ELAP) concurrent with a loss of normal access to the normal heat sink (LUHS).
- Key safety functions (core cooling, containment, spent fuel pool cooling) are established and maintained indefinitely, or until sufficient site functional capabilities can be maintained without the need for mitigation strategies.
2 PM-0619-65964 Revision: O Copyright 2019 by NuScale Power, LLC.
W!:!!J.?.~!.tr Template#: 0000-21727-F01 R5
Indefinite Coping
- " ... indefinitely, or until sufficient site functional capabilities can be maintained without the need for mitigation strategies"
- Means to plan for obtaining sufficient resources to maintain the three key safety functions until an alternate means of removing heat is established
- Allows new reactors to "establish different approaches from those of operating reactors" including using only "installed plant equipment for both the initial and long-term response"
- "Alternate means of removing heat" may be provided by installed plant equipment.
3 PM-0619-65964 Revision: 0 Copyright 2019 by NuScale Power, LLC.
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Indefinite Coping
- NuScale considers a minimum coping period of 14 days using only installed plant equipment to be sufficient time to establish "alternate means of removing heat."
- In the Fukushima Daiichi accident, without pre-planning or a hardened pool makeup connection, and with limited access to off-site resources, personnel began
- adding water to the Unit 4 SFP with fire and concrete pump trucks after 9 days; and
- injecting water via the fuel pool cooling system at 14 days.
- Beyond minimum installed equipment coping period, the continued use of installed plant equipment, ad hoc resources, and equipment repairs can be used to continue coping indefinitely.
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4
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Template#: 0000-21727-F01 R5 II
NuScale Coping Capability 5
PM-0619-65964 Revision: O Copyright 2019 by NuScale Power, LLC.
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NuScale Power Plant Design
- The NuScale Power Plant was designed to provide coping during an ELAP concurrent with a LUHS without:
- AC or DC electrical power
- Inventory addition
- Supplemental equipment
- Off-site resources
- Operator action (monitoring)
- Extended coping duration is provided by the automatic response of installed plant equipment alone.
- This strategy permits plant staff to focus on addressing the initiating event and restoring normal functional capabilities.
6 PM-0619-65964
Powo, lo, ull hcmud;na Revision: O Copyright 2019 by NuScale Power, LLC.
Template#: 0000-21727-F01 R5
Baseline Coping Capability Criteria, Conditions, and Assumptions
- 1. Plant equipme nt that is designed to be robust with respect to design basis external events is assumed to be fully available.
- 2. Plant equipme nt that is not robust is assumed to be unavailable.
- 3. Procedures and equipment relied upon should ensure that satisfactory performance of necessary fuel cooling and containment functions are maintained.
- 4. The fuel in the modules is required to remain covered at all times.
- 5. The fuel in the SFP is required to remain covered at all times.
7 PM-0619-65964 Revision: o Copyright 2019 by NuScale Power, LLC.
N~\J.~.~~!::r Template#: 0000-21727-F01 RS
Boundary Conditions
- 1. Beyond-design-basis external event occurs impacting all modules at the site.
- 2. All modules on-site initially operating at power, unless site has procedural direction to shut down due to the impending event.
- 3. Each module is successfully shut down when required (i.e., all rods inserted, no anticipated transient without scram).
- 4. On-site staff is at site administrative minimum shift staffing, levels.
- 5. No independent, concurrent events, e.g., no active security threat.
- 6. All personnel on-site are available to support site response.
- 7. Spent fuel. in dry storage is outside the scope of the event.
8 PM-0619-65964 Revision: O Copyright 2019 by NuScale Power, LLC.
N~!J.?.fl~!::.r Template#: 0000-21727-F01 R5
NuScale Power Plant Response Plant response without operator action or off-site resources!
ECCS initiation SFP level-UHS level - Top of fuel
- DHRS UHS begins initiation to boil and UHS level-
- Containment level lowers Weir bottom isolation 24 5 30 50: 4 5 I
hours days days days1 months months Installed plant safety systems
- Passive containment heat removal I I
- Passive spent fuel heat removal .1 I "1
9 PM-0619-65964
Powe, lo* ull '"'nor.kind Revision: O Copyright 2019 by NuScale Power, LLC.
Template#: 0000-21727-F01 R5
Core Cooling
- DHRS passively removes decay heat for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- The ECCS cools the core for the remainder of an ELAP.
- Modules are partially immersed in the reactor pool, which is part of the UHS.
- Passive heat removal to the UHS maintains core cooling for more than 50 days without pool inventory makeup or operator action.
10 PM-0619-65964 Revision: O Copyright 2019 by NuScale Power, LLC.
N~.Y.~,~!.~r Template#: 0000-21727-F01 RS
Containment
- Containment isolation valves (CIVs) and the CNV provide
, passive containment function. Without operator action or electrical power, the safety-related CIVs close to isolate the CNV.
- Heat removal to the UHS passively controls temperature and pressure to ensure containment integrity. Peak pressure and temperature conditions for the CNV occur early in the event when the ECCS valves open and do not challenge containment integrity.
- Containment cooling is maintained for more than 50 days without pool inventory makeup or operator action.
11 PM-0619-65964 Revision: O Copyright 2019 by NuScale Power, LLC.
i-1 ~Y.~,!;~br Template#: 0000-21727-F01 R5
Spent Fuel Pool Cooling
- The Spent Fuel Pool is part of the UHS.
- The Spent Fuel Pool is partially separated from the Refuel and Reactor Pools by the Weir Wall.
Sp~nt Fuel Pool Refuel Pool Reactor Pool Ultimate ~eat Sink
,owo, lo , ull hsmud.lnd Revision : O Copyright 2019 by NuScale Power, LLC .
Temp late#: 0000-2 1727-F01 R5
Spent Fuel Pool Cooling
- The SFP, as part of the UHS, communicates with the refueling pool and reactor pool above the SFP weir wall.
As such, the pools respond as a single volume during an ELAP until UHS level lowers below the opening in the weir wall.
- The UHS inventory maintains passive cooling of the spent fuel in the SFP for more than 150 days following initiation of an ELAP without pool inventory makeup or operator action.
13 PM-0619-65964 Revision: O Copyright 2019 by NuScale Power, LLC.
N~!J.?.~~-~r Template#: 0000-21727-F01 RS
Monitoring
- No operator action is required to establish or maintain the required safety functions for more than 50 days following the onset of an ELAP. Therefore, no instrumentation is necessary to support operator actions.
- However, instrumentation and DC electrical power are provided to allow the Control Room Operators to observe the response of installed plant equipment and verify the conditions necessary for indefinite coping have been established.
- Indications remain available for a minimum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
14 PM-0619-65964
eowo, lo, all homuo,\h,d Revision: O Copyright 2019 by NuScale Power, LLC.
Template#: 0000-21727-F01 RS
Conclusion
- NuScale Power Plant Mitigation Strategy
- Rely on the automatic response of permanently installed, safety-related plant equipment to establish and maintain the three key safety functions and provide extended coping capabilities of greater than 14 days.
- The NuScale Power Plant mitigation strategy does not require:
- AC or DC electrical power
- Inventory addition
- Off-site resources
- Operator action 15 PM-0619-65964 Revision: O Copyright 2019 by NuScale Power, LLC.
M~!:'.~.~~h.r 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 SW1 E 5BH Rockville, MO 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://wwwnuscalepower. com
- Twitter: @NuScale_Power NUSCALE' Power for all humankind 16 PM-0619-65964 Revision: O Copyright 2019 by NuScale Power, LLC.
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Supplemental Slides (Description of slide 10) 17 PM-0619-65964 Revision: O Copyright 2019 by NuScale Power, LLC.
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Template#: 0000-21727-F01 R5
NuScale Power Plant Response
- NuScale Power Module response within the first minute of the loss of all AC power and without operator action:
- Reactor trip
- Decay Heat Removal System initiation
- Containment isolation
- ECCS automatically initiates after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- Decay heat passively transferred to the UHS.
18 PM-0619-65964 Revision: O Copyright 2019 by NuScale Power, LLC.
N~!:'.?.\:,~hr Template#: 0000-21727-F01 R5
NuScale Powe r Plant Response
- After more than 5 days, the UHS begins to boil and SFP level begins to lower.
- With UHS level greater than or equal to 45', core cooling and the containm ent function are maintained. It requires more than 50 days for UHS level to lower to this point.
- Without any addition of inventory, Spent Fuel Pool level would:
- Fall below the UHS weir after more than 4 months.
- Reach the top of spent fuel after more than 5 months.
19 PM-0619-65964 Revision: O Copyright 2019 by NuScale Power, LLC.
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NuScale Power Plant Response 80 70
- Pool Level 60
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- - Top of DHRS so
- - - - . - - - - .~ - - - - - - ---- - - - - - - - - - - - - - - -
- - Top f Weir/10 ft abov, SF in SFP
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0 20 40 60 80 100 120 140 160 Time (days) 20 PM-0619-65964 Revisio n: O Copyright 2019 by NuScale Power, LLC.
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