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Category:Letter
MONTHYEARML23180A1512023-06-29029 June 2023 LLC, Request for Exemption to the Reporting Requirements of 10 CFR 50.46(a)(3) ML21102A3072021-04-15015 April 2021 OEDO-21-00155 - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC, Small Modular Reactor ML21050A4312021-02-19019 February 2021 LLC - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC Small Modular Reactor ML20247J5642020-09-11011 September 2020 Standard Design Approval for the NuScale Power Plant Based on the NuScale 600 Standard Plant Design Certification Application ML20231A8042020-08-28028 August 2020 Final Safety Evaluation Report for the NuScale Standard Plant Design ML20224A4602020-08-25025 August 2020 OEDO-20-00292-Response to the Advisory Committee on Reactor Safeguards Letter on NuScale Power, LLC, Report on the Safety Aspects of the NuScale Small Modular Reactor ML20231A5982020-08-25025 August 2020 OEDO-20-00285_NuScale Area of Focus - Boron Redistribution ML20210M8902020-07-29029 July 2020 Area of Focus - Boron Redistribution ML20195A5872020-07-13013 July 2020 LLC - Submittal of Draft Operator Licensing and Examination Standard for NuScale Small Modular Reactors ML20195C7662020-07-13013 July 2020 LLC Request for Standard Design Approval Based on the NuScale Standard Plant Design Certification Application ML20192A3262020-07-10010 July 2020 LLC, Submittal of Environmental Report: Revision Status ML20198M3932020-07-0202 July 2020 LLC Submittal of Revised Packing Slip for Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1, Dated June 19, 2020 ML20174A3472020-07-0101 July 2020 OEDO-20-00220 - Area of Focus - Probabilistic Risk Assessment and Emergency Core Cooling System Valve Performance ML20184A2872020-07-0101 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 ML20181A4322020-06-22022 June 2020 Final SER for NuScale TR-0516-49416 NON-Loss-of-Coolant Analysis Model, Rev 3 (Letter) ML20181A2702020-06-22022 June 2020 Final SER for NuScale TR-0516-49422 Loss-of-Coolant Analysis Model, Rev 2 (Letter) ML20198M3922020-06-19019 June 2020 LLC - Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1 ML20171A7312020-06-19019 June 2020 LLC, Submittal of Riser Flow Hole Methodology and Associated Changes to Final Safety Analysis Report Incorporating Its Use ML20157A2232020-06-0303 June 2020 Letter to NuScale Requesting -A for TR-0716-50350 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 ML20150E1772020-05-29029 May 2020 LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Extended Dhrs Operation and RCS Boron Redistribution (Closed Session), PM-0620-70243, 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 ML20149M1192020-05-28028 May 2020 LLC Summary of Impacts to Erai 8930 Response and Discussion on the Exemption from General Design Criterion 33 ML20141L8082020-05-20020 May 2020 LLC Submittal of Containment Response Analysis Methodology Technical Report, TR-0516-49084, Revision 3 ML20141N0122020-05-20020 May 2020 LLC Submittal of Changes to Final Safety Analysis Report, Section 6.2, Containment Systems, Section 6.3, Emergency Core Cooling System, and Technical Report TR-0516-49084, Containment Response Analysis Methodology Technical Report ML20141M7642020-05-20020 May 2020 LLC Submittal of Nuclear Steam Supply System Advanced Sensor Technical Report, TR-0316-22048, Revision 3 ML20141L7872020-05-20020 May 2020 LLC, Submittal of Second Updates to Standard Plant Design Certification Application, Revision 4 ML20141L8162020-05-20020 May 2020 LLC, Submittal of Long-Term Cooling Methodology, TR-0916-51299, Revision 3 ML20141M1142020-05-20020 May 2020 LLC Submittal of NuScale Instrument Setpoint Methodology Technical Report, TR-0616-49121, Revision 3 ML20141L8042020-05-20020 May 2020 LLC Submittal of Technical Specifications Regulatory Conformance and Development, TR-1116-52011, Revision 4 ML20128J3162020-05-18018 May 2020 OEDO-20-00167 - Response to the ACRS Letter on Combustible Gas Monitoring ML20133K0882020-05-12012 May 2020 LLC, Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution (Closed Session), PM-0420-69512, 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 ML20112F4552020-05-0101 May 2020 LLC, Design Certification Application Phases 5 and 6 Review Status ML20107F8492020-05-0101 May 2020 OEDO-2000140 - NuScale Area of Focus - Helical Tube Steam Generator Design ML20104A0792020-04-27027 April 2020 OEDO-20-00115 - Safety Evaluation Report for Topical Report TR-0516-49416, Revision 2, Non-Loss-of-Coolant Accident Analysis Methodology 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 ML20098G2372020-04-0707 April 2020 Nuscale Power, LLC Submittal of Remaining Closure Items for the Emergency Core Cooling System Valve Failure Mode Effects Analysis Audit Items 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 ML20092L8992020-04-0101 April 2020 LLC - Submittal of Updates to Standard Plant Design Certification Application, Revision 4 ML20072M6682020-03-30030 March 2020 Response to NuScale Letter Dated February 24, 2020, on Planned SDA Application Content ML20072H3332020-03-0909 March 2020 LLC - Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution, PM-0320-69218, Revision 0 ML20057D9002020-03-0606 March 2020 Submittal of Errata to Final SE for NuScale Power, LLC TR-1010-859-NP-A, Quality Assurance Program Description for the NuScale Power Plant ML20062F7262020-03-0505 March 2020 Request for Withholding Information from Public Disclosure for Nuscale Power, LLC Letter Public ML20069A1572020-03-0404 March 2020 LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Rod Ejection Accident Methodology, PM-0320-69146, Revision 0 ML20069A1772020-03-0404 March 2020 LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Non-Loss-of-Coolant Accident, PM-0320-69141, Revision 0 ML20069A9632020-03-0404 March 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report, Loss-of-Coolant Accident Evaluation Model, PM-0320-69138, 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 ML20066G2882020-02-28028 February 2020 LLC Submittal of Presentation Materials Titled ACRS Full Committee Presentation: NuScale - Steam Generator Design (Closed Session), PM-0220-69053, Revision 0 2023-06-29
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRAIO-0420-69855, LLC, Submittal of Corrected Response to NRC Request for Additional Information No. 284 (Erai No. 9225) on the NuScale Design Certification2020-04-30030 April 2020 LLC, Submittal of Corrected Response to NRC Request for Additional Information No. 284 (Erai No. 9225) on the NuScale Design Certification ML19332A1202019-11-27027 November 2019 LLC Supplemental Response to NRC Request for Additional Information No. 484 (Erai No. 8930) on the NuScale Design Certification Application ML19304B4712019-10-31031 October 2019 LLC Supplemental Response to NRC Request for Additional Information No. 466 (Erai No. 9482) on the NuScale Design Certification Application ML19296D8052019-10-23023 October 2019 LLC Response to NRC Request for Additional Information No. 526 (Erai No. 9719) on the NuScale Design Certification Application ML19283E5302019-10-10010 October 2019 LLC Supplemental Response to NRC Request for Additional Information No. 522 (Erai No. 9681) on the NuScale Design Certification Application ML19260G7352019-10-0707 October 2019 Summary of Public Meeting with NuScale to Discuss Response to RAI 9681 ML19266A5872019-09-23023 September 2019 LLC Supplemental Response to NRC Request for Additional Information No. 518 (Erai No. 9659) on the NuScale Design Certification Application ML19262G9742019-09-19019 September 2019 LLC - Submittal of Changes to Final Safety Analysis Report, Tier 1, Section 3.11, Reactor Building and Section 3.13, Control Building, and Tier 2, Section 3.8.4, Design of Category I Structure and Section 14.3, Certified ... ML19262G5762019-09-19019 September 2019 LLC - Submittal of Changes to Final Safety Analysis Report, Section 14.2, Initial Plant Test Program, Table 14.2-2, Pool Cleanup Systems Test #2, and Table 14.2-50, Module Assembly Equipment Test #50 ML19259B8102019-09-16016 September 2019 LLC Supplemental Response to NRC Request for Additional Information No. 205 (Erai No. 9044) on the NuScale Design Certification Application ML19259A0922019-09-16016 September 2019 LLC Response to NRC Request for Additional Information No. 525 (Erai No. 9705) on the NuScale Design Certification Application ML19238A3722019-08-26026 August 2019 LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application ML19238A3662019-08-23023 August 2019 LLC - Response to NRC Request for Additional Information No. 523 (Erai No. 9682) on the NuScale Design Certification Application ML19215A0032019-08-0202 August 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on the NuScale Design Certification Application ML19215A0062019-08-0202 August 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 441 (Erai No. 9485) on the NuScale Design Certification Application ML19212A7622019-07-31031 July 2019 LLC Response to NRC Request for Additional Information No. 523 (Erai No. 9682) on the NuScale Design Certification Application ML19212A3752019-07-31031 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 483 (Erai No. 9516) on the NuScale Design Certification Application ML19212A7992019-07-31031 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 427 (Erai No. 9408) on the NuScale Design Certification Application ML19212A6892019-07-31031 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 205 (Erai No. 9044) on the NuScale Design Certification Application ML19210D1592019-07-29029 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 401 (Erai No. 9447) on the NuScale Design Certification Application ML19210D7342019-07-29029 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 520 (Erai No. 9642) on the NuScale Design Certification Application ML19210E1462019-07-29029 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application ML19207B3812019-07-26026 July 2019 LLC - Response to NRC Request for Additional Information No. 427 (Erai No. 9408) on the NuScale Design Certification Application ML19207A5342019-07-26026 July 2019 LLC - Response to NRC Request for Additional Information No. 523 (Erai No. 9682) on the NuScale Design Certification Application ML19207B8522019-07-25025 July 2019 LLC Response to NRC Request for Additional Information No. 194 (Erai No. 8884) on the NuScale Design Certification Application ML19203A3152019-07-22022 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 325 (Erai No. 9268) on the NuScale Design Certification Application ML19203A3212019-07-22022 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 333 (Erai No. 9282) on the NuScale Design Certification Application ML19203A3092019-07-22022 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 54 (Erai No. 8837) on the NuScale Design Certification Application ML19203A3422019-07-22022 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 154 (Erai No. 8938) on the NuScale Design Certification Application ML19200A2482019-07-19019 July 2019 LLC Response to NRC Request for Additional Information No. 522 (Erai No. 9681) on the NuScale Design Certification Application ML19200A2082019-07-19019 July 2019 LLC - Response to NRC Request for Additional Information No. 524 (Erai No. 9691) on the NuScale Design Certification Application ML19199A1172019-07-18018 July 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 484 (Erai No. 8930) on the NuScale Design Certification Application ML19198A3252019-07-17017 July 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 249 (Erai No. 9135) on the NuScale Design Certification Application ML19196A3682019-07-15015 July 2019 LLC Response to NRC Request for Additional Information No. 516 (Erai No. 9647) on the NuScale Design Certification Application ML19191A2202019-07-10010 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application ML19184A6152019-07-0303 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 386 (Erai No. 9316) on the NuScale Design Certification Application ML19176A5802019-06-25025 June 2019 LLC Supplemental Response to NRC Request for Additional Information No. 232 (Erai No. 9113) on the NuScale Design Certification Application ML19170A3702019-06-19019 June 2019 LLC Supplemental Response to NRC Request for Additional Information No. 232 (Erai No. 9113) on the NuScale Design Certification Application ML19168A2442019-06-17017 June 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 325 (Erai No. 9268) on the NuScale Design Certification Application ML19164A1452019-06-13013 June 2019 LLC - Submittal of Containment Response Analysis Methodology Technical Report, TR-0516 -49 08 4, Revision 1 ML19157A3262019-06-0606 June 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 232 (Erai No. 9113) on the NuScale Design Certification Application ML19154A6222019-06-0303 June 2019 LLC Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on the NuScale Design Certification Application ML19154A6052019-06-0303 June 2019 LLC Response to NRC Request for Additional Information No. 514 (Erai No. 9645) on the NuScale Design Certification Application ML19151A8372019-05-31031 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 377 (Erai No. 9380) on the NuScale Design Certification Application ML19140A4592019-05-20020 May 2019 LLC Supplemental Response to NRC Request for Additional Information No. 401 (Erai No. 9447) on the NuScale Design Certification Application ML19137A2902019-05-17017 May 2019 LLC Supplemental Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application ML19137A2872019-05-15015 May 2019 LLC Response to NRC Request for Additional Information No. 519 (Erai No. 9656) on the NuScale Design Certification Application ML19126A2942019-05-0606 May 2019 LLC Supplemental Response to NRC Request for Additional Information No. 26 (Erai No. 8840) on the NuScale Design Certification Application ML19122A5092019-05-0202 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 494 (Erai No. 9548)on the Design Certification Application ML19121A6002019-05-0101 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on Design Certification Application 2020-04-30
[Table view] |
Text
RAIO-0818-61452 August 17, 2018 Docket No.52-048 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738
SUBJECT:
NuScale Power, LLC Response to NRC Request for Additional Information No.
322 (eRAI No. 9239) on the NuScale Design Certification Application
REFERENCE:
U.S. Nuclear Regulatory Commission, "Request for Additional Information No.
322 (eRAI No. 9239)," dated January 08, 2018 The purpose of this letter is to provide the NuScale Power, LLC (NuScale) response to the referenced NRC Request for Additional Information (RAI).
The Enclosure to this letter contains NuScale's response to the following RAI Question from NRC eRAI No. 9239:
- 11.02-2 This letter and the enclosed response make no new regulatory commitments and no revisions to any existing regulatory commitments.
If you have any questions on this response, please contact Carrie Fosaaen at 541-452-7126 or at cfosaaen@nuscalepower.com.
Sincerely,
~~
/ 4c~;r~ ~- Rad Director, Regulatory Affairs NuScale Power, LLC Distribution: Gregory Cranston, NRC, OWFN-8G9A Samuel Lee, NRC, OWFN-8G9A Getachew Tesfaye, NRC, OWFN-8H12 Enclosure 1: NuScale Response to NRC Request for Additional Information eRAI No. 9239 NuScale Power, LLC 1100 NE Circle Blvd. , Suite 200 Corvalis, Oregon 97330 , Office: 541.360.0500 , Fax: 541.207.3928 www.nuscalepower.com
RAIO-0818-61452 :
NuScale Response to NRC Request for Additional Information eRAI No. 9239 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com
Response to Request for Additional Information Docket No.52-048 eRAI No.: 9239 Date of RAI Issue: 01/08/2018 NRC Question No.: 11.02-2 11.2 RAI - Determining the basis for the dilution flow rates.
Regulatory Basis: 10 CFR Part 20, Appendix B; 10 CFR Part 50, Appendix I 10 CFR Part 20, Appendix B, Table 2 provides concentration limits for airborne and liquid effluents released to the general environment. 10 CFR Part 50, Appendix I provides the numerical guidance for design objectives and limiting conditions for operation.
Key Issue:
There is not sufficient information in the DCD regarding the dilution flows that are needed to determine effluent concentrations released are within regulatory limits Questions
- 1. In review of DCD section 11.2.3.3, the staff requests additional information for the stated dilution flows referenced by the applicant in DCD Section 11.2.3.3, and DCD Table 11.2-4.
The dilution flows are needed to determine the effluent concentrations released by the applicant for compliance with 10 CFR Part 20, Appendix B; and 10 CFR Part 50, Appendix I.
As discussed during the audit, the applicant references 5.56 cfs for the UWS dilution flow, and 740 cfs for the offsite dilution factor. DCD section 11.2.3.3 provides a pointer to DCD section 9.2.9, but the staff is unable to find any stated flow rates that feed into the 5.56 cfs dilution flow value. The staff requests explanation for the basis of the flow rates used for both 10 CFR Part 20 Appendix B Table 2, and 10 CFR Part 50 Appendix I compliance. In the audit it was discussed that the 740 cfs values was based on an assumed river dilution. The staff would need such assumptions to be stated in the DCD for the staff to understand the basis for the developed dilution flows.
- 2. The staff requests the applicant to provide and list the flow rate inputs used in DCD Section 11.2 to determine the 5.56 cfs flow rate value from the UWS. In addition, the staff requests the applicant to clearly state the assumption for the 740 cfs flow rate value as NuScale Nonproprietary
was discussed during the audit. The staff request the applicant clearly state assumptions in the DCD and provide a markup of the DCD in response to this RAI.
NuScale Response:
During the effort to respond to this RAI, errors were discovered that impact some of the flow rate values listed below. These values have been corrected and the FSAR has been updated accordingly.
As described in FSAR Section 11.2.3.3, the utility water system (UWS) is credited for a dilution flow of 5.34 cubic feet per second (2398 gpm), which is the total normal volumetric flow rate to the UWS single point discharge, as summarized below.
UWS Discharge Inputs Normal Flow Rate (gpm)
Cooling Tower A blowdown 1060 Cooling Tower B blowdown 1060 Site Cooling Water Tower blowdown 211 BOP Drain Collection Tank 55 Treated Sanitary discharge 10 LRWS discharge 1.3 TOTAL = 2398 The assumed offsite dilution flow of 270 cfs is the minimum required additional flow from an offsite water source (e.g., river) to ensure compliance with 10 CFR 50 Appendix I, for liquid effluents from a NuScale facility.
Impact on DCA:
FSAR Section 11.2.3.3 Table 11.2-7 and Table 11.2-8 have been been revised as described in the response above and as shown in the markup provided in this response.
NuScale Nonproprietary
NuScale Final Safety Analysis Report Liquid Waste Management System 11.2.3.3 Dilution Factors The liquid effluent from LRWS is discharged through the discharge header and ties into the UWS as shown in Figure 11.2-1g. The UWS receives discharge water from multiple sources that provides dilution for the LRWS discharge in the discharge basin (Section 9.2.9). The UWS also provides a signal to LRWS in the event that dilution flow reduces to an unacceptable level to automatically close the LRWS discharge header isolation valves (Section 11.5.2.1).
RAI 02.03.01-2, RAI 02.03.05-1, RAI 11.02-2 A dilution factor of 5.565.34 cfs of the LRWS discharge is assumed in the calculation of the site boundary (Section 2.3.4 and Figure 1.2-4)discharge concentrations, as shown in Table 11.2-4. This ensures that the discharge site boundary concentrations are within 10 CFR 20 Appendix B, Table 2, limits. The offsiteunrestricted area doses are calculated using an additional dilution factor of 740270 cfs (e.g., river), which results in the offsiteunrestricted area doses being within 10 CFR 50, Appendix I, limits.
COL Item 11.2-4: A COL applicant that references the NuScale Power Plant design certification will perform a site-specific evaluation using the site-specific dilution flow.
11.2.3.4 Site-Specific Cost-Benefit Analysis COL Item 11.2-5: A COL applicant that references the NuScale Power Plant design certification will perform a cost-benefit analysis as required by 10 CFR 50.34a and 10 CFR 50, Appendix I, to demonstrate conformance with regulatory requirements. This cost-benefit analysis is to be performed using the guidance of Regulatory Guide 1.110.
11.2.4 Testing and Inspection Requirements The LRWS preoperational tests are described in Section 14.2 and include the applicable testing and inspection requirements from RG 1.143.
Inspection and testing provisions are incorporated to enable periodic evaluation of the operability and required functional performance of active components of the system.
11.2.5 Instrumentation and Controls The LRWS waste collection is operated in the automatic mode and LRWS processing is operated in a batch-type mode. For normal operation, automated and manual valves are aligned to collect the waste from other systems, hold it until processed, and discharge or recycle treated waste.
The LRWS processing functions that use mobile radioactive waste processing equipment and interfacing-permanent-plant LRWS equipment are controlled and monitored from the WMCR by an operator. Mobile radioactive waste processing equipment skids are controlled from local control panels.
The permanent plant controls and indications for filling waste collection tanks are automatic and are controlled by the plant control system with indication in the WMCR. The Tier 2 11.2-16 Draft Revision 2
NuScale Final Safety Analysis Report Liquid Waste Management System RAI 11.02-2 Table 11.2-7: LADTAP II Inputs Parameter Value Source term Table 11.2-6 Shore-width factor 1.0 Discharge flow rate 740270 ft3/sec Impoundment reconcentration model None Irrigation rate 100 liters/m2-month Dilution factor for aquatic food, boating, shoreline, swimming and drinking water 1 Dilution factor for irrigation water usage location 1 Site type Freshwater Exposure Pathway:
- Transit time - aquatic food 0
- Transit time - swimming 0
- Transit time - shoreline 0
- Transit time - drinking water 0
- Transit time - irrigated crops 0
- Transit time - milk/meat animal water usage 0 Fraction of crops irrigated using non-contaminated water 0 Fraction of milk/meat animal feed irrigated using non-contaminated water 0 Fraction of milk/meat animal drinking water from non-contaminated water 0 Tier 2 11.2-29 Draft Revision 2
NuScale Final Safety Analysis Report Liquid Waste Management System RAI 11.02-2 Table 11.2-8: Liquid Effluent Dose Results for 10 CFR 50 Appendix I Pathway Total Body GI Tract Bone Liver Kidney Thyroid Lung Skin (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr)
[Limit] [Limit] [Limit] [Limit] [Limit] [Limit] [Limit] [Limit]
Drinking Adult 1.41E-01 1.50E-01 3.58E-02 1.54E-01 1.20E-01 1.52E-01 1.08E-01
[3] [10] [10] [10] [10] [10] [10]
Teen 9.32E-02 1.06E-01 3.43E-02 1.21E-01 8.87E-02 1.14E-01 7.81E-02
[3] [10] [10] [10] [10] [10] [10]
Child 1.60E-01 1.71E-01 9.92E-02 2.37E-01 1.71E-01 2.40E-01 1.50E-01
[3] [10] [10] [10] [10] [10] [10]
Infant 1.50E-01 1.56E-01 9.99E-02 2.57E-01 1.70E-01 2.96E-01 1.50E-01
[3] [10] [10] [10] [10] [10] [10]
Fish Adult 2.16E+00 7.27E-01 3.03E+00 2.96E+00 9.62E-01 2.29E-02 3.19E-01
[3] [10] [10] [10] [10] [10] [10]
Teen 1.25E+00 5.33E-01 3.25E+00 3.05E+00 9.77E-01 2.10E-02 3.77E-01
[3] [10] [10] [10] [10] [10] [10]
Child 5.39E-01 2.01E-01 4.09E+00 2.67E+00 8.26E-01 2.13E-02 2.98E-01
[3] [10] [10] [10] [10] [10] [10]
Shoreline Adult 1.95E-02 1.95E-02 1.95E-02 1.95E-02 1.95E-02 1.95E-02 1.95E-02 2.28E-02
[3] [10] [10] [10] [10] [10] [10] [10]
Teen 1.09E-01 1.09E-01 1.09E-01 1.09E-01 1.09E-01 1.09E-01 1.09E-01 1.27E-01
[3] [10] [10] [10] [10] [10] [10] [10]
Child 2.27E-02 2.27E-02 2.27E-02 2.27E-02 2.27E-02 2.27E-02 2.27E-02 2.66E-02
[3] [10] [10] [10] [10] [10] [10] [10]
Vegetables Adult 2.97E-01 3.29E-01 2.13E-01 3.76E-01 1.75E-01 9.62E-02 1.07E-01
[3] [10] [10] [10] [10] [10] [10]
Teen 2.97E-01 4.03E-01 3.55E-01 5.85E-01 2.56E-01 1.24E-01 1.53E-01
[3] [10] [10] [10] [10] [10] [10]
Child 3.13E-01 3.81E-01 8.42E-01 9.77E-01 4.12E-01 2.10E-01 2.37E-01
[3] [10] [10] [10] [10] [10] [10]
Leafy Vegetables Adult 3.68E-02 4.16E-02 2.65E-02 4.67E-02 2.17E-02 1.78E-02 1.31E-02
[3] [10] [10] [10] [10] [10] [10]
Teen 2.00E-02 2.76E-02 2.39E-02 3.93E-02 1.72E-02 1.30E-02 1.02E-02
[3] [10] [10] [10] [10] [10] [10]
Child 1.58E-02 1.95E-02 4.27E-02 4.90E-02 2.07E-02 1.76E-02 1.19E-02
[3] [10] [10] [10] [10] [10] [10]
Meat Adult 4.25E-02 1.33E+00 4.28E-02 4.85E-02 6.34E-02 1.68E-02 1.97E-02
[3] [10] [10] [10] [10] [10] [10]
Teen 2.31E-02 8.26E-01 3.55E-02 3.56E-02 4.91E-02 1.01E-02 1.31E-02
[3] [10] [10] [10] [10] [10] [10]
Tier 2 11.2-30 Draft Revision 2
NuScale Final Safety Analysis Report Liquid Waste Management System Table 11.2-8: Liquid Effluent Dose Results for 10 CFR 50 Appendix I (Continued)
Pathway Total Body GI Tract Bone Liver Kidney Thyroid Lung Skin (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr) (mrem/yr)
[Limit] [Limit] [Limit] [Limit] [Limit] [Limit] [Limit] [Limit]
Child 2.41E-02 5.09E-01 6.58E-02 4.51E-02 6.31E-02 1.26E-02 1.57E-02
[3] [10] [10] [10] [10] [10] [10]
Milk Adult 2.31E-01 7.59E-02 1.62E-01 3.01E-01 1.28E-01 8.11E-02 7.18E-02
[3] [10] [10] [10] [10] [10] [10]
Teen 2.38E-01 9.54E-02 2.89E-01 5.04E-01 2.04E-01 1.16E-01 1.13E-01
[3] [10] [10] [10] [10] [10] [10]
Child 2.26E-01 1.16E-01 6.90E-01 8.42E-01 3.28E-01 2.07E-01 1.75E-01
[3] [10] [10] [10] [10] [10] [10]
Infant 2.12E-01 1.06E-01 6.95E-01 9.11E-01 3.25E-01 2.55E-01 1.74E-01
[3] [10] [10] [10] [10] [10] [10]
Total Adult 2.93E+00 2.67E+00 3.53E+00 3.91E+00 1.49E+00 4.06E-01 6.58E-01 2.28E-02
[3] [10] [10] [10] [10] [10] [10] [10]
Teen 2.03E+00 2.10E+00 4.09E+00 4.44E+00 1.70E+00 5.07E-01 8.54E-01 1.27E-01
[3] [10] [10] [10] [10] [10] [10] [10]
Child 1.30E+00 1.42E+00 5.86E+00 4.85E+00 1.85E+00 7.32E-01 9.10E-01 2.66E-02
[3] [10] [10] [10] [10] [10] [10] [10]
Infant 3.63E-01 2.62E-01 7.95E-01 1.17E+00 4.95E-01 5.51E-01 3.24E-01 0.00E+00
[3] [10] [10] [10] [10] [10] [10] [10]
Tier 2 11.2-31 Draft Revision 2
NuScale Final Safety Analysis Report Liquid Waste Management System RAI 11.02-2 Table 11.2-9: Liquid Effluent Dose Results for 10 CFR 50 Appendix I 10 CFR 50, Appendix I ALARA Design Calculated Dose Objective Type of Dose (mrem/yr) (mrem/yr)
Total Body 2.8 3 Individual Organ 9.8 (child bone) 10 Tier 2 11.2-32 Draft Revision 2