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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-1118-62983 November 19, 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 Supplemental Response to NRC Request for Additional Information No. 329 (eRAI No. 9270) on the NuScale Design Certification Application
REFERENCES:
- 1. U.S. Nuclear Regulatory Commission, "Request for Additional Information No. 329 (eRAI No. 9270)," dated January 08, 2018
- 2. NuScale Power, LLC Response to NRC "Request for Additional Information No. 329 (eRAI No.9270)," dated June 04, 2018
- 3. NuScale Power, LLC Supplemental Response to NRC "Request for Additional Information No. 329 (eRAI No. 9270)," dated September 05, 2018 The purpose of this letter is to provide the NuScale Power, LLC (NuScale) supplemental response to the referenced NRC Request for Additional Information (RAI).
The Enclosure to this letter contains NuScale's supplemental response to the following RAI Question from NRC eRAI No. 9270:
- 12.02-20 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.
~-~c:::---
Sincerely,
~~
/4~k~~y, W. 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 Supplemental Response to NRC Request for Additional Information eRAI No.9270 NuScale Power, LLC 1100 NE Circle Blvd. , Suite 200 Corvalis, Oregon 97330 , Office: 541.360.0500 , Fax: 541.207.3928 www.nuscalepower.com
RAIO-1118-62983 :
NuScale Supplemental Response to NRC Request for Additional Information eRAI No. 9270 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.: 9270 Date of RAI Issue: 01/08/2018 NRC Question No.: 12.02-20 The Regulatory Basis and Background are in RAI-9270 Quesiton 31001 Key Issue 2:
The methodology used by the applicant to calculate the tritium concentration in the RCS does not account for the buildup of tritium due to recycling of previously used RCS, therefore RCS tritium concentration appears to be underestimated. NuScale has proposed an alternative and potentially non-conservative design basis RCS tritium concentration value, which is used for determining airborne activity concentrations within the plant, without demonstrating that the health and safety of occupational workers is maintained and that the potential doses are ALARA for compliance with 10 CFR Part 20. Since airborne activity concentrations in equipment cubicles is more dependent on RCS activity concentrations, and less on ultimate heat sink (UHS) pool tritium concentration, the airborne tritium activity concentrations in equipment cells may be underestimated by over a factor of 3 Question 2:
To facilitate staff understanding of the application information sufficient to make appropriate regulatory conclusions with respect to the potential production of tritium in the RCS, the staff requests that the applicant:
Explain the use of an apparent non-conservative tritium value as discussed above, and Revise DCD Chapter 12.2 to use an RCS tritium concentration value of 1.3x10+5 Bq/gm (3.5 Ci/gm), or revise DCD Chapter 12.2 to use a calculated RCS tritium concentration supported by the associated, including methods, models and assumptions, for determining the RCS coolant concentration of tritium, consistent with the system NuScale Nonproprietary
description provided in DCD Tier 2 Revision 0, including sections in Chapters 9 and sections in Chapter 11, AND Revise DCD Section 12.2.2 Airborne Radioactive Material Sources, to reflect the changes to RCS tritium concentration and the associated bases, AND Revise DCD Table 12.2-32: Input Parameters for Determining Facility Airborne Concentrations, to reflect the revised methods, models and assumptions, AND Revised DCD Table 12.2-33: Reactor Building Airborne Concentrations, to reflect the changes to tritium concentrations, OR Provide the specific alternative approaches used and the associated justification.
NuScale Response:
The NuScale response to RAI 9270 (RAIO-0618-60288; dated June 4, 2018) included a revised Reactor Building airborne concentration, provided as FSAR Table 12.2-33. Some values in this table were found to be in error, as it pertains to the column listing the airborne concentrations in the air space above the reactor pool. These airborne concentrations have been corrected and are provided in this supplemental response.
Impact on DCA:
FSAR Table 12.2-33 has 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 Radiation Sources RAI 12.02-4, RAI 12.02-20 Table 12.2-33: Reactor Building Airborne Concentrations Radionuclide CVCS Pump / Valve Room Degasifier Room Air Space above Reactor Pool (Ci/ml) (Ci/ml) (Ci/ml)
Noble Gases Kr83m 1.49E-09 1.49E-09 1.94E-141.07E-13 Kr85m 6.92E-09 6.92E-09 -
Kr85 2.21E-06 2.21E-06 -
Kr87 3.20E-09 3.20E-09 -
Kr88 1.06E-08 1.06E-08 -
Kr89 3.56E-11 3.56E-11 -
Xe131m 2.86E-08 2.86E-08 2.07E-091.52E-08 Xe133m 2.61E-08 2.61E-08 3.32E-092.36E-08 Xe133 1.95E-06 1.95E-06 4.71E-083.35E-07 Xe135m 1.07E-09 1.07E-09 9.39E-106.21E-09 Xe135 6.37E-08 6.37E-08 5.22E-103.45E-09 Xe137 1.35E-10 1.35E-10 -
Xe138 1.20E-09 1.20E-09 -
Halogens Br82 1.95E-13 1.95E-13 2.79E-172.01E-16 Br83 9.82E-13 9.82E-13 -
Br84 3.16E-13 3.16E-13 -
Br85 7.73E-15 7.73E-15 -
I129 4.86E-18 4.86E-18 -1.23E-20 I130 1.54E-12 1.54E-12 4.37E-173.04E-16 I131 4.07E-11 4.07E-11 1.19E-128.73E-12 I132 1.64E-11 1.64E-11 3.00E-152.19E-14 I133 6.05E-11 6.05E-11 1.41E-131.01E-12 I134 7.89E-12 7.89E-12 -
I135 3.68E-11 3.68E-11 1.16E-167.67E-16 Cs, Rb Rb86m 1.09E-18 1.09E-18 -
Rb86 1.39E-13 1.39E-13 1.66E-151.28E-14 Rb88 5.71E-09 5.71E-09 -
Rb89 2.11E-11 2.11E-11 -
Cs132 2.67E-15 2.67E-15 2.80E-172.16E-16 Cs134 2.40E-11 2.40E-11 3.06E-132.37E-12 Cs135m 1.30E-14 1.30E-14 -
Cs136 5.08E-12 5.08E-12 5.89E-144.56E-13 Cs137 1.47E-11 1.47E-11 1.88E-131.46E-12 Cs138 4.66E-10 4.66E-10 -
Other FP P32 3.97E-19 3.97E-19 -1.85E-20 Co57 2.96E-21 2.96E-21 -
Sr89 2.37E-14 2.37E-14 1.21E-168.94E-16 Sr90 3.98E-15 3.98E-15 2.77E-172.04E-16 Sr91 8.88E-15 8.88E-15 2.51E-181.72E-17 Sr92 4.35E-15 4.35E-15 -
Y90 9.82E-16 9.82E-16 1.48E-171.10E-16 Tier 2 12.2-66 Draft Revision 3
NuScale Final Safety Analysis Report Radiation Sources Table 12.2-33: Reactor Building Airborne Concentrations (Continued)
Radionuclide CVCS Pump / Valve Room Degasifier Room Air Space above Reactor Pool (Ci/ml) (Ci/ml) (Ci/ml)
Y91m 5.00E-15 5.00E-15 1.60E-181.10E-17 Y91 2.57E-15 2.57E-15 1.77E-171.30E-16 Y92 4.19E-15 4.19E-15 1.92E-201.17E-19 Y93 1.90E-15 1.90E-15 6.39E-194.39E-18 Zr97 2.83E-15 2.83E-15 3.12E-182.20E-17 Nb95 4.20E-15 4.20E-15 1.17E-138.78E-14 Mo99 5.16E-12 5.16E-12 2.25E-141.64E-13 Mo101 8.08E-14 8.08E-14 -
Tc99m 4.79E-12 4.79E-12 2.17E-141.58E-13 Tc99 1.49E-16 1.49E-16 1.03E-187.60E-18 Ru103 4.96E-15 4.96E-15 3.34E-172.46E-16 Ru105 1.51E-15 1.51E-15 1.02E-206.42E-20 Ru106 3.22E-15 3.22E-15 2.23E-171.64E-16 Rh103m 4.90E-15 4.90E-15 3.30E-172.43E-16 Rh105 3.45E-15 3.45E-15 1.06E-177.69E-17 Rh106 3.22E-15 3.22E-15 2.23E-17 Ag110 2.16E-15 2.16E-15 1.47E-13 Sb124 7.31E-18 7.31E-18 4.97E-203.66E-19 Sb125 6.44E-17 6.44E-17 4.47E-193.29E-18 Sb127 2.78E-16 2.78E-16 1.39E-181.01E-17 Sb129 3.18E-16 3.18E-16 -1.27E-20 Te125m 9.46E-15 9.46E-15 6.43E-174.73E-16 Te127m 3.05E-14 3.05E-14 2.09E-161.54E-15 Te127 1.18E-13 1.18E-13 2.29E-161.67E-15 Te129m 8.73E-14 8.73E-14 5.84E-164.30E-15 Te129 1.08E-13 1.08E-13 3.68E-162.71E-15 Te131m 2.82E-13 2.82E-13 7.02E-165.05E-15 Te131 1.05E-13 1.05E-13 1.58E-161.14E-15 Te132 2.07E-12 2.07E-12 9.63E-157.03E-14 Te133m 1.29E-13 1.29E-13 -
Te134 1.68E-13 1.68E-13 -
Ba137m 1.39E-11 1.39E-11 1.77E-13 Ba139 3.75E-15 3.75E-15 -
Ba140 2.56E-14 2.56E-14 1.61E-161.18E-15 La140 7.58E-15 7.58E-15 1.14E-168.48E-16 La141 1.34E-15 1.34E-15 -2.22E-20 La142 5.66E-16 5.66E-16 -
Ce141 3.94E-15 3.94E-15 2.64E-171.94E-16 Ce143 2.95E-15 2.95E-15 8.07E-185.82E-17 Ce144 3.31E-15 3.31E-15 2.29E-171.69E-16 Pr143 3.50E-15 3.50E-15 2.34E-171.72E-16 Pr144 3.28E-15 3.28E-15 2.27E-171.67E-16 Np239 6.22E-14 6.22E-14 2.51E-161.82E-15 Crud Na24 6.42E-12 6.42E-12 5.69E-143.99E-14 Cr51 3.74E-13 3.74E-13 2.49E-111.83E-11 Tier 2 12.2-67 Draft Revision 3
NuScale Final Safety Analysis Report Radiation Sources Table 12.2-33: Reactor Building Airborne Concentrations (Continued)
Radionuclide CVCS Pump / Valve Room Degasifier Room Air Space above Reactor Pool (Ci/ml) (Ci/ml) (Ci/ml)
Mn54 1.93E-13 1.93E-13 1.33E-119.81E-12 Fe55 1.44E-13 1.44E-13 1.00E-117.37E-12 Fe59 3.61E-14 3.61E-14 2.44E-121.79E-12 Co58 5.54E-13 5.54E-13 3.78E-102.78E-10 Co60 6.37E-14 6.37E-14 4.43E-123.26E-12 Ni63 3.18E-14 3.18E-14 2.21E-121.63E-12 Zn65 6.13E-14 6.13E-14 4.24E-123.12E-12 Zr95 4.69E-14 4.69E-14 3.20E-122.35E-12 Ag110m 1.56E-13 1.56E-13 1.08E-117.97E-12 W187 3.30E-13 3.30E-13 6.27E-124.48E-12 Water Activation Products H3 4.04E-07 4.04E-07 1.61E-061.46E-06 C14 3.21E-11 3.21E-11 7.77E-126.34E-12 N16 0.00E+00 0.00E+00 -
Ar41 6.28E-08 6.28E-08 -
Note: Assumes the plant consists of 12 NPMs operating on a two-year refueling cycle.
Tier 2 12.2-68 Draft Revision 3