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Category:Meeting Summary
MONTHYEARML24004A0472024-01-31031 January 2024 U.S. Nuclear Regulatory Commission Summary of the November 16, 2023, Observation Public Meeting to Discuss NuScales Us600 Exemption Request ML20274A1082020-09-30030 September 2020 Summary of September 16, 2020 Public Meeting with NuScale Power, LLC to Discuss Operator Licensing Topics ML20216A5462020-08-19019 August 2020 Public Summary of the July 15, 2020 Pre-Submittal Meeting with NuScale, LLC, Regarding Its Plans to Submit a Topical Report Using Automated Test System ML20219A4112020-08-10010 August 2020 Summary of the May 28, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss Nuscale'S Standard Design Application Control Room Staffing Topical Report-0520-69851 ML20108F5082020-05-27027 May 2020 Summary of April 15 2020 Public Meeting on NuScale EPZ Sizing Methodology TR ML20114E2162020-05-0404 May 2020 Summary of the April 1, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution of the Design Certification Application ML20114E0192020-04-27027 April 2020 Summary of the April 15, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution of the Design Certification Application ML20114E0392020-04-23023 April 2020 Meeting Summary for the April 21, 2020, Public Meeting to Discuss NuScale SDA Significance Review Process ML20097C2292020-04-0707 April 2020 Summary of the March 9, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution ML20072M7982020-03-19019 March 2020 Meeting Summary for the January 30, 2020, Public Meeting to Discuss NuScale SDA Regulatory Engagement Plan ML20072K5232020-03-11011 March 2020 Summary of the September 4, 2019, Public Teleconference with NuScale Power, Llc., Regarding Responses to Staff Requests for Additional Information (RAI) (52-048) ML19345E9362020-01-13013 January 2020 Summary of the December 9, 2019, Public Teleconference Meeting on Incorporation by Reference ML19302E4602019-10-29029 October 2019 July 22, 2019 Public Meeting - NuScale Interface Items for Penetrations and Ventilation Ducts ML19297C8772019-10-24024 October 2019 Summary of Public Meeting with NuScale to Discuss ECCS Test #47 ML19291A8872019-10-21021 October 2019 U.S. Nuclear Regulatory Commission Summary Report of Regulatory Close-out Audit of NuScale Power, LLC, Component Design Specification ML19282B1202019-10-12012 October 2019 Summary of January 9, March 5, April and August 1, 2019, Public Teleconference with NuScale Power, LLC, Regarding NON-LOCA TR RAI Responses (PROJ0769) ML19289C3982019-10-12012 October 2019 Summary of the January 9, 2019, March 5, 2019, April 23, 2019, and August 12, 2019, Public Teleconferences with NuScale Power, LLC ML19281B3982019-10-10010 October 2019 Summary of September 23, 2019 - Public Teleconference on NuScale Chapter 4 ML19281B2612019-10-0909 October 2019 Sept 25, 2019 - Public Teleconference on NuScale SDA ML19260G7352019-10-0707 October 2019 Summary of Public Meeting with NuScale to Discuss Response to RAI 9681 ML19240A3892019-10-0303 October 2019 Summary of January 8 and 29, 2019 and April 17, 2019, Public Teleconference with NuScale Power, LLC, Regarding Responses to Staff Request for Additional Information (52-048) ML19256B7002019-09-23023 September 2019 Summary of Public Meeting with NuScale to Discuss Test #107 and Test #47 in the Initial Test Program ML19260G5382019-09-23023 September 2019 Summary of 9-4-19 Public Meeting with NuScale to Discuss ITAAC ML19256B4942019-09-18018 September 2019 Summary of Public Meeting with NuScale to Discuss Radiation Shielding ITAAC ML19247C0342019-09-18018 September 2019 Summary of August 26 2019 Public Meeting with NuScale on Chapter 20 ML19252A0212019-09-12012 September 2019 August 27, 2019, Summary of Public Meeting with NuScale to Discuss Test #6, Test #47, and Test #50 in the Initial Test Program ML19255D2722019-09-12012 September 2019 Aug 26, 2019, Summary of Public Teleconference on NuScale Chapter 4 ML19242B8092019-08-30030 August 2019 Discussion Topic for August 13 and August 19, 2019, Public Meeting to Discuss AST Methodology and H2 and O2 Monitoring for the NuScale Design Certification Application ML19242B8802019-08-30030 August 2019 Discussion Topic for July 24, 2019, Public Meeting to Discuss Technical Specifications for the NuScale Design Certification Application ML19242B9932019-08-30030 August 2019 Discussion Topic May 14, 2019, Public Meeting to Discuss Accident Source Term (AST) Methodology Associated with the NuScale Design Certification Application ML19242C0162019-08-30030 August 2019 Discussion Topic May 8, 2019, Public Meeting to Discuss Post-Accident Sampling Exemption Request Associated with the NuScale Design Certification Application ML19242C4792019-08-30030 August 2019 Discussion Topics for the March 12 2019 Public Meeting to Discuss Neutron Absorbers ITAAC and COL Information Item 9.1-8 Associated with the NuScale Design Certification Application ML19228A2502019-08-27027 August 2019 Summary of Public Meeting with NuScale to Discuss Structural ITAAC ML19217A3082019-08-15015 August 2019 Summary of Public Meeting with NuScale to Discuss Initial Test Program Test #107 for the Remote Shutdown Workstation ML19212A6882019-08-12012 August 2019 Summary of Public Meeting with NuScale to Discuss Structural ITAAC ML19199A0152019-07-31031 July 2019 Summary of Public Meeting on Various ITAAC Issues ML19149A5052019-07-22022 July 2019 May 22 2019 NRC-NuScale Public Meeting Summary_Reduced Staffing Plan Validation Activities ML19171A1292019-07-17017 July 2019 Summary of Category 1 Public Teleconference with NuScale Power, LLC to Discuss of Section 3.9.4 Control Rod Drive System of the Design Certification Application ML19134A3632019-07-0808 July 2019 Summary of the April 9, 2019 Public Meeting to Discuss Accident Source Term (AST) Methodology and Post Exemption Associated with the NuScale Design Certification Application ML19176A2502019-07-0808 July 2019 Summary of June 17, 2019 Public Meeting with NuScale on MBDBE ML19178A3502019-06-27027 June 2019 Discussion Topics for April 09, 2019 Public Meeting with NuScale - Public Version ML19242B9342019-06-12012 June 2019 Discussion Topic for June 12, 2019, Public Meeting to Discuss Technical Specifications for the NuScale Design Certification Application ML19151A3382019-06-0505 June 2019 Summary of Public Meeting with NuScale to Discuss ITAAC for the Module Protection System and Safety Display and Indication System ML19087A2402019-05-0606 May 2019 Summary of March 5, 2019 Public Meeting on NuScale EPZ Sizing Methodology TR ML19106A0452019-04-24024 April 2019 Summary of Public Teleconference Held April 15, 2019, Regarding the Inspections, Tests, Analyses, and Acceptance Criteria in NuScale Power Llc'S Design Certification Application ML18340A0132019-04-17017 April 2019 July 24, 2018, Summary of Category 1 Public Teleconference with Nuscale Power, LLC, Design Certification Application Section 3.7, Seismic Design, and 3.8, Design of Category I Structures. ML18348A9442019-04-17017 April 2019 Summary of the Category 1 Public Teleconference with NuScale Power, LLC Design Certification Application Section 3.6.3, Leak-Before-Break Evaluation Procedures, and Section 3.9.4, Control Rod Drive System. ML18333A3612019-04-11011 April 2019 & 08/28/18 Summary of Public Teleconference with Nuscale Power, LLC, Regarding Responses to Staff Requests for Additional Information ML19065A1242019-04-0505 April 2019 Summary of the February 14 and 27, 2019, Public Meeting to Discuss Accident Source Term (AST) Methodology Associated with the Nuscale Design Certification Application ML19085A0412019-03-26026 March 2019 02/13/2019 and 03/06/2019 Summary of Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Progress on Emergency Core Cooling System Valve Test Plans of the Design Certification Application 2024-01-31
[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
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August 23, 2018 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors FROM: Getachew Tesfaye, Senior Project Manager /RA/
Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors
SUBJECT:
SUMMARY
OF THE JULY 26, 2018, CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION The U.S. Nuclear Regulatory Commission (NRC) held a Category 1 public teleconference on July 26, 2018, to discuss responses to the NRC staff requests for additional information associated with the NuScale Power, LLC (NuScale) design certification application. Participants included personnel from NuScale and a member of the general public.
The public meeting notice dated July 26, 2018, can be found in the NRCs Agencywide Documents Access and Management Systems under Accession No. ML18213A035. This meeting notice was also posted on the NRC public Web site.
Enclosed is the meeting agenda (Enclosure 1), list of participants (Enclosure 2), and overview (Enclosure 3).
Docket No.: 52-048
Enclosures:
- 1. Meeting Agenda
- 2. List of Attendees
- 3. Meeting Overview cc w/encl.: DC NuScale Power, LLC Listserv CONTACT: Getachew Tesfaye, NRO/DLSE 301-415-8013
ML18220A996 NRO-002 OFFICE DLSE/LB1:PM DLSE /LB1:LA DLSE/RPAC DNRL/LB1:PM NAME GTesfaye SGreen EStutzcage* GTesfaye (signed)
DATE 8/02/2018 8/22/2018 8/10/2018 8/23/2018 U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION MEETING AGENDA July 26, 2018 1:00 - 1:15 PM Introductions and Identification of topics 1:15 - 2:30 PM Discussion of U.S. Nuclear Regulatory Commission Staffs Questions regarding NuScale Power, LLCs Responses to Requests Additional Information (RAI) 9303 and 9294.
2:30 - 2:45 PM Public Comments/Questions 2:45 - 3:30 PM Discussion of NuScale Power LLCs Responses to RAI 9270 (Closed meeting) 3:30 Meeting Closure Enclosure 1
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION LIST OF ATTENDEES July 26, 2018 Name Organization Getachew Tesfaye U.S. Nuclear Regulatory Commission (NRC)
Ronald LaVera NRC Zachary Gran NRC Michael Dudek NRC Edward Stutzcage NRC Carrie Fosaaen NuScale Power, LLC (NuScale)
Chris Maxwell NuScale Edan Engstrom NuScale Jon Bristol NuScale Scott Harris NuScale Mark Shaver NuScale Elizabeth English NuScale Jim Osborn NuScale Sara Fields Member of the public Enclosure 2
U.S. NUCLEAR REGULATORY COMMISSION OVERVIEW OF THE JULY 26, 2018, TELECONFERENCE TO DISCUSS THE NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION The purpose of this teleconference was to discuss the results of the U.S. Nuclear Regulatory Commission (NRC) staffs review of NuScale Power, LLCs (NuScale) Responses to Requests for Additional Information (RAI) 9303, 9294, and 9270.
The following is the summary of the NRC staffs feedback and agreed upon next steps for the resolution of the remaining issues.
- 1. RAI 9303, Question 12.03-52:
- a. NRC Feedback: In the response to RAI 9303, Question 12.03-52, NuScale indicates that an Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) verifying that the NuScale radioactive waste systems are designed and constructed in accordance with Regulatory Guide (RG) 1.143, is unnecessary because:
- The NuScale radioactive waste systems do not have any safety-related or risk-significant functions.
- The NuScale radioactive waste systems do not support the safety or risk-significant functions of another system.
- The radioactive waste systems do not contain top-level design features, as described in Final Safety Analysis Report (FSAR) Section 14.3.2.1.1, for shielding that protects the health and safety of workers.
- The health and safety of the public is protected by ITAAC that ensure high radiation will be contained within the Radioactive Waste Building (RWB). The related ITAAC verifies the following top-level design features:
o High radiation liquid in the liquid radioactive waste system (LRWS) is automatically isolated from the environment by containing the liquid in the LRWS.
o High radiation gas in the gaseous radioactive waste system (GRWS) is automatically isolated from the environment by containing the gas in the GRWS.
o High radiation gas in the RWB is contained and precluded from leakage to the outside environment by keeping the RWB pressure negative relative to the outside environment.
1 Enclosure 3
o The as-built RW-IIa RWB maintains its structural integrity under the design basis loads.
The NRC staff has reviewed NuScales response and has determined that even though the radwaste systems are nonsafety-related, they process and contain radioactive waste generated from all NuScale units in the plant and contain some of the most radioactive components in the plant outside of the containment (other than spent fuel). In addition, the ITAAC ensuring that the LRWS and GRWS isolates does not provide any assurance that the systems are designed and constructed to the design criteria in RG 1.143 and does not ensure that releases will not occur due to potential failures of the equipment. In addition, the staff notes that the proposed draft standardized ITAAC sent to NuScale (see Agencywide Documents Access and Management Systems Accession Nos. ML16096A132 for letter and ML16097A123 for the draft standard ITAAC tables), contains ITAAC R07, which is an ITAAC to verify that the systems are designed and constructed in accordance with the RG 1.143 criteria. As such, the staff reiterated its position that an ITAAC ensuring that the radwaste systems are designed and constructed in accordance with RG 1.143. The NRC staff requested that NuScale to re-evaluate its response to RAI 9303, Question 12.03-52 in order to minimize the potential releases to the public and the environment and to minimize exposure to workers.
- b. Next Step: NuScale understood the NRC staffs question and disagreed with the staff regarding the need for ITAAC. NuScale stated that the structure is designed in accordance with the RG 1.143 design criteria and the commitment to the RG is clearly spelled out in the FSAR. They further stated that there are several mechanisms other than ITAAC that the commitment can be verified during construction including NRCs construction inspection program and the licensees quality assurance program. NuScales position is based on the nonsafety-related radwaste system structure not meeting the Tier 1/ITAAC First Principle (Nuclear Energy Institute (NEI) 15-02) to require an ITTAC. The staff informed NuScale that NRC has not endorsed the NEI First Principle. The NRC staff will further discuss NuScales position internally and will interact with NuScale if needed.
- 2. RAI 9294, Question 12.03-23:
- a. NRC Staff Feedback:
- 1. In the response to Question 12.03-23, the applicant indicates that the LRWS processing skids are vendor packages that will incorporate integral shielding, as required by equipment specification. Because these processing skid designs are not finalized, and equipment specifications are not yet written, the RWB shielding analysis modeled additional shielding. Specifically, the shielding analysis for the RWB utilizes an additional one-inch thick plate of steel covering the LRWS ion exchange and charcoal bed cubical, and an additional two-inch thick plate of steel covering the drum dryer skid cubicals.
However, the applicant did not provide any Interface Requirements, as described in SRP Section 14.3 and as required by 10 CFR 52.47(a)(25), and would need to address 10 CFR 52.47(a)(26) for any interface requirements developed. Therefore, the staff requested NuScale to update the response to 2
provide interface requirements for shielding that was not included as part of the design control document (DCD).
As an alternative, the staff requested that NuScale revise the responses to Questions 12.3-23 and 12.03-27, in all of the notes to Tier 2, Table 12.3-7 and Tier 1, Table 3.12-1, replace the words credited with provided. For example, Note 2 in Table 3.12-1 would state, An additional one inch of steel on top of the low-conductivity waste demineralizers and granulated activated charcoal processing skid inside the liquid radioactive waste mobile processing area is provided. This would ensure that the shielding is provided when the plant is built, instead of the shielding just being credited in the calculations, and would negate the need for an interface requirement.
- 2. For clarification, Table 12.3-6 shows the notes being added on FSAR pages 12.3-34 and 12.3-40. In the next DCD revision, please specify whether the notes will be added to the heading row on all pages and not just pages 12.3-34 and 12.3-40?
- b. Next Step:
Item 1 - NuScale agreed to submit a supplemental responses to Questions 12.3-23 and 12.03-27, by replacing the words credited with provided in the notes for Tier 2, Table 12.3-7 and Tier 1, Table 3.12-1.
Item 2 - NuScale confirmed that the notes are added to the heading row on all pages and not just pages 12.3-34 and 12.3-40 that will be submitted in the next DCD revision.
- 3. RAI 9294, Question 12.03-25:
- a. NRC Staff Feedback: In the response to Question 12.03-25, the applicant provided information on removable shielding used in the plant. However, there does not appear to be any information in the DCD regarding the radiation attenuation capabilities of the removable shielding, such as the ability to provide adequate attenuation to maintain the radiation zones specified.
The NRC staff asks NuScale to update the response and DCD, as appropriate to provide this information. Also, ensure that the response addresses the attenuation capabilities of the floor shield plugs for the high integrity container (HIC) Storage Room and HIC Filling Room, which are not identified in Chapter 12 (but are instead discussed in Chapter 11).
- b. Next Step: NuScale understood the NRC staffs question and agreed to submit supplemetal response with FSAR markup to address the concerns.
- 4. RAI 9294, Question 12.03-26:
- a. NRC Staff Feedback:
- 1. In the response to Question 12.03-26, the applicant indicates that the FSAR Chapter 12 shielding evaluation for the revised bioshield design will be incorporated into Revision 2 of the FSAR in 2018. However, the response 3
provides no proposed DCD markups showing the proposed changes.
NuScale is requested to supplement the response to provide the proposed DCD changes so that the staff can evaluate the changes and close the RAI.
Having this information will facilitate the staffs ability to review the changes and facilitate closing this item. Otherwise, this item will remain open and in evaluation until after the changes can be evaluated in Revision 2.
- 2. As discussed in the response to Question 12.03-26, NuScale proposed to remove, the polyethylene is being removed from the bioshield design.
However, DCD Section 12.3.2.2 states, In addition to concrete, other types of materials such as steel, water, tungsten, and polymer composites are considered for both permanent and temporary shielding. The staff requests additional information regarding any additional shielding material using polyethylene? If not, polymer composites should be removed from DCD Section 12.3.2.2. If there are additional polymer composites being used, please describe where they are being used and how they are being protected from environmental conditions. Please update the response as appropriate.
- 3. In the response to Question 12.03-26, the applicant specifies that certain design details and materials related to shielding have not been finalized, therefore, the COL applicant will be responsible for providing information on the testing and inspection of potentially degradable shielding materials, for those areas. However, it is unclear from reviewing the response if there are any shielding materials within the scope of the DCD that could be subject to degradation due to environmental conditions. Please specify if there is any shielding being used within the scope of the DCD that could degrade due to environmental conditions? If so, the response should be updated to provide this information.
- 4. The response to Question 12.03-26 specifies that the radiation shielding design details and materials related to items, such as shield wall penetration shielding, have not been finalized. It also specifies that as the details of the design, testing, and inspection of potentially degradable shielding materials will be the responsibility of the COL applicant. The staff requests additional information on how information will be conveyed to the COL applicant regarding which shields and materials the COL applicant will have to ensure will not degrade due to environmental conditions. NuScale is requested to update the response to include this information.
- b. Next Step:
Item 1 - NuScale acknowledged that a supplemental response with the missing FSAR markup is needed for the staff to complete its evaluation. However, they were unable to commit if that change would be included in the Revision 2 of the FSAR. The staff informed NuScale that this item will be tracked as an open item if the supplemental response with the FSAR markup is not submitted in time to support the Phase 2 chapter completion.
Item 2 - NuScale understood the NRC staffs question and provided further clarification. The NRC staff found the clarification acceptable and both agreed no further action is needed regarding this question.
4
Item 3 - NuScale understood the NRC staffs question and provided further clarification. The NRC staff found the clarification acceptable and both agreed no further action is needed regarding this question.
Item 4 - NuScale agreed to address this issue in a supplemental response to RAI 9295. The NRC staff will link RAI 9294, Question 12.03-26 to RAI 9295 internally for tracking purpose.
- 5. RAI No. 9270, Question 12.02-20 RCS tritium due to buildup (discussed in the closed portion of the meeting. Proprietary information redacted.)
- a. NRC Staff Feedback: In response to this RAI, NuScale added Table 11.1-8. In this table the value of [ ] is provided for the Primary Coolant Average Concentration (Tritium). Please discuss rational for using the average value as opposed to the peak value when calculating airborne activity.
From which calculation sheet is the value of [ ] obtained? In EC-0000-3398_Rev3_0000_6075 Letdown, Cells B31/31 the Time Weighted and Peak tritium concentrations are [ ].
- b. Next Step: NuScale understood the NRC staffs question and gave a detailed explantion of their rational for using average value instead of peak value and why it is conservative. The staff stated that the NRC standard is to use peak value. Both the NRC staff and NuScale agreed to digest what they have heard and enagage at a later date if needed.
5