ML24073A102: Difference between revisions
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{{#Wiki_filter:March 14, 2024 | {{#Wiki_filter:March 14, 2024 | ||
MEMORANDUM TO: | MEMORANDUM TO: Scott W. M oore, Executive Director AdvisoryCommitteeonReactorSaf eguards | ||
FROM: | FROM: Br ian W. Smith, Director /RA/ | ||
Division of New and Renewed Licenses OfficeofNuc | Division of New and Renewed Licenses OfficeofNuc lear Reactor Regulation | ||
==SUBJECT:== | ==SUBJECT:== | ||
NUSCALE POWER, LLC, SAFETY EVALUATION FOR STANDARD DESIGN APPROVAL APPLICATION FINAL SAFETY ANLAYSIS REPORT CHAPTERS 2, 10, 11, 13, 17 (NOT INCLUDING 17.4) | NUSCALE POWER, LLC, SAFETY EVALUATION FOR STANDARD DESIGN APPROVAL APPLICATION FINAL SAFETY ANLAYSIS REPORT CHAPTERS 2, 10, 11, 13, 17 (NOT INCLUDING 17.4) | ||
By {{letter dated|date=October 31, 2023|text=letter dated October 31, 2023}} (Agencywide Documents Access a | By {{letter dated|date=October 31, 2023|text=letter dated October 31, 2023}} (Agencywide Documents Access a nd Management System (ADAMS) Accession No. ML23306A033), NuScale Power, LLC (NuScale ) submitted the Standard Design Approval (SDA) application, Revision 1 in accor dance with requirements of Title 10 of the Code of Federal Regulation (10 CFR) Part 52, Subpart E, Standard Design Approvals. NuScale requested NRC review, approval, and granting of SDA for its US460 standard plant design. | ||
Based on our review of the application, the staff is providing | Based on our review of the application, the staff is providing the Advisory Committee on Reactor Safeguards (ACRS) the ADAMS Accession No. for its safety evalua tion (SE), without open items for the following five chapters of the SDA application Fi nal Safety Analysis Report: | ||
: 1. | : 1. Chapter 2, Site Characteristics and Site Parameters (ML24040 A063) | ||
: 2. | : 2. Chapter 10, Steam and Power Conversion System (ML24011A133) | ||
: 3. | : 3. Chapter 11, Radioactive Waste Management (ML24016A033) | ||
: 4. | : 4. Chapter 13, Conduct of Operations (ML23355A271) | ||
: 5. | : 5. Chapter 17, Quality Assurance and Reliability Assurance (Not Including Section 17.4) | ||
[ML23346A042] | [ML23346A042] | ||
These SEs are being provided to support a meeting of the subcom | These SEs are being provided to support a meeting of the subcom mittee of the ACRS on March 19, 2024. | ||
CONTACT: Getachew Tesfaye, NRR/DNRL 301-415-8013 | CONTACT: Getachew Tesfaye, NRR/DNRL 301-415-8013 | ||
S. Moore | S. Moore 2 | ||
The U.S. Nuclear Regulatory Commission staff concludes that the | The U.S. Nuclear Regulatory Commission staff concludes that the SEs do not contain any information exempt from public disclosure. NuScale has verified the staffs conclusion that these SEs contain no such exempt information. | ||
Docket No. 05200050 | Docket No. 05200050 | ||
ML24073A102 | ML24073A102 *via email NRR-043 OFFICE DNRL/NRLB:PM DNRL/NLIB:LA DNRL/NRLB:BC* DNRL:D* | ||
NAME | NAME GTesfaye SGreen MJardaneh BSmith DATE 03/12/2024 03/13/2024 03/13/2024 03/14/2024}} | ||
Revision as of 13:24, 5 October 2024
| ML24073A102 | |
| Person / Time | |
|---|---|
| Site: | 05200050 |
| Issue date: | 03/14/2024 |
| From: | Beverly Smith, Getachew Tesfaye NRC/NRR/DNRL/NRLB |
| To: | Scott Moore Advisory Committee on Reactor Safeguards |
| References | |
| Download: ML24073A102 (3) | |
Text
March 14, 2024
MEMORANDUM TO: Scott W. M oore, Executive Director AdvisoryCommitteeonReactorSaf eguards
FROM: Br ian W. Smith, Director /RA/
Division of New and Renewed Licenses OfficeofNuc lear Reactor Regulation
SUBJECT:
NUSCALE POWER, LLC, SAFETY EVALUATION FOR STANDARD DESIGN APPROVAL APPLICATION FINAL SAFETY ANLAYSIS REPORT CHAPTERS 2, 10, 11, 13, 17 (NOT INCLUDING 17.4)
By letter dated October 31, 2023 (Agencywide Documents Access a nd Management System (ADAMS) Accession No. ML23306A033), NuScale Power, LLC (NuScale ) submitted the Standard Design Approval (SDA) application, Revision 1 in accor dance with requirements of Title 10 of the Code of Federal Regulation (10 CFR) Part 52, Subpart E, Standard Design Approvals. NuScale requested NRC review, approval, and granting of SDA for its US460 standard plant design.
Based on our review of the application, the staff is providing the Advisory Committee on Reactor Safeguards (ACRS) the ADAMS Accession No. for its safety evalua tion (SE), without open items for the following five chapters of the SDA application Fi nal Safety Analysis Report:
- 1. Chapter 2, Site Characteristics and Site Parameters (ML24040 A063)
- 2. Chapter 10, Steam and Power Conversion System (ML24011A133)
- 3. Chapter 11, Radioactive Waste Management (ML24016A033)
- 4. Chapter 13, Conduct of Operations (ML23355A271)
- 5. Chapter 17, Quality Assurance and Reliability Assurance (Not Including Section 17.4)
[ML23346A042]
These SEs are being provided to support a meeting of the subcom mittee of the ACRS on March 19, 2024.
CONTACT: Getachew Tesfaye, NRR/DNRL 301-415-8013
S. Moore 2
The U.S. Nuclear Regulatory Commission staff concludes that the SEs do not contain any information exempt from public disclosure. NuScale has verified the staffs conclusion that these SEs contain no such exempt information.
Docket No. 05200050
ML24073A102 *via email NRR-043 OFFICE DNRL/NRLB:PM DNRL/NLIB:LA DNRL/NRLB:BC* DNRL:D*
NAME GTesfaye SGreen MJardaneh BSmith DATE 03/12/2024 03/13/2024 03/13/2024 03/14/2024