Je veux savoir à propos de…

khammond on DSKJM1Z7X2PROD with PROPOSALS

35018

Federal Register / Vol. 86, No. 124 / Thursday, July 1, 2021 / Proposed Rules
D. Tier 1 means the portion of the designrelated information contained in the generic DCD that is approved and certified by this appendix Tier 1 information. The design descriptions, interface requirements, and site parameters are derived from Tier 2
information. Tier 1 information includes:
1. Definitions and general provisions;
2. Design descriptions;
3. Inspections, tests, analyses, and acceptance criteria ITAAC;
4. Significant site parameters; and 5. Significant interface requirements.
E. Tier 2 means the portion of the designrelated information contained in the generic DCD that is approved but not certified by this appendix Tier 2 information. Compliance with Tier 2 is required, but generic changes to and plant-specific departures from Tier 2
are governed by Section VIII of this appendix. Compliance with Tier 2 provides a sufficient, but not the only acceptable, method for complying with Tier 1.
Compliance methods differing from Tier 2
must satisfy the change process in Section VIII of this appendix G. Regardless of these differences, an applicant or licensee must meet the requirement in paragraph III.B of this appendix to reference Tier 2 when referencing Tier 1. Tier 2 information includes:
1. Information required by 52.47a and c, with the exception of generic TS and conceptual design information;
2. Supporting information on the inspections, tests, and analyses that will be performed to demonstrate that the acceptance criteria in the ITAAC have been met; and 3. COL action items COL license information identify certain matters that must be addressed in the site-specific portion of the FSAR by an applicant who references this appendix. These items constitute information requirements but are not the only acceptable set of information in the FSAR. An applicant may depart from or omit these items, provided that the departure or omission is identified and justified in the FSAR. After issuance of a construction permit or COL, these items are not requirements for the licensee unless such items are restated in the FSAR.
F. Departure from a method of evaluation described in the plant-specific DCD used in establishing the design bases or in the safety analyses means:
1. Changing any of the elements of the method described in the plant-specific DCD
unless the results of the analysis are conservative or essentially the same; or 2. Changing from a method described in the plant-specific DCD to another method unless that method has been approved by the NRC for the intended application.
G. All other terms in this appendix have the meaning set out in 10 CFR 50.2, 10 CFR
52.1, or Section 11 of the Atomic Energy Act of 1954, as amended, as applicable.
III. Scope and Contents A. Incorporation by reference approval.
NuScale standard design hereafter referred as NuScale material is approved for incorporation by reference by the Director of the Office of the Federal Register under 5
U.S.C. 552a and 1 CFR part 51,
VerDate Sep<11>2014

16:17 Jun 30, 2021

Jkt 253001

Incorporation by Reference. You may obtain copies of the generic DCD from NuScale Power, LLC, 6650 SW Redwood Lane, Suite 210, Portland, Oregon 97224. You can view the generic DCD online in the NRC
Library at https www.nrc.gov/reading-rm/
adams.html. In ADAMS, search under ADAMS Accession No. ML20225A071. If you do not have access to ADAMS or if you have problems accessing documents located in ADAMS, contact the NRCs Public Document Room PDR reference staff at 1800397
4209, 3014153747, or by email at PDR.Resource@nrc.gov. Copies of the NuScale materials are available in the ADAMS Public Documents collection. All approved material is available for inspection at the National Archives and Records Administration NARA. For information on the availability of this material at NARA, email at fedreg.legal@nara.gov or go to https www.archives.gov/federal-register/cfr/
ibrlocations.html.
1. NuScale Standard Plant Design Certification Application, Certified Design Descriptions and Inspections, Tests, Analyses, & Acceptance Criteria ITAAC, Part 2Tier 1, Revision 5, July 2020.
2. NuScale Standard Plant Design Certification Application, Part 2Tier 2, Revision 5, July 2020, including:
a. Chapter One, Introduction and General Description of the Plant.
b. Chapter Two, Site Characteristics and Site Parameters.
c. Chapter Three, Design of Structures, Systems, Components and Equipment.
d. Chapter Four, Reactor.
e. Chapter Five, Reactor Coolant System and Connecting Systems.
f. Chapter Six, Engineered Safety Features.
g. Chapter Seven, Instrumentation and Controls.
h. Chapter Eight, Electric Power.
i. Chapter Nine, Auxiliary Systems.
j. Chapter Ten, Steam and Power Conversion System.
k. Chapter Eleven, Radioactive Waste Management.
l. Chapter Twelve, Radiation Protection.
m. Chapter Thirteen, Conduct of Operations.
n. Chapter Fourteen, Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria.
o. Chapter Fifteen, Transient and Accident Analyses.
p. Chapter Sixteen, Technical Specifications.
q. Chapter Seventeen, Quality Assurance and Reliability Assurance.
r. Chapter Eighteen, Human Factors Engineering.
s. Chapter Nineteen, Probabilistic Risk Assessment and Severe Accident Evaluation.
t. Chapter Twenty, Mitigation of BeyondDesign-Basis Events.
u. Chapter Twenty-One, Multi-Module Design Considerations.
3. DCA Part 4, Volume 1, Revision 5.0, Generic Technical Specifications, NuScale Nuclear Power Plants, Volume 1:
Specifications.
4. DCA Part 4, Volume 2, Revision 5.0, Generic Technical Specifications, NuScale Nuclear Power Plants, Volume 2: Bases.

PO 00000

Frm 00020

Fmt 4702

Sfmt 4702

5. ES03041381NP, Human-System Interface Style Guide, December 2019, Revision 4, Docket: 52048.
6. RP021510815NP, Concept of Operations, May 2019, Revision 3, Docket:
52048.
7. RP031617614NP, Human Factors Engineering Operating Experience Review Results Summary Report, 12/07/2016, Revision 0, Docket: PROJ0769.
8. RP031617615NP, Human Factors Engineering Functional Requirements Analysis and Function Allocation Results Summary Report, 12/2/16, Revision 0, Docket: PROJ0769.
9. RP031617616NP, Human Factors Engineering Task Analysis Results Summary Report, April 2019, Revision 2, Docket: 52
048.
10. RP031617617NP, Human Factors Engineering Staffing and Qualifications Results Summary Report, 12/02/2016, Revision 0, Docket: PROJ0769.
11. RP031617618NP, Human Factors Engineering Treatment of Important Human Actions Results Summary Report, 12/02/2016, Revision 0, Docket: PROJ0769.
12. RP031617619NP, Human Factors Engineering Human-System Interface Design Results Summary Report, April 2019, Revision 2, Docket: 52048.
13. RP051649116NP, Control Room Staffing Plan Validation Results, 12/02/2016, Revision 1, Docket: PROJ0769.
14. RP09148534NP, Human Factors Engineering Program Management Plan, April 2019, Revision 5, Docket: 52048.
15. RP09148543NP, Human Factors Verification and Validation Implementation Plan, April 2019, Revision 5, Docket: 52048.
16. RP09148544NP, Human Factors Engineering Design Implementation Implementation Plan, November 2019, Revision 4, Docket: 52048, NuScale Nonproprietary.
17. RP101861289NP, Human Factors Engineering Verification and Validation Results Summary Report, July 2019, Revision 1, Docket: 52048.
18. RP121520253NP, Control Room Staffing Plan Validation Methodology, 12/02/2016, Revision 3, Docket: PROJ0769.
19. TR011620781NP, Fluence Calculation Methodology and Results, July 2019, Revision 1, Docket: 52048.
20. TR011620825NPA, Applicability of AREVA Fuel Methodology for the NuScale Design, June 2016, Revision 1, Docket:
PROJ0769.
21. TR011621012NPA, NuScale Power Critical Heat Flux Correlations, December 2018, Revision 1, Docket: PROJ0769.
22. TR031622048NP, Nuclear Steam Supply System Advanced Sensor Technical Report, May 2020, Revision 3, Docket: 52
048.
23. TR051513952NPA, Risk Significance Determination, October 2016, Revision 0, Docket: PROJ0769, NuScale Nonproprietary.
24. TR051649084NP, Containment Response Analysis Methodology Technical Report, May 2020, Revision 3, Docket: 52
048.
25. TR051649416NPA, Non-Loss-ofCoolant Accident Analysis Methodology, July 2020, Revision 3, Docket: PROJ0769.

E:FRFM01JYP1.SGM

01JYP1