ML24269A008

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Audit Status - the Staff Review of the NuScale Power, LLC Standard Design Approval (SDA) Application - NuScale US460
ML24269A008
Person / Time
Site: 05200050
Issue date: 10/24/2024
From: Getachew Tesfaye
NRC/NRR/DNRL/NRLB
To: Fosaaen C
NuScale
References
Download: ML24269A008 (7)
v • d • e


Text

October 24, 2024 Ms. Carrie Fosaaen Vice President, Regulatory Affairs NuScale Power, LLC 1100 NE Circle Boulevard, Suite 200 Corvallis, OR 97330

SUBJECT:

AUDIT STATUS - THE STAFF REVIEW OF THE NUSCALE POWER, LLC STANDARD DESIGN APPROVAL APPLICATION - NUSCALE US460

Dear Ms. Fosaaen:

This letter provides the status of the recently closed regulatory audit conducted by the U.S.

Nuclear Regulatory Commission (NRC) staff as part of its safety review of the NuScale Power, LLC (NuScale) Standard Design Approval Application (SDAA), Revision 1, submitted on October 31, 2023 (Agencywide Documents Access and Management System (ADAMS)

Package Accession No. ML23306A033). The audit was conducted from March 27, 2023 through August 31, 2024 (ML23067A300). In addition to the SDAA, the audit scope included the following associated licensing topical reports (LTRs): (1) TR-0516-49422, Loss-of-Coolant Accident [LOCA] Evaluation Model, Revision 3 (ML23008A002); (2) TR-0516-49416, Non-Loss-of-Coolant Accident Analysis Methodology, Revision 4 (ML23005A305); (3) TR 124587, Extended Passive Cooling and Reactivity Control Methodology, Revision 0 (ML23005A308);

and (4) TR-131981, Methodology for the Determination of the Onset of Density Wave Oscillations (DWO), Revision 1 (ML23198A244). The audit facilitated efficiencies in the safety review by allowing the staff to review and discuss supporting material with the objective of improving communication and understanding of complex technical topics. The audit ended on August 31, 2024, and a formal exit meeting was held on September 3, 2024.

During the audit, the NRC staff presented 1247 document requests and items for explanation in the audit. Of these, 1062 items were resolved in the audit, the remaining items have either been processed as formal requests for additional information or voided. The staff has communicated to NuScale that the following items related to the final safety analysis report (FSAR) and the associated LTRs resolved in the audit need to be submitted on the docket:

Chapter 1

1. Information related to FSAR Section 1.6, Material Referenced.

One Item: 1.6-1 (with the updated Table 1.6-2 from Audit Item A-4.4-1 response that includes a new technical report).

Chapter 2

1. Information related to FSAR Section 2.5.4, Stability of Subsurface Materials and Foundations.

Three Items: 2.5.4-1, 2.5.4-7, and 2.5.4-8 Chapter 3

1. Information related to FSAR Section 3.5.1, Missile Selection and Description.

One Item: 3.5.1.3-2

2. Information related to FSAR Section 3.7.2, Seismic System Analysis.

One Item: 3.7.2-32

3. Information related to FSAR Section 3.8.5, Foundations.

One Item: 3.8.5-8

4. Information related to FSAR Section 3.9.2, Dynamic Testing and Analysis of Systems, Components, and Equipment.

Four Items: 3.9.2-26, 3.9.2-28, 3.9.2-34, 3.9.2-35

5. Information related to FSAR Section 3.11, Environmental Qualification of Mechanical and Electrical Equipment.

One Item: 3.11-7 Chapter 4

1. Information related to FSAR Section 4.2, Fuel System Design Two Items: 4.2-5, 4.2-9
2. Information related to FSAR Section 4.3, Nuclear Design Seven Items: 4.3-10, 4.3-25, 4.3-29, 4.3-30, 4.3-31, 4.3-32, 4.3-33
3. Information related to FSAR Section 4.4, Thermal and Hydraulic Design Two Items: 4.4-1, 4.4-3
4. Information related to FSAR Section 4.5.2, Reactor Internals and Core Support Structure Materials One Item: 4.5.2-4
5. Information related to Licensing Technical Report, NuFuel-HTP2TM Fuel and Control Rod Assembly Designs Three Items: 4. FuelCR.TeR-3, 4.FuelCR.TeR-6, 4.FuelCR.TeR-10 Chapter 5
1. Information related to FSAR Section 5.2.4.1, Inservice Inspection and Testing Program One Item: 5.2.4.1-2
2. Information related to FSAR Section 5.2.5, Reactor Coolant Pressure Boundary Leakage Detection One Item: 5.2.5-6
3. Information related to FSAR Section 5.3.2.23, Operating Procedures One Item: 5.3.2.2-1
4. Information related to FSAR Section 5.4, Reactor Coolant System Component and Subsystem Design Two Items: 5.4-9, 5.4-10
5. Information related to FSAR Section 5.4.3, Decay Heat Removal System Three Items: 5.4.3-3, 5.4.3-5, 5.4.3-7
6. Information related to FSAR Section 5.4.5, Pressurizer One Item: 5.4.5-1 Chapter 6
1. Information related to FSAR Section 6.1, Engineered Safety Feature Materials.

Five Items: 6.1.1-2, 6.1.1-3, 6.1.1-4, A-6.1.1-5, and 6.1.1-6

2. Information related to FSAR Section 6.2, Containment Structure.

One Item: 6.2.5-1

3. Information related to FSAR Section 6.3, Emergency Core Cooling System.

Five Items: 6.3.2.2.1-1, 6.3-5, 6.3-12, 6.3-6, and 6.3-8 Chapter 8

1. Information related to FSAR Section 8.3, Onsite Power Systems.

Ten Items: EDAS audit meeting Action Item 1, Item 2, Item 3, Item 4, Item 5, Item 6, Item 9, Item 14, 8.3-16, FSAR markups in CP-3915 Chapter 8 and 15 incorp. DC Power TR-102621 into FSAR Chapter 9

1. Information related to FSAR Section 9.1.5, Overhead Heavy Load Handling Systems.

One Item: 9.1.5-8 Chapter 15

1. Information related to FSAR Chapter 15 Transient and Accident Analysis One Item: 15-2
2. Information related to FSAR Section 15.0.4 Consequence Analyses of Design-Basis Source Terms One Item: 15.0.3.7-2
3. Information related to FSAR Section 15.0.4 Safe, Stabilized Condition One Item: 15.0.4-1
4. Information related to FSAR Section 15.0.5 Extended Passive Cooling for Decay and Residual Heat Removal Two Items: 15.0.5-1 (part a), 15.0.5-3
5. Information related to FSAR Section 15.1.1 Decrease in Feedwater Temperature Two Items: 15.1.1-3, 15.1.1-9
6. Information related to FSAR Section 15.1.2 Increase in Feedwater Flow Two Items: 15.1.2-1, 15.1.2-3
7. Information related to FSAR Section 15.1.3 Increase in Steam Flow One Item: 15.1.3-2
8. Information related to FSAR Section 15.1.5 Steam Piping Failures Inside and Outside of Containment One Item: 15.1.5-1
9. Information related to FSAR Section 15.1.6 Loss of Containment Vacuum and Containment Flooding One Item: 15.1.6-2
10. Information related to FSAR Section 15.2.4 Closure of Main Steam Isolation Valve(s)

One Item: 15.2.4-1

11. Information related to FSAR Section 15.2.7 Loss of Normal Feedwater Flow One Item: 15.2.7-1
12. Information related to FSAR Section 15.4.1 Uncontrolled Control Rod Assembly Withdrawal from a Subcritical or Low Power Startup Condition Three Items: 15.4.1-1S, 15.4.1-2, 15.4.1-2S
13. Information related to FSAR Section 15.4.3 Control Rod Misoperation (System Malfunction or Operator Error)

One Item: 15.4.3-5

14. Information related to FSAR Section 15.4.7 Inadvertent Loading and Operation of a Fuel Assembly in an Improper Position Two Items: 15.4.7-1, 15.4.7-4
15. Information related to FSAR Section 15.4.8 Spectrum of Rod Ejection Accidents Two Items: 15.4.8-5, 15.4.8-6
16. Information related to FSAR Section 15.6.2 Failure of Small Lines Carrying Primary Coolant Outside Containment One Item: 15.6.2-2
17. Information related to FSAR Section 15.6.5 Loss-of-Coolant Accidents Resulting from Spectrum of Postulated Piping Breaks within the Reactor Coolant Pressure Boundary Two Items: 15.6.5-1, 15.6.5-13, 15.6.5-14
18. Information related to FSAR Section 15.9 Stability Two Items: 15.9-2, 15.9-3 Chapter 16
1. Information related to Part 2 Chapter 16, Part 4, and TR-101310-NP, US460 Standard Design Approval Technical Specifications Development, Revision 0, Section 3.0.

Three Items: 16-9, 16-13, 16-14, and 16.3.6.3-1

2. Information related to Generic Technical Specification 3.0, LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.

One Item: 16.3.0.4-1

3. Information related to Generic Technical Specification 3.5.3, Ultimate Heat Sink.

One Item: 16.3.5.3-3 (including removal of hyphen from "long-term")

4. Information related to Generic Technical Specification 3.3.1, Module Protection System (MPS) Instrumentation.

Three Items: 16.3.3.1-7, 16.3.3.1-9, and 16.3.3.1-11

5. Information related to Generic Technical Specification 3.5.1, Emergency Core Cooling System (ECCS).

Two Items: 16.3.5.1-4 and 16.3.5.1-5

6. Information related to Generic Technical Specification 3.3, INSTRUMENTATION.

One Item: 16.3.3-2

7. Information related to Generic Technical Specification 3.1.2, Core Reactivity.

One Item: 16.3.1.2-1

8. Information related to Generic Technical Specification 3.5.4, Emergency Core Cooling System Supplemental Boron (ESB).

One Item: 16.3.5.4-1

9. Information related to Generic Technical Specification 2.1.2, Reactor Coolant System (RCS) Pressure SL One Item: 16.2.1.2-2 (initial response: responses to items b and c only; and revised response)
10. Information related to EDAS in US460 SDAA Part 4 Item: FSAR markups in CP-3915 Chapter 8 and 15 incorp. DC Power TR-102621 into FSAR
11. Information related to Generic Technical Specification 3.6.3, Containment Closure.

One Item: 16.3.6.3-2 Chapter 19

1. Information related to FSAR Section 19.1, Probabilistic Risk Assessment.

Ten Items: 19.1-53, 19.1-55: Responses to items 1, 3a, 3b, and 6 only, 19.1-62, 19.1-63, 19.1-61: FSAR markups only, 19.1-64, 19.1-65, and 19.1-66: Responses to Question 1, Question 2b (only the response including the embedded table, the associated figures are not necessary), and Question 3; 19.1-5: 1) FSAR markups in CP-3915 Chapter 8 and 15 incorp. DC Power TR-102621 into FSAR; 2) the integrated revised response to Audit Items A-19.1-5, A-19.1-37, A-17.4-10, and A-16-18 in the Chapter 17.4 ERR; 3) Initial response posted 5/3/23 in the eRR; 19.1-37: 1) FSAR markups in CP-3915 Chapter 8 and 15 incorp. DC Power TR-102621 into FSAR; 2) the integrated revised response to Audit Items A-19.1-5, A-19.1-37, A-17.4-10, and A-16-18 in the Chapter 17.4 ERR; 3)

Initial response posted 8/30/23 in the eRR

2. Information related to FSAR Section 19.2, Severe Accident Evaluation.

Three Items: 19.2-32, 19.2-33, and 19.2-34 XPC

1. Information related to NuScale Topical Report: "Extended Passive Cooling and Reactivity Control Methodology, Revision 0 (ADAMS Accession No. ML23005A308)," TR-124587, Revision 0 Nine Items: XPC.LTR-14, XPC.LTR-15, XPC.LTR-20, XPC.LTR-22, XPC.LTR-25, XPC.LTR-26, XPC.LTR-27, XPC.LTR-30, XPC.LTR-33 LOCA
1. Information related to NuScale Topical Report: "Loss-of-Coolant Accident Evaluation Model," TR-0516-49422, Revision 3 Nine Items: LOCA.LTR-35, LOCA.LTR-36, LOCA.LTR-37, LOCA.LTR-38, LOCA.LTR-39, LOCA.LTR-40, LOCA.LTR-41, LOCA.LTR-42, LOCA.LTR-48 Non-LOCA
1. Information related to NuScale Topical Report: "Non-Loss-of-Coolant Accident Analysis Methodology," TR-0516-49416, Revision 0 Thirty-one Items: NonLOCA.LTR-2, NonLOCA.LTR-5, NonLOCA.LTR-8, NonLOCA.LTR-22, NonLOCA.LTR-23, NonLOCA.LTR-24, NonLOCA.LTR-25, NonLOCA.LTR-26, NonLOCA.LTR-28, NonLOCA.LTR-29, NonLOCA.LTR-30, NonLOCA.LTR-33, NonLOCA.LTR-34, NonLOCA.LTR-35, NonLOCA.LTR-36,

NonLOCA.LTR-37, NonLOCA.LTR-38, NonLOCA.LTR-39, NonLOCA.LTR-40, NonLOCA.LTR-41, NonLOCA.LTR-44S, NonLOCA.LTR-43S, NonLOCA.LTR-45, NonLOCA.LTR-49, NonLOCA.LTR-54, NonLOCA.LTR-57, NonLOCA.LTR-58, NonLOCA.LTR-59, NonLOCA.LTR-61, NonLOCA.LTR-62, NonLOCA.LTR-68 The information requested under each identifying number will be described in detail when NuScale submits the information for docketing as discussed in the audit.

If you have any questions, I can be reached at (301) 415-8013 or by email at Getachew.Tesfaye@ nrc.gov.

Sincerely,

/RA/

Getachew Tesfaye, Senior Project Manager New Reactor Licensing Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation Docket No: 05200050 cc: DC NuScale Power LLC Listserv

ML24269A008

  • via email NRR-106 OFFICE NRR/DNRL/NRLB: PM NRR/DNRL/NLIB:LA NAME GTesfaye SGreen*

DATE 09/24/2024 09/25/2024 OFFICE NRR/DNRL/NRLB: BC NRR/DNRL/NRLB: PM NAME MJardaneh*

GTesfaye DATE 10/18/2024 10/24/2024

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