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Enclosure 1: ACRS Presentation Chapter 17 - Quality Assurance and Reliability Assurance, PM-1218-63732, Revision 0
	ML18347A203
Person / Time
Site:	NuScale
Issue date:	12/18/2018
From:	Conley P, Infanger P; NuScale
To:	; Office of New Reactors
References
	LO-1218-63754 PM-1218-63732, Rev 0
	Download: ML18347A203 (16)
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L0-1218°63754 :

"ACRS Presentation Chapter 17 -Quality Assurance and Reliability Assurance," PM-1218-63732, Revision 0 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207 .3928 www.nuscalepower.com

NuScale Nonproprietary ACRS Presentation Chapter 17 -

Quality Assurance and Reliability Assurance Patrick Conley Engineering Programs Paul lnfanger Licensing Project Manager December 18, 2018 PM-1218-63 732 Revision: 0 Copyright 2018 by NuScale Power, LLC.

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Purpose

Provide FSAR Chapter 17 overview

- Quality Assurance Program (QAP)

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Quality Assurance Program

Established in accordance with 10 CFR 50 App B and ASME NQA-1*-2008 with NQA-1a-2009 addenda as endorsed by RG 1.28, Rev. 4

- Consistent with guidance in NUREG -0800 and NEI 11-04A Rev. 0 QAPD template

Consists of

- Approved TR-1010-859-NP-A, "Quality Assuran ce Program Description for the N uScale Power Plant," Rev. 3

- Quality Manage ment Plan (QMP) - identifies requirements fully implemented and requirements not within scope of design phase, but may be implemented in future

- Implementing procedures listed in QMP 3

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QAP (cont'd)

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1[* Q:uality Assurance during the Des:ign.Phase. 11*.Described* in 17.5* : * .**

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Quality Assurance during the Construction and : Not applicable to design

Operation Phase . certification Item COL 17.5-1 1* 17 .3 ... J~alit}' AssuranceProg'ran,~°-escri~tion - .*. --*. J secuon 17.5 . . - -- - *.* - ]

17.5 : Quality Assurance Program Description ~ .: Does not address

Design Certification, Early Site Permits, and : construction and design QA New License Applicants activities that begin once

construction begins 4

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COL Items

17.4-1 Describe RAP to be conducted during operations

17.4-2 Identify site-specific SSC in RAP

17.4-3 Identify QA co~trols for RAP SSC during site-specific design, procurement, fabrication, construction, and preoperational testing

17.5-1 Describe QAP applicable to site-specific design, construction, and operation

17.6-1 Describe 10 CFR 50.65 maintenance effectiveness monitoring program 5

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RAls

Only three RAls on Ch 17

- RAI 8879 17.04-1 (chemical and volume control system)

- RAI 8879 17 .04-2 (expert panel)

- RAI 8909 17.04-3 (backup power)

All three are Resolved-Closed 6

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D-RAP Process

Complies with NUREG-0800, Section 17.4

Process controlled by procedure

SSC risk categorization determined by SME and confirmed by expert panel, which makes final decision

- Expert panel consists of Design Engineering, Operations, PRA, and Safety Analysis

- Licensing is a non-mandatory member 7

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D-RAP Process {cont'd)

PRA input based on approved TR-0515-13952-NP-A "Risk Significance Determination," Rev. 0

Default classification is "risk-significant" for safety-related functions, unless PRA specifically determines SSC functionality is not risk-significant

Engineering Change Control process determines if expert panel review is required -

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RTNSS

FSAR 17.4.3.3 states the process for evaluating SSC for the regulatory treatment of non-safety systems (RTNSS) program is described in FSAR 19.3

- No RTNSS criterion met

- No RTNSS SSCs in design 9

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Figure 17.4-1: Nu Scale 0-RAP Process for SSC Risk Significance Determination System Functions ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - .

Safety Analysis QUANTIFIED PRA RESULTS (At,,?u11ollr, ShMc"'n, In~~~ Fh!,

lnlom*I Floods)

System Function System Function Regulalor,* Treatment of CategorlzaUon Breakdown to SSC q SSC Classification

~on-Safety S~*stoms iRIIISS)

Other Conslderailo.'lS

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NO EXPERT PANEL D

Additional Expert Panel Considerations NO SSC Not Risk Significant (Document Basis)

Operating Experlance YES PRA and Severe Accident Insights Design Phase Risk and Assumptions Significant SSC (D-RAP List)

Defense-in-depth Systems Interactions (RTNSS E) 10 PM-1218-63732

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Risk Significance Determination (RSD)

Table 1. NuScale criteria for risk significance Parameter Criteria for Risk Significance Component-level basic event Conditional CDF > 3 x 1o-6/yr

.System-level basic event Conditional CDF > 1 x 1o-5/yr Component-level basic event Conditional LRF > 3 x 1o-7/yr System-level basic event Conditional LRF > 1 x 1o-6/yr Basic event/contributor Total FV > 0.20

- Key conditions and limitations in RSD topical report SER

Only applicable to NuScale

Risk-informed applications include consideration of risk-significant SSCs with other concepts (e.g., defense in depth)

Technically adequate PRA that addresses all hazards and all modes

Thresholds based on very low CDF (< 1x10-7 per year)

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D-RAP PRA Candidates

Candidate risk-significant SSCs from PRA

- Systems

emergency core cooling system (ECCS)

module protection system

ultimate heat sink

- Components

ECCS reactor vent valves and reactor recirculation valves

decay heat removal system actuation valves

reactor safety valves

containment system containment isolation valves (CIVs)

chemical and volume control system CIVs

containment evacuation system CIVs

combustion turbine generator 12 PM-1218-63732 Revision: 0 Copyright 2018 by NuScale Power, LLC.

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D-RAP PRA Candidates (cont'd)

- Other events and initiators (Fussel-Vesely FV>20°/o)

Reactor Building crane

LOCA inside containment

LOCA outside containment

)

loss of offsite power

internal fires

internal floods

- Human actions (FV>20%)

chemical and volume control system actuation

containment flooding and drain system actuation 13 PM-1218-63732 Revision: 0 Copyright 2018 by NuScale Power, LLC.

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Final D-RAP Results

Table 17.4-1: Risk-significant D-RAP SSC

- containment system

- steam generator system

- reactor core system

- control. rod drive system

-- reactor coolant system

- emergency core cooling system

- decay heat removal system

- ultimate heat sink

- module protection system

- neutron monitoring system

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