ML18031A915

LLC Response to NRC Request for Additional Information No. 131 (Erai No. 8970) on the NuScale Design Certification Application

ML18031A915
Person / Time
Site:	NuScale
Issue date:	01/31/2018
From:	Rad Z NuScale
To:	Document Control Desk, Office of New Reactors
References
RAIO-0118-58469
Download: ML18031A915 (7)

Text

RAIO-0118-58469 January 31, 2018 Docket No.52-048 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738

SUBJECT:

NuScale Power, LLC Response to NRC Request for Additional Information No.

131 (eRAI No. 8970) on the NuScale Design Certification Application

REFERENCE:

U.S. Nuclear Regulatory Commission, "Request for Additional Information No.

131 (eRAI No. 8970)," dated August 05, 2017 The purpose of this letter is to provide the NuScale Power, LLC (NuScale) response to the referenced NRC Request for Additional Information (RAI).

The Enclosure to this letter contains NuScale's response to the following RAI Question from NRC eRAI No. 8970:

03.08.04-10 This letter and the enclosed response make no new regulatory commitments and no revisions to any existing regulatory commitments.

If you have any questions on this response, please contact Marty Bryan at 541-452-7172 or at mbryan@nuscalepower.com.

Sincerely, Zackary W. Rad Director Regulatory Affairs

Director, NuScale Power, LLC Distribution: Gregory Cranston, NRC, OWFN-8G9A Samuel Lee, NRC, OWFN-8G9A Marieliz Vera, NRC, OWFN-8G9A : NuScale Response to NRC Request for Additional Information eRAI No. 8970 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com

RAIO-0118-58469 :

NuScale Response to NRC Request for Additional Information eRAI No. 8970 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com

Response to Request for Additional Information Docket No.52-048 eRAI No.: 8970 Date of RAI Issue: 08/05/2017 NRC Question No.: 03.08.04-10 10 CFR 50, Appendix A, GDC 1, 2, and 4, provide requirements to be met by SSC important to safety. In accordance with these requirements, DSRS Section 3.8.4 provides review guidance pertaining to the design of seismic Category I structures, other than the containment.

DSRS Section 3.8.4 references AISC N690-1994 including Supplement 2 (2004) as being acceptable to the staff for establishing the load and load combinations, design and analysis procedures, and structural acceptance criteria, for seismic Category I Steel Structures. FSAR Sections 3.8.4.2.1, 3.8.4.3, and 3.8.4.5, indicate the use of AISC N690-2012 for the design of seismic Category I structures. Provide specific reasons for using AISC N690-2012 in place of AISC N690-1994 including Supplement 2 (2004).

NuScale Response:

A design code comparison was performed for ANSI/AISC N690-1994 including Supplement 2 (2004) and ANSI/AISC N690-12, specific to design load combinations in the NuScale Power Plant design of Seismic Category I steel structures.

The use of ANSI/AISC N690-12 was to obtain loads from allowable strength design load combinations for use in the analysis of two safety related, Seismic Category I Nuscale Power Module (NPM) steel supports. The NPM is supported at the bottom of containment vessel (CNV) skirt and at the CNV lug locations (located approximately halfway up the NPM). The bottom CNV support is a passive ring that resists horizontal loads from the CNV produced by the safe shutdown earthquake (SSE). The lug supports are also passive supports designed to resist the horizontal loads from the CNV produced by the SSE.

For the design of the NPM supports, the worst load case from the load combinations is applied.

To ensure that the governing load case between the codes was used, a check was performed to ensure that the governing load combination from ANSI/AISC N690-12 either matched or enveloped the governing load combination in ANSI/AISC N690-1994. The governing load combination was determined to be ANSI/AISC N690-12 equation NB2-15 due to the high NuScale Nonproprietary

seismic load transfer from the NPM, and includes DSRS Section 3.8.4 supplemental criteria in the load combination. This load combination does not contain load coefficients, but it does allow for a strength increase of 1.6; 1.5 for fasteners and members experiencing axial tension or shear (1.5 used in the calculation). This is comparable to the related load combination from ANSI/AISC N690-1994, equation 8, which is assigned a stress limit coefficient of 1.6.

The use of ANSI/AISC N690-12 load combination equation NB2-15 as the equation that produces the highest applied loads is an acceptable substitute for ANSI/AISC N690-1994 equation 8 . The safety related steel structures using N690-12 are designed for this load combination and concluded to be conservative, safe designs, similar to the same design if produced by use of ANSI/AISC N690-1994 load combinations.

Additionally, in the analysis and design of these two structural steel supports, other NRC accepted codes; ACI 349-06, ASME BPVC Section II, Part D 2013, ASTM design specifications and AISC steel construction manual 14th edition, second printing, were used. NuScale utilizes, when applicable, the latest engineering design codes, standards, and specifications for design.

This is considered good engineering practice since using the latest revisions of codes and standards takes advantage of the latest test data and analysis of materials and design procedures to create a more predictable and cost effective solution.

Impact on DCA:

FSAR Tier 2, Section 3.8.4.5 and Table 1.9-3 have been revised as described in the response above and as shown in the markup provided in this response.

NuScale Nonproprietary

Tier 2 NuScale Final Safety Analysis Report RAI 03.08.04-10, RAI 05.03.01-3, RAI 06.02.04-8, RAI 08.01-1, RAI 08.01-1S1, RAI 08.02-4, RAI 08.02-6, RAI 08.03.02-1, RAI 09.02.06-1, RAI 10.03.06-4, RAI 10.04.07-1, RAI 14.03.12-2, RAI 14.03.12-3 Table 1.9-3: Conformance with NUREG-0800, Standard Review Plan (SRP) and Design Specific Review Standard (DSRS)

SRP or DSRS Section, AC AC Title/Description Conformance COL Comments Section Rev: Title Status Applicability SRP 1.0, Rev 2: II.1 No Specific Acceptance Criteria - - No Specific Acceptance Criteria. X Introduction and Interfaces SRP 1.0, Rev 2: II.2 SRP Acceptance Criteria Conforms Applicable None. Ch 1 Introduction and Associated with Each Referenced Interfaces SRP section SRP 1.0, Rev 2: II.3 Performance of New Safety Conforms Applicable None. Ch 1 Introduction and Features and Design Qualification Interfaces Testing Requirements SRP 2.0, (March 2007): Site II.1 Specific SRP Acceptance Criteria Conforms Applicable This acceptance criterion is a pointer to 2.0 Characteristics and Site Contained in Related SRP Chapter other SRP sections.

Parameters 2 or Other Referenced SRP 1.9-56 sections SRP 2.0, (March 2007): Site II.2 COL Application Referencing an Not Applicable Applicable This acceptance criterion is applicable 2.0 Characteristics and Site Early Site Permit only to COL applicants that do not Parameters reference the DCA.

SRP 2.0, (March 2007): Site II.3 COL Application Referencing a Not Applicable Applicable This acceptance criterion is for COL 2.0 Characteristics and Site Certified Design applicants to meet the design Parameters parameters established in the Design Certification Application.

SRP 2.0, (March 2007): Site II.4 COL Application Referencing an Not Applicable Applicable This acceptance criterion is for COL 2.0 Characteristics and Site Early Site Permit and a Certified applicants to meet the design Conformance with Regulatory Criteria Parameters Design parameters established in the Design Certification Application.

SRP 2.0, (March 2007): Site II.5 COL Application Referencing Not Applicable Applicable This acceptance criterion is applicable Not Applicable Characteristics and Site Neither an Early Site Permit Nor a only to COL applicants that do not Parameters Certified Design reference the DCA.

SRP 2.0, (March 2007): Site App A Table 1: Examples of Site Partially Conforms Applicable NuScale provides design Parameters Table 2.0-1 Draft Revision 1 Characteristics and Site Characteristics and Site where applicable.

Parameters Parameters SRP 2.0, (March 2007): Site App A Table 2: Examples of Site-Related Partially Conforms Applicable NuScale provides design Parameters Table 2.0-1 Characteristics and Site Design Parameters and Design where applicable.

Parameters Characteristics

Table 1.9-3: Conformance with NUREG-0800, Standard Review Plan (SRP) and Design Specific Review Tier 2 NuScale Final Safety Analysis Report Standard (DSRS) (Continued)

SRP or DSRS Section, AC AC Title/Description Conformance COL Comments Section Rev: Title Status Applicability SRP 3.5.1.5, Rev 4: Site II.1 Compliance with 10 CFR 100 Not Applicable Applicable The NuScale certified design assumes Not Applicable Proximity Missiles (Except no proximity missiles.

Aircraft)

SRP 3.5.1.5, Rev 4: Site II.2 Compliance with GDC 4 Not Applicable Applicable The NuScale certified design assumes Not Applicable Proximity Missiles (Except no proximity missiles.

Aircraft)

SRP 3.5.1.6, Rev 4: Aircraft II.1 and II.2 Various Not Applicable Applicable The NuScale certified design assumes 3.5.1.6 Hazards no aircraft hazard missiles.

SRP 3.5.1.6, Rev 4: Aircraft III.8.B.1 Postulated Site Parameters Conforms Applicable The NuScale certified design assumes Table 2.0-1 Hazards no aircraft hazard missiles.

SRP 3.5.1.6, Rev 4: Aircraft III.8.B.2 Site Parameters Included as Tier 1 Conforms Applicable The NuScale certified design assumes Table 2.0-1 Hazards Information no aircraft hazard missiles.

SRP 3.5.1.6, Rev 4: Aircraft III.8.B.3 Site Parameters Summary Table Conforms Applicable The NuScale certified design assumes Table 2.0-1 Hazards no aircraft hazard missiles.

SRP 3.5.1.6, Rev 4: Aircraft III.8.B.4 Basis for Site Parameters Conforms Applicable The NuScale certified design assumes Table 2.0-1 1.9-69 Hazards no aircraft hazard missiles.

SRP 3.5.2, Rev 3: II (no Capability of SSCs to Withstand Conforms Applicable None. 3.5.2 Structures, Systems, and number) the Effects of Externally Components to be Generated Missiles Protected From Externally-Generated Missiles SRP 3.5.3, Rev. 3: Barrier II.1.A For Local Damage Prediction - Conforms Applicable None. 3.5.3 Design Procedures Concrete SRP 3.5.3, Rev. 3: Barrier II.1.B For Local Damage Prediction - Conforms Applicable None. 3.5.3 Conformance with Regulatory Criteria Design Procedures Steel SRP 3.5.3, Rev. 3: Barrier II.1.C For Local Damage Prediction - Not Applicable Not Applicable This acceptance criterion specifies 3.5.3 Design Procedures Composite sections provisions when using composite or multi-element barriers. NuScale does not intend to use composite or multi-element barriers.

SRP 3.5.3, Rev. 3: Barrier II.2 For Overall Damage Prediction Partially Conforms Applicable This acceptance criterion is applicable 3.5.3 Draft Revision 1 Design Procedures except for reference to subtier ANSI/

AISC N690-1994 with Supplement 2 (2004). NuScale intends to use the 20062012 version of this standard.

NuScale Final Safety Analysis Report Design of Category I Structures mass are defined by specifying the multiplier for each load case considered. In this model, all long term loads were assigned a multiplier of 1.0, live loads a multiplier of 0.25, and snow loads a multiplier of 0.75. Live load mass participation requirements for dynamic analyses are given in Section 3.8.4.3.4. Table 3.8.4-9 lists the additional masses to be included from various load cases and its corresponding multipliers, which are considered as one of the mass sources for the CRB SAP2000 models for 1-g and dynamic analyses performed.

Load cases are developed in (or converted to) SAP2000 to address the different design loads discussed in Section 3.8.4.3. These cases are individually evaluated or combined to address the load combinations identified in Table 3.8.4-1 and Table 3.8.4-2 for the CRB.

3.8.4.5 Structural Acceptance Criteria The load cases for the RXB and CRB are provided in Table 3.8.4-1 and Table 3.8.4-2.

These tables identify the design code applied for each load combination.

RAI 03.08.04-25 Code requirements are outlined in Table 3.8.4-12 which indicates the design codes for each Seismic Category based on the type of structure or loading.

RAI 03.08.04-10 Limits for allowable stresses, strains, deformations and other design criteria for the reinforced concrete structures are in accordance with ACI 349/349R and its appendices as modified by the exceptions specified in RG 1.142. Structural acceptance criteria for the steel components are in accordance with AISC N690 (Reference 3.8.4-6). Load combination 10 from Table 3.8.4-1 has been determined to be the controlling load combination. As such, this load combination was used to assess the adequacy of the structures. The use of AISC N690 (Reference 3.8.4-6) was to obtain loads from allowable strength design load combinations for use in the analysis of safety related, seismic category I steel structures. Load combination comparisons are performed on a case by case basis between AISC N690-1994 including Supplement 2 (2004) and AISC N690-2012 for verification that AISC N690-2012 provides the governing case.

Appendix 3B, Reactor Building and Control Building Design Approach and Critical Section Details, provides results for selected sections of both the RXB and CRB.

Section 3.8.5.5 identifies acceptance criteria applicable to additional basemat load combinations.

3.8.4.6 Materials, Quality Control and Special Construction Techniques 3.8.4.6.1 Materials The principal construction materials for structures are concrete, reinforcing steel, structural steel, stainless steel, bolts, anchor bolts and weld electrodes.

Table 3.8.4-10 provides the specifics of the materials considered for the structural design.

Tier 2 3.8-67 Draft Revision 1