ML18228A860

From kanterella
Jump to navigation Jump to search
LLC Supplemental Response to NRC Request for Additional Information No. 416 (Erai No. 9460) on the NuScale Design Certification Application
ML18228A860
Person / Time
Site: NuScale
Issue date: 08/16/2018
From: Rad Z
NuScale
To:
Document Control Desk, Office of New Reactors
References
RAIO-0818-61438
Download: ML18228A860 (6)
v • d • e


Text

RAIO-0818-61438 August 16, 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 Supplemental Response to NRC Request for Additional Information No. 416 (eRAI No. 9460) on the NuScale Design Certification Application

REFERENCES:

1. U.S. Nuclear Regulatory Commission, "Request for Additional Information No. 416 (eRAI No. 9460)," dated April 11, 2018
2. NuScale Power, LLC Response to NRC "Request for Additional Information No. 416 (eRAI No.9460)," dated June 07, 2018 The purpose of this letter is to provide the NuScale Power, LLC (NuScale) supplemental response to the referenced NRC Request for Additional Information (RAI).

The Enclosure to this letter contains NuScale's supplemental response to the following RAI Question from NRC eRAI No. 9460:

14.03.03-11 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 Carrie Fosaaen at 541-452-7126 or at cfosaaen@nuscalepower.com.

Sincerely, Zackary W. Rad Director, Regulatory Affairs NuScale Power, LLC Distribution: Gregory Cranston, NRC, OWFN-8G9A Omid Tabatabai, NRC, OWFN-8G9A Samuel Lee, NRC, OWFN-8G9A : NuScale Supplemental Response to NRC Request for Additional Information eRAI No. 9460 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com

RAIO-0818-61438 :

NuScale Supplemental Response to NRC Request for Additional Information eRAI No. 9460 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.: 9460 Date of RAI Issue: 04/11/2018 NRC Question No.: 14.03.03-11 10 CFR 52.47(b)(1) requires The proposed inspections, tests, analyses, and acceptance criteria that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, a facility that incorporates the design certification has been constructed and will be operated in conformity with the design certification, the provisions of the [Atomic Energy] Act, and the Commission's rules and regulations. In supporting this requirement, staff identified that clarifications are necessary for the inspections, tests, and analyses (ITA) associated with ITAAC 02.01.04 and 03.11.08 in order to clearly demonstrate that the acceptance criteria are met. Specifically, the ITA should mention an "inspection and analysis" instead of only "an inspection," as in order to meet the acceptance criteria, the analysis associated with the as-built Pipe Break Hazard Analysis Report must be fully completed. This completed analysis guides the inspection and is necessary to demonstrate the acceptance criteria has been met.

NuScale Response:

This response supplements NuScale's eRAI No. 9460, Question 14.03.03-11 response (ML18158A507). During a July 23, 2018 telephone conference call, NRC staff requested that ITAAC 02.01.04 and 03.11.08 identify an "inspection and analysis" instead of only "an inspection" in their respective inspections, tests, and analyses (ITA) columns. Staff concluded that citing only "an inspection" in the ITA column does not meet the acceptance criteria for these ITAAC.

The analysis that is associated with the as-built Pipe Break Hazard Analysis Report must be completed in order to meet the acceptance criteria of these ITAAC.

Revisions have been made to Tier 1, Table 2.1-4, ITAAC No. 4 and Table 3.11-2, ITAAC No. 8 to add "and analysis" after "An inspection" in their ITA columns.

Impact on DCA:

Tier 1, Tables 2.1-4 and 3.11-2 have been revised as described in the response above and as shown in the markup provided in this response.

NuScale Nonproprietary

NuScale Tier 1 NuScale Power Module RAI 06.02.06-22, RAI 06.02.06-23, RAI 08.01-1, RAI 08.01-1S1, RAI 08.01-2, RAI 14.03.03-3S1, RAI 14.03.03-4S1, RAI 14.03.03-6S1, RAI 14.03.03-7S1, RAI 14.03.03-8, RAI 14.03.03-11S1 Table 2.1-4: NuScale Power Module Inspections, Tests, Analyses, and Acceptance Criteria No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria

1. The NuScale Power Module ASME An inspection will be performed of the The ASME Code Section III Design Code Class 1, 2 and 3 piping systems NuScale Power Module ASME Code Reports (NCA-3550) exist and listed in Table 2.1-1 comply with ASME Class 1, 2 and 3 as-built piping system conclude that the for the NuScale Code Section III requirements. Design Reports required by ASME Power Module ASME Code Class 1, 2 Code Section III. and 3 as-built piping systems listed in Table 2.1-1 meet the requirements of ASME Code Section III, NCA-3550.
2. The NuScale Power Module ASME An inspection will be performed of the ASME Code Section III Data Reports for Code Class 1 and 2 components NuScale Power Module ASME Code the NuScale Power Module ASME conform to the rules of construction of Class 1 and 2 as-built component Data Code Class 1 and 2 components listed ASME Code Section III. Reports required by ASME Code in Table 2.1-2 and interconnecting Section III. piping exist and conclude that the requirements of ASME Code Section III are met.
3. The NuScale Power Module ASME An inspection will be performed of the ASME Code Section III Data Reports for Code Class CS components conform to NuScale Power Module ASME Code the NuScale Power Module ASME the rules of construction of ASME Class CS as-built component Data Code Class CS components listed in Code Section III. Reports required by ASME Code Table 2.1-2 exist and conclude that the Section III. requirements of ASME Code Section III are met.
4. Safety-related SSC are protected An inspection and analysis will be Protective features are installed in against the dynamic and performed of the as-built high- and accordance with the as-built Pipe environmental effects associated with moderate-energy piping systems and Break Hazard Analysis Report and postulated failures in high- and protective features for the safety-related SSC are protected moderate-energy piping systems. safety-related SSC. against or qualified to withstand the dynamic and environmental effects associated with postulated failures in high- and moderate-energy piping systems.
5. The NuScale Power Module ASME An analysis will be performed of the The as-built LBB analysis for the ASME Code Class 2 piping systems and ASME Code Class 2 as-built piping Code Class 2 piping systems listed in interconnected equipment nozzles are systems and interconnected Table 2.1-1 and interconnected evaluated for LBB. equipment nozzles. equipment nozzles is bounded by the as-designed LBB analysis.
6. The RPV beltline material has a Charpy A vendor test will be performed of the An ASME Code Certified Material Test upper-shelf energy of greater than 75 Charpy V-Notch specimen of the RPV Report exists and concludes that the ft-lb minimum. beltline material. initial RPV beltline material Charpy upper-shelf energy is greater than 75 ft-lb minimum.

Tier 1 2.1-12 Draft Revision 2

NuScale Tier 1 Reactor Building RAI 14.03.03-1, RAI 14.03.03-11S1 Table 3.11-2: Reactor Building Inspections, Tests, Analyses, and Acceptance Criteria No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 1 Fire and smoke barriers provide An inspection will be performed of the The following RXB fire and smoke confinement so that the impact from RXB as-built fire and smoke barriers. barriers exist in accordance with the internal fires, smoke, hot gases,or fire fire hazards analysis, and have been suppressants is contained within the qualified for the fire rating specified in RXB fire area of origin. the fire hazards analysis:

  • fire-rated doors
  • fire-rated walls, floors, and ceilings
  • flood resistant doors
  • curbs and sills
  • walls
  • National Electrical Manufacturer's Association enclosures 3 The Seismic Category I RXB is An inspection will be performed of the The RXB floor elevation at ground protected against external flooding in RXB as-built floor elevation at ground entrances is higher than the maximum order to prevent flooding of safety- entrances. external flood elevation.

related SSC within the structure.

4 The RXB includes radiation shielding An inspection will be performed of the The thickness of RXB radiation barriers for normal operation and as-built RXB radiation shielding shielding barriers is greater than or post-accident radiation shielding. barriers. equal to the required thickness specified in Table 3.11-1.

5 The RXB includes radiation An inspection will be performed of the The RXB radiation attenuating doors attenuating doors for normal as-built RXB radiation attenuating are installed in their design location operation and for post-accident doors. and have a radiation attenuation radiation shielding. These doors have a capability that meets or exceeds that radiation attenuation capability that of the wall within which they are meets or exceeds that of the wall installed in accordance with the within which they are installed. approved door schedule design.

6 The RXB is Seismic Category I and i. An inspection and analysis will be i. A design report exists and maintains its structural integrity under performed of the as-built RXB. concludes that the deviations the design basis loads. ii. An inspection will be performed of between the drawings used for the as- built RXB. construction and the as-built RXB have been reconciled, and the RXB maintains its structural integrity under the design basis loads.

ii. The dimensions of the RXB critical sections conform to the approved design.

Tier 1 3.11-7 Draft Revision 2

NuScale Tier 1 Reactor Building Table 3.11-2: Reactor Building Inspections, Tests, Analyses, and Acceptance Criteria (Continued)

No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 7 Non-Seismic Category I SSC located An inspection and analysis will be A report exists and concludes that the where a potential for adverse performed of the as-built non-Seismic Non-Seismic Category I SSC located interaction with a Seismic Category I Category I SSC in the RXB. where a potential for adverse SSC exists in the RXB will not impair interaction with a Seismic Category I the ability of Seismic Category I SSC to SSC exists in the RXB will not impair perform their safety functions during the ability of Seismic Category I SSC to or following a SSE. perform their safety functions during or following an SSE as demonstrated by one or more of the following criteria:

  • Seismic Category I SSC are isolated from non-Seismic Category I SSC, so that interaction does not occur.
  • Seismic Category I SSC are analyzed to confirm that the ability to perform their safety functions is not impaired as a result of impact from non-Seismic Category I SSC.
  • A non-Seismic Category I restraint system designed to Seismic Category I requirements is used to assure that no interaction occurs between Seismic Category I SSC and non-Seismic Category I SSC.

8 Safety-related SSC are protected An inspection and analysis will be Protective features are installed in against the dynamic and performed of the as-built high- and accordance with the as-built Pipe environmental effects associated with moderate-energy piping systems and Break Hazard Analysis Report and postulated failures in high- and protective features for the safety- safety-related SSC are protected moderate-energy piping systems. related SSC located in the RXB outside against or qualified to withstand the the Reactor Pool Bay. dynamic and environmental effects associated with postulated failures in high- and moderate-energy piping systems.

Tier 1 3.11-8 Draft Revision 2

Retrieved from "https://kanterella.com/w/index.php?title=ML18228A860&oldid=2615965"