ML20175A905
| ML20175A905 | |
| Person / Time | |
|---|---|
| Site: | 99900003 |
| Issue date: | 06/23/2020 |
| From: | NRC |
| To: | NRC/NRR/DNRL/NRLB |
| References | |
| Download: ML20175A905 (7) | |
Text
From: Franovich, Rani Sent: Tuesday, June 23, 2020 7:32 PM To: GEH-BWRX-300RAIsPEm Resource
Subject:
Request for Additional Information 9745 Attachments: Letter 4 RAI_9745 Public.pdf Rani Rani Franovich NuScale Design Certification GE-Hitachi BWRX-300 Design Review
Hearing Identifier: GEH_BWRX300_RAIs_Public Email Number: 6 Mail Envelope Properties (BY5PR09MB43586EACC273479B7AD82D2B8F940)
Subject:
Request for Additional Information 9745 Sent Date: 6/23/2020 7:32:20 PM Received Date: 6/23/2020 7:32:24 PM From: Franovich, Rani Created By: Rani.Franovich@nrc.gov Recipients:
"GEH-BWRX-300RAIsPEm Resource" <GEH-BWRX-300RAIsPEm.Resource@nrc.gov>
Tracking Status: None Post Office: BY5PR09MB4358.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 126 6/23/2020 7:32:24 PM Letter 4 RAI_9745 Public.pdf 148647 image002.jpg 13302 image004.png 26665 Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
OFFICIAL USE ONLY - PROPRIETARY INFORMATION Request for Additional Information 9745 Issue Date: 06/22/2020 Application
Title:
GEH BWRX-300 Topical Reports Operating Company: GE Hitachi Nuclear Energy (Wilmington, NC)
Docket No. 99900003 Review Section: 03.09.06 - Functional Design Qualification and Inservice Testing Programs for Pumps, Valves, and Dynamic Restraints Application Section:
QUESTIONS 03.09.06-15 SER Section 3.9.6: NRC Standard Review Plan (SRP) Section 3.9.6 specifies that the NRC staff will review the functional design, qualification, and inservice testing (IST) program for pumps, valves, and dynamic restraints to perform their design-basis safety functions. The NRC regulations in 10 CFR Part 50, Appendices A and B, and 10 CFR 50.55a include requirements for the capability of pumps, valves, and dynamic restraints to perform their safety functions. Section 2.2.7, "Containment Isolation Valves," in NEDC-33911 describes the various containment isolation valves (CIVs) used in the BWRX-300 nuclear power plant. The capability of CIVs to perform their design-basis functions is safety significant to provide assurance that the containment of the BWRX-300 reactor can be safely isolated and prevent radioactive release to the environment that exceeds regulatory requirements. In accordance with 10 CFR Part 50, Appendix A, GDC 1, 2, 4, 54, 55, 56, and 57 for the various CIVs to be used in the BWRX-300, the NRC staff requests the following:
(a) Any first of a kind (FOAK) features, (b) Valve and actuator types, (c) Valve size, (d) Qualification, such as compliance with ASME Standard QME-1-2007 (or later edition) as accepted in NRC Regulatory Guide 1.100, (e) Plans for valve and actuator diversity, (f) Incorporation of lessons learned from CIV performance, (g) Accessibility for inservice testing (IST) activities in accordance with 10 CFR 50.55a, (h) Design features to avoid thermal binding or pressure locking of the valves, as applicable, and (i) OM Code leakage classification.
OFFICIAL USE ONLY - PROPRIETARY INFORMATION
OFFICIAL USE ONLY - PROPRIETARY INFORMATION If any of this information is not available at this time, the NRC staff requests that GEH clarify the plans to provide this information during future licensing activities for the BWRX-300 nuclear power plant.
03.09.06-16 SER Section 3.9.6: NRC Standard Review Plan (SRP) Section 3.9.6 specifies that the NRC staff will review the functional design, qualification, and inservice testing (IST) program for pumps, valves, and dynamic restraints to perform their design-basis safety functions. The NRC regulations in 10 CFR Part 50, Appendices A and B, and 10 CFR 50.55a include requirements for the capability of pumps, valves, and dynamic restraints to perform their safety functions. Section 2.2.8, Passive Containment Cooling System (PCCS), in NEDC-33911 provides an overview description of the PCCS for the BWRX-300 that ((. The PCCS provides a (( }}. However, the topical report is not clear regarding the use of any valves or pumps in the PCCS. In accordance with 10 CFR Part 50, Appendix A, GDC 1, 2, 4, 54, 55, 56, and 57, the NRC staff requests that GEH describe any valves or pumps that are part of the PCCS for the BWRX-300, and their design and qualification. 03.09.06-17 SER Section 3.9.6: Section 5.1.1, 10 CFR 50.34(f), in NEDC-33911 discusses compliance with specific requirements in 10 CFR 50.34(f) related to the TMI-2 accident lessons learned. In describing compliance with 10 CFR 50.34(f)(2)(xiv) with respect to containment isolation systems, NEDC-33911 indicates that the CIVs do not reopen on resetting of the signals. NRC Standard Review Plan (SRP) Section 3.9.6 specifies that the NRC staff will review the functional design, qualification, and inservice testing (IST) program for pumps, valves, and dynamic restraints to perform their design-basis safety functions. The NRC regulations in 10 CFR Part 50, Appendices A and B, and 10 CFR 50.55a include requirements for the capability of pumps, valves, and dynamic restraints to perform their safety functions. The capability of CIVs to perform their design-basis functions is safety significant to provide assurance that the containment of the BWRX-300 reactor can be safely isolated and prevent radioactive release to the environment that exceeds regulatory requirements. The NRC staff requests that GEH clarify the CIV designs will prevent valve disc movement during their long-term isolation function. 03.09.06-18 SER Section 3.9.6: NRC Standard Review Plan (SRP) Section 3.9.6 specifies that the NRC staff will review the functional design, qualification, and inservice testing (IST) program for pumps, valves, and dynamic restraints to perform their design-basis safety functions. The NRC regulations in 10 CFR Part 50, Appendices A and B, and 10 CFR 50.55a include requirements for the capability of pumps, valves, and dynamic restraints to perform their safety functions. The NRC staff review under SRP Section 3.9.6 includes planned alternatives and their safety significance to the editions and addenda of the ASME Boiler and Pressure Vessel Code (BPV Code) and ASME Operation and Maintenance of Nuclear Power Plants (OM Code). Section 5.2, "Regulatory Guides," in NEDC-33911 does not discuss NRC Regulatory Guide (RG) 1.84, RG 1.147, or RG 1.192, as they relate to the acceptability of Code Cases for the ASME BPV OFFICIAL USE ONLY - PROPRIETARY INFORMATION
OFFICIAL USE ONLY - PROPRIETARY INFORMATION Code and ASME OM Code for design, inservice inspection, and IST activities in satisfying 10 CFR 50.55a, respectively. The NRC staff requests GEH to clarify the intent of the topical report regarding these RGs. 03.09.06-19 SER Section 3.9.6: NRC Standard Review Plan (SRP) Section 3.9.6 specifies that the NRC staff will review the functional design, qualification, and inservice testing (IST) program for pumps, valves, and dynamic restraints to perform their design-basis safety functions. The NRC regulations in 10 CFR Part 50, Appendices A and B, and 10 CFR 50.55a include requirements for the capability of pumps, valves, and dynamic restraints to perform their safety functions. Section 5.3, "NUREG-0800 Standard Review Plan Guidance," in NEDC-33911 does not address the plans to satisfy SRP Section 3.9.6 for the functional design, qualification, and IST programs for pumps, valves, and dynamic restraints, to provide assurance of their design-basis capability. The NRC staff requests GEH to clarify the intent of the topical report regarding SRP Section 3.9.6. 03.09.06-20 SER Section 3.9.6: NRC Standard Review Plan (SRP) Section 3.9.6 specifies that the NRC staff will review the functional design, qualification, and inservice testing (IST) program for pumps, valves, and dynamic restraints to perform their design-basis safety functions. The NRC regulations in 10 CFR Part 50, Appendices A and B, and 10 CFR 50.55a include requirements for the capability of pumps, valves, and dynamic restraints to perform their safety functions. Section 5.4, Generic Issues, and Section 5.5, Operational Experience and Generic Communications, in NEDC-33911 only discusses two items with respect to these topics. As part of its SRP Section 3.9.6 review, the NRC staff evaluates the consideration of safety significant aspects of generic issues, operational experience, and generic communications for the functional design, qualification, and IST programs for pumps, valves, and dynamic restraints to provide assurance that those components are capable of performing their design-basis functions. The NRC staff requests that GEH clarify that an up-to-date evaluation of generic issues, and operational experience and generic communications, will be provided during future licensing activities under 10 CFR Part 50 or Part 52. OFFICIAL USE ONLY - PROPRIETARY INFORMATION}}