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Category:Meeting Summary
MONTHYEARML24004A0472024-01-31031 January 2024
U.S. Nuclear Regulatory Commission Summary of the November 16, 2023, Observation Public Meeting to Discuss NuScales Us600 Exemption Request
ML20274A1082020-09-30030 September 2020
Summary of September 16, 2020 Public Meeting with NuScale Power, LLC to Discuss Operator Licensing Topics
ML20216A5462020-08-19019 August 2020
Public Summary of the July 15, 2020 Pre-Submittal Meeting with NuScale, LLC, Regarding Its Plans to Submit a Topical Report Using Automated Test System
ML20219A4112020-08-10010 August 2020
Summary of the May 28, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss Nuscale'S Standard Design Application Control Room Staffing Topical Report-0520-69851
ML20108F5082020-05-27027 May 2020
Summary of April 15 2020 Public Meeting on NuScale EPZ Sizing Methodology TR
ML20114E2162020-05-0404 May 2020
Summary of the April 1, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution of the Design Certification Application
ML20114E0192020-04-27027 April 2020
Summary of the April 15, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution of the Design Certification Application
ML20114E0392020-04-23023 April 2020
Meeting Summary for the April 21, 2020, Public Meeting to Discuss NuScale SDA Significance Review Process
ML20097C2292020-04-0707 April 2020
Summary of the March 9, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution
ML20072M7982020-03-19019 March 2020
Meeting Summary for the January 30, 2020, Public Meeting to Discuss NuScale SDA Regulatory Engagement Plan
ML20072K5232020-03-11011 March 2020
Summary of the September 4, 2019, Public Teleconference with NuScale Power, Llc., Regarding Responses to Staff Requests for Additional Information (RAI) (52-048)
ML19345E9362020-01-13013 January 2020
Summary of the December 9, 2019, Public Teleconference Meeting on Incorporation by Reference
ML19302E4602019-10-29029 October 2019
July 22, 2019 Public Meeting - NuScale Interface Items for Penetrations and Ventilation Ducts
ML19297C8772019-10-24024 October 2019
Summary of Public Meeting with NuScale to Discuss ECCS Test #47
ML19291A8872019-10-21021 October 2019
U.S. Nuclear Regulatory Commission Summary Report of Regulatory Close-out Audit of NuScale Power, LLC, Component Design Specification
ML19282B1202019-10-12012 October 2019
Summary of January 9, March 5, April and August 1, 2019, Public Teleconference with NuScale Power, LLC, Regarding NON-LOCA TR RAI Responses (PROJ0769)
ML19289C3982019-10-12012 October 2019
Summary of the January 9, 2019, March 5, 2019, April 23, 2019, and August 12, 2019, Public Teleconferences with NuScale Power, LLC
ML19281B3982019-10-10010 October 2019
Summary of September 23, 2019 - Public Teleconference on NuScale Chapter 4
ML19281B2612019-10-0909 October 2019
Sept 25, 2019 - Public Teleconference on NuScale SDA
ML19260G7352019-10-0707 October 2019
Summary of Public Meeting with NuScale to Discuss Response to RAI 9681
ML19240A3892019-10-0303 October 2019
Summary of January 8 and 29, 2019 and April 17, 2019, Public Teleconference with NuScale Power, LLC, Regarding Responses to Staff Request for Additional Information (52-048)
ML19256B7002019-09-23023 September 2019
Summary of Public Meeting with NuScale to Discuss Test #107 and Test #47 in the Initial Test Program
ML19260G5382019-09-23023 September 2019
Summary of 9-4-19 Public Meeting with NuScale to Discuss ITAAC
ML19256B4942019-09-18018 September 2019
Summary of Public Meeting with NuScale to Discuss Radiation Shielding ITAAC
ML19247C0342019-09-18018 September 2019
Summary of August 26 2019 Public Meeting with NuScale on Chapter 20
ML19252A0212019-09-12012 September 2019
August 27, 2019, Summary of Public Meeting with NuScale to Discuss Test #6, Test #47, and Test #50 in the Initial Test Program
ML19255D2722019-09-12012 September 2019
Aug 26, 2019, Summary of Public Teleconference on NuScale Chapter 4
ML19242B8092019-08-30030 August 2019
Discussion Topic for August 13 and August 19, 2019, Public Meeting to Discuss AST Methodology and H2 and O2 Monitoring for the NuScale Design Certification Application
ML19242B8802019-08-30030 August 2019
Discussion Topic for July 24, 2019, Public Meeting to Discuss Technical Specifications for the NuScale Design Certification Application
ML19242B9932019-08-30030 August 2019
Discussion Topic May 14, 2019, Public Meeting to Discuss Accident Source Term (AST) Methodology Associated with the NuScale Design Certification Application
ML19242C0162019-08-30030 August 2019
Discussion Topic May 8, 2019, Public Meeting to Discuss Post-Accident Sampling Exemption Request Associated with the NuScale Design Certification Application
ML19242C4792019-08-30030 August 2019
Discussion Topics for the March 12 2019 Public Meeting to Discuss Neutron Absorbers ITAAC and COL Information Item 9.1-8 Associated with the NuScale Design Certification Application
ML19228A2502019-08-27027 August 2019
Summary of Public Meeting with NuScale to Discuss Structural ITAAC
ML19217A3082019-08-15015 August 2019
Summary of Public Meeting with NuScale to Discuss Initial Test Program Test #107 for the Remote Shutdown Workstation
ML19212A6882019-08-12012 August 2019
Summary of Public Meeting with NuScale to Discuss Structural ITAAC
ML19199A0152019-07-31031 July 2019
Summary of Public Meeting on Various ITAAC Issues
ML19149A5052019-07-22022 July 2019
May 22 2019 NRC-NuScale Public Meeting Summary_Reduced Staffing Plan Validation Activities
ML19171A1292019-07-17017 July 2019
Summary of Category 1 Public Teleconference with NuScale Power, LLC to Discuss of Section 3.9.4 Control Rod Drive System of the Design Certification Application
ML19134A3632019-07-0808 July 2019
Summary of the April 9, 2019 Public Meeting to Discuss Accident Source Term (AST) Methodology and Post Exemption Associated with the NuScale Design Certification Application
ML19176A2502019-07-0808 July 2019
Summary of June 17, 2019 Public Meeting with NuScale on MBDBE
ML19178A3502019-06-27027 June 2019
Discussion Topics for April 09, 2019 Public Meeting with NuScale - Public Version
ML19242B9342019-06-12012 June 2019
Discussion Topic for June 12, 2019, Public Meeting to Discuss Technical Specifications for the NuScale Design Certification Application
ML19151A3382019-06-0505 June 2019
Summary of Public Meeting with NuScale to Discuss ITAAC for the Module Protection System and Safety Display and Indication System
ML19087A2402019-05-0606 May 2019
Summary of March 5, 2019 Public Meeting on NuScale EPZ Sizing Methodology TR
ML19106A0452019-04-24024 April 2019
Summary of Public Teleconference Held April 15, 2019, Regarding the Inspections, Tests, Analyses, and Acceptance Criteria in NuScale Power Llc'S Design Certification Application
ML18340A0132019-04-17017 April 2019
July 24, 2018, Summary of Category 1 Public Teleconference with Nuscale Power, LLC, Design Certification Application Section 3.7, Seismic Design, and 3.8, Design of Category I Structures.
ML18348A9442019-04-17017 April 2019
Summary of the Category 1 Public Teleconference with NuScale Power, LLC Design Certification Application Section 3.6.3, Leak-Before-Break Evaluation Procedures, and Section 3.9.4, Control Rod Drive System.
ML18333A3612019-04-11011 April 2019
& 08/28/18 Summary of Public Teleconference with Nuscale Power, LLC, Regarding Responses to Staff Requests for Additional Information
ML19065A1242019-04-0505 April 2019
Summary of the February 14 and 27, 2019, Public Meeting to Discuss Accident Source Term (AST) Methodology Associated with the Nuscale Design Certification Application
ML19085A0412019-03-26026 March 2019
02/13/2019 and 03/06/2019 Summary of Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Progress on Emergency Core Cooling System Valve Test Plans of the Design Certification Application
2024-01-31
[Table view]
Category:Memoranda
MONTHYEARML24004A0472024-01-31031 January 2024
U.S. Nuclear Regulatory Commission Summary of the November 16, 2023, Observation Public Meeting to Discuss NuScales Us600 Exemption Request
ML20274A1082020-09-30030 September 2020
Summary of September 16, 2020 Public Meeting with NuScale Power, LLC to Discuss Operator Licensing Topics
ML20199M1492020-08-19019 August 2020
Memo Transmitting Summary of the July 15, 2020 Pre-Submittal Meeting with NuScale, LLC, Regarding Its Plans to Submit a Topical Report Using Automated Test System
ML20219A4112020-08-10010 August 2020
Summary of the May 28, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss Nuscale'S Standard Design Application Control Room Staffing Topical Report-0520-69851
ML20210M0772020-07-28028 July 2020
Memo - Category 1 Public Meeting - Audit Exit NuScale Emergency Core Cooling System Boron Redistribution Issue and Applicable Design Changes
ML20160A2472020-07-28028 July 2020
Audit Summary Memo NuScale ECCS Boron Redistribution Issue
ML20176A1582020-07-10010 July 2020
Audit Summary 2019 Memo NuScale Chapter 15
ML20108F5082020-05-27027 May 2020
Summary of April 15 2020 Public Meeting on NuScale EPZ Sizing Methodology TR
ML20140A1892020-05-19019 May 2020
Public Meeting Summary May 14, 2020, NuScale Boron Redistribution Issue
ML20114E2162020-05-0404 May 2020
Summary of the April 1, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution of the Design Certification Application
ML20114E0192020-04-27027 April 2020
Summary of the April 15, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution of the Design Certification Application
ML20114E0392020-04-23023 April 2020
Meeting Summary for the April 21, 2020, Public Meeting to Discuss NuScale SDA Significance Review Process
ML20097C2292020-04-0707 April 2020
Summary of the March 9, 2020, Category 1 Public Teleconference with NuScale Power, LLC to Discuss the Emergency Core Cooling System Boron Distribution
ML20072M7982020-03-19019 March 2020
Meeting Summary for the January 30, 2020, Public Meeting to Discuss NuScale SDA Regulatory Engagement Plan
ML20076D8852020-03-16016 March 2020
Summary Report for the January 2019 Regulatory Audit of NuScale Chapter 20
ML20072K5232020-03-11011 March 2020
Summary of the September 4, 2019, Public Teleconference with NuScale Power, Llc., Regarding Responses to Staff Requests for Additional Information (RAI) (52-048)
ML20059N6872020-03-0202 March 2020
Regulatory Audit Plan for NuScale DCA Chapters 6, 7, and 15
ML20054A0602020-02-28028 February 2020
Regulatory Audit Report for NuScale DCA Inadvertent Actuation Block (Iab) Operating Range Change
ML20044E3522020-02-18018 February 2020
Memo to ACRS Rod Ejection Accident Methodology SER
ML20049H1872020-02-18018 February 2020
Memo to ACRS Rea NON-LOCA TR SE
ML20049H5442020-02-18018 February 2020
Letter to NuScale NON-LOCA TR SER
ML20042E0242020-02-12012 February 2020
LOCA Topical Report Phase IV Audit Report - Public
ML20042E0392020-02-12012 February 2020
NON-LOCA Topical Report Phases 3 and 4 Audit Report
ML20010D1312020-01-16016 January 2020
Audit Summary Memo NuScale LOCA TR
ML19345E9362020-01-13013 January 2020
Summary of the December 9, 2019, Public Teleconference Meeting on Incorporation by Reference
ML19340A9712020-01-13013 January 2020
U.S. Nuclear Regulatory Commission Report of the Regulatory Follow-Up Audit Performed Between May 1, 2019, Through September 19, 2019, Regarding the Nuscale Stress and Fatigue Analysis of Major Design Components (Public)
ML20006G4202020-01-0808 January 2020
ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapters 2, 8 and 12
ML19343C7562020-01-0808 January 2020
Generator Tube - Siet Audit Report (Public)
ML20006G5752019-12-20020 December 2019
Proposed Recommendation for ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 8, Electric Power
ML19331A3972019-12-20020 December 2019
U.S. Nuclear Regulatory Commission Report of the Regulatory follow-up Audit Performed Between 8/22/19 - 9/24/19, Regarding NuScale Power, Seismic Category I Equipment and Environment Qualification of Electrical Equipment Specifications
ML19340A0152019-12-20020 December 2019
U.S. Nuclear Regulatory Commission'S Report of the Regulatory Audit Performed Between March 4, 2019, Through September 10, 2019, for Nuscale Power, LLC, Regarding Nuscale'S Power Module Leakage Flow Instability Analysis - Public Memo
ML20006G4892019-12-19019 December 2019
Proposed Recommendation for ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 2, Site Characteristics and Site Parameters
ML19340A0192019-12-19019 December 2019
U.S. Nuclear Regulatory Commission Report - Regulatory Audit Between 03/20/19 - 10/09/19 - Emergency Core Cooling System Valve Design Demonstration Testing and Follow-Up Items NuScale Power, LLC, Standard Plant Design Certification
ML20006G7002019-12-19019 December 2019
Proposed Recommendation for ACRS Review of NuScale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 12, Radiation Protection
ML19143A1042019-12-12012 December 2019
DCA - Safety Evaluation with No Open Items for Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors - Memo
ML19168A1382019-12-12012 December 2019
LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 3, Design of Structures, Systems, Components and Equipment
ML19169A2992019-12-11011 December 2019
Memo to ACRS Transmitting SER - Chapter 15
ML19169A1322019-12-10010 December 2019
Memo to ACRS Transmitting SER
ML19165A2792019-12-0909 December 2019
Nuscale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 1, Introduction and General Discussion
ML19168A1682019-12-0909 December 2019
Nuscale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 4, Reactor - Memo
ML19168A2002019-12-0909 December 2019
Memo to ACRS Transmitting SER - Chapter 6
ML19169A3142019-12-0404 December 2019
LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 16, Technical Specifications - Memo
ML19169A3322019-12-0404 December 2019
LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 20, Mitigation of Beyond-Design-Basis Events - Memo
ML19169A2952019-11-26026 November 2019
Memo to ACRS Transmitting SER
ML19319C2322019-11-26026 November 2019
U.S. Nuclear Regulatory Commission Summary Report of Regulatory follow-up Audit of Design Documents for NuScale Containment Isolation Valves and Reactor Safety Valves
ML19270G6762019-11-22022 November 2019
Audit Summary for the Regulatory Audit of NuScale Power, LLC, Final Safety Analysis Report Chapter 15, Transient and Accident Analyses, (Memo)
ML19169A2912019-11-22022 November 2019
Memo to ACRS Transmitting SER
ML19169A1192019-11-22022 November 2019
Memo to ACRS Transmitting Phase 4 SER for Chapter 8
ML19162A2732019-11-15015 November 2019
LLC, Design Certification Application Memo - Safety Evaluation with No Open Items for Chapter 18, Human Factors Engineering
ML19162A0962019-11-13013 November 2019
Nuscale Power, LLC, Design Certification Application - Safety Evaluation with No Open Items for Chapter 2, Site Characteristics and Site Parameters
2024-01-31
[Table view] |
Text
July 17, 2019 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors FROM: Marieliz Vera, Project Manager /RA/
Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors
SUBJECT:
SUMMARY
OF THE MAY 22, 2019, CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC, TO DISCUSS OF SECTION 3.9.4, CONTROL ROD DRIVE SYSTEM, OF THE DESIGN CERTIFICATION APPLICATION The U.S. Nuclear Regulatory Commission (NRC) held a Category 1 public teleconference on May 22, 2019, to discuss Section 3.9.4, Control Rod Drive System, of the NuScale Power, LLC (NuScale) Design Certification Application. Participants included personnel from NuScale.
The public meeting notice can be found in the Agencywide Documents Access and Management Systems under Accession No. ML19142A075. This meeting notice was also posted on the NRC public website.
The meeting agenda and list of participants can be found in Enclosures 1 and 2, respectively.
CONTACT: Marieliz Vera, NRO/DLSE 301-415-5861
S. Lee 2 Summary:
Purpose:
Discuss the potential for boric acid to accumulate in the Control Rod Drive Mechanisms (CRDMs) due to the volatility of boric acid in the reactor coolant.
The NRC staff began the meeting by summarizing points made during the Advisory Committee on Reactor Safeguards (ACRS) subcommittee meeting on Chapter 4 and 5 - the ACRS inquired about unique environmental conditions for the control rod drive mechanisms, which are very similar in configuration to existing pressurized water reactors (PWRs), but operate in different environmental conditions. Specifically, an ACRS member inquired about the potential for chemical buildup formed by substances evaporating off the top of the pressurizer water level and this goo (as the ACRS member put it) preventing the rod from inserting into the core.
The NRC staff elaborated on the concern, stating that significant accumulation of particulates such as boric acid crystals around the moveable elements of the CRDM latch mechanism could inhibit the ability of the latches to release the control rod drive shafts and scram the reactor.
This accumulation need not be limited to a single CRDM, so this may lead to a common cause failure of all control rod drive mechanisms.
The NRC staff indicated that a similar phenomenon is being evaluated for boron dilution under Request for Additional Information (RAI) 8930, Question 15-27, but for long-term cooling after Emergency Core Cooling System (ECCS) actuation.
Because the metal surfaces of the CRDM are cooled by the CRDM cooling coils, these metal surfaces are cooler and would be a preferential site for solid boron accumulation. The volatility of boric acid increases with temperature, so the high operating temperature above the pressurizer during normal operation could magnify this effect.
During the ACRS full committee meeting, held on May 2, 2019, a NuScale representative indicated that the presence of noncondensable gases in the CRDM would displace any steam which could carry the previously mentioned goo into the CRDM for deposition. While noncondensable gases may be present, the necessary volume of these gases to displace this steam would be rather significant, given that the NuScale normal operating conditions are substantially higher than atmospheric pressure and the temperature of the ultimate heat sink.
Additionally, because of the temperature differential between the components cooled by the CRDM cooling coils and the rest of the reactor coolant system, it is feasible that a driving force could push steam up into the housing, where it will mix with the noncondensable gases, condense, and recirculate back into the pressurizer.
The NRC staff sought to understand the potential for boric acid accumulation in the CRDMs and if NuScale had considered this effect or knew of any studies that could provide insights on the effect of boric acid on NuScales CRDM operation.
NuScale personnel provided their characterization of the ACRS concerns - summarized as the operating environment of the CRDMs as well a bathtub ring effect on the surface of the drive shaft at the liquid/steam interface.
The bathtub ring effect was described by NuScale as not plausible for the NuScale design, as the effect is generally associated with air at less than 100 percent humidity, and NuScales design will be at saturated conditions. Even if something were to accumulate around the shaft,
S. Lee 3 NuScale indicated that it would not be significant enough to impede the rods from dropping, based on observations from misalignment testing conducted in Germany, where grossly misaligned steel supports did not slow the rods during testing. Staff agrees, considering the significant weight of the shaft.
NuScale then discussed the CRDM operating environment. The CRDM coils are cooled by the cooling coil system. Each discrete volume of gases from the pressurizer in this localized area will be cooled, concentrating any hydrogen at the top, since the steam and boron will condense and drop back into the pressurizer. Each new volume of gases that travels into this space will further concentrate the hydrogen. NuScales best estimate of the hydrogen development is that within roughly 10 minutes, the space will be hydrogen solid. Hydrogen is added during startup to de-oxygenate the reactor cooling system (RCS) in addition to any that is generated during operation. Startup is different for NuScale than the existing PWR fleet, in that they do not go water-solid in the pressurizer then create a steam bubble with the pressurizer heaters. Instead, the water level is over the pressurizer heaters, but the space above is nitrogen.
The chemistry aspects of boron were discussed. NuScale and NRC staff discussed the studies and experiments found during literature reviews - NuScale intends to share these in response to RAI 8930 on a similar, but unrelated topic. NuScale believes that the boron will remain with the H2O molecules in vapor or liquid form and will not plate out. NuScale also shared some operating experience from San Onofre, where a small amount (small percentage, but large quantity) of boron was added to the secondary side of the steam generators and, despite significant volumes of steam passing through the turbine, no deposition was observed.
The staff reviewing RAI 8930 did not agree with NuScales position, but this topic will be discussed at a later meeting.
Overall summary - NuScale believes that any boric acid carried by water vapor, at a concentration below the solubility limit, will not separate from the H2O molecules.
Docket No.52-048
Enclosures:
- 1. Meeting Agenda
- 2. List of Attendees cc w/encls.: DC NuScale Power, LLC Listserv
ML19171A129 *via e-mail NRC-002 OFFICE NRO/DLSE/LB1: PM NRO/DLSE/LB1: LA NRO/DNRL/LB1: PM NAME MVera MMoore MVera DATE 6/11//2019 06/20/2019 07/17/2019 U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC TO DISCUSS SECTION 3.9.4, CONTROL ROD DRIVE SYSTEM, OF THE CERTIFICATION APPLICATION May 22, 2019 11:00 a.m. - 12:00 p.m.
AGENDA Public Meeting 11:00 - 11:15 a.m. Welcome and Introductions 11:15 - 11:30 a.m. Technical discussion 11:30 - 11:40 a.m. Public - Questions and Comments 11:40 - 12:00 p.m. Closed portion
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC TO DISCUSS SECTION 3.9.4, CONTROL ROD DRIVE SYSTEM, OF THE CERTIFICATION APPLICATION LIST OF ATTENDEES May 22, 2019 NAME AFFILIATION Marieliz Vera U.S. Nuclear regulatory Commission (NRC)
Nicholas Hansing NRC Ryan Nolan NRC Timothy Lupold NRC Rebecca Karas NRC Carl Thurston NRC Marty Bryan NuScale Power, LLC (NuScale)
Wayne Massie NuScale JJ Arthur NuScale Colin Sexton NuScale Derek Noel NuScale Vern Pence NuScale Jonathon Muniga NuScale