ML18260A221

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Memo, Summary of the September 11, 2018, Category 1 Public Teleconference with NuScale Power, LLC Design Certification Application Final Safety Analysis Report, Tier 2, Section 3.9.6, Functional Design, Qualification, and Inservice Testing
ML18260A221
Person / Time
Site: NuScale
Issue date: 09/24/2018
From: Vera M
NRC/NRO/DLSE/LB1
To: Samson Lee
NRC/NRO/DLSE/LB1
Vera M/415-5861
References
Download: ML18260A221 (5)


Text

September 24, 2018 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 SEPTEMBER 11, 2018, CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION FINAL SAFETY ANALYSIS REPORT, TIER 2, SECTION 3.9.6, FUNCTIONAL DESIGN, QUALIFICATION, AND INSERVICE TESTING PROGRAMS FOR PUMPS, VALVES, AND DYNAMIC RESTRAINTS The U.S. Nuclear Regulatory Commission (NRC) held a Category 1 public teleconference on September 11, 2018, to discuss Final Safety Analysis Report (FSAR) Tier 2, Chapter 3, Design of Structures, Systems, Components and Equipment, Section 3.9.6, Functional Design, Qualification, and Inservice Testing Programs for Pumps, Valves, and Dynamic Restraints, of the NuScale Power, LLC (NuScale) Design Certification. Participants included personnel from NuScale and members of the public.

The public meeting notice can be found in the Agencywide Documents Access and Management Systems under Accession No. ML18254A056. 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:

The purpose of this meeting was to discuss the boron effects evaluation during the emergency core cooling system (ECCS) valve design demonstration testing.

The NRC staff discussed that the design demonstration testing of the safety features for the ECCS valves to support the NuScale Design Certification should demonstrate that boron deposits resulting from flashing of the reactor coolant in the ECCS valve main control chamber, inadvertent actuation block (IAB) valve, and associated tubing will not adversely affect the performance of the IAB valve (a) to close and seal in a timely manner to prevent the main valve from opening prematurely; and (b) to open at the proper differential pressure between the reactor coolant system and the containment vessel to allow the pressure in the main control chamber to be reduced such that the main valve will fully open in a timely manner.

Also, the ECCS valve design demonstration testing should demonstrate that the portions of the ECCS valve system in low temperature areas (such as the trip valves and associated tubing in the reactor pool) will not be adversely impacted by boron precipitation that could result in inadequate blowdown of the tubing that interferes with the proper performance of the ECCS valve system (including the IAB valve, main control chamber, trip valve, and tubing) to prevent premature opening of the main valve and to allow timely opening of the main valve.

NuScale intends to submit a letter describing its plans for the design demonstration testing of the ECCS valves.

Docket No.52-048

Enclosures:

1. Meeting Agenda
2. List of Attendees cc w/encls.: DC NuScale Power, LLC Listserv

ML18260A221

  • via email NRC-002 OFFICE NRO/DLSE/LB1: PM NRO/DLSE/LB1: LA NRO/DNRL/LB1: PM NAME MVera MMoore MVera DATE 09/17/2018 09/19/2018 09/24/2018

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION FINAL SAFETY ANALYSIS REPORT, TIER 2, SECTION 3.9.6, FUNCTIONAL DESIGN, QUALIFICATION, AND INSERVICE TESTING PROGRAMS FOR PUMPS, VALVES, AND DYNAMIC RESTRAINTS September 11, 2018 11:00 a.m. - 12:00 p.m.

AGENDA Public Meeting 11:00-11:10am Welcome and Introductions 11:10-11:45am Technical discussion 11:45-12:00pm Public - Questions and Comments

1 U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION FINAL SAFETY ANALYSIS REPORT, TIER 2, SECTION 3.9.6, FUNCTIONAL DESIGN, QUALIFICATION, AND INSERVICE TESTING PROGRAMS FOR PUMPS, VALVES, AND DYNAMIC RESTRAINTS LIST OF ATTENDEES September 11, 2018 NAME AFFILIATION Marieliz Vera U.S. Nuclear regulatory Commission (NRC)

Timothy Lupold NRC Thomas Scarbrough NRC Ryan Nolan NRC Marty Bryan NuScale Power, LLC (NuScale)

Zack Houghton NuScale Paul Infanger NuScale Daniel Lassiter NuScale Colin Sexton NuScale Greg Myers NuScale Sarah Fields Public