ML19134A239

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25-High Energy Line Break (HELB)
ML19134A239
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Issue date: 05/20/2019
From: Michael Benson, Sara Lyons, Robert Tregoning
Office of Nuclear Regulatory Research
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High Energy Line Break (HELB)

Michael Benson, Sara Lyons, Robert Tregoning Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission NRC/Industry Materials Programs Technical Information Exchange May 21-22, 2019

High Energy Line Break Issue

  • HELB Class 1 piping locations in some plants are limited to a cumulative usage factor (CUF) of 0.1

- Some plants may have difficulty meeting this limit for subsequent license renewal

- Identified as a possible issue for new plants

  • EPRI proposed a risk-informed alternative for establishing postulated break locations (EPRI 1022873, 2011) 2

Branch Technical Position 3-4

- Safety-related components must be designed to accommodate the effects of and to be compatible with the environmental conditions associated with postulated accidents

- Describes methods acceptable to the staff for complying with GDC 4

- Provides guidance for jet force modeling

- References Branch Technical Position 3-4 (BTP 3-4)

  • Branch Technical Position 3-4

- Includes criteria for selecting postulated break locations

  • Stress-based criteria
  • CUF criterion 3

History of CUF Criterion

  • First record - 1972 Giambusso letter (Appendix B of BTP 3-3, ML070800027)
  • Early BTP versions only consider CUF criterion when the maximum stress range exceeds a certain value; provision eliminated in later versions
  • January 2012 public meeting on fatigue issues (ML120120028)

- EPRI presented risk-informed approach to postulated break locations (Report 1022873)

- If environmental effects were accounted for, staff demonstrated willingness to accept 0.4

- Staff was not aware of a compelling reason to update the criterion at that time

  • Economic Simplified Boiling Water Reactor Design Certification

- Staff permitted a relaxed CUF criterion if environmental effects considered

- BTP3-4 updated to state CUF limit of 0.4 when environmental effects considered

  • Recently, staff has developed a draft technical letter report describing the history of BTP 3-4, with a focus on the CUF criterion 4

HELB/CUF Issue Timeline at NRC 2010 NRR/NRO User Need Request (UNR) included investigation of CUF criterion 2012

  • January 5th Environmentally Assisted Fatigue (EAF) public meeting (meeting summary: ML120120028)
  • Industry identified no need to address until 2020s
  • NRC delayed work associated with 2010 UNR until completion of xLPR 2014 NRO escalated HELB issue for new reactors 2015 Second NRR/NRO UNR included investigation of CUF criterion 2018 September 25th EAF public meeting (meeting summary:

ML18289A322) 5

Technical Letter Report

  • Discusses current stress and fatigue criteria in BTP 3-4
  • Summarizes historical background of BTP 3-4 development
  • Describes existing proposed alternatives to the current CUF criterion 6

Current Status

  • Technical Letter Report documenting background and known bases for CUF criteria for existing and new reactors is being finalized for public release
  • NRC staff informally reviewing EPRIs risk-informed proposal (EPRI 1022873)
  • June 11, 2019 - NRC public meeting to discuss HELB and potential drivers warranting further work 7

Public Meeting Draft Agenda

  • Introductions and meeting objective
  • Background
  • Overview of EPRI 1022873 report
  • Overview of NRC comments on EPRI 1022873 report

- SLR for BWRs

- SLR for PWRs

- Design certification for new reactors

  • Discussion of next steps to:

- identify a regulatory path forward

- develop the technical basis supporting proposed changes 8