ML22143A836

18 - 2022 NRC-Industry Mtls Exchange Mtg - NRC Xlpr Presentation

ML22143A836
Person / Time
Issue date:	05/25/2022
From:	Matthew Homiack NRC/RES/DE
To:
Kalikian R, 301-415-5590
Shared Package
ML22143A408	List: ML22140A021 ML22140A023 ML22143A694 ML22143A825 ML22143A826 ML22143A827 ML22143A828 ML22143A829 ML22143A830 ML22143A831 ML22143A832 ML22143A834 ML22143A836 ML22143A837 ML22143A838 ML22143A839 ML22143A840 ML22143A842 ML22143A843 ML22143A844 ML22143A862 ML22143A875 ML22143A887
References
Download: ML22143A836 (9)

Text

E x t r e m e l y L o w P r o b a b i l i t y o f R u p t u r e

( x L P R ) C o d e N R C P e r s p e c t i v e s Matthew Homiack Materials Engineer U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research Division of Engineering Reactor Engineering Branch Matthew.Homiack@nrc.gov

+1 (301) 415-2427

2 F r a c t u r e M e c h a n i c s D i f f e r e n t A n a l y s i s A p p r o a c h e s Stress

+

Toughness +

Crack Growth +

Crack Size Life Probabilistic Approach Deterministic Approach Conservatively High Value Conservatively Low Value Conservatively High Value Conservatively High Value Multiple Calculations Aggregated to Give Probability of Failure over Time Single Calculation Plus Margin Gives

Single, Conservative Result

> Stress-Corrosion Cracking

> Thermal and Mechanical Fatigue

> Crack Initiation

> Leak Rate Calculations

> Residual Stress Effects

> Water Chemistry

> Ultrasonic Inspections

> Seismic Effects

> Mechanical Mitigation 3

x L P R C o d e C a p a b i l i t i e s a n d L i m i t a t i o n s

> Models Only Certain Failure Modes

> Limited to Butt-Weld Geometry

> Only Performs Component-Level Analyses 3

NUREG-2247 / Electric Power Research Institute (EPRI) 3002013307 Extremely Low Probability of Rupture Version 2 Probabilistic Fracture Mechanics Code R e c e n t l y C o m p l e t e d N R C P r o j e c t s 4

ML21225A736 TLR-RES/DE/REB-2021-09 Probabilistic Leak-Before-Break Evaluation of Westinghouse Four-Loop Pressurized-Water Reactor Primary Coolant Loop Piping using the Extremely Low Probability of Rupture Code ML21217A088 TLR-RES/DE/REB-2021-14-R1 Probabilistic Leak-Before-Break Evaluations of Pressurized-Water Reactor Piping Systems using the Extremely Low Probability of Rupture Code ML22088A006

O n g o i n g N R C P r o j e c t s 5

International Benchmark Co-leading Study Organized through the Nuclear Energy Agency Software Maintenance and Development Continued Cooperation with EPRI

Summer 2022

> Improved preprocessor with 64-bit support

> Minor bug fixes identified through leak-before-break studies

> Other user enhancements x L P R V e r s i o n 2. 2 R e l e a s e 6

7 F u t u r e N R C P l a n s 7

> C o n t i n u e t o m a i n t a i n a n d d e v e l o p t h e c o d e t o t h e s t a t e - o f - p r a c t i c e

> U s e t h e x L P R c o d e t o s u p p o r t r i s k - i n f o r m e d d e c i s i o n s o n l i c e n s i n g r e v i e w s a n d o t h e r r e g u l a t o r y a c t i v i t i e s

> B u i l d t h e i n t e r n a t i o n a l u s e r c o m m u n i t y

June 14th Public meeting with EPRI to Discuss Use of the xLPR Code for Loss-of-Coolant Accident Frequency Estimates

> Details and agenda are in the public meeting announcement (ML22133A035)

P u b l i c M e e t i n g A n n o u n c e m e n t MARK CALENDAR 8

H a v e Q u e s t i o n s o r N e e d I n f o r m a t i o n o n x L P R ?

xlpr@nrc.gov xlpr@epri.com 9