ML22143A836
| ML22143A836 | |
| Person / Time | |
|---|---|
| Issue date: | 05/25/2022 |
| From: | Matthew Homiack NRC/RES/DE |
| To: | |
| Kalikian R, 301-415-5590 | |
| Shared Package | |
| ML22143A408 | List: |
| 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