St. Rosinski et Ro. Hardies, Pressurized thermal shock screening criteria re-evaluation effort - US industry activities, INT J PRES, 78(2-3), 2001, pp. 147-153
Citations number
6
Categorie Soggetti
Mechanical Engineering
Journal title
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING
A joint project is under way between the US nuclear power industry and the
US Nuclear Regulatory Commission (NRC) to re-evaluate the pressurized therm
al shock (PTS) screening criteria as presently defined in title 10 of the C
ode of Federal Regulations, 10 CFR 50.61. Advances in probabilistic risk as
sessment (PRA), probabilistic fracture mechanics (PFM), thermal hydraulics
(TH), and overall plant risk assessment are being incorporated into a compr
ehensive program to establish a technical basis for revising the present sc
reening criteria. US industry activities are being coordinated through the
Reactor Pressure Vessel Integrity Issue Task Group (RPV Integrity ITG) of t
he EPRI Materials Reliability Project (MRP). The EPRI MRP was formed in 199
8 to identify and address issues that could affect operability of major com
ponents in pressurized water reactor (PWR) plants. Major activities are coo
rdinated with the nuclear steam supply system (NSSS) vendors, the vendor ow
ner's groups, The Nuclear Energy Institute (NEI), and the NRC. The MRP prov
ides for a unified industry approach to resolution of technical and regulat
ory issues related to PWR materials degradation. A major task under the Rea
ctor Pressure Vessel Integrity Issue Task Group (RPV Integrity ITG) is to s
upport industry activities associated with the pressurized PTS re-evaluatio
n effort. This paper provides a brief overview of the EPRI MRP program, the
RPV Integrity ITG, and industry activities associated with the PTS re-eval
uation effort. (C) 2001 Elsevier Science Ltd. All rights reserved.