Document: NRC Regulatory Guide
Document ID: da2e0703-3488-44b0-b6d0-089aac7cae3d
Document Type: regulatory_guide
Title: Format and Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0037/ML003740028.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.154
CFR Part: 
CFR Title: 

Content:
ce cooling water 2.2 Reactor Vessel Summarize the reactor vessel construction and i t s material properties. Use tables, drawings, or graphs t o show: O Vessel design (including weld locations and hot leg and cold 1 eg penetrations). Vessel materials and chemical composition i n the b e l t l i n e region (including both base and weld material properties). O Vessel fabrication procedures, p a r t i c u l a r l y welding and cladding. 0 Vessel properties (e. g. , RTNDT, i n i t i a l RTNDT, appropriate fracture C toughness data, including the upper-shelf regime, residual stresses, flaw density distribution, etc. ). Describe and j u s t i f y methods used t o calculate o r otherwise determine properties. Available information on the vessel properties should be reexamined i n detail t o f i l l any gaps i n the supporting data f o r making an estimate o f RTNDT and t o support resolution o f any disagreements about the v a l i d i t y o f values used. Few data are currently available and validated t o support the selection o f a value f o r the i n i t i a l RTNDT The confidence t h a t can be placed i n estimates of the i n i t i a l RTHDT depends not only on material tests but also on the accu- rate documentation of we1 d i ng technique, weld wire used, and weld f l u x used. The c r e d i b i l i t y o f such estimates could be enhanced by performing more tests on archival material, by discovering previously unreported t e s t results on weld specimens from the particular plant, o r by evaluating properties o f welds considered typical o f the p l ant-speci f i c we1 d. 2.3 Fluence Present (or incorporate by reference t o a submitted report) the current and projected fluence on the vessel using benchmarked computer programs and methodology and information from neutron f l u x surveillance dosimetry. Use the weld locations and fluence values t o i d e n t i f y the c r i t i c a l welds. Show how the 1. , fluence varies along the length and depth o f the c r i t i c