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:
ion and may also be referenced by the submitted analyses. 2. PLANT DATA This chapter i s t o b r i e f l y describe plant systems and operations pertinent t o PTS. Chapter 2 o f Reference 3 (the H. 0. Robinson analysis by ORNL) provides a good example. Supporting appendices o r references are t o present the design and operating data used i n the analysis o r needed t o understand the analysis. References t o other dbcuments (e. g. , the f i n a l safety analysis report (FSAR)) should indicate specific sections. ( R e l i a b i l i t y data, however, are t o be i n Section 3.4, "Sequence Quantification," or i t s supporting appendices and references. ) 2.1 Systems Pertinent t o PTS Summarize design and operating features o f systems pertinent t o PTS. I l l u s t r a t e each system with a simplified process and instrumentation diagram o r a single l i n e diagram. I d e n t i f y on each i l l u s t r a t i o n any interfaces w i t h other systems. For each system, include a table summarizing key design and operating data. Give the maximum, minimum, and nominal values f o r those cases i n which design data may vary with time ( f o r example, high-pressure i n j e c t i o n (HPI) water temperature may vary with season). Such values used i n the analysis should be i d e n t i f i e d and j u s t i f i e d . Refer t o appendices o r other documents (e. g. , specific sections o f the FSAR) as necessary f o r more details. Systems t o be considered should include pertinent portions of: Reactor cooling system Condensate and main feedwater systems Steam system Auxi 1 i ary feedwater system Reactor protection system Chemical and volume control system Emergency core cooling systems Instrumentation and, control systems Support systems - Electric power - Instrument a i r - Service 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