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:
f Overcooling Sequences f o r the H. B. Robinson Unit 2 PTS Study," EG&G, USNRC Report NUREGAR-3935, July 1985. T. G. Theofanous e t al., "Decay o f Buoyancy Driven S t r a t i f i e d Layers w i t h Appl ication t o PTS ,I1 Purdue University , USNRC Report NUREG/CR-3700, May 1984. T. G. Theofanous e t al. , "REMIX: Computer Program f o r Temperature Transients Due t o High Pressure I n j e c t i o n i n a Stagnant Loop," Purdue University , USNRC Report NUREGKR-3701, May 1986. T. G. Theofanous e t al., "Buoyancy Effects on Overcooling Transients Calculated f o r the USNRC Pressurized Thermal Shock Study," Purdue University , USNRC Report NUREG/CR-3702, May 1986. Bart Daly, "Three-Dimensional Calculations o f Transient Fluid-Thermal Mixing i n the Downcomer o f the Calvert C l i f f s - 1 Plant Using SOLA-PTS," LASL, USNRC Report NUREG/CR-3704, Apri 1 1984. Martin Torrey and Bart Daly, "SOLA-PTS: A Transient 3-D Algorithm f o r F l uid-Thermal Mixing and Wall Heat Transfer i n Complex Geometries," LASL, USNRC Report NUREG/CR-3822, July 1984. F. X. Do1 an e t a1 . , "Faci 1 i ty and Test Design Report: 1/2-Scal e Thermal Mixing Project ," USNRC Report NUREGAR-3426, Vols. 1 and 2, September 1985. R. D. Cheverton and D. G. Ball, "OCA-P, A Deterministic and Probabilistic Fracture-Mechanics Code f o r Application t o Pressure Vessels ,I1 Oak Ridge National Laboratory, USNRC Report NUREG/CR-3618 (ORNL-5991), July 1984. F. A. Simonen e t al., "VISA-I1 - A Computer Code f o r Predicting the Proba- b i 1 i t y o f Reactor Vessel Fai 1 ure ,I1 Battel l e Pacific Northwest Laboratories, USNRC Report NUREG/CR-4486, Apri 1 1986. USNRC Regulatory Guide 1.99, "Effects o f Residual Elements on Predicted Radiation Damage t o Reactor Vessel Materials. " REGULATORY ANALYSIS The pressurized thermal shock (PTS) rule, § 50.61 of 10 CFR Part 50 (July 23, 1985--50 FR 29937), requires collection and reporting of material properties data, analyses of flux reduction options, and detailed