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:
ther f l u x reduc- tions t o c r i t i c a l areas o f the vessel wall t h a t would reduce the r i s k o f con- tinued operation beyond the screening c r i t e r i o n should be considered. I f such additional f l u x reductions are needed, i n view o f the i r r e v e r s i b i l i t y o f embr-ittlement, the .Ticensee should consider early implementation before reaching the screening criterion. For licensees who are considering applications t o extend the operating license beyond i t s present expiration date, i t may be pru- dent t o implement the reduction as early as possible t o avoid the necessity o f vessel annealing or replacement. 8.2 Operating Procedures and Training Program Improvements Operator actions and associated p l a n t response play a key r o l e i n the i n i t i a t i o n and mitigation o f PTS events. Therefore, ensure t h a t the actions are based on approved technical guidelines t h a t include an integrated'evaluation o f relevant technical considerations, including, but not l i m i t e d to, PTS, core cooling, environmental releases, and containment i n t e g r i t y . The evaluation should address the following types o f concerns: * Frequent real i s t i c "team" t r a i n i n g should be conducted, exposing the operators t o potential PTS transients and t h e i r precursor events. The t r a i n i n g should give the operators actual practice i n controlling reactor system pressure and cooldown rates during PTS situations. Specific t r a i n i n g should include, but not be l i m i t e d to, reactor cool- ant pump t r i p c r i t e r i a , the HPI t h r o t t l i n g c r i t e r i o n , control o f natural circulation, recovery from inade,quate core cooling, recovery from s o l i d plant operations, and the use o f PORVs t o control primary overpressure. O Instructions should be based on analyses t h a t include consideration o f system response delay times (e. g. , loop transport time, thermal transport time). O Whether o r not there