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To give some perspective:

The first Technical Specification for a Westinghouse PWR is for no more than 1 gallon per minute unidentified leakage from the primary coolant system. Primary coolant system water is not highly radioactive. The issue is where the leak is. If it is from an incore insturmentation tube, that is one thing. If however it is from the pressure vessel itself, that is another.

I remember an event when a swageloc fitting at the seal table broke off. We were doing maintenance at the seal table at the time while the reactor was at power. Of course, due to this event NRC no longer permits maintenance on incore instumentation at power.

Before moving to nuclear weapons and radio isotopic thermal electric generators, I worked for several years at as a nuclear licensing engineer at a Westinghouse PWR site. We went through more song and dances from Pressurized Thermal Shock to Stress Corrosion Cracking to Station Blackout.