You have any indications for that beeing a problem? The BN600 is operating for 40 years and I never heard of specific problems in respect to stability and power regulatiin.
Having a simple reaction to power level changes is very useful for a civilian reactor, as it means you don't need as much training before you can operate the plant.
Fairly obviously, any nuclear plant running a PWR will spend a lot of money for USN nukes, simply because of how often we drilled various emergencies that an electrical generation plant just never has time to do.
According to my knowledge, conventional light water reactors can operate between 50 and 100% power, when you reduce the power output even further it takes a lot of time to bring it up again.
I still didn't get an answer to that question, what makes you think, it would be very different with molten salt or netal cooled reactors?
A commercial plant isn't going to change power as much as marine plant granted, but that doesn't mean stability isn't important. Note also that current commercial plants are used a base load units that see little variation. However, it doesn't necessarily follow that future plants will have the same use. A SMR used for a standalone station will likely see loading much closer to that of a naval plant with significant load swings. Likewise, if you assume the future power grid is largely renewables (which are unpredictable and highly variable) and nuclear plants, it is likely the nuclear plants will not be able to operate solely as constant power base load units, but will be required to response much more to load and renewable output fluctuations.
The bigger point is that nuclear power is an area where the consequences of accidents are so severe that a very very stringent doctrines of accident prevention and control is necessary. One aspect of this is the desirability of technically simple, predictable and highly reliable systems. These are complex systems, and higher order interactions and nuances can have severe effects. See for instance TMI where operators responding to indications as trained based on preventing one type of casualty (going solid) actually resulted in an unanticipated different and more severe failure (LOCA). Or EBR-1 suffering a partial core melting incident eventually traced to transient thermal gradients causing temporary fuel rod bowing and a reactivity excursion. BWR/PWR reactors certainly have complexities and failure modes, but we also have a solid understanding of their behavior and how to design to mitigate these risks.
It is highly likely that a new reactor design (new in the context of widespread use) will have various quirks and issues which will be learned the hard way over time. Prudence demands a hard look at the degree to which there's actually real benefit to the change, and if that benefit outweighs the risk. As an example, the potential benefit of burning actinides in waste is utterly meaningless in the real world when you consider that we have technically solid solutions for long term waste storage, the process of separation is complex with attendant risk, and the long lived radioactivity in question is also fairly low in intensity.
As to BN600 stability, we may not have any documentation citing stability as an issue, but conversely how much insight do any of us actually have on the day to day difficulties in operation and maintenance of that plant, or any of the non BWR/PWR plants? For that matter, I'd suggest most folks commenting don't have practical light water reactor experience either.