-
allowable leak rate increase
-
isolation valve delayed actuation
-
filtration system’s simplification
-
mitigation system’s delayed actuation
As a result, these changes can
offer:
- reduced O&M costs,
- reduced occupational exposure,
- increased plant availability,
As well as improved plant safety
in the form of:
- reduced core damage,
- improved performance of safety
equipment and systems,
- elimination of unnecessary wear on
equipment.
Potential AST applications
include:
- elimination or reclassification of
charcoal filtration systems (PWR & BWR)
- elimination of isolation valve’s
automatic actuation or delayed actuation (PWR & BWR)
- improved EDG reliability through
reduced sequenced loading (PWR & BWR)
- delayed actuation of control room
pressurization systems (PWR & BWR)
- elimination of MSIV leakage control
and/or improved MSIV allowable limits (BWR)
- increased secondary containment
draw-down times (BWR)
- improved operating margin for
containment pressure (PWR)
Guidance for the application of
the AST is now defined in SRP 15.0.1, "Radiological Consequence
Analyses Using Alternate Source Terms," and Regulatory Guide 1.183,
"Alternative Radiological Source Terms for Evaluating Design Basis Accidents at
Nuclear Power Reactors."
The AAC staff has been
responsible for the original radiological consequence analysis of ten (10)
BWRs/PWRs in the USA, Asia, and Europe. In addition, the staff has
experience in the radiological consequence reanalysis of over twenty (20) additional units. Our experience in this area includes all aspects of
source term determinations, on-site and off-site radionuclide transport
calculations, habitability analyses, and related calculations and safety
analyses in support of areas such as EQ and RMS set-points.
AAC’s recent and current involvement in
this emerging nuclear safety analysis technology includes:
For more information on how AST applications can
lower your O&M costs and increase plant safety margins, contact AAC at
