The design objective of the containment isolation system is to allow the normal or emergency passage of fluids through the containment boundary while preserving the ability of the boundary to prevent or limit the escape of fission products that may result from postulated accidents. This SRP section, therefore, is con-cerned with the isolation of fluid systems which penetrate the containment boundary, including the design and testing requirements for isolation barriers and actuators. Isolation barriers include valves, closed piping systems, and blind flanges. The CSB review of the applicant's safety analysis report (SAR) regarding contain-ment isolation provisions covers the following aspects: I 1. The design of containment isolation pr...
The ASB reviews all structures, systems, and components (SSC) provided to support the reactor facili...
This SRP section covers the radiological consequences of failures outside the containment of small l...
A potential source of fission product leakage following a loss-of-coolant accident (LOCA) is the lea...
For Mark I, II, and III- pressure-suppression type boiling water reactor (BWR) plant containments, t...
The CSB reviews the information in the applicant's safety analysis report (SAR) con-cerning the...
The primary containment isolation instrumentation automatically initiates closure of appropriate pri...
For pressurized water reactor (PWR) plants with dry containments, the CSB review covers the followin...
BACKGROUND The primary containment isolation instrumentation automatically initiates closure of appr...
The areas reviewed in this section of the applicant's safety analysis report (SAR) include thos...
Direct cycle boiling water reactor (BWR) plants have redundant quick-acting isola-tion valves on eac...
The ASB review of the structures, systems, and components (SSC) to be protected from externally gene...
CSB reviews the information presented in the applicant's safety analysis report (SAR) concernin...
The areas reviewed in this section of the applicant's safety analysis report (SAR) include thos...
The ASB review of the structures, systems, and components (SSC) to be protected from internally gene...
The description of the fission product control systems and structures are reviewed to (a) provide a ...
The ASB reviews all structures, systems, and components (SSC) provided to support the reactor facili...
This SRP section covers the radiological consequences of failures outside the containment of small l...
A potential source of fission product leakage following a loss-of-coolant accident (LOCA) is the lea...
For Mark I, II, and III- pressure-suppression type boiling water reactor (BWR) plant containments, t...
The CSB reviews the information in the applicant's safety analysis report (SAR) con-cerning the...
The primary containment isolation instrumentation automatically initiates closure of appropriate pri...
For pressurized water reactor (PWR) plants with dry containments, the CSB review covers the followin...
BACKGROUND The primary containment isolation instrumentation automatically initiates closure of appr...
The areas reviewed in this section of the applicant's safety analysis report (SAR) include thos...
Direct cycle boiling water reactor (BWR) plants have redundant quick-acting isola-tion valves on eac...
The ASB review of the structures, systems, and components (SSC) to be protected from externally gene...
CSB reviews the information presented in the applicant's safety analysis report (SAR) concernin...
The areas reviewed in this section of the applicant's safety analysis report (SAR) include thos...
The ASB review of the structures, systems, and components (SSC) to be protected from internally gene...
The description of the fission product control systems and structures are reviewed to (a) provide a ...
The ASB reviews all structures, systems, and components (SSC) provided to support the reactor facili...
This SRP section covers the radiological consequences of failures outside the containment of small l...
A potential source of fission product leakage following a loss-of-coolant accident (LOCA) is the lea...