This SRP section covers the radiological consequences of failures outside the containment of small lines connected to the primary coolant pressure boundary, such as instrument lines and sample lines. The review includes the following: 1. The identification of small lines postulated to fail and the isolation provisions for these lines, including the applicability of General Design Criterion 55 (Ref. 1), which requires isolation capability of the line inside and outside containment, and Regulatory Guide 1.11 (Ref. 2), which requires isolation capability outside containment for those lines that are exempt from GDC 55. The implementation of these regulatory positions and guidelines is reviewed by the Containment Systems Branch (CSB) under SRP S...
International audienceTo examine how existing plans for the post-emergency phase assessment and mana...
An accident scenario in which the end-fitting of one channel of the Pickering-B, Canadian Pressurize...
The ASB reviews all structures, systems, and components (SSC) provided to support the reactor facili...
This SRP section covers the review of the radiological consequences of a postulated steam generator ...
The SRP Section 15.1.5 covers the review by the Reactor Systems Branch (RSB) of the main steam line ...
This SRP section covers the review of the radiological consequences of a postulated fuel handling ac...
The CSB reviews the information in the applicant's safety analysis report (SAR) con-cerning the...
A potential source of fission product leakage following a loss-of-coolant accident (LOCA) is the lea...
The pressure suppression pool is reviewed under this plan only when the applicant claims credit for ...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1998.Includes bi...
For Mark I, II, and III- pressure-suppression type boiling water reactor (BWR) plant containments, t...
The CSB reviews the analyses of the mass and energy release to assure that the data used to evaluate...
The design objective of the containment isolation system is to allow the normal or emergency passage...
For pressurized water reactor (PWR) plants with dry containments, the CSB review covers the followin...
Critical experiments are described, and the hazards attendant to these experiments are evaluated for...
International audienceTo examine how existing plans for the post-emergency phase assessment and mana...
An accident scenario in which the end-fitting of one channel of the Pickering-B, Canadian Pressurize...
The ASB reviews all structures, systems, and components (SSC) provided to support the reactor facili...
This SRP section covers the review of the radiological consequences of a postulated steam generator ...
The SRP Section 15.1.5 covers the review by the Reactor Systems Branch (RSB) of the main steam line ...
This SRP section covers the review of the radiological consequences of a postulated fuel handling ac...
The CSB reviews the information in the applicant's safety analysis report (SAR) con-cerning the...
A potential source of fission product leakage following a loss-of-coolant accident (LOCA) is the lea...
The pressure suppression pool is reviewed under this plan only when the applicant claims credit for ...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1998.Includes bi...
For Mark I, II, and III- pressure-suppression type boiling water reactor (BWR) plant containments, t...
The CSB reviews the analyses of the mass and energy release to assure that the data used to evaluate...
The design objective of the containment isolation system is to allow the normal or emergency passage...
For pressurized water reactor (PWR) plants with dry containments, the CSB review covers the followin...
Critical experiments are described, and the hazards attendant to these experiments are evaluated for...
International audienceTo examine how existing plans for the post-emergency phase assessment and mana...
An accident scenario in which the end-fitting of one channel of the Pickering-B, Canadian Pressurize...
The ASB reviews all structures, systems, and components (SSC) provided to support the reactor facili...