The AEB review under this appendix covers the following areas: 1. The plant response to a control rod ejection accident. 2. The calculation of whole-body and thyroid doses at the exclusion area boundary and low population zone outer boundary due to the releases resulting from a rod ejection accident. The purpose of the review is to assure that the plant procedures for recovery from a rod ejection accident and the plant technical specifications are properly taken into account in computing the whole-body and thyroid doses at the nearest exclusion area boundary (EAB) and low population zone (LPZ) outer boundary, and to compare the calculated doses against the appropriate guidelines. A secondary review is performed by the CPB and the resultc Ar...
Purpose of review: This is a summary of the nuclear accident at the Tokyo Electric Power Company Fuk...
Appendix A-5 of Draft Regulatory Guide DG-1199 'Alternative Radiological Source Term for Evaluating ...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1998.Includes bi...
The CPB evaluates the consequences of a control rod ejection accident in the area of physics. The re...
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...
This SRP section covers the review of the radiological consequences of a postulated steam generator ...
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 ...
This SRP section covers the radiological consequences of failures outside the containment of small l...
The transient that results from a postulated feedwater line break is sensitive to the break discharg...
The objectives are to assess the risks of severe accidents initiated during plant operational states...
The applicant's identification of potential accident situations in the vicinity of the plant is...
1. The protective coating systems (paints) used inside the containment are evaluated as to suitabili...
Information is presented by the applicant and reviewed by the staff concerning atmospheric dispersio...
Purpose of review: This is a summary of the nuclear accident at the Tokyo Electric Power Company Fuk...
Appendix A-5 of Draft Regulatory Guide DG-1199 'Alternative Radiological Source Term for Evaluating ...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1998.Includes bi...
The CPB evaluates the consequences of a control rod ejection accident in the area of physics. The re...
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...
This SRP section covers the review of the radiological consequences of a postulated steam generator ...
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 ...
This SRP section covers the radiological consequences of failures outside the containment of small l...
The transient that results from a postulated feedwater line break is sensitive to the break discharg...
The objectives are to assess the risks of severe accidents initiated during plant operational states...
The applicant's identification of potential accident situations in the vicinity of the plant is...
1. The protective coating systems (paints) used inside the containment are evaluated as to suitabili...
Information is presented by the applicant and reviewed by the staff concerning atmospheric dispersio...
Purpose of review: This is a summary of the nuclear accident at the Tokyo Electric Power Company Fuk...
Appendix A-5 of Draft Regulatory Guide DG-1199 'Alternative Radiological Source Term for Evaluating ...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1998.Includes bi...