Author: U.S. Nuclear Regulatory Commission. Piping Review Committee. Pipe Crack Task GroupPublisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 418
Book Description
Report of the US Nuclear Regulatory Commission Piping Review Committee. Volume 3. Evaluation of Potential for Pipe Breaks
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The Executive Director for Operations (EDO) in establishing the Piping Review Committee concurred in its overall scope that included an evaluation of the potential for pipe breaks. The Pipe Break Task Group has responded to this directive. This report summarizes a review of regulatory documents and contains the Task Group's recommendations for application of the leak-before-break (LBB) approach to the NRC licensing process. The LBB approach means the application of fracture mechanics technology to demonstrate that high energy fluid piping is very unlikely to experience double-ended ruptures or their equivalent as longitudinal or diagonal splits. The Task Group's reommendations and discussion are founded on current and ongoing NRC staff actions as presented in Section 3.0 of this report. Additional more detailed comments and discussion are presented in Section 5.0 and in Appendices A and B. The obvious issues are the reexamination of the large pipe break criteria and the implications of any changes in the criteria as they influence items such as jet loads and pipe whip. The issues have been considered and the Task Group makes the following recommendations.
Report of the U.S. Nuclear Regulatory Commission Piping Review Committee : evaluation of potential for pipe breaks
Author: Report of the U.S. Nuclear Regulatory Commission Piping Review Committee
Author: U.S. Nuclear Regulatory Commission. Piping Review Committee. Pipe Crack Task GroupPublisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 418
Book Description
Report of the U.S. Nuclear Regulatory Commission Piping Review Committee: Evaluation of seismic designs: a review of seismic design requirements for nuclear power plant piping
Author: U.S. Nuclear Regulatory Commission. Piping Review Committee. Pipe Crack Task GroupPublisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 200
Book Description
Report of the US Nuclear Regulatory Commission Piping Review Committee. Volume 5. Summary - Piping Review Committee Conclusions and Recommendations
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
This document summarizes a comprehensive review of NRC requirements for Nuclear Piping by the US NRC Piping Review Committee. Four topical areas, addressed in greater detail in Volumes 1 through 4 of this report, are included: (1) Stress Corrosion Cracking in Piping of Boiling Water Reactor Plants; (2) Evaluation of Seismic Design; (3) Evaluation of Potential for Pipe Breaks; and (4) Evaluation of Other Dynamic Loads and Load Combinations. This volume summarizes the major issues, reviews the interfaces, and presents the Committee's conclusions and recommendations for updating NRC requirements on these issues. This report also suggests research or other work that may be required to respond to issues not amenable to resolution at this time.
Report of the US Nuclear Regulatory Commission Piping Review Committee. Volume 4. Evaluation of Other Loads and Load Combinations
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Six topical areas were covered by the Task Group on Other Dynamic Loads and Load Combinations as described below: Event Combinations - dealing with the potential simultaneous occurrence of earthquakes, pipe ruptures, and water hammer events in the piping design basis; Response Combinations - dealing with multiply supported piping with independent inputs, the sequence of combinations between spacial and modal components of response, and the treatment of high frequency modes in combination with low frequency modal responses; Stress Limits/Dynamic Allowables - dealing with inelastic allowables for piping and strain rate effects; Water Hammer Loadings - dealing with code and design specifications for these loadings and procedures for identifying potential water hammer that could affect safety; Relief Valve Opening and Closing Loads - dealing with the adequacy of analytical tools for predicting the effects of these events and, in addition, with estimating effective cycles for fatigue evaluations; and Piping Vibration Loads - dealing with evaluation procedures for estimating other than seismic vibratory loads, the need to consider reciprocating and rotary equipment vibratory loads, and high frequency vibratory loads. NRC staff recommendations or regulatory changes and additional study appear in this report.
Methodologies for Assessing Pipe Failure Rates in Advanced Water Cooled Reactors
Author: IAEAPublisher: International Atomic Energy Agency
ISBN: 9201505221
Category : Technology & Engineering
Languages : en
Pages : 183
Book Description
This publication, which draws upon the outcome of an IAEA coordinated research project, presents methodologies for assessing pipe failure rates in advanced water cooled reactors (WCRs), including a comprehensive review of good practices for the assessment of piping reliability parameters for advanced WCRs. Good practices are those processes and analytical tasks that would be expected in piping reliability analysis in order for the results to be realistic representations of piping structural integrity. This publication builds on technical insights that have been obtained using different methodologies when applied in multiple analytical contexts and responding to the requirements of different national codes and standards. It provides Member States with a strong technical basis for establishing design and plant centric piping reliability parameters for input into probabilistic safety assessment studies, in-service inspection programme development, and operational support. Additionally, an objective evaluation and inter-comparison of methods used in participating Member States is outlined leading to a harmonization of the practices relevant to newly deployable advanced WCRs.
Federal Register
Author: Report of the U.S. Nuclear Regulatory Commission Piping Review Committee, Volume 4
Author: U.S. Nuclear Regulatory Commission. Piping Review CommitteePublisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages :
Book Description
Author: