U.S. Nuclear Regulatory Commission, Division of Safety Issue Resolution
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The organization U.S. Nuclear Regulatory Commission, Division of Safety Issue Resolution represents an institution, an association, or corporate body that is associated with resources found in Indiana State Library.
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U.S. Nuclear Regulatory Commission, Division of Safety Issue Resolution
Resource Information
The organization U.S. Nuclear Regulatory Commission, Division of Safety Issue Resolution represents an institution, an association, or corporate body that is associated with resources found in Indiana State Library.
- Label
- U.S. Nuclear Regulatory Commission, Division of Safety Issue Resolution
- Authority link
- (EG-IN)1155127
- Subordinate unit
- Division of Safety Issue Resolution
100+ Items by the Organization U.S. Nuclear Regulatory Commission, Division of Safety Issue Resolution
Context
Context of U.S. Nuclear Regulatory Commission, Division of Safety Issue ResolutionContributor of
- A Prioritization of generic safety issues : main report and supplements 1-12
- A prioritization of generic safety issues : revision insertion instructions
- A simplified model of aerosol removal by containment sprays
- A simplified model of aerosol scrubbing by a water pool overlying core debris interacting with concrete : draft report for comment
- A simplified model of aerosol scrubbing by a water pool overlying core debris interacting with concrete : final report
- Accident source terms for light-water nuclear power plants : draft report for comment
- An Assessment of BWR Mark III containment challenges, failure modes, and potential improvements in performance
- An Assessment of BWR Mark-II containment challenges, failure modes, and potential improvements in performance
- An analysis of operational experience during low power and shutdown and a plan for addressing human reliability assessment issues
- An overview of BWR Mark-I containment venting risk implications
- An overview of BWR Mark-I containment venting risk implications : an evaluation of potential Mark-1 containment improvements
- Analysis of public comments on the proposed rule on nuclear power plant license renewal
- Analysis of risk reduction measures applied to shared essential service water systems at multi-unit sites
- Analysis of standby and demand stress failures modes : methodology and applications to EDGs and MOVs
- Analysis of the LaSalle unit 2 nuclear power plant : risk methods integration and evaluation program (RMIEP)
- Assessment of ISLOCA risk-methodology and application to a Babcock and Wilcox nuclear power plant
- Assessment of ISLOCA risk-methodology and application to a Combustion Engineering plant
- Assessment of ISLOCA risk-methodology and application to a Westinghouse four-loop ice condenser plant
- Assessment of ice-condenser containment performance issues
- BWR Mark II ex-vessel corium interaction analyses
- BWR reactor water cleanup system flexible wedge gate isolation value qualification and high energy flow interruption test
- Calculations in support of a potential definition of large release
- Control room habitability system review models
- Development and use of a train-level probabilistic risk assessment
- EXTRAN, a computer code for estimating concentrations of toxic substances at control room air intakes
- Enhancements to data collection and reporting of single and multiple failure events
- Enhancements to the accident precursor methodology
- Environmental assessment for final rule on nuclear power plant license renewal : final report
- Estimate of radionuclide release characteristics into containment under severe accident conditions : draft report for comment
- Estimate of radionuclide release characteristics into containment under severe accident conditions : final report
- Evaluation of Generic issue 115, "Enhancement of the reliability of Westinghouse solid state protection system"
- Evaluation of boiling water reactor water-level sensing line break and single failure : generic issue 101 boiling water reactor level redundancy - technical findings
- Evaluation of exposure limits to toxic gases for nuclear reactor control room operators
- Evaluation of generic issue 57 : effects of fire protection system actuation on safety-related equipment
- Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, unit 1
- Evaluation of potential severe accidents during low power and shutdown operations at Surry, unit 1
- Evaluation of safety implications of control systems in LWR nuclear power plants : technical findings related to USI A-47
- Evaluation of severe accident risks, Vol. 1, Methodology for the containment, source term, consequence, and risk integration analyses
- Evaluation of severe accident risks, Vol. 2, Quantification of major input parameters
- Evaluation of severe accident risks, Vol. 7, Zion, Unit 1
- Evaluation of systems interactions in nuclear power plants : technical findings related to unresolved safety issue A-17
- FPFP2̲ : a code for following airborne fission products in generic nuclear plant flow paths
- Fault tree, event tree, and piping & instrumentation diagram (FEP) editors, version 4.0 : reference manual
- Generic environmental impact statement for license renewal of nuclear plants : draft report for comment
- History and current status of Generation 3 thermal sleeves in Westinghouse nuclear power plants
- Hydrogen combustion, control, and value-impact analysis for PWR dry containments
- ISLOCA research program : final report
- Integrated reliability and risk analysis system (IRRAS), version 4.0
- Integrated risk assessment for the LaSalle unit 2 nuclear power plant : phenomenology and risk uncertainty evaluation program (PRUEP)
- Interfacing systems LOCA : boiling water reactors
- Interfacing systems LOCA : pressurized water reactors
- Iodine evolution and pH control
- Iodine speciation and partitioning in PWR steam generator accidents : final report
- Loss of essential service water in LWRs (GI-153) : scoping study
- MACCS version 1.5.11.1 : a maintenance release of the code
- Methods for external event screening quantification : risk methods integration and evaluation program (RMIEP) methods development
- Microcomputer applications of, and modifications to, the modular fault trees
- Mitigation of direct containment heating and hydrogen combustion events in ice condenser plants : analyses with the CONTAIN code and NUREG-1150 PRA methodology
- Models and Results Database (MAR-D), version 4.0 : reference manual
- Multiple system responses program : identification of concerns related to a number of specific regulatory issues
- Neutron spectra at different high flux isotope reactor (HFIR) pressure vessel surveillance locations
- PWR dry containment issue characterization
- PWR dry containment parametric studies
- Parametric study of the potential for BWR ECCS strainer blockage due to LOCA generated debris : draft report for comment
- Parametric study of the potential for BWR ECCS strainer blockage due to LOCA generated debris : final report
- Perspectives on reactor safety
- Preliminary evaluation of snubber single failures
- Pressure-dependent fragilities for piping components : pilot study on Davis-Besse Nuclear Power Station
- Procedure for analysis of common-cause failures in probabilistic safety analysis
- Proceedings of Workshop I in Advanced Topics in Risk and Reliability Analysis : model uncertainty, its characterization and quantification : held at Governor Calvert House and Conference Center, Annapolis, Maryland, October 20-22, 1993
- Proceedings of the Public Workshop on Nuclear Power Plant License Renewal : held in Reston, Virginia, November 13-14, 1989
- Proceedings of the Workshop on Program for Elimination of Requirements Marginal to Safety : held at Holiday Inn, Bethesda, MD, April 27-28, 1993
- Quantitative analysis of potential performance improvements for the dry PWR containment
- Recommendations for resolution of public comments on USI A-40, seismic design criteria
- Regulatory analysis for Generic issue 23, reactor coolant pump seal failure : draft report for comment
- Regulatory analysis for final rule on nuclear power plant license renewal : final report
- Regulatory analysis for resolution of USI A-17 : systems interactions in nuclear power plants
- Regulatory analysis for resolution of USI A-47 : safety implications of control systems in LWR nuclear power plants : final report
- Regulatory analysis for the resolution of Generic issue 125.II.7, "Reevaluate provision to automatically isolate feedwater from steam generator during a line break"
- Regulatory analysis for the resolution of Generic issue 130 : essential service water system failures at multi-unit sites
- Regulatory analysis for the resolution of generic issue 115, enhancement of the Reliability of the Westinghouse Solid State Protection System
- Regulatory analysis for the resolution of generic issue 142 : leakage through electrical isolators in instrumentation circuits
- Regulatory analysis for the resolution of generic issue 143 : availability of chilled water system and room cooling
- Regulatory analysis for the resolution of generic issue 153 : loss of essential service water in LWRs
- Regulatory analysis for the resolution of generic issue 57 : effects of fire protection system actuation on safety-related equipment
- Regulatory analysis for the resolution of generic issue 82, "beyond design basis accidents in spent fuel pools"
- Regulatory analysis for the resolution of generic issue 99, loss of RHR capability in PWRs
- Regulatory analysis for the resolution of generic issue C-8, "main steam isolation valve leakage and LCS failure"
- Regulatory analysis for the resolution of generic safety issue 105 : interfacing system loss-of-coolant accident in light-water reactors
- Regulatory analysis for the resolution of generic safety issue 106 : piping and the use of highly combustible gases in vital areas
- Regulatory analysis for the resolution of generic safety issue 29 : bolting degradation or failure in nuclear power plants
- Regulatory and backfit analysis : unresolved safety issue A-45, shutdown decay heat removal requirements
- Regulatory options for nuclear plant license renewal : draft for comment
- Resolution of generic safety issue 29 : bolting degradation or failure in nuclear power plants
- Review and development of common nomenclature for naming and labeling schemes for probabilistic risk assessment
- Review of Diablo Canyon Probabilistic Risk Assessment
- Review of current literature related to generic safety issue 15
- Risk analysis of highly combustible gas storage, supply, and distribution systems in PWR plants
- Risk evaluation for a B&W pressurized water reactor, effects of fire protection system actuation on safety-related equipment : evaluation of generic issue 57
- Risk evaluation for a General Electric BWR, effects of fire protection system actuation on safety-related equipment : evaluation of generic issue 57
- Risk evaluation for a Westinghouse PWR, effects of fire protection system actuation on safety-related equipment : evaluation of generic issue 57
- SAPHIRE technical reference manual : IRRAS/SARA version 4.0
- Screening of generic safety issues for license renewal considerations
- Severe accident source term characteristics for selected Peach Bottom sequences predicted by MELCOR code
- Simplified containment event tree analysis for the Sequoyah ice condenser containment
- Statistical analysis of fatigue strain-life data for carbon and low-alloy steels
- Summary and analysis of public comments on NUREG-1317 : regulatory options for nuclear plant license renewal : final report
- Summary of Chernobyl followup research activities
- Summary of MELCOR 1.8.2 calculations for three LOCA sequences (AG, S2D, and S3D) at the Surry plant
- Supplement 17 to NUREG-0933 : "a prioritization of generic safety issues" : revision insertion instructions
- Survey and evaluation of aging risk assessment methods and applications
- System analysis and risk assessment system (SARA) : version 4.0
- Systems analysis programs for hands-on integrated reliability evaluations (SAPHIRE), version 5.0
- Technical evaluation of generic issue 113 : dynamic qualification and testing of large bore hydraulic snubbers
- Technical findings for proposed integrated resolution of generic issue 128, electric power reliability
- Technical findings report for generic issue 135 : steam generator and steam line overfill issues
- The Response of BWR Mark II containments to station blackout severe accident sequences
- The Response of BWR Mark III containments to short-term station blackout severe accident sequences
- Timing analysis of PWR fuel pin failures : draft report for comment
- Timing analysis of PWR fuel pin failures : final report
- Value impact analysis of generic issue 143, "Availability of heating, ventilation, air conditioning (HVAC) and chilled water systems"
- Value-impact analysis of regulatory options for resolution of generic issue C-8 : MSIV leakage and LCS failure
- Value/impact analyses of accident preventive and mitigative options for spent fuel pools
- Value/impact analysis for generic issue 51 : improving the reliability of open-cycle service-water systems
- Value/impact analysis of Generic issue 94, "Additional low temperature overpressure protection for light water reactors"
- XSOR codes users manual
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