Document Identifier |
Title |
BNL Tech Reports:
A-3270-11-26-84 |
Scoping Test on Containment Purge and Vent Seal Material |
BNL Tech Reports:
A-3270-12-86 |
Aging and Life Extension Assessment Program (ALEAP) Systems Level Plan |
BNL Tech Reports:
A-3270R-2-90 |
Interim Report - Aging Effects of Important Balance of Plant Systems in Nuclear Power Plants |
BNL Tech Reports:
TR-3270-6-90 |
Maintenance Team Inspection Results: Insights Related to Plant Aging |
BNL Tech Reports:
TR-3270-9-90 |
An Operational Assessment of the Babcock & Wilcox and Combustion Engineering Control Rod Drives |
BNL Tech Reports:
A-3270-6-21-91 |
Degradation Modeling: Extensions and Applications |
BNL Tech Reports:
EGG-SSRE-8972 |
Estimating Hazard Functions for Repairable Components |
BNL Tech Reports:
EGG-SSRE-9017 |
User's Guide to PHAZE, a Computer Program for Parametric Hazard Function Estimation |
BNL Tech Reports:
EGG-SSRE-9777 |
Isolation Valve Assessment (IVA) Software Version 3.10, User's Manual |
BNL Tech Reports:
EGG-SSRE-9926 |
Evaluation of EPRI Draft Report NP-7065-Review of NRC/INEL Gate Valve Test Program |
BNL Tech Reports:
EGG-SSRE-10039 |
An Evaluation of the Effects of Valve Body Erosion on Motor-Operated Valve Operability |
BNL Tech Reports:
Letter Report |
Summaries of Research Reports Submitted in Connection with the Nuclear Plant Aging Research (NPAR) Program |
NUREG-1144, V3 |
Nuclear Plant Aging Research (NPAR) Program Plan, Status and Accomplishments, Rev. 2 |
NUREG/CP-0100 |
Proceedings of the International Nuclear Power Plant Aging Symposium |
NUREG/CP-0105 Vol. 3 |
Proceedings of the Seventeenth Water Reactor Safety Information Meeting (aging session only) |
NUREG/CR-2641
(ORNL/TM-8271) |
The In-Plant Reliability Data Base for Nuclear Power Plant Components: Data Collection and Methodology Report |
NUREG/CR-3154
(ORNL/TM 8647) |
The In-Plant Reliability Data Base for Nuclear Power Plant Components: Interim Report - The Valve Component |
NUREG/CR-4144
(PNL-5389) |
Importance Ranking Based on Aging Consideration of Components Included in Probabilistic Risk Assessments |
NUREG/CR-4279 V1
(PNL-5479) |
Aging and Service Wear of Hydraulic and Mechanical Snubbers Used on Safety-Related Piping and Components of Nuclear Power Plants |
NUREG/CR-4302 V1
(ORNL-6193) |
Aging and Service Wear of Check Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plants |
NUREG/CR-4302 V2
(ORNL-6193) |
Aging and Service Wear of Check Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plants |
NUREG/CR-4380
(ORNL-6226) |
Evaluation of the Motor-Operated Valve Analysis and Test System (MOVATS) to Detect Degradation, Incorrect Adjustments, and Other Abnormalities in Motor Operated Valves |
NUREG/CR-4597 V1
(ORNL-6282) |
Aging and Service Wear of Auxiliary Feedwater Pumps for PWR Nuclear Power Plants, Vol. 1: Operating Experience and Failure Identification |
NUREG/CR-4597 V2
(ORNL-6282) |
Aging and Service Wear of Auxiliary Feedwater Pumps for PWR Nuclear Power Plants, Vol. 2: Aging Assessment and Monitoring Method Evaluations |
NUREG/CR-4652
(ORNL/TM-10059) |
Concrete Component Aging and Its Significance Relative to Extension of Nuclear Power Plants |
NUREG/CR-4692
(ORNL/NOAC-233) |
Operating Experience Review of Failures of Power Operated Relief Valves and Block Valves in Nuclear Power Plants |
NUREG/CR-4731 V1
(EGG-2469) |
Residual Life Assessment of Major Light Water Reactor Components, Vol. 1 |
NUREG/CR-4731 V2
(EGG-2469) |
Residual Life Assessment of Major Light Water Reactor Components - Overview, Vol. 2 |
NUREG/CR-4747 V1
(EGG-2473) |
An Aging Failure Survey of Light Water Reactor Safety Systems and Components, V1 |
NUREG/CR-4747 V2
(EGG-2473) |
An Aging Failure Survey of Light Water Reactor Safety Systems and Components, V2 |
NUREG/CR-4819 V1 (ORNL/SUB/83-28915/4) |
Aging and Service Wear of Solenoid-Operated Valves Used in Safety Systems of Nuclear Power Plants |
NUREG/CR-4819 V2
(ORNL/TM-12038) |
Aging and Service Wear of Solenoid-Operated Valves Used in Safety Systems of Nuclear Power Plants: Evaluation of Monitoring Methods |
NUREG/CR-4967
(EGG-2514) |
Nuclear Plant Aging Research on High Pressure Injection Systems |
NUREG/CR-4977 V1
(EGG-2505 V1) |
SHAG Test Series: Seismis Research on an Aged United States Gate Valve and on a Piping System in the Decommissioned Heissdampfreaktor (HDR): Summary, V1 |
NUREG/CR-4977 V2
(EGG-2505 V2) |
SHAG Test Series: Seismis Research on an Aged United States Gate Valve and on a Piping System in the Decommissioned Heissdampfreaktor (HDR): Appendices, V2 |
NUREG/CR-5057
(PNL-6397) |
Aging Mitigation and Improved Programs for Nuclear Service Diesel Generators |
NUREG/CR-5159
(KEI-1559) |
Prediction of Check Valve Performance and Degradation in Nuclear Power Plant Systems |
NUREG/CR-5248
(PNL-6701) |
Prioritization of TIRALEX-Recommended Components for Further Aging Research |
NUREG/CR-5314 V3
EGG-2562) |
Life Assessment Procedures for Major LWR Components |
NUREG/CR-5378
(EGG-2567) |
Aging Data Analysis and Risk Assessment - Development and Demonstration Study |
NUREG/CR-5379 V1
(PNL-6560) |
Nuclear Plant Service Water System Aging Degradation Assessment: Phase I, Vol. 1 |
NUREG/CR-5379 V2
(PNL-6560) |
Nuclear Plant Service Water System Aging Degradation Assessment: Phase II, Vol. 2 |
NUREG/CR-5386
(PNL-6911) |
Basis for Snubber Aging Research: Nuclear Plant Aging Research Program |
NUREG/CR-5404 V1
(ORNL-6566, V1) |
Auxiliary Feedwater System Aging Study, V1 |
NUREG/CR-5404 V2
(ORNL-6566, V2) |
Auxiliary Feedwater System Aging Study, Phase I Follow-On Study |
NUREG/CR-5406 V1
(EGG-2569, V1) |
BWR Reactor Water Cleanup System Flexible Wedge Gate Isolation Valve Qualification and High Energy Flow Interruption Test, V2: Analysis and Conclusions |
NUREG/CR-5406 V2
(EGG-2569, V2) |
BWR Reactor Water Cleanup System Flexible Wedge Gate Isolation Valve Qualification and High Energy Flow Interruption Test, V2: Data Report |
NUREG/CR-5406 V3
(EGG-2569, V3) |
BWR Reactor Water Cleanup System Flexible Wedge Gate Isolation Valve Qualification and High Energy Flow Interruption Test, V3: Review of Issues Associated with the BWR Containment Isolation Valve Closure |
NUREG/CR-5419
(BNL-NUREG-5221) |
Aging Assessment of Instrument Air Systems in Nuclear Power Plants |
NUREG/CR-5479
(ORNL/TM/11398) |
Current Applications of Vibration Monitoring and Neutron Noise Analysis: Detection and Analysis of Structural Degradation of Reactor Vessel Internals from Operational Aging |
NUREG/CR-5490 V1
(PNL-7190) |
Regulatory Instrument Review: Management of Aging of LWR Major Safety Components |
NUREG/CR-5507
(BNL-NUREG-52222) |
Results from the Nuclear Plant Aging Research Program: Their Use in Inspection Activities |
NUREG/CR-5510 |
Evaluations of Core Melt Frequency Effects due to Component Aging Maintenance |
NUREG/CR-5515
(ETEC 88-01) |
Light Water Reactor Pressure Isolation Valve Performance Testing |
NUREG/CR-5519 V1
(ORNL-6607/V1) |
Aging of Control and Service Air Compressors and Dryers Used in Nuclear Power Plants |
NUREG/CR-5555 |
Aging Assessment of the Westinghouse PWR Control Rod Drive System |
NUREG/CR-5558
(EGG-2600) |
Generic Issue 87: Flexible Wedge Gate Valve Test Program: Phase II Results and Analysis |
NUREG/CR-5583
(KEI No. 1656) |
Prediction of Check Valve Performance and Degradation in Nuclear Power Plant Systems-Wear and Impact Tests |
NUREG/CR-5587
(SAIC-92/1137) |
Approaches for Age-Dependent Probabilistic Safety Assessments With Emphasis on Prioritization and Sensitivity Studies |
NUREG/CR-5646
(EGG-2655) |
Piping System Response During High Level Simulated Seismic Tests at the Heissdampfreaktor Facility (SHAM Test Facility) |
NUREG/CR-5693
(BNL-NUREG-52283) |
Aging Assessment of Component Cooling Water Systems in Pressurized Water Reactors-Phase II |
NUREG/CR-5699 V1
(ORNL-6666/V1) |
Aging and Service Wear of Control Rod Drive Mechanisms for BWR Nuclear Plants - V1 |
NUREG/CR-5706
(ORNL-6671) |
NRC Bulletin 88-04: Potential Safety-Related Pump Loss- An Assessment of Industry Data |
NUREG/CR-5720
(EGG-2643) |
Motor-Operated Valve Research Update |
NUREG/CR-5754
(ORNL/TM-11876) |
Boiling-Water Reactor Internals Aging Degradation Study-Phase I |
NUREG/CR-5779 V1
(ORNL-6687) |
Aging of Non-Power-Cycle Heat Exchangers Used in Nuclear Power Plants |
NUREG/CR-5783
(BNL-NUREG-52299) |
Aging Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives |
NUREG/CR-5807 |
Improvements in Motor Operated Gate Valve Design and Prediction Models for Nuclear Power Plant Systems |
NUREG/CR-5848 |
Recordkeeping Needs to Mitigate the Impact of Aging Degradation |
NUREG/CR-5870
(PNL-8051) |
Results of LWR Snubber Aging Research |
NUREG/CR-5944
(ORNL-6734)V2 |
A Characterization of Check Valve Degradation and Failure Experience in the Nuclear Power Industry |
NUREG/CR-6001
(PNL-8020) |
Aging Assessment of BWR Standby Liquid Control Systems |
NUREG/CR-6029 |
Aging Assessment of Nuclear Air Treatment System HEPA Filters and Adsorbers - Phase 1 |
NUREG/CR-6043 V1
(PNL-8614) |
Phase I Aging Assessment of Essential HVAC Chillers Used in Nuclear Power Plants |
NUREG/CR-6048
(ORNL-TM-12371) |
Pressurized-Water Reactor Internals Aging Degradation Study --A Phase I Report |
ORNL/NRC/LTR-91/25 |
Throttled Valve Cavitation and Erosion |
PNL-5722 |
Operating Experience and Aging Assessment of ECCS Pump Room Coolers |
PNL-6287 |
Study Group Review of Nuclear Service Diesel Generator Testing and Aging Mitigation |
PNL-7516 |
Emergency Diesel Generator Technical Specifications Study Results |
PNL-7823 |
Maintenance Practices to Manage Aging: A Review of Several Technologies |
PNL-SA-20219 |
ASME Subsection ISTD Recommendations Based upon NPAR Snubber Aging Research Results |