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George Antaki, Fellow ASME, has over 40 years of experience in nuclear power plants and process facilities, in the areas of design, safety analysis, startup, operation support, inspection, fitness for services and integrity analysis, retrofits and repairs. George has held engineering and management positions at Westinghouse and Washington Group Int
ernational, where he has performed work at power and process plants, and consulted for the Department of Energy (DOE), the Nuclear Regulatory Commission (NRC) and the Electric Power Research Institute (EPRI).
Evaluation of Degraded and Nonconforming Conditions For ASME III and B31.1 and B31.7 Class 2 and Class 3 Pressure Boundary Nuclear Plant Components
Monday, 11 March 2019
1. Definitions 1.1 Degraded Condition A degraded condition as defined in NRC Inspection Manual 0326 Paragraph 03.02: “A degraded condition is one in which the qualification of an SSC or its functional capability is reduced. Examples of degraded conditions are failures, malfunctions, deficiencies, deviations, and defective material and equipment. Examples of conditions that can reduce the capability of a system are aging, erosion, corrosion, improper operation, and maintenance.” 1.2 Nonconforming Condition A nonconforming condition as defined in US NRC Inspection Manual 0326 Paragraph 03.06: “ A nonconforming condition is a condition of an SSC that involves a failure to meet the CLB or a situation in which quality has been reduced because of factors such as improper design, testing, construction, or modification. The following are examples of nonconforming conditions: An SSC fails to conform to one or more applicable codes or standards (e.g., the CFR, operating license, TSs, UFSAR, and/or licensee...
EPRI Publishes "Roadmap to Integrity Evaluation and Repair of Nuclear Plant Piping"
Thursday, 03 January 2019
EPRI has just published the report “Roadmap to Integrity Evaluation and Repair of Nuclear Plant Piping” EPRI report number 3002013156, dated December 2018, prepared by Becht Nuclear Services, under EPRI Project Manager T. Eckert. The methods and criteria for the evaluation of degraded and non-conforming conditions in piping systems in nuclear power plants are dispersed among a number of ASME XI Code sections, Appendices, Code Cases, and US NRC regulatory requirements, generic letters, and inspection manual sections. This multitude of requirements makes it necessary to have this roadmap to help the engineer make the right fitness-for-service evaluation and the right repair decision. The EPRI road map addresses the fitness-for-service evaluation methods and criteria for the two most common damage mechanisms in nuclear power plant piping systems: Wall thinning, and cracking. The roadmap also addresses non-conformance caused by overloads, i.e. operating loads that exceed the design loads. Regarding repairs of nuclear plant...
Roadmap to Integrity Evaluation and Repair of Nuclear Plant Piping
Using NB-3200 FEA As An Option To Stress Equations In NB-3600
Monday, 27 August 2018
The ASME B&PV Section III Div.1 Code 2013 Edition is currently approved in 10CFR50.55(a). The 2013 edition, permits elastic FEA per NB-3200 in place of the stress equations of NB-3600, as follows: For pressure design - “NB-3611.2 Acceptability When Stresses Exceed Stress Limits. When the stresses as determined by the methods given in NB-3630 exceed the limits thereof, the design can be accepted, provided it meets the requirements of NB-3200.” For shakedown check Eq. (10)(12)(13) - For the shakedown check, quoting from NB- NB-3653.1 Satisfaction ofFor shakedown check Eq. (10)(12)(13) - For the shakedown check, quoting from NB- NB-3653.1 Satisfaction ofPrimary Plus Secondary Stress Intensity Range. “(b) If for one or more pairs of load sets eq. (a)(10) is not met, thepiping product may still be satisfactory, provided that the conditions of NB-3653.6 are met or provided that therequirements of NB-3200 are satisfied.” Equations (10), (12) and (13), with...
Five Keys to a Cost-Effective Repair/Modification Package for Tanks-Vessels-Piping
Thursday, 25 January 2018
: Process : Does the repair change the process chemistries, physics (fluid phase), and thermo-hydraulics (flow rates, pressures, temperatures)? Does the modification change the control room indications and the operating envelopes? Material : Are the selected metallic materials (base metal and welds) and non-metallic materials (gaskets, packings, etc.) compatible with the existing materials, with the environment, and with the service, for the design life of the repair? Is the material compliant with (a) the material specification (ASTM or ASME II), (b) the supplementary Code requirements, and (c) the supplementary plant-specific requirements? Will the material be procured from an approved supplier; does it require supplementary Quality Controls? ASME Code design : Does the modification alter the system layout? If yes, has the layout been checked for good practice and consistency with the process design (item 1 above)? Are the loads and load combinations well defined and categorized as Service Levels A, B,...
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Materials Degradation and Corrosion
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