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Author: W. C. Liu
Publisher: CreateSpace
ISBN: 9781500373955
Category : Technology & Engineering
Languages : en
Pages : 68
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Book Description
The Nuclear Regulatory Commission (NRC) published its license renewal rule, Title 10 of the Code of Federal Regulations (10 CFR) Part 54, on May 8, 1995, providing the requirements for renewal of operating licenses for nuclear power plants. 10 CFR 54.21(a)(1)(i) requires an aging management review of containment structures to ensure that the effects of aging will be managed so that their intended functions will be maintained for the period of extended operation. In 1990, the Nuclear Management and Resources Council (NUMARC), now the Nuclear Energy Institute (NEI), submitted for NRC review, the industry reports (IRs), NUMARC Report 90–01 and NUMARC Report 90–10, addressing aging management issues associated with PWR containments and BWR containments for license renewal, respectively.
Author: W. C. Liu
Publisher: CreateSpace
ISBN: 9781500373955
Category : Technology & Engineering
Languages : en
Pages : 68
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Book Description
The Nuclear Regulatory Commission (NRC) published its license renewal rule, Title 10 of the Code of Federal Regulations (10 CFR) Part 54, on May 8, 1995, providing the requirements for renewal of operating licenses for nuclear power plants. 10 CFR 54.21(a)(1)(i) requires an aging management review of containment structures to ensure that the effects of aging will be managed so that their intended functions will be maintained for the period of extended operation. In 1990, the Nuclear Management and Resources Council (NUMARC), now the Nuclear Energy Institute (NEI), submitted for NRC review, the industry reports (IRs), NUMARC Report 90–01 and NUMARC Report 90–10, addressing aging management issues associated with PWR containments and BWR containments for license renewal, respectively.
Author: W. C. Liu
Publisher:
ISBN: 9780160547447
Category :
Languages : en
Pages : 66
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Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 63
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Book Description
In 1990, the Nuclear Management and Resources Council (NUMARC), now the Nuclear Energy Institute (NEI), submitted for NRC review, the industry reports (IRs), NUMARC Report 90-01 and NUMARC Report 90-10, addressing aging management issues associated with PWR containments and BWR containments for license renewal, respectively. In 1996, the Commission amended 10 CFR 50.55a to promulgate requirements for inservice inspection of containment structures. This rule amendment incorporates by reference the 1992 Edition with the 1992 Addenda of Subsections IWE and IWL of the ASME Code addressing the inservice inspection of metal containments/liners and concrete containments, respectively. The purpose of this report is to reconcile the technical information and agreements resulting from the NUMARC IR reviews which are generally described in NUREG-1557 and the inservice inspection requirements of subsections IWE and IWL as promulgated in {section}50.55a for license renewal consideration. This report concludes that Subsections IWE and IWL as endorsed in {section}50.55a are generally consistent with the technical agreements reached during the IR reviews. Specific exceptions are identified and additional evaluations and augmented inspections for renewal are recommended.
Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 10
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Book Description
Author: United States. Congress. Office of Technology Assessment
Publisher: Congress
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 196
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Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 208
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Book Description
Continued operation of nuclear power plants for periods that extend beyond their original 40-year license period is a desirable option for many U.S. utilities. U.S. Nuclear Regulatory Commission (NRC) approval of operating license renewals is necessary before continued operation becomes a reality. Effective aging management for plant components is important to reliability and safety, regardless of current plant age or extended life expectations. However, the NRC requires that aging evaluations be performed and the effectiveness of aging management programs be demonstrated for components considered within the scope of license renewal before granting approval for operation beyond 40 years. Both the NRC and the utility want assurance that plant components will be highly reliable during both the current license term and throughout the extended operating period. In addition, effective aging management must be demonstrated to support Maintenance Rule (10 CFR 50.65) activities.
Author:
Publisher:
ISBN:
Category : Heat exchangers
Languages : en
Pages :
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Book Description
Author: James T. Nakos
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 20
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Book Description
The U.S. Department of Energy (DOE) and the Electric Power Research Institute (EPRI), in cooperation with nuclear power plant utilities and the Nuclear Energy Institute, have prepared equipment aging evaluations of nuclear power plant equipment for life extension considerations. Specifically, these evaluations focused on equipment considered important for plant license renewal (U.S. Code of Federal Regulations 10CFR54). [open-quotes]Industry Reports[close-quotes] (IRs), jointly funded by DOE and EPRI, evaluated the aging of major systems, structures, and components (e.g., reactor pressure vessels, Class I structures, PWR and BWR containments, etc.) and contain a mixture of technical and licensing information. [open-quotes]Aging Management Guidelines[close-quotes] (AMGs), funded by DOE, evaluate aging for commodity types of equipment (e.g., pumps, electrical switchgear, heat exchangers, etc.) and concentrate on technical issues only. AMGs are intended for systems engineers and plant maintenance staff. A significant number of technical issues were resolved during IR interactions with the U.S. Nuclear Regulatory Commission (NRC). However, certain technical issues have not been resolved and are considered [open-quotes]open[close-quotes]. Examples include certain issues related to fatigue, neutron irradiation embrittlement, intergranular stress corrosion cracking (IGSCC) and electrical cable equipment qualification. Direct NRC interaction did not take place during preparation of individual AMGs due to their purely technical nature. The eventual use of AMGs in a future license renewal application will likely require NRC interaction at that time. With a few noted exceptions, the AMG process indicated that current aging management practices of U.S. utilities were effective in preventing age-related degradation. This paper briefly describes the IR and AMG processes and summarizes the unresolved technical issues identified through preparation of the documents.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 185
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Book Description
This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in Boiling Water Reactor (BWR) and Pressurized Water Reactor (PWR) commercial nuclear power plant motor control centers important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.
Author: Stephen Booker
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages :
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Book Description
