ANO-1 Experiences Using Structural Tools During License Renewal Application

2004 ◽  
Author(s):  
Reza Ahrabli
Keyword(s):  
Renewal Process ◽  
Nuclear Regulatory Commission ◽  
Structural Components ◽  
Aging Effects ◽  
Considerable Time ◽  
Renewal Program ◽  
Review Reports ◽  
Regulatory Commission ◽  
Effects Of Aging ◽  
License Renewal

Arkansas Nuclear One, Unit 1 (ANO-1) submitted an application to the Nuclear Regulatory Commission (NRC) to extend its operating license for an additional 20 years on January 31, 2000. NRC regulations governing the license renewal process require the preparation of an Integrated Plant Assessment (IPA) to demonstrate that the effects of aging on systems, structures and components (SSCs) at ANO-1 are adequately managed. ANO participated in the B&W (now Framatome) Owners Group (BWOG) Generic License Renewal Program (GLRP) in developing the B&WOG “Aging Effects for Structures and Structural Components”, commonly referred to the “Structural Tools”. The Structural Tools (Mechanical and Electrical Tools are also available) is a generic evaluation based on material and environments that assist the user in performing an evaluation of aging effects. Using the Tools, considerable time was saved in preparing Aging Management Review Reports (AMRR) since the reviewer did not have to independently research potential causes of aging effects for the materials and environments being reviewed. This paper summarizes the ANO-1 experiences in preparing AMRRs utilizing the Structural Tools.

ANO-2 Experiences Using Structural Tools During License Renewal Application

2005 ◽  
Author(s):  
Reza Ahrabli
Keyword(s):  
Renewal Process ◽  
Nuclear Regulatory Commission ◽  
Structural Components ◽  
Aging Effects ◽  
Considerable Time ◽  
Renewal Program ◽  
Review Reports ◽  
Regulatory Commission ◽  
Effects Of Aging ◽  
License Renewal

Arkansas Nuclear One, Unit 2 (ANO-2) submitted an application to the Nuclear Regulatory Commission (NRC) to extend its operating license for an additional 20 years on October 15, 2003. NRC regulations governing the license renewal process require the preparation of an Integrated Plant Assessment (IPA) to demonstrate that the effects of aging on systems, structures and components (SSCs) at ANO-2 are adequately managed. ANO participated in the B&W (now AREVA) Owners Group (BWOG) Generic License Renewal Program (GLRP) in developing the BWOG “Aging Effects for Structures and Structural Components”, commonly referred to as “Structural Tools”. The Structural Tools is a generic evaluation based on material and environments that assist the user in performing an evaluation of aging effects. Using the Tools, considerable time was saved in preparing Aging Management Review Reports (AMRR) since the reviewer did not have to independently research potential causes of aging effects for the materials and environments being reviewed. This paper summarizes the ANO-2 experiences in preparing AMRRs utilizing the Structural Tools.

License Renewal Demonstration Project

2002 ◽  
Author(s):  
Barry J. Elliot ◽  
Jerry Dozier
Keyword(s):  
United States ◽  
State Of The Art ◽  
Nuclear Regulatory Commission ◽  
The United States ◽  
Management Program ◽  
Lessons Learned ◽  
Demonstration Project ◽  
Aging Effects ◽  
Regulatory Commission ◽  
License Renewal

Generic Aging Lessons Learned (GALL) report, License Renewal Standard Review Plan (SRP-LR), and regulatory guide were issued by the United States Nuclear Regulatory Commission (NRC) in June 2001. The intent of these documents was to provide the technical and process basis that will lead to a more effective, efficient and predictable license renewal process for industry and the NRC. The GALL report provides the aging effects on components and structures, identifies the relevant existing plant programs, and evaluates the program attributes to manage aging effects for License Renewal. The GALL report also identifies when existing plant programs would require further evaluation for License Renewal. The SRP-LR allows the applicant to reference the GALL report to demonstrate that the programs at the applicant’s facility correspond to those reviewed and approved in the GALL report. Programs that correspond to those in the GALL report will not need further detailed review by the staff. Implementation of the aging management program are verified as part of the license renewal inspection program. The GALL report identifies one acceptable way of demonstrating that components and structures have adequate aging management programs. However, applicants may propose alternatives to the programs identified in GALL. During the license renewal review, the NRC primarily focuses on areas where existing programs should be augmented or new programs developed for License Renewal. This paper will provide an overview of these documents and some of the lessons learned during a demonstration project in the application of the new guidance. This topic will be of interest to the U.S. participants considering License Renewal and desiring to know state-of-the-art information about License Renewal in the United States.

Generic Aging Management Programs for License Renewal of PWR Reactor Coolant System Components

2002 ◽  
Author(s):  
V. N. Shah ◽  
Y. Y. Liu
Keyword(s):  
Extended Period ◽  
Nuclear Regulatory Commission ◽  
Lessons Learned ◽  
Aging Effects ◽  
Pressurized Water ◽  
Reactor Coolant ◽  
Water Reactors ◽  
Regulatory Commission ◽  
License Renewal ◽  
Coolant System

The paper reviews the existing aging management programs (AMPs) for the reactor coolant system (RCS) components in pressurized water reactors (PWRs), including the reactor pressure vessel and internals, the reactor coolant system and connected lines, pressurizer, reactor coolant pumps, valves, and steam generators. These programs have been evaluated in the U.S. Nuclear Regulatory Commission (NRC) report Generic Aging Lessons Learned (GALL), NUREG-1801, for their use in the license renewal process. These AMPs include both generic and plant-specific programs. The generic AMPs are acceptable for managing aging effects during an extended period of operation and do not require further evaluation; the plant-specific AMPs require further evaluation. The use of the GALL report should facilitate both preparation of a license renewal application and timely and uniform review by the NRC staff.

Operating Nuclear Plant License Renewal Program Status and Trends

2011 ◽  
Author(s):  
Garry G. Young
Keyword(s):  
Renewal Process ◽  
Nuclear Plant ◽  
Positive Trend ◽  
Plant Operation ◽  
Renewal Program ◽  
Status And Trends ◽  
The Status ◽  
Main Factors ◽  
License Renewal ◽  
The U.S

As of February 2011, the NRC has renewed the operating licenses for 62 nuclear units, which will allow for up to 60 years of safe nuclear plant operation. In addition, the NRC has license renewal applications under review for 20 units and nuclear plant owners of more than 17 units have announced plans to submit license renewal applications over the next few years. This brings the total of renewed licenses and announced plans for license renewal to over 95% of the 104 currently operating nuclear units in the U.S. This paper presents the status of the U.S. license renewal process, the positive trend in regulatory stability through 2007, and the negative trend in regulatory stability after 2007. From 2000 through 2007, the NRC was able to complete the license renewal review and issue renewed licenses in 30 months or less for 100% of the license renewal applicants. In fact, approximately 77% of the reviews were completed in 22 months or less. Since 2007, NRC reviews have become much less predictable, with 21% of the reviews exceeding 30 months and only 7% being completed in 22 months or less. In fact, some reviews currently underway have exceeded 60 months and the reviews remain incomplete. One of the main factors leading to the loss of timely regulatory reviews has been the NRC adjudicatory process for license renewal, although the safety and environmental review processes have also become less timely since 2007. The factors that contributed to the positive and the negative trends are presented.

US Nuclear Regulatory Commission Perspective on Buried and Underground Piping Issues at Nuclear Power Plants in the United States

2014 ◽  
Author(s):  
David Alley
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Action Plan ◽  
Nuclear Regulatory Commission ◽  
The United States ◽  
Buried Pipe ◽  
Development Organizations ◽  
Regulatory Commission ◽  
License Renewal

This paper provides a historical perspective on the need for, and development of, buried and underground piping tanks programs at nuclear power plants. Nuclear power plant license renewal activities, Nuclear Regulatory Commission Buried Piping Action Plan, and the rationale for addressing the issue of buried pipe through an industry initiative as opposed to regulation are discussed. The paper also addresses current NRC activities including the results of Nuclear Regulatory Commission inspections of buried piping programs at nuclear power plants as well as Nuclear Regulatory Commission involvement in industry and standards development organizations. Finally, the paper outlines the Nuclear Regulatory Commission’s future plans concerning the issue of buried piping at US nuclear power plants.

scholarly journals Quality assurance program for Angra 1 licence renewal and long-term operation

2021 ◽  
Vol 9 (2B) ◽  
Author(s):  
YOUSSEF MORGHI ◽  
Amir Zacarias Mesquita ◽  
Ana Rosa BALIZA MAIA
Keyword(s):  
Quality Assurance ◽  
Nuclear Power ◽  
Nuclear Regulatory Commission ◽  
Quality Assurance Program ◽  
Term Operation ◽  
Safety Requirements ◽  
Plant Safety ◽  
Regulatory Commission ◽  
License Renewal

In Brazil, according to Cnen standard, a nuclear power plant has authorization to operate for 40 years. Angra 1 commercial operation started in 1985 and it has license to operate until 2024. Eletronuclear aims to extend the operation of the Angra 1 plant from 40 to 60 years. To obtain the license renewal by more than 20 years (long-term operation), Eletronuclear will need to meet the requirements of 10 CFR Part 54, Cnen NT-CGRC-007/18 and NT-CGRC-008/18 (Cnen technical notes). To obtain a license renewal to a long-term operation it is necessary to demonstrate that the plants will operate according to safety requirements, through analysis, testing, aging management, system upgrades, as well as additional inspections. Plant operators and regulators must always ensure that plant safety is maintained and, when it is possible, strengthened during the long-term operation of the plant. One of the documents to obtain a license renewal to a long-term operation is the Quality Assurance Program (QAP). Angra 1 has a QAP according to 10CFR 50 App B and Cnen NN 1.16 for safety related items. However, according to 10 CFR50.34, Nureg-1800 Appendix A.2, Nureg-1801 Appendix A-1 of Nuclear Regulatory Commission (NRC) and NT-CGRC-007/18 and NT-CGRC-008/18 of Cnen, the QAP needs to include the items that are not safety related but are included in the Aging Management. This article will discuss the Angra 1 QAP for the license renewal to a long-term operation according the standards approved by Cnen.

Long Term Operation of Nuclear Power Plants: Status in the U.S.

2013 ◽  
Author(s):  
Garry G. Young
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Regulatory Commission ◽  
Safe Operation ◽  
Term Operation ◽  
The Status ◽  
Regulatory Commission ◽  
License Renewal ◽  
The U.S

As of January 2013, the U.S. Nuclear Regulatory Commission (NRC) has renewed the operating licenses of 73 nuclear units out of a total of 104 licensed units, allowing for up to 60 years of safe operation. In addition, the NRC has license renewal applications under review for 15 units and more than 13 additional units have announced plans to submit applications over the next few years [1]. This brings the total of renewed licenses and plans for renewal to over 97% of the 104 operating nuclear units in the U.S. This paper presents the status of the U.S. license renewal process and issues being raised for possible applications for subsequent renewals for up to 80 years of operation. By the end of 2013 there will be 26 nuclear plants in the U.S. (or 25% of the 104 units) that will be eligible to seek a second license renewal and by the end of 2016 this number will increase to about 50% of the 104 licensed units. Although some nuclear plant owners have announced plans to shutdown before reaching 60 years, the majority are keeping the option open for long term operation beyond 60 years. The factors that impact decisions for both the first license renewals and subsequent renewals for 80 years of safe operation are presented and discussed in this paper.

License Renewal Environmental Fatigue Screening Application

2014 ◽  
Author(s):  
Christopher T. Kupper ◽  
Mark A. Gray
Keyword(s):  
Nuclear Regulatory Commission ◽  
Plant Component ◽  
Screening Process ◽  
The Us ◽  
Piping Systems ◽  
Class 1 ◽  
Major Equipment ◽  
Regulatory Commission ◽  
License Renewal ◽  
Detailed Application

In NUREG-1801 (GALL) Revision 0 and Revision 1, the US Nuclear Regulatory Commission (NRC) defined the locations evaluated in NUREG/CR-6260 as a minimum acceptable set for evaluation of environmentally assisted fatigue (EAF), in addressing license renewal for nuclear plant components. Within GALL Revision 2, the NRC revised the expectation, so that plants also investigate the possibility of other locations being more limiting. To address GALL Revision 2 and NUREG-1800 Revision 2, an EAF screening methodology was developed that considers all Safety Class 1 reactor coolant pressure boundary components in major equipment and piping systems that are susceptible to EAF, including those locations listed in NUREG/CR-6260. While the overall screening process steps are similar to those published by EPRI, elements of the detailed application of some steps were performed using alternative techniques. The screening process utilized the comprehensive database of plant component fatigue qualifications available in NSSS vendor documentation, and yielded a comprehensive list of lead indicator locations for EAF consideration. This paper describes the overall process and alternate methods in the context of a specific plant license renewal application.

Comparison of Component Fatigue Test Data With Proposed EAF Methodologies for Austenitic Stainless Steel

2009 ◽  
Author(s):  
Rim Nayal ◽  
Hasan Charkas
Keyword(s):  
Stainless Steel ◽  
Fatigue Life ◽  
Fatigue Test ◽  
Low Cycle Fatigue ◽  
Nuclear Regulatory Commission ◽  
Fatigue Curve ◽  
Asme Code ◽  
Regulatory Commission ◽  
License Renewal ◽  
The Impact

The U.S. Nuclear Regulatory Commission (NRC) currently requires evaluation of the effect of environmental fatigue for both license renewal and new plants. NRC required the use of methodology in EPRI MRP-47, Rev. 1 addressing NUREG/CR-5704, be used for license renewal of stainless steel (SS) components, and NUREG/CR-6909 for use in new plants. These two methodologies are based on applying an environmental correction factor (Fen) on the number of in-air design cycles. These factors are applied to the fatigue usage from each individual range of stress (or range of strain). The focus of this paper is to compare the two aforementioned methodologies; this includes comparison of the fatigue curve as well as the comparison of the environmental correction factors (Fen). Fatigue test results data reported by others are also compared with these two methodologies. It is important to evaluate the impact of using any of those methodologies on the design fatigue life of the components. It is concluded that NUREG/CR-5704 is more severe than NUREG/CR-6909 in the LCF (low-cycle fatigue) regime, while NUREG/CR-6909 is more severe elsewhere, and both NUREG’s extremely underestimate fatigue life in PWR environment. It is also concluded that the current ASME-code fatigue curve for stainless steel reasonably estimates fatigue life in an LWR environment with reasonable margins.

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