IEEE 1205-2006 Guide for Assessing@ Monitoring@ and Mitigating Aging Effects on Class 1E Equipment Used in Nuclear Power Generating Stations Corrigendum 1: Thermal Aging Model Corrections
ForwardEquipment Used in Nuclear Power Generating Stations was developed as a revision to IEEE Std 1205-1993. This revision updated aging assessment approaches to be consistent with current methodologies being used by the industry in response to regulatory requirements [lo CFR 50.65 (Maintenance Rule) and 10 CFR 54 (License Renewal rule)] and related industry initiatives. This corrigendum makes three minor corrections to IEEE Std 1205-2000. The second significant digit accuracy of the Boltzman constant is corrected at two locations in the document and the temperature subscript in the summation expression for calculating the Arrhenius weighted temperature is corrected from a ??1?? to an <??i@@. (This introduction is not part of IEEE Std 1205-2000@ IEEE Guide for Assessing@ Monitoring@ and Mitigating Aging Effects on Class 1E Equipment Used in Nuclear Power Generating Stations.) Class 1E equipment in nuclear power generating stations must meet its safety functional requirements throughout its service life. This is accomplished through a systematic and disciplined program of quality assurance covering design@ qualification@ manufacturing@ storage@ installation@ operation@ maintenance@ periodic testing@ and surveillance. As part of the maintenance@ surveillance@ and periodic testing programs@ Class 1E equipment is maintained in a state of readiness by various methods that include@ as appropriate@ periodic refurbishment andor replacement. Also@ for some Class 1E equipment located in harsh environment areas in the plant@ rigorous testing andor analysis is employed to demonstrate a qualified life. For equipment located in mild environment areas@ a qualified life demonstration is generally not required; an effective program of surveillance and maintenance is sufficient to identify and mitigate potential aging degradation. Continuation of these programs should ensure that Class 1E equipment is capable of performing its intended safety function during its service life. It is not the intent of this guide to imply that new programs be established for the purpose of aging assessment. Aging assessments should not be directed toward an endless search for data and information@ but rather should be an effort that is practical@ cost-effective@ and based on collecting and evaluating a minimum set of data and information collected preferably from existing programs. The service life of some equipment may include operation beyond its design or qualified life@ and even beyond a plant??s original license term. To accomplish this@ a technical basis is necessary to demonstrate that the Class 1E equipment is capable of continued safe operation during any renewed license term of the plant. For equipment qualified to IEEE Std 323-1974 or IEEE Std 323-1983@ this technical basis exists for its original qualified life. The potential for significant aging needs to be effectively assessed so that necessary mitigating actions are taken to assure dependable and safe operation of the plant@ including extension beyond original qualified life. In 1988@ the Nuclear Power Engineering Committee (NPEC) of IEEE recognized a need for and directed Working Group 3.4 to prepare a guide to supplement its existing body of standards. This guide was to - Provide guidance in the areas of aging assessment@ control@ and mitigation. - Promote uniformity in the methods used for developing the technical basis cited previously. While it would have been possible to incorporate this guide into related standards@ the decision was made to develop a stand-alone document for the following reasons: - It would be expedient and promote consistency by providing guidance that can be incorporated into future standards. - It would help disseminate the body of knowledge and promote uniformity in application methods while minimizing the confusion that could result from the differences in the licensing bases of the various operating nuclear power plants. The Working Group??s effort culminated in 1993 with the original issue of IEEE Std 1205. At the time of original issue of IEEE Std 1205-1993@ the industry focus for assessing and mitigating aging degradation was on identifying and addressing aging mechanisms. This approach derived from the rigorous aging analyses performed in support of earlier environmental qualification (EQ) programs. In 1991@lO CFR 50.65 (Maintenance Rule) was published. In 1995 10 CFR 54 (License Renewal Rule) was amended. As a result of these two regulation changes and industry interactions in response [e.g.@ NE1 95-10 (Revision i)@ Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule]@the emphasis for addressing aging degradation shifted from identifying aging mechanisms to identifying aging effects. Since the original issue of IEEE Std 1205-1993@ the Working Group has also received feedback on a need to better integrate the various clauses of this guide in order to improve its usefulness. In 1997@ the NPEC authorized Working Group 3.4 to revise IEEE Std 1205-1993 to incorporate industry feedback and to bring the approaches discussed in the guide into closer conformance with present industry philosophy. To this end@ the following changes to the guide have been adopted - Developed new block diagrams that update the aging assessment@ monitoring@ and mitigation process for consistency with current industry philosophy and better show and integrate the relationships between the process steps. - Reversed the order of Clause 4 and Clause 5@ and revised Clause 5@ Clause 6@ and Clause 7 for improved consistency with the new process block diagrams. - Added a new Annex C on condition monitoring. - Updated the example assessments now found in Annex D for consistency with the revised Clause 6@ and added two new examples on electric cable and electric penetrations. - Added a new Annex E on attributes of an effective aging management program. The Working Group believes that this guide is useful in supporting EQ Program aging assessment updates@ Maintenance Rule related failure evaluations@ other root cause evaluations@ License Renewal aging management reviews@ as well as special case maintenance problem evaluations. While the scope of this guide is limited to Class 1E equipment@ the principles can be applied equally well to non-Class 1E equipment. A future activity of the Working Group is to extract candidate monitoring methods for aging effects from Table Al@ evaluate continued viability@ and incorporate into a future update of Annex C. Attention is called to the possibility that implementation of this guide may require use of subject matter covered by patent rights. By publication of this guide@ no position is taken with respect to the existence or validity of any patent rights in connection therewith. The IEEE shall not be responsible for identifying patents for which a license may be required by an IEEE standard or for conducting inquiries into the legal validity or scope of those patents that are brought to its attention.ScopeThis document provides the guidelines for assessing@ monitoring@ and mitigating aging degradation effects on Class 1E equipment used in nuclear power generating stations.
IEEE 1205-2006 history
2014IEEE 1205-2014 Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Nuclear Power Generating Stations and Other Nuclear Facilities
2006IEEE 1205/COR 1-2006 Assessing, monitoring, and mitigating aging effects on class 1E equipment used in nuclear power generating stations - Corrigendum 1: Thermal aging model; Corrections
2006IEEE 1205-2006 Guide for Assessing@ Monitoring@ and Mitigating Aging Effects on Class 1E Equipment Used in Nuclear Power Generating Stations Corrigendum 1: Thermal Aging Model Corrections
2000IEEE 1205-2000 Guide for Assessing, Monitoring, and Mitigating Aging Effects on Class 1E Equipment Used in Nuclear Power Generating Stations
1993IEEE 1205-1993 Guide for Assessing@ Monitoring@ and Mitigating Aging Effects on Class 1E Equipment Used in Nuclear Power Generating Stations