NEI 17-06, “Guidance On Using IEC 61508 SIL Certification .

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NEI 17-06, “Guidance on Using IEC 61508 SILCertification to Support the Acceptance of CommercialGrade Digital Equipment for Nuclear Safety RelatedApplications” Revision BPrepared by the Nuclear Energy InstituteSeptember 2019 NEI 2019. All rights reserved.nei.org

September 2019Table of Contents1INTRODUCTION . 11.1 PURPOSE . 11.2 REGULATORY BASIS . 11.3 ACCEPTANCE OF SAFETY INTEGRITY LEVEL AS-VERIFICATION OF DEPENDABILITY CRITICALCHARACTERISTICS . 31.4 ACRONYMS . 41.5 REFERENCES . 52SAFETY INTEGRITY LEVEL (SIL) . 82.1 DESCRIPTION OF THE THIRD PARTY SAFETY INTEGRITY LEVEL (SIL) CERTIFICATION PROCESS . 82.2 DESCRIPTION OF THE CRITICAL DEPENDABILITY CHARACTERISTICS PER NRC-ENDORSED EPRI-TR106439. 113EPRI RESEARCH OF THE SIL CERTIFICATION PROCESS . 133.1 SCOPE OF THE EPRI RESEARCH . 133.2 SUMMARY OF THE EPRI RESEARCH . 144ACCEPTANCE OF COMMERCIAL GRADE DIGITAL EQUIPMENT FOR SAFETY APPLICATIONSCERTIFIED TO A PARTICULAR SIL . 214.1 APPLICATION OF THE SIL CERTIFICATION PROCESS . 214.2 TECHNICAL EVALUATION & ACCEPTANCE METHOD . 214.3 SELECTION OF SIL CERTIFIED EQUIPMENT . 255SUPPLIER’S QUALITY ASSURANCE PROGRAM . 265.1 ORGANIZATION . 265.2 PROCUREMENT DOCUMENT CONTROL . 265.3 CONTROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES . 275.4 QA EVIDENCE FOR DIGITAL DEPENDABILITY . 275.4.1QA Evidence for Digital Dependability. 275.4.2Supplier Tasks Associated Digital Dependability Evidence . 275.5 CORRECTIVE ACTION . 286U.S. NUCLEAR INDUSTRY OVERSIGHT OF THE SIL CERTIFICATION PROCESS . 286.1 ORGANIZATION . 286.2 VERIFICATION THAT THE SIL CERTIFICATION PROCESS CONTINUES TO BE CONSISTENT WITH NRCENDORSED PRACTICES . 28 NEI 2019. All rights reserved.nei.org ii

September 20196.3 VERIFICATION THAT IMPLEMENTATION OF THE 3RD PARTY IEC 61508 SIL CERTIFICATION PROCESSCONTINUES TO BE CONSISTENT WITH NRC ACCEPTED PRACTICES . 29APPENDIX A: EXAMPLE SIL CERTIFICATES . 30 NEI 2019. All rights reserved.nei.org iii

September 201911.1INTRODUCTIONPurposeThe purpose of this supplemental guidance is to provide an acceptable approach for procuring andaccepting commercial grade digital equipment that have a safety integrity level (SIL) certification by anaccredited third party SIL certification body for nuclear safety-related applications. Making use ofinternationally accredited SIL certification services benefits licensees and their suppliers throughexpanded access to expert services, improved standardization on equipment quality evaluations,improved regulatory confidence, and reduced cost without compromising safety.This approach takes advantage of the internationally recognized SIL certification process when acceptingcommercial grade digital equipment for use in safety applications for the nuclear industry. Purchasers(licensees and suppliers of basic components) that procure commercial grade equipment for safetyapplications are able to rely on the third party SIL certification process in lieu of conducting acommercial grade survey (including a critical design review) to provide reasonable assurance that criticalcharacteristics, and in particular dependability critical characteristics described in EPRI Technical Report106439, “Guideline on Evaluation and Acceptance of Commercial Grade Digital Equipment for NuclearSafety Applications” are adequately controlled. The third party SIL certifiers are companies withaccreditation by an accreditation body (AB), such as the American National Standards Institute [ANSI]),that are signatories to the International Accreditation Forum [IAF]. The net result will be increasedconfidence in the ability of these devices to perform their safety functions, as well as substantialreduction in duplication of effort for accepting commercial grade equipment across the industry.1.2Regulatory BasisBasic components are items and services relied upon to perform a safety related function at UScommercial nuclear power plants and are required to be controlled under a quality assurance programcomplying with 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants andFuel Reprocessing Plants”. A commercial grade item is an item that is not a basic component.Dedication (commercial grade dedication) is an acceptance process undertaken to provide reasonableassurance that a commercial grade item accepted for use as a basic component will perform its intendedsafety function and, in this respect, is deemed equivalent to an item designed and manufactured undera 10 CFR Part 50, Appendix B, QA program.When it is not possible to purchase items from a supplier that controls items in accordance with a10CFR50, Appendix B-compliant QA program, items can be purchased as commercial grade items andaccepted via the dedication process. The entity performing this dedication is referred to as the Supplier(i.e., third party dedicator, OEM or licensee with an Appendix B program) in this document.Although the suppliers of commercial grade items and services are not required to comply with 10 CFRPart 50, Appendix B requirements, the commercial grade dedication activities must be performed undera Quality Assurance Program that meets the requirements of 10 CFR Part 50, Appendix B. NEI 2019. All rights reserved.nei.org 1

September 2019The NRC has endorsed EPRI TR-106439 as “an acceptable method for dedicating commercial gradedigital equipment for use in nuclear power plant safety applications and meets the requirements of 10CFR Part 21.” 1EPRI TR-106439 contains guidance on all aspects of commercial grade dedication of commercial gradedigital equipment. EPRI TR-106439 identifies a unique type of critical characteristics for commercialgrade digital equipment called dependability. The following excerpts from EPRI TR-106439 are germaneto the scope of third party SIL certification [underlining added for emphasis]: a third type of critical characteristics, referred to in this guideline [EPRI TR-106439] as dependability,becomes significantly more important when dedicating digital equipment including software This is the category in which dedication of digital equipment differs the most from that of other types ofcomponents. It addresses attributes that typically cannot be verified through inspection and testingalone and are generally affected by the process used to produce the device The dependability attributes, which include items such as reliability and built-in quality, are generallyinfluenced strongly by the process and personnel used by the manufacturer in the design, development,verification, and validation of the software-based equipment.The dependability of a digital device also can be heavily influenced by designed-in elements, includingrobustness of the hardware and software architectures, self-checking features such as watchdog timers,and failure management schemes such as use of redundant processors with automatic fail-overcapabilities. Evaluation of these attributes requires that the dedicator focus on more than just thedevelopment and QA processes. It may require gaining an understanding of the specific software andhardware features embodied in the design, and ensuring that they are correct and appropriate in light ofthe requirements of the intended application. Accordingly, a survey team may need to include specialistswho understand the device design, the software, and the system in which it will be applied, in addition toquality assurance and programmatic issues.The dependability category captures those critical characteristics that must be evaluated to form anappropriate judgment regarding built-in quality of a software-based device. It also includescharacteristics related to problem reporting and configuration control. Verification of thesecharacteristics typically involves a survey of the vendor's processes (Method 2 [of NP-5652]), and reviewof the vendor performance record and product operating history (Method 4) Source inspections wouldnot be used in verifying built-in quality of pre-existing software, because the software development hasalready occurred. A commercial product may be judged to have sufficient quality, even if its development process lackedsome of the rigorous steps of modern software engineering and/or some formal documentation.Reaching a reasonable level of assurance of quality of a commercial grade digital item typically involvesmaking a judgment based on a combination of the product development process and its documentation,operating history, testing, review of design features such as failure management, and other factorsnoted in the critical characteristics matrix, Table 4-1 [in EPRI TR-106439].1 U.S. Nuclear Regulatory Commission, Safety Evaluation Report, “Review of EPRI Topical Report TR-106439, Guideline on Evaluation andAcceptance of Commercial Grade Digital Equipment for Nuclear Safety Applications.” TAC No. M94127, ADAMS accession no. 9810150223. NEI 2019. All rights reserved.nei.org 2

September 2019This supplemental guidance document describes a method for using the accredited SIL certificationprocess in lieu of a commercial grade survey as a dedication acceptance method to provide reasonableassurance that critical characteristics of digital devices, and in particular dependability characteristics,are adequately controlled. This supplemental guidance is applicable to dedicating entities subject to thequality assurance requirements of 10 CFR Part 50, Appendix B (e.g., 10 CFR Part 50, 10 CFR Part 52, 10CFR Part 71 and 10 CFR Part 72 licensees and affected suppliers).1.3Acceptance of Safety Integrity Level As-Verification of Dependability CriticalCharacteristicsThe supplemental guidance within this document describes an approach to rely on third party SILcertifications, by companies accredited by ANSI and other signatories to IAF, in lieu of a commercialgrade survey to verify adequate control of critical characteristics, in particular the dependabilitycharacteristics described in EPRI TR-106439. The approach used to develop this guidance was tocompare the third party SIL certification process with the EPRI TR-106439 dependability criticalcharacteristics to evaluate their similarity and determine whether any additional actions are necessaryto address differences.Section 2 describes the third party SIL certification process, and Section 3 provides the US nuclearindustry’s evaluation of the third party SIL certification process including a comparison with NRCaccepted practices (i.e., EPRI TR-106439). Section 6 describes the approach for the US nuclear industryto provide continued oversight of the third party SIL certification process in order to confirm that thethird party SIL certification process can continue to be used in lieu of commercial grade surveys for thepurpose of verifying the EPRI TR-106439 dependability critical characteristics.Based upon the conclusion that the third party SIL certification process is essentially equivalent to acommercial grade survey verifying the EPRI TR-106439 dependability critical characteristics, it has beendetermined that the third party SIL certifications, by companies accredited by IAF signatories, can beused in lieu of a commercial grade survey to verify EPRI TR-106439 dependability critical characteristics.This conclusion requires procurement documents to include a few requirements. Section 4 describeshow Purchasers of commercial grade digital equipment should use the third party SIL certifications aspart of their commercial grade dedication activities. It is noted that this supplemental guidance shouldbe used in conjunction with the overall guidance on commercial grade dedication (i.e., EPRI TR-106439and EPRI 3002002982). In addition, Section 5 describes information that Purchasers should ensure isincluded in their Quality Assurance Programs.The following are the actions and steps that are necessary in order for a Purchaser to accept third partySIL certification of commercial grade digital equipment, by companies accredited by IAF signatoryorganizations, in lieu of performing a commercial grade survey to evaluate the EPRI TR-106439dependability critical characteristics. Additional detail on performing these steps is discussed insubsequent sections of this guidance.1. The method to use a third party SIL certification by a company accredited by a signatory to IAF inlieu of a commercial grade survey (alternative method) for verification of EPRI TR-106439dependability critical characteristics is documented in the Purchaser’s QA program.2. The method the Purchaser needs to follow, and document in their QA Program, consists of: NEI 2019. All rights reserved.nei.org 3

September 2019i.Adopt NRC-endorsed NEI 17-06 into the QA programii.The purchase documents require that:a. A copy of the SIL certificate for the commercial grade digital equipment beingpurchased be providedb. SIL certification has not expiredc. SIL certification precautions and limitations be included in the SIL certificate orin the safety manuald. A certificate of conformance that the third party SIL certifier is accredited by asignatory to IAF.iii.It is validated, at receipt inspection, that the commercial grade digital equipmentsupplier documentation certifies that:e. The commercial grade digital equipment matches that defined in the SILcertificate providedf.1.4The purchase order’s requirements are metAcronymsABAccreditation BodyACAdministrative ControlsANSIAmerican National Standards InstituteCBCertifying BodyCCCritical CharacteristicsCDRCritical Design ReviewCFRCode of Federal RegulationsCGSCommercial Grade SurveysCOTSCommercial Off The ShelfDSADocumented Safety AnalysesE/E/PEElectrical, Electronic, and Programmable ElectronicEPRIElectric Power Research InstituteFMEAFailure Modes Effects Analysis NEI 2019. All rights reserved.nei.org 4

September 2019FMEDAFailure Modes, Effects and Diagnostic AnalysisFSMFunctional Safety ManagementIAFInternational Accreditation ForumIECInternational Electrotechnical CommissionMLAMulti-Lateral AgreementNEINuclear Energy InstituteNRCNuclear Regulatory CommissionNUPICNuclear Procurement Issues CorporationOEMOriginal Equipment ManufacturerPFDavgAverage Probability of Dangerous Failure on DemandPFHProbability of Failure per HourQAQuality AssuranceQCQuality ControlSILSafety Integrity LevelSIFSafety Instrumented FunctionSIFSafety Instrumented SystemSLMSafety Layer MatrixSQASoftware Quality AssuranceSRSSafety Requirements SpecificationSSSafety SignificantSSCSafety, Systems, and Components1.5References1. EPRI TR-106439, “Guideline on Evaluation and Acceptance of Commercial Grade DigitalEquipment for Nuclear Safety Applications,” October 1996, Electric Power Research Institute.2. 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and FuelReprocessing Plants” NEI 2019. All rights reserved.nei.org 5

September 20193. U.S. Nuclear Regulatory Commission, “Safety Evaluation by the Office of Nuclear ReactorRegulation Electric Power Research Institute Topical Report, TR-106439, “Guideline onEvaluation and Acceptance of Commercial Grade Digital Equipment for Nuclear SafetyApplications.” TAC No. M94127, ADAMS accession no. 9810150223.4. EPRI 3002002982, “Plant Engineer: Guideline for the Acceptance of Commercial-Grade Items inNuclear Safety-Related Applications: Revision 1 to EPRI NP-5652 and TR-102260,” September 22,2014, Electric Power Research Institute.5. IEC 61508, Edition 2.0 “Functional safety of electrical/electronic/programmable electronicsafety-related systems,” International Electrotechnical Commission.6. ISO/IES 17065, “Conformity assessment — Requirements for bodies certifying products,processes and services,” September 15, 2012.7. EPRI 1011710, “Handbook for Evaluating Critical Digital Equipment and Systems,” November2005, Electric Power Research Institute.8. EPRI 3002011817, “Safety Integrity Level (SIL) Certification Efficacy for Nuclear Power,” ElectricPower Research Institute, July 2019.9. IEC 61511-1, “Functional safety – Safety instrumented systems for the process industry sector –Part 1: Framework, definitions, system, hardware and application programming requirements,Edition 2.1, August 2017.10. IEC 61513, “Nuclear power plants - Instrumentation and control important to safety - Generalrequirements for systems”11. IEC 60880, “Nuclear Power Plants – Instrumentation and Control Systems Important to Safety –Software Aspects for Computer-Based Systems,”12. IEC 62138, “Nuclear power plants - Instrumentation and control systems important to safety Software aspects for computer-based systems performing category B or C functions,”13. IEC 60987, “Nuclear power plants - Instrumentation and control important to safety - Hardwaredesign requirements for computer-based systems,”14. IEEE 603-2018, “IEEE Standard Criteria for Safety Systems for Nuclear Power GeneratingStations,”15. IEEE 379, “IEEE Standard for Application of the Single-Failure Criterion to Nuclear PowerGenerating Station Safety Systems,”16. IEEE 7-4.3.2, “IEEE Standard Criteria for Programmable Digital Devices in Safety Systems ofNuclear Power Generating Stations,”17. EPRI TR-107330, ‘Generic Requirement Specifications for Qualifying a Commercially AvailablePLC for Safety-Related Applications in Nuclear Power Plants,” Electric Power Research Institute. NEI 2019. All rights reserved.nei.org 6

September 201918. NRC Regulatory Issue Summary 2002-22 Supplement 1, Clarification on Endorsement of NuclearEnergy Institute Guidance in Designing Digital Upgrades in Instrumentation and ControlSystems,” May 31, 2018, US Nuclear Regulatory commission.19. NRC Regulatory Guides RG 1.28, Revision 5, “Quality Assurance Program Criteria (Design andConstruction),” ML17207A293, U.S. Nuclear Regulatory Commission.20. NRC Regulatory Guides 1.144, Revision 1, “Auditing of Quality Assurance Programs for NuclearPower Plants, ML13038A428, September 1980, U.S. Nuclear Regulatory Commission.21. Functional Safety- An IEC 61508 SIL 3 Compliant Development Process- 3rd Edition, M. Medoff &R. Faller, exida, 2014.22. WIKA, “Operating Instructions for the Differential Pressure Gauge with Micro Switches, ModelDPGS40TA, with Component Testing”,https://www.wika.us/upload/OI DPGS40TA en de fr es 69312.pdf NEI 2019. All rights reserved.nei.org 7

September 201922.1SAFETY INTEGRITY LEVEL (SIL)Description of the Third Party Safety Integrity Level (SIL) Certification ProcessThe third-party certification process involves manufacturers seeking compliance with IEC 61508, thethird-party certifier reviewing their efforts, and an accreditor verifying the third-party certifier’s reviewpractices. The main aspect that makes this process interesting is that the manufacturer is engaged andseeking to develop & manufacture products to meet the safety focused requirements defined in IEC61508.This process is initiated by a manufacturer identifying a business case for producing products that arecapable of a particular SIL, commonly 2 or 3, for a defined scope of safety functions. Then they plan outtheir development based on the requirements of IEC 61508. This international standard provides ageneric approach for all safety life-cycle activities for systems comprised of electrical, electronic, and/orprogrammable electronic elements that are used to perform safety functions and adopts a risk-informedapproach by which the safety integrity requirements can be determined. That standard drives thedevelopment process to incorporate measures to ensure both systematic integrity and reliability. Part ofthe approach used to achieve systematic integrity is the use of rigorous lifecycle style developmentprocesses such as requirements definition, hardware and software design documentation, andverification and validation. Another part is the use of failure analysis, and to then use those results tobuild in safety features such as self-diagnostics, failure tolerance, failure recovery, fail to safe state, andenvironmental tolerance. To achieve reliability, care is taken to choose proven subcomponents, followdesign margin practices, and to use fault tolerant architectures. Reliability is then verified to be of anadequate level by modeling and estimating it using subcomponent failure rates and schematics of theproduct.The significance of choosing a particular SIL is that it drives the level of rigor applied to the developmentprocess and it sets specific quantitative reliability goals. The application of the SIL to the quantitativereliability goals implemented in tables that correlate a Average Probability of Dangerous Failure onDemand (PFDavg) or Probability of Failure per Hour (PFH) range to each SIL. It is understood thatsystematic integrity (built-in quality) can’t be measured in terms of a quantitative value, such as theprobability of failure, so a qualitative case must be built to provide the necessary evidence. This case forsystematic integrity is based on the use of processes and procedures during the product developmentphase that reduce the likelihood of design errors. The specific processes and procedures used are whatare driven by a particular SIL. Part 3 of IEC 61508 focuses on the software development aspects and thisdocument contains tables that are used to select those processes and procedures that will be used tobuild the case of meeting a systematic capability level. IEC 61508 introduces the concept of systematiccapability, which applies to an element with respect to its confidence that the systematic safety integritymeets the requirements of the specified safety integrity level. For example, a table is shown below fromIEC 61508 (in the table R means recommended and HR means highly recommended): NEI 2019. All rights reserved.nei.org 8

September 2019The manufacturer’s efforts culminate into a final safety case that contains the evidence of meeting thereliability goals and the systematic integrity (built-in quality) capability levels that are associated withthe particular SIL. The final safety case is then a deliverable to the entity that has been asked by themanufacturer to certify the subject product. This safety case typically consists of a Functional SafetyManagement (FSM) Plan, Safety Requirements Specification (SRS), Validation Test Plan, ToolJustification, Software Development Process Description, Coding Standard, Software Module Testing,Software Integration Testing, Failure Analysis, Probability of Failure Calculation, and the Safety Manual.This list can vary depending on the product and manufacturer, but the overall collection of documents isconsistently intended to make the case for dependable operation. Figure 2.1 illustrates an examplecollection of documents that could be provided to a third-party certifier and highlights the certifier’sevaluation process of the subject product. NEI 2019. All rights reserved.nei.org 9

September 2019Figure 2.1. Typical Certification Process (Figure 1.3 from Reference 21)The third-party certifier (typically referred to as the certification body) proceeds to evaluate thedocumentation, manufacturer, and product to determine whether the requirements of IEC 61508 havebeen met for the desired SIL. The certification body’s process includes visiting and auditing themanufacturer’s design and manufacturing facilities, reviewing design documentation, and verifyingcalculations and technical evaluations. The certification body will also evaluate data such as warrantyreturns and failure rates. After this process is complete a certificate is granted, or gaps are identified tothe manufacturer to be addressed before a certificate can be granted. The manufacturer can addressgaps and re-initiate the certification process as many times as necessary or can abandon the effort ifgaps are too significant.When a certificate is granted, the certification body will establish criteria for maintaining its validity. Thecriteria may be time-period based, and/or change management based. Whenever any of the criteria areno longer being met the manufacturer must initiate a new effort to have the certification body performthe appropriate actions to re-establish the validity of the certificate.To be a credible entity, the certification body is accredited by the national accreditation body. Thisaccreditation is typically in accordance with ISO 17065. The accreditation bodies that primarily performthis type of work are the Deutsche Akkreditierungsstelle (DAkkS), in Germany, and the AmericanNational Standards Institute (ANSI), in the USA. The accreditation body performs audits and monitorsactivities of the certification body in order to confirm that their processes and procedures, and their NEI 2019. All rights reserved.nei.org 10

September 2019corresponding implementation follows ISO 17065. Accreditations remain valid for a certain time periodand then must be re-established through repeating the appropriate audits and evaluations.2.2Description of the Critical Dependability Characteristics per NRC-Endorsed EPRI-TR106439EPRI TR 106439 defines dependability as, “ a broad concept incorporating various characteristics ofdigital equipment, including reliability, safety, availability, maintainability, and others. [Adapted fromNUREG/CR-6294]”The process of commercial grade dedication as described in 10 CFR 21 requires the identification ofcritical characteristics for the basic component to be dedicated. EPRI TR 106439 adds a special type ofcritical characteristic applicable to digital components to be dedicated: dependability.EPRI TR 106439 describes dependability critical characteristics as attributes that typically cannot beverified through inspection and testing alone and are generally affected by the process used to producethe device. The dependability attributes are influenced by the process and personnel in the design,development, verification, and validation of the digital equipment (e.g., such as reliability and built-inquality). High quality is assessed by examining the systematic life cycle approach from requirementsthrough implementation, with verification and validation steps, and appropriate documentation foreach phase of the lifecycle.The dependability attributes also include designed-in elements, including robustness of the hardwareand programmable logic architectures, self-checking features, real-time performance, and failuremanagement schemes (e.g., fail safe). EPRI TR 106439 refers to this assessment as a critical designreview (CDR). The CDR requires an understanding of the specific programmable logic and hardwarefeatures embodied in the design, to verify that they are correct and appropriate in light of therequirements of the intended application.The CDR includes the evaluation of complexity of the programmable logic and device architecture (e.g.,number of functions, inputs and outputs, internal communications, and interfaces with other systems ordevices). EPRI TR-106439 includes a list of example activities that could be included in this review, butultimately states that “The dedicator must determine which activities are appropriate for eachapplication. In general, the choice and extent of activities undertaken to verify adequate quality, and thespecific criteria applied in making the assessment, depend on the safety significance and complexity ofthe device.” Since the evaluation of safety significance and complexity is not clearly defined in the USnuclear industry, this guidance leads to some ambiguity as to how this review should be performed. EPRITR-106439 does include four examples of how the process can be utilized for various situations, and theUS NRC’s safety evaluation of the

NEI 17-06, “Guidance on Using IEC 61508 SIL Certification to Support the Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Related Applications” Revision B .

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