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{{#Wiki_filter:Figure 1 DRAFT Approach for a New I&C Regulatory Guidance Infrastructure 10 CFR 50                    10 CFR 50                                  10 CFR 50                              10 CFR 52 10 CFR 50.55a                            Domestic Licensing of                                                                                          Licenses, Certifications, and Codes and Standards                      Production and Utilization Appendix A                                  Appendix B                      Approvals for Nuclear Power Facilities            General Design Criteria                  Quality Assurance Criteria                        Plants IEEE 6031991 IEEE 2791971 Standard Criteria for Safety Systems Criteria for Safety Systems        Criteria for Safety System Computers                      SingleFailure Criterion                          Software Development and Digital Reliability                  Equipment Qualification                                    Instrument Sensing Lines                                    Periodic Testing                                Setpoints             Accident Monitoring Instrumentation Update and streamline:                    Update and streamline:                            Update and streamline:                                                                                                                                                      Update and streamline:                                Update and streamline:                                                              Update and streamline:
{{#Wiki_filter:SoftwareDevelopmentandDigitalReliability CriteriaforSafetySystems EquipmentQualification PeriodicTesting SingleFailureCriterion InstrumentSensingLines CriteriaforSafetySystemComputers Setpoints AccidentMonitoringInstrumentation Updateandstreamline:
Update and streamline:                                Update and streamline:                                                                                                                                          Update and streamline:
RegGuide1.168(Verification,Validation,Release&
Reg Guide 1.153 (Criteria for Safety      Reg Guide 1.152 (Use of Computers in              RG 1.53 (Application of the SingleFailure                                                                                                                                  Reg Guide 1.151 (Instrument Sensing Lines)>          Reg Guide 1.22 (Periodic Testing of Actuation                                        RG 1.97 (Criteria for Accident Monitoring Reg Guide 1.168 (Verification, Validation, Release & Reg Guide 1.180 (EMI and RFI Interference on                                                                                                                    Reg Guide 1.105 (Setpoints for Safety Systems) > IEEE 603 (Criteria for Safety  Safety Systems) >                               Criterion to Safety Systems) > IEEE 379                                                                                                                                    ANSI/ISA 67.02.01 (Nuclear SafetyRelated            Systems)                                                                            Instrumentation for Nuclear Power Audit for Digital Systems) > IEEE1012 (Standard for Instrumentation)> MILSTD461E/IEC 61000/                                                                                                                      Related Instrumentation)> ISAS67.04 Systems for Nuclear Power Generating      IEEE 74.3.2 (Criteria for Programmable          (Application of SingleFailure Criterion to                                                                                                                                  InstrumentSensing Line Piping and Tubing                                                                                                  Plants)> IEEE 497 (Criteria for Accident Verification and Validation) and IEEE1028 (Standard  IEEE Std 1050/IEEE Std C62.41/IEEE Std C62.45                                                                                                                  (Setpoints for SafetyRelated Stations)                                 Digital Devices in Safety Systems of              Nuclear Power Generating Station Safety                                                                                                                                      Standard for Use in Nuclear Power Plants)             Reg Guide 1.118 (Periodic Testing of Power                                          Monitoring Instrumentation for Nuclear for Software Review and Audit)                                                                                                                                                                                        Instrumentation Used in Nuclear Power Nuclear Power Generating Stations)                Systems)                                                                                                                                                                                                                            and Protection Systems) > IEEE338 (Periodic Plants)                                Power Generating Stations)
AuditforDigitalSystems)>IEEE1012(Standardfor VerificationandValidation)andIEEE1028(Standard forSoftwareReviewandAudit)
Reg Guide 1.47 (Bypassed and Inoperable                                                                                                                                                                        Reg Guide 1.209 (EQ of SafetyRelated Surveillance Testing of Nuclear Power Status Indication)> IEEE 603                                                                                                                            Reg Guide 1.169 (Configuration Management Plan        Computer Instrumentation and Controls) >
RegGuide1.169(ConfigurationManagementPlan forSoftware)>IEEE828(StandardforSoftware ConfigurationManagementPlans)
Generating Station Safety) for Software) > IEEE828 (Standard for Software      IEEE323 (IEEE Standard for Qualifying Class 1E Reg Guide 1.62 (Manual Initiation of                                                                                                                    Configuration Management Plans)                       Equipment for Nuclear Power Generating Protection Systems)> IEEE 603                                                                                                                                                                                Stations)
RegGuide1.170(SoftwareTestDocumentationfor Software)>IEEE829(StandardforSoftwareTest Documentation)
Reg Guide 1.170 (Software Test Documentation for Reg Guide 1.75 (Physical Independence of                                                                                                                Software) > IEEE829 (Standard for Software Test Electric Systems)> IEEE 384 (Criteria for                                                                                                              Documentation)
RegGuide1.171(SoftwareUnitTestingforSoftware)
Independence of Class 1E Equipment and Circuits)                                                                                                                                                Reg Guide 1.171 (Software Unit Testing for Software)
>IEEE1008(StandardforSoftwareandTesting)
                                                                                                                                                        > IEEE1008 (Standard for Software and Testing)
RegGuide1.172(SoftwareRequirements SpecificationsforSoftware)>IEEE830 (RecommendedPracticesforSoftwareRequirements Specifications)
Reg Guide 1.172 (Software Requirements Specifications for Software) > IEEE830 (Recommended Practices for Software Requirements Specifications)
RegGuide1.173(DevelopingSoftwareLifeCycle ProceduresforSoftware)>IEEE1074(Standardfor DevelopingSoftwareLifecycleProcesses)
Reg Guide 1.173 (Developing Software Life Cycle Procedures for Software) > IEEE1074 (Standard for Developing Software Lifecycle Processes)
Updateandstreamline:
Notes:
RegGuide1.153(CriteriaforSafety Systems)>IEEE603(CriteriaforSafety SystemsforNuclearPowerGenerating Stations)
RegGuide1.47(BypassedandInoperable StatusIndication)>IEEE603 RegGuide1.62(ManualInitiationof ProtectionSystems)>IEEE603 RegGuide1.75(PhysicalIndependenceof ElectricSystems)>IEEE384(Criteriafor IndependenceofClass1EEquipmentand Circuits)
Updateandstreamline:
RegGuide1.180(EMIandRFIInterferenceon Instrumentation)>MILSTD461E/IEC61000/
IEEEStd1050/IEEEStdC62.41/IEEEStdC62.45 RegGuide1.209(EQofSafetyRelated ComputerInstrumentationandControls)>
IEEE323(IEEEStandardforQualifyingClass1E EquipmentforNuclearPowerGenerating Stations)
Updateandstreamline:
RegGuide1.22(PeriodicTestingofActuation Systems)
RegGuide1.118(PeriodicTestingofPower andProtectionSystems)>IEEE338(Periodic SurveillanceTestingofNuclearPower GeneratingStationSafety)
Figure 1 DRAFT Approach for a New I&C Regulatory Guidance Infrastructure Updateandstreamline:
RG1.53(ApplicationoftheSingleFailure CriteriontoSafetySystems)>IEEE379 (ApplicationofSingleFailureCriterionto NuclearPowerGeneratingStationSafety Systems)
Updateandstreamline:
RegGuide1.151(InstrumentSensingLines)>
ANSI/ISA67.02.01(NuclearSafetyRelated InstrumentSensingLinePipingandTubing StandardforUseinNuclearPowerPlants)
Updateandstreamline:
RegGuide1.152(UseofComputersin SafetySystems)>
IEEE74.3.2(CriteriaforProgrammable DigitalDevicesinSafetySystemsof NuclearPowerGeneratingStations)
Updateandstreamline:
RegGuide1.105(SetpointsforSafety RelatedInstrumentation)>ISAS67.04 (SetpointsforSafetyRelated InstrumentationUsedinNuclearPower Plants)
Updateandstreamline:
RG1.97(CriteriaforAccidentMonitoring InstrumentationforNuclearPower Plants)>IEEE497(CriteriaforAccident MonitoringInstrumentationforNuclear PowerGeneratingStations) 10CFR50 AppendixA GeneralDesignCriteria 10CFR50 AppendixB QualityAssuranceCriteria 10CFR50 DomesticLicensingof ProductionandUtilization Facilities 10CFR52 Licenses,Certifications,and ApprovalsforNuclearPower Plants 10CFR50.55a CodesandStandards IEEE6031991 IEEE2791971 StandardCriteriaforSafety Systems Notes:
(1) An evaluation would be required to assess the technical feasibility of updating/streamlining the regulatory guides shown in the figure, including the potential consolidation of guidance documents sharing a common topic.
(1) An evaluation would be required to assess the technical feasibility of updating/streamlining the regulatory guides shown in the figure, including the potential consolidation of guidance documents sharing a common topic.
(2) While not shown in the figure, the potential vision for the I&C regulatory guidance infrastructure allows for incorporating, as appropriate, the current set of digital I&C interim guidance into durable I&C regulatory guidance. For example, DI&C-ISG-04 (Highly Integrated Control Rooms & Digital Communication Systems) could be retired by revising Reg Guide 1.152 to endorse IEEE 7-4.3.2-2016, which captures the information from this interim staff guidance document.
(2) While not shown in the figure, the potential vision for the I&C regulatory guidance infrastructure allows for incorporating, as appropriate, the current set of digital I&C interim guidance into durable I&C regulatory guidance. For example, DI&C-ISG-04 (Highly Integrated Control Rooms & Digital Communication Systems) could be retired by revising Reg Guide 1.152 to endorse IEEE 7-4.3.2-2016, which captures the information from this interim staff guidance document.
(3) For the development of new standards, as well as the need to endorse IEC standards, an evaluation would be required to determine if these can be endorsed via existing regulatory guides thus avoiding the need for developing new ones.}}
(3) For the development of new standards, as well as the need to endorse IEC standards, an evaluation would be required to determine if these can be endorsed via existing regulatory guides thus avoiding the need for developing new ones.}}

Latest revision as of 05:44, 13 December 2024

Figure 1 Draft Approach for a New I&C Regulatory Guidance Infrastructure
ML20100J219
Person / Time
Issue date: 04/09/2020
From: Paul Kallan
NRC/NRR/DNRL/NRLB
To:
Kallan P
References
Download: ML20100J219 (1)
v • d • e


Text

SoftwareDevelopmentandDigitalReliability CriteriaforSafetySystems EquipmentQualification PeriodicTesting SingleFailureCriterion InstrumentSensingLines CriteriaforSafetySystemComputers Setpoints AccidentMonitoringInstrumentation Updateandstreamline:

RegGuide1.168(Verification,Validation,Release&

AuditforDigitalSystems)>IEEE1012(Standardfor VerificationandValidation)andIEEE1028(Standard forSoftwareReviewandAudit)

RegGuide1.169(ConfigurationManagementPlan forSoftware)>IEEE828(StandardforSoftware ConfigurationManagementPlans)

RegGuide1.170(SoftwareTestDocumentationfor Software)>IEEE829(StandardforSoftwareTest Documentation)

RegGuide1.171(SoftwareUnitTestingforSoftware)

>IEEE1008(StandardforSoftwareandTesting)

RegGuide1.172(SoftwareRequirements SpecificationsforSoftware)>IEEE830 (RecommendedPracticesforSoftwareRequirements Specifications)

RegGuide1.173(DevelopingSoftwareLifeCycle ProceduresforSoftware)>IEEE1074(Standardfor DevelopingSoftwareLifecycleProcesses)

Updateandstreamline:

RegGuide1.153(CriteriaforSafety Systems)>IEEE603(CriteriaforSafety SystemsforNuclearPowerGenerating Stations)

RegGuide1.47(BypassedandInoperable StatusIndication)>IEEE603 RegGuide1.62(ManualInitiationof ProtectionSystems)>IEEE603 RegGuide1.75(PhysicalIndependenceof ElectricSystems)>IEEE384(Criteriafor IndependenceofClass1EEquipmentand Circuits)

Updateandstreamline:

RegGuide1.180(EMIandRFIInterferenceon Instrumentation)>MILSTD461E/IEC61000/

IEEEStd1050/IEEEStdC62.41/IEEEStdC62.45 RegGuide1.209(EQofSafetyRelated ComputerInstrumentationandControls)>

IEEE323(IEEEStandardforQualifyingClass1E EquipmentforNuclearPowerGenerating Stations)

Updateandstreamline:

RegGuide1.22(PeriodicTestingofActuation Systems)

RegGuide1.118(PeriodicTestingofPower andProtectionSystems)>IEEE338(Periodic SurveillanceTestingofNuclearPower GeneratingStationSafety)

Figure 1 DRAFT Approach for a New I&C Regulatory Guidance Infrastructure Updateandstreamline:

RG1.53(ApplicationoftheSingleFailure CriteriontoSafetySystems)>IEEE379 (ApplicationofSingleFailureCriterionto NuclearPowerGeneratingStationSafety Systems)

Updateandstreamline:

RegGuide1.151(InstrumentSensingLines)>

ANSI/ISA67.02.01(NuclearSafetyRelated InstrumentSensingLinePipingandTubing StandardforUseinNuclearPowerPlants)

Updateandstreamline:

RegGuide1.152(UseofComputersin SafetySystems)>

IEEE74.3.2(CriteriaforProgrammable DigitalDevicesinSafetySystemsof NuclearPowerGeneratingStations)

Updateandstreamline:

RegGuide1.105(SetpointsforSafety RelatedInstrumentation)>ISAS67.04 (SetpointsforSafetyRelated InstrumentationUsedinNuclearPower Plants)

Updateandstreamline:

RG1.97(CriteriaforAccidentMonitoring InstrumentationforNuclearPower Plants)>IEEE497(CriteriaforAccident MonitoringInstrumentationforNuclear PowerGeneratingStations) 10CFR50 AppendixA GeneralDesignCriteria 10CFR50 AppendixB QualityAssuranceCriteria 10CFR50 DomesticLicensingof ProductionandUtilization Facilities 10CFR52 Licenses,Certifications,and ApprovalsforNuclearPower Plants 10CFR50.55a CodesandStandards IEEE6031991 IEEE2791971 StandardCriteriaforSafety Systems Notes:

(1) An evaluation would be required to assess the technical feasibility of updating/streamlining the regulatory guides shown in the figure, including the potential consolidation of guidance documents sharing a common topic.

(2) While not shown in the figure, the potential vision for the I&C regulatory guidance infrastructure allows for incorporating, as appropriate, the current set of digital I&C interim guidance into durable I&C regulatory guidance. For example, DI&C-ISG-04 (Highly Integrated Control Rooms & Digital Communication Systems) could be retired by revising Reg Guide 1.152 to endorse IEEE 7-4.3.2-2016, which captures the information from this interim staff guidance document.

(3) For the development of new standards, as well as the need to endorse IEC standards, an evaluation would be required to determine if these can be endorsed via existing regulatory guides thus avoiding the need for developing new ones.

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