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Category:Regulatory Guide
MONTHYEARML23263A9972024-02-0202 February 2024 Watermarked - DG-5072 - Rev 0 of RG 5.90 - Guidance for Alternative Physical Security Requirements for Small Modular Reactors and Non-Light-Water Reactors ML23286A2682024-02-0202 February 2024 Watermarked - DG-5074 - Access Authorization - Econcurrence Version Clean (02-03-23) ML23286A2822024-02-0202 February 2024 Watermarked - DG-5076 - Physical Protection for Part 53 - 10-13-23 ML23286A2512024-02-0202 February 2024 Watermarked DG-5073 - Fitness for Duty Program for Part 53 - 10-13-23 ML23286A2862024-02-0202 February 2024 Watermarked - DG-5078, Fatigue Management for Nuclear Power Plant Personnel -10-13-23 ML23286A2782024-02-0202 February 2024 Watermarked - DG-5075 - Cyber Security 10-13-23 ML23194A1942023-08-31031 August 2023 Draft Regulatory Guide DG-1404, Revision 1 (RG 1.253 Rev 0) Guidance on Ticap for Non-LWRs ML23012A2422023-02-28028 February 2023 DG-1374 RG 1.152 Rev 4 Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants ML22165A0722023-02-28028 February 2023 DG-4027, Draft Regulatory Guide 4.2 Supplement 1, Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications, Revision 2 ML23018A2932023-02-16016 February 2023 Draft Regulatory Guide DG-1418 (RG 1.212 Rev 2), Sizing Large Lead-Acid Storage Batteries. (ACRS Copy) Regulatory Guide 5.892022-11-0101 November 2022 Rev.0, Fitness-for-Duty Programs for Commercial Power Reactor and Category I Special Nuclear Material Licensees ML22067A0142022-03-31031 March 2022 Rev 3 ACRS Spent Fuel Heat Generation in an ISFSI ML22048B8222022-02-18018 February 2022 DG-1389 (ACRS Version for 3-16-22 Meeting) - Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors ML22040A0822021-10-30030 October 2021 Document to Support ACRS Subcommittee Meeting - Redline RG 1.57, Rev 3, Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components ML21167A3512021-06-0101 June 2021 Rev 5 Final Watermarked for ACRS ML21092A1512021-05-0505 May 2021 Rev. 4 ACRS Version ML21092A1342021-05-0505 May 2021 Rev. 2 ACRS Version ML21181A2492021-04-30030 April 2021 Watermark for ACRS Fc Meeting RG 1.9 Rev 5 ML21006A3352021-04-0101 April 2021 DG 1381 for Rev 0 of RG 1.244 - Control of Heavy Loads for Nuclear Facilities ML20168A8832021-04-0101 April 2021 DG-1371, Proposed Rev 6 of RG 1.26, Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants ML21006A3372021-04-0101 April 2021 Regulatory Analysis - DG 1381 - Control of Heavy Loads for Nuclear Facilities ML21083A2892021-02-28028 February 2021 Draft for Acrs Review ML21048A4482021-02-17017 February 2021 Rev. 2 ML20120A6292021-01-31031 January 2021 Operation and Maintenance Code Case Acceptability, ASME OM Code, Revision 4, (DG-1368) ML20120A6332021-01-31031 January 2021 Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, Revision 39, (DG-1366) ML20120A6272021-01-31031 January 2021 ASME Code Cases Not Approved for Use, Revision 7 (DG-1369) ML20120A6312021-01-31031 January 2021 Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 20, (DG-1367) ML21011A2312021-01-31031 January 2021 Rev 4 (Draft for ACRS Fc Review on 2-3-21) ML21012A1972021-01-12012 January 2021 a Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion, RG 1.208, Revision 0 Regulatory Guide 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities2020-12-31031 December 2020 Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities ML20183A4232020-12-31031 December 2020 Draft Regulatory Guide DG-1361 (Proposed Rev. 2 to Reg. Guide 1.89), Environmental Qualification of Certain Electrical Equipment Important to Safety for Nuclear Power Plants ML20238B8732020-12-29029 December 2020 Public Comment Resolutions on DG-1362 for RG 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities ML20282A2982020-12-0404 December 2020 DG-3055, Rev 0, Regulatory Guide (RG) 3.76, Implementation of Aging Management Requirements for Spent Fuel Storage Renewals ML20282A2992020-12-0404 December 2020 Regulatory Analysis for DG-3055, Rev 0, Regulatory Guide (RG) 3.76, Implementation of Aging Management Requirements for Spent Fuel Storage Renewals ML20210M0472020-12-0101 December 2020 Draft Regulation Guide DG-1288: Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspections of Piping ML20231A8562020-11-30030 November 2020 Draft Regulatory Guide DG-1360, Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants ML20231A8352020-11-30030 November 2020 Draft Regulatory Guide DG-1359, Fire Protection for Nuclear Power Plants ML20307A0462020-11-0202 November 2020 Draft for ACRS Public Meeting, RG 1.200, R3, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities ML20210M0442020-10-28028 October 2020 Regulatory Analysis: Draft Regulatory Guide DG-1288 - an Approach for Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspection of Piping (Proposed Revision 2 of Regulatory Guide 1.178, Dated September 2003) ML20154K5842020-09-17017 September 2020 Results of Periodic Review of Regulatory Guide (RG) 1.78 ML20182A7882020-08-31031 August 2020 DG 1373 for RG 1.240 - Fresh and Spent Fuel Pool Criticality Analyses ML20055G8232020-08-0707 August 2020 DG 1363 for Proposed Rev 4 to Regulatory Guide (RG) 1.105 - Setpoints for Safety-Related Instrumentation Regulatory Guide 3.152020-07-31031 July 2020 Regulatory Guide 3.15. Rev 2, Standard Format and Content of License Applications for Receipt and Storage of Unirradiated Power Reactor Fuel and Associated Radioactive Material at a Nuclear Power Plant Regulatory Guide 1.2362020-07-30030 July 2020 Draft for ACRS Review ML20119A6142020-04-28028 April 2020 Response to Comments for RG 1.236 for ACRS ML20105A4672020-04-14014 April 2020 Memo to OCA - for Revision 1 of Regulatory Guide 8.39, Release of Patients Administered Radioactive Material ML20099F0262020-04-0707 April 2020 Public Comment Resolution Table for DG 1341 (Regulatory Guide (RG) 1.188, Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses, Rev. 2 ML19206A4892020-02-0606 February 2020 Draft Regulatory Guide DG-1287, an Approach for Plant-Specific, risk-Informed Decisionmaking: Technical Specifications ML19116A0772019-08-31031 August 2019 Draft Regulatory Guide DG-5040, Urine Specimen Collection and Test Results Review Under 10 CFR Part 26, Fitness for Duty Programs. ML19203A0892019-07-31031 July 2019 Assessment of the Continued Adequacy of Revision 2 of Regulatory Guide 1.99 - Technical Letter Report 2024-02-02
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MONTHYEARML23263A9972024-02-0202 February 2024 Watermarked - DG-5072 - Rev 0 of RG 5.90 - Guidance for Alternative Physical Security Requirements for Small Modular Reactors and Non-Light-Water Reactors ML23286A2512024-02-0202 February 2024 Watermarked DG-5073 - Fitness for Duty Program for Part 53 - 10-13-23 ML23286A2682024-02-0202 February 2024 Watermarked - DG-5074 - Access Authorization - Econcurrence Version Clean (02-03-23) ML23286A2782024-02-0202 February 2024 Watermarked - DG-5075 - Cyber Security 10-13-23 ML23286A2822024-02-0202 February 2024 Watermarked - DG-5076 - Physical Protection for Part 53 - 10-13-23 ML23286A2862024-02-0202 February 2024 Watermarked - DG-5078, Fatigue Management for Nuclear Power Plant Personnel -10-13-23 ML23194A1942023-08-31031 August 2023 Draft Regulatory Guide DG-1404, Revision 1 (RG 1.253 Rev 0) Guidance on Ticap for Non-LWRs ML23012A2422023-02-28028 February 2023 DG-1374 RG 1.152 Rev 4 Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants ML22165A0722023-02-28028 February 2023 DG-4027, Draft Regulatory Guide 4.2 Supplement 1, Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications, Revision 2 ML23018A2932023-02-16016 February 2023 Draft Regulatory Guide DG-1418 (RG 1.212 Rev 2), Sizing Large Lead-Acid Storage Batteries. (ACRS Copy) ML22067A0142022-03-31031 March 2022 Rev 3 ACRS Spent Fuel Heat Generation in an ISFSI ML22048B8222022-02-18018 February 2022 DG-1389 (ACRS Version for 3-16-22 Meeting) - Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors ML22040A0822021-10-30030 October 2021 Document to Support ACRS Subcommittee Meeting - Redline RG 1.57, Rev 3, Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components ML21181A2492021-04-30030 April 2021 Watermark for ACRS Fc Meeting RG 1.9 Rev 5 ML21006A3372021-04-0101 April 2021 Regulatory Analysis - DG 1381 - Control of Heavy Loads for Nuclear Facilities ML21006A3352021-04-0101 April 2021 DG 1381 for Rev 0 of RG 1.244 - Control of Heavy Loads for Nuclear Facilities ML20168A8832021-04-0101 April 2021 DG-1371, Proposed Rev 6 of RG 1.26, Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants ML20120A6272021-01-31031 January 2021 ASME Code Cases Not Approved for Use, Revision 7 (DG-1369) ML20120A6312021-01-31031 January 2021 Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 20, (DG-1367) ML20120A6332021-01-31031 January 2021 Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, Revision 39, (DG-1366) ML20120A6292021-01-31031 January 2021 Operation and Maintenance Code Case Acceptability, ASME OM Code, Revision 4, (DG-1368) ML20183A4232020-12-31031 December 2020 Draft Regulatory Guide DG-1361 (Proposed Rev. 2 to Reg. Guide 1.89), Environmental Qualification of Certain Electrical Equipment Important to Safety for Nuclear Power Plants ML20210M0472020-12-0101 December 2020 Draft Regulation Guide DG-1288: Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspections of Piping ML20231A8562020-11-30030 November 2020 Draft Regulatory Guide DG-1360, Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants ML20231A8352020-11-30030 November 2020 Draft Regulatory Guide DG-1359, Fire Protection for Nuclear Power Plants ML20307A0462020-11-0202 November 2020 Draft for ACRS Public Meeting, RG 1.200, R3, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities ML20210M0442020-10-28028 October 2020 Regulatory Analysis: Draft Regulatory Guide DG-1288 - an Approach for Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspection of Piping (Proposed Revision 2 of Regulatory Guide 1.178, Dated September 2003) ML20055G8232020-08-0707 August 2020 DG 1363 for Proposed Rev 4 to Regulatory Guide (RG) 1.105 - Setpoints for Safety-Related Instrumentation NUREG-1575, Rev. 2, Multi-Agency Radiation Survey and Site Investigation Manual (Marssim), Draft for Public Comment2020-05-31031 May 2020 NUREG-1575, Rev. 2, Multi-Agency Radiation Survey and Site Investigation Manual (Marssim), Draft for Public Comment ML21008A5742020-05-31031 May 2020 Appendices to Marssim Revision 2 Draft for Public Comment ML20119A6142020-04-28028 April 2020 Response to Comments for RG 1.236 for ACRS ML19206A4892020-02-0606 February 2020 Draft Regulatory Guide DG-1287, an Approach for Plant-Specific, risk-Informed Decisionmaking: Technical Specifications ML19116A0772019-08-31031 August 2019 Draft Regulatory Guide DG-5040, Urine Specimen Collection and Test Results Review Under 10 CFR Part 26, Fitness for Duty Programs. ML19045A4352019-05-31031 May 2019 Draft Regulatory Guide DG-1356, Guidance for Implementation of 10 CFR 50.59, Changes, Test and Experiments. ML16172A2402019-04-30030 April 2019 Draft Regulatory Guide (DG)-1283, Safety Related Concrete Structures for Nuclear Power Plants ML17258A5792019-04-30030 April 2019 DG-1284, Anchoring Components and Structural Supports in Concrete ML19042A1722019-03-31031 March 2019 Draft Regulatory Guide (DG)-7010, Leakage Tests on for Shipment of Radioactive Material ML18158A3032019-01-31031 January 2019 Draft Regulatory Guide DG-1352, Instrument Sensing Lines ML18087A1692018-10-31031 October 2018 Draft Regulatory Guide DG-4019, Environmental Dosimetry - Performance Specifications, Testing, and Data Analysis ML18087A1672018-10-31031 October 2018 DG-4019 Reg Analysis ML18016A1292018-08-31031 August 2018 Draft Regulatory Guide (DG)-5061, Cyber Security Programs for Nuclear Power Reactors. ML18232A5002018-08-31031 August 2018 Marked Up Draft Regulatory Guide for Cyber Security Programs for Nuclear Power Reactors. (Rdlso - Rg 5.71 Rev. 0 Vs DG-5061) ML18234A0962018-08-31031 August 2018 Draft Regulatory Guide DG-5057, Special Nuclear Material Control and Accounting System for Non-Fuel Cycle Facilities ML17353A7272018-06-30030 June 2018 Draft Regulatory Guide (DG) 1349, Standard Format and Content for Post-Shutdown Decommissioning Activities Report. ML18086A6902018-06-30030 June 2018 Draft Regulatory Guide DG-1351, Dispositioning of Technical Specifications That Are Insufficient to Ensure Plant Safety ML17348B4852018-06-30030 June 2018 Draft Regulatory Guide (DG) 1348, Assuring the Availability of Funds for Decommissioning Production or Utilization Facilities. ML17347A7942018-06-30030 June 2018 Draft Regulatory Guide (DG) 1347, Decommissioning of Nuclear Power Reactors. ML16091A2672018-02-28028 February 2018 Draft Regulatory Guide (DG)-1329, Proposed Revision 4 to Regulatory Guide Rg 1.8, Qualification and Training of Personnel for Nuclear Power Plants. Regulatory Guide 1.2322018-02-27027 February 2018 Guidance for Developing Principal Design Criteria for Non-Light-Water Reactors ML16165A2982017-07-31031 July 2017 Draft Guide (DG) - 1291 Evaluating Deviations and Reporting Defects and Noncompliance Under 10 CFR Part 21 2024-02-02
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August 11, 1972 SAFETY GUIDE 31 CONTROL OF STAINLESS STEEL WELDING A. Introduction General Design Criterion 1, "Quality Standards and Records," of Appendix A to 10 CFR Part 50, "General Design Criteria for Nuclear Power Plants," requires that structures, systems, and components important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety function to be performed.
Appendix B to 10 CFR Part 50,"Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," requires that measures be established to assure materials control and control of special processes such as welding, and that proper testing be performed.
This guide describes an acceptable method of implementing these requirements with regard to.e control of welding when fabricating and.ing austenitic stainless steel components and ems.B. Discussion The ASME Boiler and Pressure Vessel Code,Section III, "Nuclear Power Plant Components,"'
specifies certain requirements associated with manufacturing Class 1, 2, and 3 components.
Although welds fabricated for core support structures of austenitic stainless steel are not presently within the scope of Section III, they should meet Class 1 requirements.
- 1. Procedure QualificationsSection III requires adherence to ASME Boiler and Pressure Vessel Code,Section IX, "Welding Qualifications,"'
one of the requirements being procedure qualifications for welds.Review of the requirements of procedure qualifications stated in Section IX indicates the desirability of... 1Copies may be obtained from American Society of.]*lhanical Engineers, United Engineering Center, 345 47th Street, New York, N.Y. 10017.supplementary requirements to assure adequate control of weld metal properties when welding austenitic stainless steel. Specifically, the assurance of satisfactory welds in austenitic stainless steel of the AISI 3XX series can be increased significantly and, in particular, the sensitivity to fissuring or hot cracking can be reduced by maintaining the amount of delta-ferrite in the weld metal between 5 and 15 percent.Experiments indicate that 5-10 percent delta-ferrite in welds for austenitic structures provides optimum resistance to fissuring or hot cracking.
An acceptable range of delta-ferrite for welding wrought austenitic structures is 5-12 percent. However, a higher delta-ferrite range of 5-15 percent is acceptable for welding duplex cast structures.
Section IX acceptance standards for fissures or cracks in transverse side bend tests were not intended to cover microfissures as such; however, the subject is covered in specification MIL-E-0022200/2B (SHIPS), dated September 15, 1970, which states that 3 fissures smaller than 1 / 16 inch (0.015 inch) need not be counted. Although the formation of microfissures in welds also depends on factors other than delta-ferrite content and heat input, it is generally agreed that there will be few, if any, small fissures in a side bend test of weld metal deposited with the proper heat input and containing 5-15 percent delta-ferrite.
In addition to supplementing procedure qualification requirements of Section IX by specifying acceptable delta-ferrite content in the weld metal, 31.1 tests and examinations should be made to assure that this specification is met and that unacceptable microfissures will not result. The use of chemical analysis of the undiluted weld deposit to determine key constituents combined with the use of the Schaeffler diagram to predict its delta-ferrite content and a nondestructive examination of 1he weld using a magnetic measurement device, such as the Severn Ferrite indicator, are available techniques to determine delta-ferrite content, and both should be included in the procedure qualifications.
Another important variable in the control of weld metal is heat input.Excessive heat input often results in a large weld puddle and a slow cooling rate of the weld metal. The resulting slower solidification rate has a tendency to diminish ferrite retention and to result in large grain size microstructures, which in turn increase the tendency both for impurities to segregate at the grain boundaries and for fissure formation.
A heat input that gives an acceptable solidification rate (temperature gradient) in a heavy weld cross section may not be acceptable for a thinner weld cross section because of the smaller heat sink. Control of only the maximum interpass temperature, used to assure a satisfactory temperature gradient in a heavy, cross section, may not be sufficient to control microfissuring in thinner sections and, consequently, control of heat input should also be utilized.
Heat input, measured in kilojoules per lineal inch (kJ/in) of weld, is considered low when less than 25 kJ/in, intermediate in the range 25 to 50 kJ/in, and high above 50 kJ/in. Microfissuring in weld thickness of 1 to 2 inches has been observed in manual arc welded joints which were deposited with an intermediate heat input of about 40 kJ/in. If a low heat input of about 25 kJ/in is utilized, the assurance of a satisfactory weld will be enhanced, regardless of thickness and, in particular, the probability of segregation and microfissuring will be reduced.Control of both local and gross heat input is important in welding.Experience indicates that welds produced manually are more likely to be unacceptable than welds produced by automatic welding machines.
This results principally because local and gross heat inputs are more controllable in automatic rather than manual weld production.
In order to control gross and local heat inputs during the welding process (these cannot be measured directly) and to assure a proper solidification rate of weld metal, the variables of amperage, voltage, and speed of travel should all be specified in procedure qualifications.
To provide reasonable assurance that there will be no unacceptable microfissures in weld metal, macroscopic examination on a guided transverse side bend test specimen should be included as part of the procedure qualifications.
All results of the above tests and examinations should be included in the certified qualification test report required by Section IX.2. Production Welds Procedure qualification by itself does not assure that production welds will meet the delta-ferrite and heat input requirements specified in the procedure qualification.
Section III specifies requirements for welding materials.
In addition to meeting these requirements, each Lot and Heat of welding material for production welds should be shown to be satisfactory by analysis to predict the delta-ferrite level. In order to assure that production welds are satisfactory, it is desirable that the production welds themselves be examined nondestructively using a magnetic measurement device such as the Severn ferrite indicator.
Since such devices have limitations regarding the physical depth to which they can examine weld material, it may be necessary to perform several examinations for each weld. The number of examinations to be conducted for each weld should reflect the thickness of the weld metal 31.2 pass, the number of passes , per joint, the capability of 'the instrument used, and the heats of the weld materials.
Sufficient examinations should be conducted through the thickness of the weld to provide reasonable assurance that the delta-ferrite content is within the specified limits (the number of examinations required for each weld will vary from weld to weld and is dependent upon the factors enumerated above). In the event the examination indicates that the delta-ferite in the production weld is not within the specified, range, macroscopic examinations should be performed on transverse side bend specimens from the welds to determine if cracks or fissures exist. Since high reliance is placed on procedure qualifications, instruments used in examining production welds should be calibrated against the same standard as that used when developing procedure qualifications.
In addition to monitoring the normal welding variables during performance of production welds, the voltage, amperage, and speed of travel should be periodically monitored to verify compliance with those included in procedure qualifications.
C. Regulatory Position Welds for austenitic stainless steel core support structures should comply with the fabrication requirements specified in the ASME Boiler and Pressure Vessel Code (ASME B&PV Code) for Section III, Class 1 components.
Weld fabrications for austenitic stainless steel core support structures and Class 1, 2, and 3 components should comply with Section III and Section IX of the ASME B&PV Code supplemented by the following:
- 1. The procedure qualification 2 should require that: a. weld deposits contain between 5 and 12-15 percent delta-ferrite, b. chemical analysis be performed on undiluted weld deposits and that 2 ASME Boiler and Pressure Vessel Code, Section Ix.delta-ferrite content be predicted by using the Schaeffler diagram 3 or its equivalent, c. delta-ferrite content in weld metal be determined using magnetic measurement devices 4 such as the Severn ferrite indicator, d. heat input during welding be specified in terms of amperage, voltage, speed of travel, and interpass temperature limits (all values being selected to promote a rapid cooling rate across the weldment), e. macroscopic examination be performed on transverse side bend test specimens to determine fissures or cracks (or absence of same) in weld metal.2. The results of the destructive and nondestructive tests required in regulatory position 1. above should be included in the certified qualification test report.2 3. The welding materials used for production welds should meet the requirements of Section III of the ASME B&PV Code. In addition, each Lot or Heat of welding material should meet the requirements of regulatory position L.a. and 1.b. above.4. Production welds should be examined to verify that delta-ferrite level is between 5 and 12-15 percent in weld metal. The number of examinations to assure compliance with delta-ferrite level should be based on the thickness of weld metal per pass, the number of passes per joint, the instruments used, and heats of materials.
Instruments used should be calibrated against the same standard as that used when developing procedure qualifications.
.3 American Society for Metals Handbook, Vol. 6, at 246-47.4 Welding Research Council Bull. No. 132, The Measurement of Delta-Ferrite in Austenitic Stainless Steels (August 1968).31.3 V 5. In the event that requirements of regulatory position 4. above are not met, additional examinations should be performed in accordance with regulatory position 1.e. above.6. Production welding should be monitored, to verify compliance with the requirements in regulatory position 1. above for amperage, voltage, speed of travel, and other essential variables.
31.4