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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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Text
August 11, 1972 SAFETY GUIDE 31 CONTROL OF STAINLESS STEEL WELDING A. Introduction supplementary requirements to assure adequate control of weld metal General Design Criterion 1, "Quality properties when welding austenitic Standards and Records," of Appendix A to 10 stainless steel. Specifically, the CFR Part 50, "General Design Criteria for assurance of satisfactory welds in Nuclear Power Plants," requires that structures, austenitic stainless steel of the AISI systems, and components important to safety be 3XX series can be increased designed, fabricated, erected, and tested to significantly and, in particular, the quality standards commensurate with the sensitivity to fissuring or hot cracking importance of the safety function to be can be reduced by maintaining the performed. Appendix B to 10 CFR Part 50, amount of delta-ferrite in the weld "Quality Assurance Criteria for Nuclear Power metal between 5 and 15 percent.
Plants and Fuel Reprocessing Plants," requires that measures be established to assure materials Experiments indicate that 5-10 percent control and control of special processes such as delta-ferrite in welds for austenitic welding, and that proper testing be performed. structures provides optimum resistance This guide describes an acceptable method of to fissuring or hot cracking. An implementing these requirements with regard to acceptable range of delta-ferrite for
.e control of welding when fabricating and welding wrought austenitic structures is
. ing austenitic stainless steel components and 5-12 percent. However, a higher ems. delta-ferrite range of 5-15 percent is acceptable for welding duplex cast B. Discussion structures.
The ASME Boiler and Pressure Vessel Code, Section IX acceptance standards for Section III, "Nuclear Power Plant fissures or cracks in transverse side Components,"' specifies certain requirements bend tests were not intended to cover associated with manufacturing Class 1, 2, and 3 microfissures as such; however, the components. Although welds fabricated for core subject is covered in specification support structures of austenitic stainless steel are MIL-E-0022200/2B (SHIPS), dated not presently within the scope of Section III, September 15, 1970, which states that they should meet Class 1 requirements. 3 fissures smaller than 1/ 16 inch (0.015 inch) need not be counted. Although
- 1. Procedure Qualifications the formation of microfissures in welds also depends on factors other than Section III requires adherence to ASME delta-ferrite content and heat input, it Boiler and Pressure Vessel Code, is generally agreed that there will be Section IX, "Welding Qualifications,"' few, if any, small fissures in a side bend one of the requirements being test of weld metal deposited with the procedure qualifications for welds. proper heat input and containing 5-15 Review of the requirements of percent delta-ferrite.
procedure qualifications stated in Section IX indicates the desirability of In addition to supplementing procedure qualification requirements of Section
... 1Copies may be obtained from American Society of
.]*lhanical Engineers, United Engineering Center, 345 IX by specifying acceptable 47th Street, New York, N.Y. 10017. delta-ferrite content in the weld metal, 31.1
tests and examinations should be made segregation and microfissuring will be to assure that this specification is met reduced.
and that unacceptable microfissures will not result. The use of chemical Control of both local and gross heat analysis of the undiluted weld deposit input is important in welding.
to determine key constituents Experience indicates that welds combined with the use of the produced manually are more likely to Schaeffler diagram to predict its be unacceptable than welds produced delta-ferrite content and a by automatic welding machines. This nondestructive examination of 1he weld results principally because local and using a magnetic measurement device, gross heat inputs are more controllable such as the Severn Ferrite indicator, are in automatic rather than manual weld available techniques to determine production. In order to control gross delta-ferrite content, and both should and local heat inputs during the be included in the procedure welding process (these cannot be qualifications. measured directly) and to assure a proper solidification rate of weld metal, Another important variable in the the variables of amperage, voltage, and control of weld metal is heat input. speed of travel should all be specified in Excessive heat input often results in a procedure qualifications. To provide large weld puddle and a slow cooling reasonable assurance that there will be rate of the weld metal. The resulting no unacceptable microfissures in weld slower solidification rate has a metal, macroscopic examination on a tendency to diminish ferrite retention guided transverse side bend test and to result in large grain size specimen should be included as part of microstructures, which in turn increase the procedure qualifications. All results of the above tests and examinations the tendency both for impurities to segregate at the grain boundaries and should be included in the certified for fissure formation. qualification test report required by Section IX.
A heat input that gives an acceptable 2. Production Welds solidification rate (temperature gradient) in a heavy weld cross section Procedure qualification by itself does may not be acceptable for a thinner not assure that production welds will weld cross section because of the meet the delta-ferrite and heat input smaller heat sink. Control of only the requirements specified in the procedure maximum interpass temperature, used qualification.Section III specifies to assure a satisfactory temperature requirements for welding materials. In gradient in a heavy, cross section, may addition to meeting these requirements, not be sufficient to control each Lot and Heat of welding material microfissuring in thinner sections and, for production welds should be shown consequently, control of heat input to be satisfactory by analysis to predict should also be utilized. Heat input, the delta-ferrite level. In order to assure measured in kilojoules per lineal inch that production welds are satisfactory, (kJ/in) of weld, is considered low when it is desirable that the production welds less than 25 kJ/in, intermediate in the themselves be examined range 25 to 50 kJ/in, and high above 50 nondestructively using a magnetic kJ/in. Microfissuring in weld thickness measurement device such as the Severn of 1 to 2 inches has been observed in ferrite indicator. Since such devices manual arc welded joints which were have limitations regarding the physical deposited with an intermediate heat depth to which they can examine weld input of about 40 kJ/in. If a low heat material, it may be necessary to input of about 25 kJ/in is utilized, the perform several examinations for each assurance of a satisfactory weld will be weld. The number of examinations to enhanced, regardless of thickness and, be conducted for each weld should in particular, the probability of reflect the thickness of the weld metal 31.2
pass, the number of passes ,per joint, delta-ferrite content be predicted the capability of 'the instrument used, by using the Schaeffler diagram 3 and the heats of the weld materials. or its equivalent, Sufficient examinations should be c. delta-ferrite content in weld metal conducted through the thickness of the be determined using magnetic weld to provide reasonable assurance measurement devices 4 such as the that the delta-ferrite content is within Severn ferrite indicator, the specified limits (the number of d. heat input during welding be examinations required for each weld specified in terms of amperage, will vary from weld to weld and is voltage, speed of travel, and dependent upon the factors interpass temperature limits (all enumerated above). In the event the values being selected to promote a examination indicates that the rapid cooling rate across the delta-ferite in the production weld is weldment),
not within the specified, range, e. macroscopic examination be macroscopic examinations should be performed on transverse side bend performed on transverse side bend test specimens to determine specimens from the welds to determine fissures or cracks (or absence of if cracks or fissures exist. Since high same) in weld metal.
reliance is placed on procedure qualifications, instruments used in examining production welds should be calibrated against the same standard as 2. The results of the destructive and that used when developing procedure nondestructive tests required in qualifications. In addition to regulatory position 1. above should be monitoring the normal welding included in the certified qualification variables during performance of test report. 2 production welds, the voltage, amperage, and speed of travel should be
- 3. The welding materials used for periodically monitored to verify production welds should meet the compliance with those included in requirements of Section III of the procedure qualifications.
ASME B&PV Code. In addition, each C. Regulatory Position Lot or Heat of welding material should meet the requirements of regulatory position L.a. and 1.b. above.
Welds for austenitic stainless steel core support structures should comply with the fabrication requirements specified in the 4. Production welds should be examined ASME Boiler and Pressure Vessel Code to verify that delta-ferrite level is (ASME B&PV Code) for Section III, Class 1 between 5 and 12-15 percent in weld components. Weld fabrications for metal. The number of examinations to austenitic stainless steel core support assure compliance with delta-ferrite structures and Class 1, 2, and 3 components level should be based on the thickness should comply with Section III and Section of weld metal per pass, the number of IX of the ASME B&PV Code supplemented passes per joint, the instruments used, by the following: and heats of materials. Instruments used should be calibrated against the
- 1. The procedure qualification 2 should same standard as that used when require that: developing procedure qualifications.
- a. weld deposits contain between 5 and 12-15 percent delta-ferrite,
.3American Society for Metals Handbook, Vol. 6, at
- b. chemical analysis be performed on 246-47.
undiluted weld deposits and that 4 Welding Research Council Bull. No. 132, The 2
ASME Boiler and Pressure Vessel Code, Section Measurement of Delta-Ferrite in Austenitic Stainless Ix. Steels (August 1968).
31.3
V
- 5. In the event that requirements of 6. Production welding should be regulatory position 4. above are not monitored, to verify compliance with met, additional examinations should be the requirements in regulatory position performed in accordance with 1. above for amperage, voltage, speed regulatory position 1.e. above. of travel, and other essential variables.
31.4