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{{#Wiki_filter:'U.S. NUCLEAR REGULATORY COMMISSION                                                                                                                     May 1975 REGULATORY GUIDE
{{#Wiki_filter:'U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF STANDARDS DEVELOPMENT
REGULATORY GUIDE  
                                                                      REGULATORY GUIDE 3.29 PREHEAT AND INTERPASS TEMPERATURE CONTROL FOR THE
OFFICE OF STANDARDS DEVELOPMENT  
              WELDING OF LOW-ALLOY STEEL FOR USE IN FUEL REPROCESSING PLANTS
REGULATORY GUIDE 3.29 PREHEAT AND INTERPASS TEMPERATURE CONTROL FOR THE  
                      AND IN PLUTONIUM PROCESSING AND FUEL FABRICATION PLANTS
WELDING OF LOW-ALLOY STEEL FOR USE IN FUEL REPROCESSING PLANTS  
AND IN PLUTONIUM PROCESSING AND FUEL FABRICATION PLANTS


==A. INTRODUCTION==
==A. INTRODUCTION==
This guide describes a method acceptable to the NRC
Section 50.34, "Contents of Applications; Technical Information," of 10 CFR Part 50, "Ucensing of Produc tion and Utilization Facilities," requires, among other things, that each application for a construction permit or operating license for a fuel reprocessing plant include a discussion of how the applicable requirements of Appen dix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50
                                                                                      staff for meeting these requirements with regard to the Section 50.34, "Contents of Applications; Technical                             control of welding of low-alloy steel components for Information," of 10 CFR Part 50, "Ucensing of Produc                                 fuel reprocessing plants and for plutonium processing tion and Utilization Facilities," requires, among other                               and fuel fabrication plants.
will be satisfied. As used in Appendix B, "quality assurance" comprises all those planned and systematic actions necessary to provide adequate confidence that safety-related structures, systems, and components will perform Satisfactorily in service. Appendix B requires, in part, that measures be established to ensure that special processes, including welding, are controlled and accomp lished by qualified personnel using qualified procedures, and that proper process monitoring be performed. Para graph 70.22(f) of 10 CFR Part 70, "Special Nuclear Material," requires that each application for a license to possess and use special nuclear material in a plutonium processing and fuel fabrication plant contain a des cription of the quality assurance program to be applied to the design, fabrication, construction, testing, and operation of the structures, systems, and components of the plant and that the description include a discussion of how the criteria of Appendix B to Part 50 will be met.


things, that each application for a construction permit or operating license for a fuel reprocessing plant include a                                                         
Paragraph 70.23(b) of 10 CFR Part 70 provides that the Commission will approve construction of a plutonium processing and fuel fabrication plant when it has deter mined that the design bases and the quality assurance program provide reasonable assurance of protection against natural phenomena and the consequences of potential accidents, noting that the criteria in Appendix B to-0 CFR Part 50 will be used by the CommissionIn determining the adequacy of the quality assurance pro gram- This guide describes a method acceptable to the NRC
staff for meeting these requirements with regard to the control of welding of low-alloy steel components for fuel reprocessing plants and for plutonium processing and fuel fabrication plants.


==B. DISCUSSION==
==B. DISCUSSION==
discussion of how the applicable requirements of Appen dix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50                                    The American Society of Mechanical Engineers Boiler will be satisfied. As used in Appendix B, "quality                                    and Pressure Vessel Code* (ASME Code), Section III,
The American Society of Mechanical Engineers Boiler and Pressure Vessel Code* (ASME Code), Section III,  
assurance" comprises all those planned and systematic                                  "Nuclear Power Plant Components," and Section VIII,
"Nuclear Power Plant Components," and Section VIII,  
actions necessary to provide adequate confidence that                                  "Pressure Vessels," specify requirements for fabricating safety-related structures, systems, and components will                                components as indicated In the section titles. Many of perform Satisfactorily in service. Appendix B requires, in                            the requirements of this Code can also be applied to part, that measures be established to ensure that special                              safety-related structures, systems, and components of processes, including welding, are controlled and accomp                                fuel reprocessing plants and plutonium processing and lished by qualified personnel using qualified procedures,                              fuel fabrication plants. Specific portions of the ASME
"Pressure Vessels," specify requirements for fabricating components as indicated In the section titles. Many of the requirements of this Code can also be applied to safety-related structures, systems, and components of fuel reprocessing plants and plutonium processing and fuel fabrication plants. Specific portions of the ASME  
and that proper process monitoring be performed. Para                                  Code and of other applicable codes and standards have graph 70.22(f) of 10 CFR Part 70, "Special Nuclear                                    been used for fabricating components for such plants.
Code and of other applicable codes and standards have been used for fabricating components for such plants.


Material," requires that each application for a license to                            Acceptable practices can differ significantly because possess and use special nuclear material in a plutonium                                there has not been sufficient guidance toward standard processing and fuel fabrication plant contain a des                                    ization. In the interest of standardization, this guide cription of the quality assurance program to be applied                                specifies procedures acceptable to the NRC staff for the to the design, fabrication, construction, testing, and                                control of preheat and interpass temperatures for'
Acceptable practices can differ significantly because there has not been sufficient guidance toward standard ization. In the interest of standardization, this guide specifies procedures acceptable to the NRC staff for the control of preheat and interpass temperatures for'  
operation of the structures, systems, and components of                                welding of low alloy steels for use In the plants discussed the plant and that the description include a discussion of                            albove. These procedures, which draw on those used for how the criteria of Appendix B to Part 50 will be met.                                nuclear power plants, will provide a uniform quality Paragraph 70.23(b) of 10 CFR Part 70 provides that the                                level consistent with the function of safety-related Commission will approve construction of a plutonium                                    structures, systems, and componentsiof fuel reprocessing processing and fuel fabrication plant when it has deter                              plants and of plutonium processing and fuel fabrication mined that the design bases and the quality assurance                                plants.
welding of low alloy steels for use In the plants discussed albove. These procedures, which draw on those used for nuclear power plants, will provide a uniform quality level consistent with the function of safety-related structures, systems, and componentsiof fuel reprocessing plants and of plutonium processing and fuel fabrication plants.


program provide reasonable assurance of protection against natural phenomena and the consequences of
*American Society of Mechanical Engineers 'Boiler and Pressure Vessel Code, 1974 Edition. AI references to the ASME  
                                                                                            *American Society of Mechanical Engineers 'Boiler and potential accidents, noting that the criteria in Appendix                              Pressure Vessel Code, 1974 Edition. AI references to the ASME
Code wre to the 1974 edition. Copies may be obtained from the American Society of Mechanical -Engineers, United Engineering Center, 345 East 47th Street, New York, N.Y. 10017.
B to-0 CFR Part 50 will be used by the CommissionIn                                    Code wre to the 1974 edition. Copies may be obtained from the determining the adequacy of the quality assurance pro                                  American Society of Mechanical -Engineers, United Engineering gram-                                                                                  Center, 345 East 47th Street, New York, N.Y. 10017.


USNRC REGULATORY GUIDES                                         Comments should be sent to the Secretary of the Commission. U.S Nuclear Regulatory Guides are issued to describe and make available to the public           Regulatory rvKe.    Gommisson. Washington. D.C.                ttention: Docketing end methods acceptable to the NRC.staff of Implementing specific parts of the Commoilon's regulatlons. to delineate techniques used by the staff in eralu-          The guideswe Issuedin the fo*owingon broad divisions:
USNRC REGULATORY GUIDES  
ating specific problems or postulated accidents. or to provide guidance to appi cents. Regulatory Guides are not substitutes for regulations, and compliance          1. Power Reacto.,                      S. Products with them Is not required. Methods end solutions different from thas 0ot mut in      2. Research and Test Reactors          7. Transportation the ugudes  will be acceptable if they provide a basis for the findings requisite to  $. Fuels and Matedria Facilties      ,L Occupational fheath the Isauanc or continuance of a permit or license by the Commission.                  4. Environmental and Sting            9. Antitrust Review Comments and suggestione for improvements in these guides am encouraged              5. Materials and Plant Protection    10. General at all times, and guides will be revised. es appropriate. to accommodate eam mants and to reflect now information or experlence. However. comments on              Coies of published guides may be obtained by written request Indicating the this guide, If received within about two months after its issuance, will be par-      divisions desired to the US. Nuclear Regulatory Commission. Washington. D.C.
Comments should be sent to the Secretary of the Commission. U.S Nuclear Regulatory Guides are issued to describe and make available to the public Regulatory Gommisson. Washington. D.C.


ticularly useful in evaluating the need for an early revision.                       N05S. Attention: Director. Office of Standards Development.
rvKe.
 
ttention: Docketing end methods acceptable to the NRC.staff of Implementing specific parts of the Commoilon's regulatlons. to delineate techniques used by the staff in eralu- The guideswe Issuedin the fo*owingon broad divisions:
ating specific problems or postulated accidents. or to provide guidance to appi cents. Regulatory Guides are not substitutes for regulations, and compliance
1. Power Reacto.,
S. Products with them Is not required. Methods end solutions different from thas 0ot mut in
2. Research and Test Reactors
7. Transportation the ugudes will be acceptable if they provide a basis for the findings requisite to
$. Fuels and Matedria Facilties
,L Occupational fheath the Isauanc or continuance of a permit or license by the Commission.
 
4. Environmental and Sting
9. Antitrust Review Comments and suggestione for improvements in these guides am encouraged
5. Materials and Plant Protection
10. General at all times, and guides will be revised. es appropriate. to accommodate eam mants and to reflect now information or experlence. However. comments on Coies of published guides may be obtained by written request Indicating the this guide, If received within about two months after its issuance, will be par- divisions desired to the US. Nuclear Regulatory Commission. Washington. D.C.
 
ticularly useful in evaluating the need for an early revision.
 
N05S. Attention: Director. Office of Standards Development.


I I
I I
May 1975


Procedure Qualification                                               In addition to the minimum preheat temperature, a maximum interpass temperature should be specified. If Section III and Section VIII require adherence to           the weld metal should transform at too high a tempera Section IX, "Welding and Brazing Qualifications," of the         ture, the required mechanical properties for the metal ASME Code, including the requirements governing pro               may not be met. The maximum Interpass temperature cedure qualifications for welds. Review of the require           varies for different steels, as does the minimum preheat ments of Section IX for procedure qualifications and the         temperature, and should be selected on the basis of such fabrication requirements of Sections II and VIII                 influencing factors as the chemical composition of the indicates the desirability of supplementary requirements         steel.
Procedure Qualification Section III and Section VIII require adherence to Section IX, "Welding and Brazing Qualifications," of the ASME Code, including the requirements governing pro cedure qualifications for welds. Review of the require ments of Section IX for procedure qualifications and the fabrication requirements of Sections II  
and VIII  
indicates the desirability of supplementary requirements to ensure adequate control of welding variables in the production welding of low-alloy steels.


to ensure adequate control of welding variables in the production welding of low-alloy steels.                          Production Welds The assurance of satisfactory welds in low-alloy steels can be increased significantly and, in particular, the pro           The procedure qualification by itself does not ensure pensity for cracks (cold cracks) or reheat cracks forming         that the production welds will be made within the in underbead areas and heat-affected zones (HAZ) can               specified preheat temperature range. To ensure that the be minimized by maintaining proper preheat tempera                 welds will be acceptable, the metal temperature should tures on the base metals concurrent with controls on               be monitored during the welding process and through other welding variables.                                          postweld heat treatment.
The assurance of satisfactory welds in low-alloy steels can be increased significantly and, in particular, the pro pensity for cracks (cold cracks) or reheat cracks forming in underbead areas and heat-affected zones (HAZ) can be minimized by maintaining proper preheat tempera tures on the base metals concurrent with controls on other welding variables.


Cold cracking can occur when the steel is hardened;
Cold cracking can occur when the steel is hardened;  
i.e., undergoes a phase transformation to martensite in                        
i.e., undergoes a phase transformation to martensite in the HAZ and/or weld metal. The martensite exhibits brittle fracture tendencies, and it may not be able to withstand rapid cooling and the volume change associ ated with the phase transformation without the occur rence of local cracking. This susceptibility to cracking increases with higher stresses, such as those experienced with increased thickness or welding under constraint of the parts being welded, .and also increases with a de crease in welding energy input. In order to avoid or mini mize the effects of hardening associated with phase transformation, a longer cooling time is needed for the weld; in other words, the preheat temperature should be maintained high enough to achieve an acceptable con dition of the phase transformation.
 
It is generally recognized that atomic hydrogen absorption and diffusion into and through the region being welded have an important influence an the tendency to form cracks. While the level of hydrogen in weld filler metal is low enough to preclude adverse effects in the welds, greater quantities of hydrogen can be present in the weld region from the dissociation of moisture in hygroscopic welding fluxes or adsorbed on metal surfaces if the welding fluxes and surfaces have not been properly dried before weld deposition. Em brittlement of metal in the weld area due to the presence of hydrogen generally occurs at lower temperatures and may be prevented by prolonging the time the weldment is maintained at preheating temperature or by per forming a postweld heat treatment. Prolonged time at preheating can prevent or interrupt local hardening and assist in reducing adverse effects of a potential hydrogen gradient. This gradient would disappear by means of diffusion of the hydrogen before the weldment Is returned to room temperature. Therefore, the minimum preheat temperature should be established to ensure a desirable cooling rate for the weld, and this temperature should be maintained until a postweld heat treatment has been achieved.
 
In addition to the minimum preheat temperature, a maximum interpass temperature should be specified. If the weld metal should transform at too high a tempera ture, the required mechanical properties for the metal may not be met. The maximum Interpass temperature varies for different steels, as does the minimum preheat temperature, and should be selected on the basis of such influencing factors as the chemical composition of the steel.
 
Production Welds The procedure qualification by itself does not ensure that the production welds will be made within the specified preheat temperature range. To ensure that the welds will be acceptable, the metal temperature should be monitored during the welding process and through postweld heat treatment.


==C. REGULATORY POSITION==
==C. REGULATORY POSITION==
the HAZ and/or weld metal. The martensite exhibits brittle fracture tendencies, and it may not be able to              Weld fabrlcation* for low-alloy steel components withstand rapid cooling and the volume change associ            important to safety should comply with acceptable fab ated with the phase transformation without the occur            rication requirements and should be performed by quali rence of local cracking. This susceptibility to cracking        fled welders and welding procedures in accordance with increases with higher stresses, such as those experienced        the requirements of Section IX of the ASME Code with increased thickness or welding under constraint of          supplemented by the following:
Weld fabrlcation* for low-alloy steel components important to safety should comply with acceptable fab rication requirements and should be performed by quali fled welders and welding procedures in accordance with the requirements of Section IX of the ASME Code supplemented by the following:  
the parts being welded, .and also increases with a de crease in welding energy input. In order to avoid or mini            1. The procedure qualification should require that:
1. The procedure qualification should require that:  
mize the effects of hardening associated with phase transformation, a longer cooling time is needed for the                  a. A minimum preheat and a maximum interpass weld; in other words, the preheat temperature should be            temperature be specified.
a. A minimum preheat and a maximum interpass temperature be specified.
 
maintained high enough to achieve an acceptable con dition of the phase transformation.                                      b. The welding procedure be qualified at the minimum preheat temperature.


It is generally recognized that atomic hydrogen absorption and diffusion into and through the region                2. For production welds, the preheat temperature being welded have an important influence an the                  should be maintained until a postweld heat treatment tendency to form cracks. While the level of hydrogen in          has been performed.
b. The welding procedure be qualified at the minimum preheat temperature.


weld filler metal is low enough to preclude adverse effects in the welds, greater quantities of hydrogen can              3. Production welding should be monitored to verify be present in the weld region from the dissociation of            that the limits on preheat and Interpass temperatures are moisture in hygroscopic welding fluxes or adsorbed on            maintained.
2. For production welds, the preheat temperature should be maintained until a postweld heat treatment has been performed.


metal surfaces if the welding fluxes and surfaces have not been properly dried before weld deposition. Em                    4. In the event that regulatory positions C.1, C.2, brittlement of metal in the weld area due to the presence        and C.3 above are not met, the weld is subject to of hydrogen generally occurs at lower temperatures and            rejection. However, the soundness of the weld may be may be prevented by prolonging the time the weldment              verified by an acceptable examination procedure.
3. Production welding should be monitored to verify that the limits on preheat and Interpass temperatures are maintained.


is maintained at preheating temperature or by per forming a postweld heat treatment. Prolonged time at preheating can prevent or interrupt local hardening and                             
4. In the event that regulatory positions C.1, C.2, and C.3 above are not met, the weld is subject to rejection. However, the soundness of the weld may be verified by an acceptable examination procedure.


==D. IMPLEMENTATION==
==D. IMPLEMENTATION==
assist in reducing adverse effects of a potential hydrogen gradient. This gradient would disappear by means of                  The purpose of this section is to provide information diffusion of the hydrogen before the weldment Is                  to applicants and licensees regarding the NRC staff's returned to room temperature. Therefore, the minimum              plans for utilizing this regulatory guide.
The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for utilizing this regulatory guide.


preheat temperature should be established to ensure a desirable cooling rate for the weld, and this temperature should be maintained until a postweld heat treatment
*Applies also to welding and weld repairs after Initial fabrica tion when a postweld stress-relieving heat treatment Is used.
                                                                      *Applies also to welding and weld repairs after Initial fabrica has been achieved.                                              tion when a postweld stress-relieving heat treatment Is used.


3..9-2
3..9-2


Except in those cases in which the applicant proposes         For 'those applications docketed on or before Novem an acceptable alternative method for complying with           ber 3, 1975, the NRC staff may reevaluate the appli
Except in those cases in which the applicant proposes an acceptable alternative method for complying with  
2J specified portions of the Commission's regulations, the       cation on a case-by-case basis to ensure that acceptable method described herein will be used in the evaluation         weld qualification and production welding procedures of submittals in connection with applications for permits     are being used.
2J  
specified portions of the Commission's regulations, the method described herein will be used in the evaluation of submittals in connection with applications for permits and licenses docketed after November 3, 1975.


and licenses docketed after November 3, 1975.
For 'those applications docketed on or before Novem ber 3, 1975, the NRC staff may reevaluate the appli cation on a case-by-case basis to ensure that acceptable weld qualification and production welding procedures are being used.


3.29-3
3.29-3


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Latest revision as of 03:10, 17 January 2025

Preheat & Interpass Temperature Control for Welding of Low-Alloy Steel for Use in Fuel Reprocessing Plants & in Plutonium Processing & Fuel Fabrication Plants
ML003739381
Person / Time
Issue date: 05/31/1975
From:
Office of Nuclear Regulatory Research
To:
References
RG-3.29
Download: ML003739381 (4)


'U.S. NUCLEAR REGULATORY COMMISSION

REGULATORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 3.29 PREHEAT AND INTERPASS TEMPERATURE CONTROL FOR THE

WELDING OF LOW-ALLOY STEEL FOR USE IN FUEL REPROCESSING PLANTS

AND IN PLUTONIUM PROCESSING AND FUEL FABRICATION PLANTS

A. INTRODUCTION

Section 50.34, "Contents of Applications; Technical Information," of 10 CFR Part 50, "Ucensing of Produc tion and Utilization Facilities," requires, among other things, that each application for a construction permit or operating license for a fuel reprocessing plant include a discussion of how the applicable requirements of Appen dix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50

will be satisfied. As used in Appendix B, "quality assurance" comprises all those planned and systematic actions necessary to provide adequate confidence that safety-related structures, systems, and components will perform Satisfactorily in service. Appendix B requires, in part, that measures be established to ensure that special processes, including welding, are controlled and accomp lished by qualified personnel using qualified procedures, and that proper process monitoring be performed. Para graph 70.22(f) of 10 CFR Part 70, "Special Nuclear Material," requires that each application for a license to possess and use special nuclear material in a plutonium processing and fuel fabrication plant contain a des cription of the quality assurance program to be applied to the design, fabrication, construction, testing, and operation of the structures, systems, and components of the plant and that the description include a discussion of how the criteria of Appendix B to Part 50 will be met.

Paragraph 70.23(b) of 10 CFR Part 70 provides that the Commission will approve construction of a plutonium processing and fuel fabrication plant when it has deter mined that the design bases and the quality assurance program provide reasonable assurance of protection against natural phenomena and the consequences of potential accidents, noting that the criteria in Appendix B to-0 CFR Part 50 will be used by the CommissionIn determining the adequacy of the quality assurance pro gram- This guide describes a method acceptable to the NRC

staff for meeting these requirements with regard to the control of welding of low-alloy steel components for fuel reprocessing plants and for plutonium processing and fuel fabrication plants.

B. DISCUSSION

The American Society of Mechanical Engineers Boiler and Pressure Vessel Code* (ASME Code),Section III,

"Nuclear Power Plant Components," and Section VIII,

"Pressure Vessels," specify requirements for fabricating components as indicated In the section titles. Many of the requirements of this Code can also be applied to safety-related structures, systems, and components of fuel reprocessing plants and plutonium processing and fuel fabrication plants. Specific portions of the ASME

Code and of other applicable codes and standards have been used for fabricating components for such plants.

Acceptable practices can differ significantly because there has not been sufficient guidance toward standard ization. In the interest of standardization, this guide specifies procedures acceptable to the NRC staff for the control of preheat and interpass temperatures for'

welding of low alloy steels for use In the plants discussed albove. These procedures, which draw on those used for nuclear power plants, will provide a uniform quality level consistent with the function of safety-related structures, systems, and componentsiof fuel reprocessing plants and of plutonium processing and fuel fabrication plants.

  • American Society of Mechanical Engineers 'Boiler and Pressure Vessel Code, 1974 Edition. AI references to the ASME

Code wre to the 1974 edition. Copies may be obtained from the American Society of Mechanical -Engineers, United Engineering Center, 345 East 47th Street, New York, N.Y. 10017.

USNRC REGULATORY GUIDES

Comments should be sent to the Secretary of the Commission. U.S Nuclear Regulatory Guides are issued to describe and make available to the public Regulatory Gommisson. Washington. D.C.

rvKe.

ttention: Docketing end methods acceptable to the NRC.staff of Implementing specific parts of the Commoilon's regulatlons. to delineate techniques used by the staff in eralu- The guideswe Issuedin the fo*owingon broad divisions:

ating specific problems or postulated accidents. or to provide guidance to appi cents. Regulatory Guides are not substitutes for regulations, and compliance

1. Power Reacto.,

S. Products with them Is not required. Methods end solutions different from thas 0ot mut in

2. Research and Test Reactors

7. Transportation the ugudes will be acceptable if they provide a basis for the findings requisite to

$. Fuels and Matedria Facilties

,L Occupational fheath the Isauanc or continuance of a permit or license by the Commission.

4. Environmental and Sting

9. Antitrust Review Comments and suggestione for improvements in these guides am encouraged

5. Materials and Plant Protection

10. General at all times, and guides will be revised. es appropriate. to accommodate eam mants and to reflect now information or experlence. However. comments on Coies of published guides may be obtained by written request Indicating the this guide, If received within about two months after its issuance, will be par- divisions desired to the US. Nuclear Regulatory Commission. Washington. D.C.

ticularly useful in evaluating the need for an early revision.

N05S. Attention: Director. Office of Standards Development.

I I

May 1975

Procedure Qualification Section III and Section VIII require adherence to Section IX, "Welding and Brazing Qualifications," of the ASME Code, including the requirements governing pro cedure qualifications for welds. Review of the require ments of Section IX for procedure qualifications and the fabrication requirements of Sections II

and VIII

indicates the desirability of supplementary requirements to ensure adequate control of welding variables in the production welding of low-alloy steels.

The assurance of satisfactory welds in low-alloy steels can be increased significantly and, in particular, the pro pensity for cracks (cold cracks) or reheat cracks forming in underbead areas and heat-affected zones (HAZ) can be minimized by maintaining proper preheat tempera tures on the base metals concurrent with controls on other welding variables.

Cold cracking can occur when the steel is hardened;

i.e., undergoes a phase transformation to martensite in the HAZ and/or weld metal. The martensite exhibits brittle fracture tendencies, and it may not be able to withstand rapid cooling and the volume change associ ated with the phase transformation without the occur rence of local cracking. This susceptibility to cracking increases with higher stresses, such as those experienced with increased thickness or welding under constraint of the parts being welded, .and also increases with a de crease in welding energy input. In order to avoid or mini mize the effects of hardening associated with phase transformation, a longer cooling time is needed for the weld; in other words, the preheat temperature should be maintained high enough to achieve an acceptable con dition of the phase transformation.

It is generally recognized that atomic hydrogen absorption and diffusion into and through the region being welded have an important influence an the tendency to form cracks. While the level of hydrogen in weld filler metal is low enough to preclude adverse effects in the welds, greater quantities of hydrogen can be present in the weld region from the dissociation of moisture in hygroscopic welding fluxes or adsorbed on metal surfaces if the welding fluxes and surfaces have not been properly dried before weld deposition. Em brittlement of metal in the weld area due to the presence of hydrogen generally occurs at lower temperatures and may be prevented by prolonging the time the weldment is maintained at preheating temperature or by per forming a postweld heat treatment. Prolonged time at preheating can prevent or interrupt local hardening and assist in reducing adverse effects of a potential hydrogen gradient. This gradient would disappear by means of diffusion of the hydrogen before the weldment Is returned to room temperature. Therefore, the minimum preheat temperature should be established to ensure a desirable cooling rate for the weld, and this temperature should be maintained until a postweld heat treatment has been achieved.

In addition to the minimum preheat temperature, a maximum interpass temperature should be specified. If the weld metal should transform at too high a tempera ture, the required mechanical properties for the metal may not be met. The maximum Interpass temperature varies for different steels, as does the minimum preheat temperature, and should be selected on the basis of such influencing factors as the chemical composition of the steel.

Production Welds The procedure qualification by itself does not ensure that the production welds will be made within the specified preheat temperature range. To ensure that the welds will be acceptable, the metal temperature should be monitored during the welding process and through postweld heat treatment.

C. REGULATORY POSITION

Weld fabrlcation* for low-alloy steel components important to safety should comply with acceptable fab rication requirements and should be performed by quali fled welders and welding procedures in accordance with the requirements of Section IX of the ASME Code supplemented by the following:

1. The procedure qualification should require that:

a. A minimum preheat and a maximum interpass temperature be specified.

b. The welding procedure be qualified at the minimum preheat temperature.

2. For production welds, the preheat temperature should be maintained until a postweld heat treatment has been performed.

3. Production welding should be monitored to verify that the limits on preheat and Interpass temperatures are maintained.

4. In the event that regulatory positions C.1, C.2, and C.3 above are not met, the weld is subject to rejection. However, the soundness of the weld may be verified by an acceptable examination procedure.

D. IMPLEMENTATION

The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for utilizing this regulatory guide.

  • Applies also to welding and weld repairs after Initial fabrica tion when a postweld stress-relieving heat treatment Is used.

3..9-2

Except in those cases in which the applicant proposes an acceptable alternative method for complying with

2J

specified portions of the Commission's regulations, the method described herein will be used in the evaluation of submittals in connection with applications for permits and licenses docketed after November 3, 1975.

For 'those applications docketed on or before Novem ber 3, 1975, the NRC staff may reevaluate the appli cation on a case-by-case basis to ensure that acceptable weld qualification and production welding procedures are being used.

3.29-3

UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D. C.

20555 OFFICIAL BUSINESS

PENALTY FOR PR IVATE USE, $300

POSTAGE AND FEES PAID

UNITED STATES NUCLrAN

REGULATORY COMMISSION

K