Regulatory Guide 3.28
| ML003739371 | |
| Person / Time | |
|---|---|
| Issue date: | 05/31/1976 |
| From: | Office of Nuclear Regulatory Research |
| To: | |
| References | |
| RG-3.28 | |
| Download: ML003739371 (3) | |
U.S. NUCLEAR REGULATORY COMMISSION
REGULATORY GUIDE
OFFICE OF STANDARDS DEVELOPMENT
REGULATORY GUIDE 3.28 WELDER QUALIFICATION FOR WELDING IN AREAS
OF LIMITED ACCESSIBILITY 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, "Licensing of Production 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 Appendix 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 con fidence that safety-related structures, systems, and com ponents will perform satisfactorily in service. Appendix B requires, in part, that measures be established to ensure that special processes, including welding, are controlled and accomplished by qualified personnel using qualified procedures. Paragraph 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 description of the quality assurance program to be applied to the design, fabrica tion, construction, testing, and operation of the struc tures, 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 determined that the design bases and the quality assurance program provide rea sonable assurance of protection against natural phenomena and the consequences of potential accidents, noting that the criteria in Appendix B to 10 CFR Part
50 will be used by the Commission in determining the adequacy of the quality assurance program.
This guide describes a method acceptable to the NRC
staff for meeting these requirements with regard to the control of welding of nuclear 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 Coded (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 standardization.
In the interest of standardization, this guide specifies procedures acceptable to the NRC
staff for the qualification of welders for welding In areas of limited accessibility in the plants discussed above. 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 components of fuel reprocessing plants and of plutonium processing and fuel fabrication plants.
- American Society of Mechanical Engineers Boiler and Pressure Vessel Code, 1974 Edition. Ali references to the ASME
Code are 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 secretery of the Commission. U.S. Nuclear Regulatory Commission. Wsshington. D.C. 2055.
Attention: Docketing end Regulatory Guides are issued to describe end make available to the public Service Sction.
methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations. to delineate techniques used by the staff in evalu- The guides are Issued in the following ten breed divisions:
eting specific problems or postulated accidents. or to provide guidance to appli.
cants. Regulatory Guides are not substitutes for regulation
s. and compliance
1. Power Reactors
5. Products with them is not required. Methods and solutions different from those set out
2. Research end Test Reactors
7 Transportation the guides will be acceptable If they provide a basis for the findings requisite to
3. Ftuefs nd Materalsfacilites SL Occupationai Health the issuance or continuance of a permit or license by the Commission.
4. Environmental and Siting S. Antitrust Review Comments and suggestions for Improvements in these guides we encouraged S. Materials and Plant Protection
10. General at all times, end guides will be revised, as appropriate, to accommodate come ments and to reflect new information or experience. However. comments on Copies of. published guides may be obtained by written request Indicating the this guide. if received within about two months after its issuance. will be per- divisions desired to the US. Nuclear Regulatory Commission. Washington. D.C.
ficularly useful in evaluating the need for en early revision.
20MB. Attention: Director. Office of Standards Development.
May 1976
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Performance Qualification Section III and Section VIII require adherence to ASME Boiler and Pressure Vessel Code,Section IX,
"Welding and Brazing Qualifications."
One of the requirements is welder qualification for production welds. Review of the requirements of Section IX for performance qualifications indicates the desirability of supplementary requirements to provide better control of welder technique in the production welding of low-alloy and high-alloy steels. Specifically, the assurance of satisfactory welds in locations of restricted direct physical and visual accessibility can be increased sig nificantly by qualifying the welder under conditions simulating the space limitations under which the actual welds must be made.
Experience has shown that a welder qualified to weld components under normal fabricating conditions may not produce acceptable welds if the accessibility to the weld area is restricted. Limited accessibility can occur when component parts are joined or repaired in the final assembly or at the plant site where other adjacent components or structures prevent the welder from assuming an advantageous position during the welding operation. This disadvantage is particularly important in the welding of high-alloy steels and nickel base alloys because welder technique such as electrode manipulation is an important variable in the welding procedure.
Section IX, paragraph QW-350, specifies conditions for which a welder must requalify, but it lacks specific reference to conditions with limited accessibility and visibility. It is general practice in nuclear shipbuilding to include requirements for welder accessibility to pro duction welds. This practice requires that conditions of restricted welder accessibility to a production weld be simulated when the clearance is less than 30 cm (12 inches) in any direction from the joint. However, requalification would not be required for different restricted accessibility conditions unless other essential elements listed in Section IX are changed.
Section IX,
paragraph QW-120,
specifies test positions for groove welds. Positions 2G and 5G with a corner structural enclosure that limits access to within
30 to 35 cm (12 to 14 inches) on two sides and overhead would provide acceptable simulation of welder acces sibility. Evaluation of tests should be in accordance with Section IX with at least one test specimen representing the least favorable position imposed on the welder.
As an alternative, the structure to be welded, in.
cluding its actual access limits, may be simulated. From this mockup, one test specimen should be taken from the weld location representing the least favorable posi tion imposed on the welder. The test specimen should be evaluated in accordance with the radiographic require ments of Section IX, paragraphs QW-302.2 and QW-318.
In addition, the test section should be sectioned for macro examination and hardness evaluation of the composite weldment with particular attention to the root fusion and weld toe conditions.
Production Welds The welding qualification (procedure and perform ance) by itself does not ensure that the production welds will be made within the specified requirements. To ensure that the welds will be acceptable, the welding process should be audited for correct application of procedure parameters and welder technique.
C. REGULATORY POSITION
Weld fabrication and repair for safety-related struc tures, systems, and components of wrought low-alloy and high-alloy steels, including nickel base alloys and stainless steels, or other materials such as static and centrifugal castings and bimetallic joints should be performed by qualified welders and procedures in accordance with the requirements of Section IX of the ASME Code supplemented by the following:
I. The performance qualifitation should require test ing of the welder under sisjulated access conditions when physical conditions restrict the welder's access to a production weld to less than 30 to 35 cm (12 to 14 inches) in any direction from the joint.
2. Requalification is required:
a. When significantly different restricted acces sibility conditions occur, or b. When any of the essential welding variables listed in Section IX are changed.
3. Production welding should be monitored and adherence to welding qualifipation requirements should be certified.
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.
Except in those cases in which the applicant proposes an acceptable alternative method for complying with 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 October 20, 1975.
If an applicant wishes to use this regulatory guide in developing submittals for applications docketed on or before October 20, 1975, the pertinent portions of the application will be evaluated on the basis of this guide.
3.28-2
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