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{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION                                                                   June 1991 R E GUlaTORY
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION  
                                                                                                                    GUIDE
R E GUlaTORY
                                  OFFICE OF NUCLEAR REGULATORY RESEARCH
June 1991 GUIDE
                                                        REGULATORY GUIDE 7.11 FRACTURE TOUGHNESS CRITERIA OF BASE MATERIAL
OFFICE OF NUCLEAR REGULATORY RESEARCH  
                                  FOR FERRITIC STEEL SHIPPING CASK CONTAINMENT
REGULATORY GUIDE 7.11 FRACTURE TOUGHNESS CRITERIA OF BASE MATERIAL  
                      VESSELS WITH A MAXIMUM WALL THICKNESS OF 4 INCHES (0.1 m)
FOR FERRITIC STEEL SHIPPING CASK CONTAINMENT  
                                    (Previously issued as Drafts MS 144-4 and DG-7001)
VESSELS WITH A MAXIMUM WALL THICKNESS OF 4 INCHES (0.1 m)  
(Previously issued as Drafts MS 144-4 and DG-7001)
A.
 
INTRODUCTION
Part 71, "Packaging and Transportation of Ra dioactive Material," of Title 10 of the Code of Fed eral Regulations requires that packages used to trans port radioactive materials withstand the conditions in
§ 71.71, "Normal Conditions of Transport," and
§ 71.73, "Hypothetical Accident Conditions."
In this guide, the terms packaging, shipping cask, and shipping container are used interchangeably.
 
The regulations require that accident conditions with an initial temperature as low as -20'F (-29°C)
be considered. At this temperature, several types of ferritic steels are brittle and subject to fracture. This guide describes fracture toughness criteria and test methods acceptable to the NRC staff for use in evalu ating Type B (U) and Type B (M)l ferritic steel ship ping cask containment vessel base material having a maximum thickness of 4 inches (0.1 m) and having a maximum static yield strength of 100 ksi (690 kPa). 
The containment vessel is a major component of the containment system as defined in § 71.4 of 10 CFR
Part 71. This guide is applicable to the containment vessel only and not to other components of the pack age.
 
Alternative fracture toughness criteria and test methods may be used provided the applicant can
,'Type B(U) and Type B(M) packages are defined in 10 CFR 71.4.
 
USNRC REGULATORY GUIDES
Regulatory Guides are issued to describe and make available to the pub lie methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the staff in evaluating specific problems or postulated accidents, or to pro vide guidance to applicants. Regulatory Guides are not substitutes for regulations, and compliance with them Is not required. Methods and solutions different from those set out in the guides wilf be acceptable if.
 
they provide a basis for the findings requisite to the issuance or continu ance of a permit or license by the Commission.
 
This guide was Issued after consideration of comments received from the public, Comments and suggestions for improvements In these guides are encouraged at all times, and guides will be revised, as ap propriate, to accommodate comments and to reflect new Information or experience.
 
Written comments may be submitted to the Regulatory Publications Branch, DFIPS, ADM, U.S. Nuclear Regulatory Commission, Washing ton, DC 20555.


==A. INTRODUCTION==
demonstrate that their use will ensure equivalent safety.
demonstrate that their use will ensure equivalent safety.


Part 71, "Packaging and Transportation of Ra dioactive Material," of Title 10 of the Code of Fed                                  Any information collection activities mentioned eral Regulations requires that packages used to trans                          in this regulatory guide are contained as requirements port radioactive materials withstand the conditions in                        in 10 CFR Part 71, which provides the regulatory ba
Any information collection activities mentioned in this regulatory guide are contained as requirements in 10 CFR Part 71, which provides the regulatory ba sis for this guide. The information collection require ments in 10 CFR Part 71 have been cleared under OMB Clearance No. 3150-0008.
§ 71.71, "Normal Conditions of Transport," and                                sis for this guide. The information collection require
 
§ 71.73, "Hypothetical Accident Conditions."                              In  ments in 10 CFR Part 71 have been cleared under this guide, the terms packaging, shipping cask, and                           OMB Clearance No. 3150-0008.
B.
 
DISCUSSION
This guide presents fracture toughness criteria and test methods that can be used for evaluating ferritic steel containment vessel base material having a maximum wall thickness of 4 inches (0.1 m) with a maximum static yield strength of 100 ksi (690 kPa). 
Section III of the ASME Boiler and Pressure Vessel Code (Ref. 1) contains requirements for mate rial fracture toughness; however, these requirements were developed for reactor components only and do not address hypothetical accident conditions appro priate for packaging (e.g., severe impact loads at low temperatures). Therefore, the code requirements are not directly applicable to shipping container design.
 
NUREG/CR-1815, "Recommendations for Pro tecting Against Failure by Brittle Fracture in Ferritic Steel Shipping Containers up to Four Inches Thick"
(Ref. 2), contains background and other information The guides are issued in the following ten broad divisions:
 
===1. Power Reactors ===
2. Research and Test Reactors
3. Fuels and Materials Facilities
4. Environmental and Siting
5. Materials and Plant Protection
 
===6. Products ===


shipping container are used interchangeably.
===7. Transportation ===


==B. DISCUSSION==
===8. Occupational Health ===
The regulations require that accident conditions with an initial temperature as low as -20'F (-29°C)                                  This guide presents fracture toughness criteria be considered. At this temperature, several types of                          and test methods that can be used for evaluating ferritic steels are brittle and subject to fracture. This                      ferritic steel containment vessel base material having guide describes fracture toughness criteria and test                          a maximum wall thickness of 4 inches (0.1 m) with a methods acceptable to the NRC staff for use in evalu                          maximum static yield strength of 100 ksi (690 kPa).
9. Antitrust and Financial Review
ating Type B (U) and Type B (M)l ferritic steel ship ping cask containment vessel base material having a                                  Section III of the ASME Boiler and Pressure maximum thickness of 4 inches (0.1 m) and having a                            Vessel Code (Ref. 1) contains requirements for mate maximum static yield strength of 100 ksi (690 kPa).                            rial fracture toughness; however, these requirements The containment vessel is a major component of the                             were developed for reactor components only and do containment system as defined in § 71.4 of 10 CFR                              not address hypothetical accident conditions appro Part 71. This guide is applicable to the containment                          priate for packaging (e.g., severe impact loads at low vessel only and not to other components of the pack                          temperatures). Therefore, the code requirements are age.                                                                         not directly applicable to shipping container design.
10. General Copies of issued guides may be purchased from the Government Printing Office at the current GPO price. Information on current GPO prices may be obtained by contacting the Superintendent of Documents, U.S.


Alternative fracture toughness criteria and test NUREG/CR-1815, "Recommendations for Pro methods may be used provided the applicant can                                tecting Against Failure by Brittle Fracture in Ferritic Steel Shipping Containers up to Four Inches Thick"
Government Printing Office, Post Office Box 37082, Washington, DC
,'Type B(U) and Type B(M) packages are defined in 10 CFR 71.4.                (Ref. 2), contains background and other information USNRC REGULATORY GUIDES                                The guides are issued in the following ten broad divisions:
20013-7082, telephone (202)275-2060 or (202)275-2171, Issued guides may also be purchased from the National Technical Infor mation Service on a standing order basis. Details on this service may be obtained by writing NTIS, 5285 Port Royal Road, Springfield, VA 22,161.
Regulatory Guides are issued to describe and make available to the pub lie methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the          1. Power Reactors                    6.  Products staff in evaluating specific problems or postulated accidents, or to pro    2.  Research and Test Reactors        7.  Transportation vide guidance to applicants. Regulatory Guides are not substitutes for      3.  Fuels and Materials Facilities    8.  Occupational Health regulations, and compliance with them Is not required. Methods and          4.  Environmental and Siting          9.  Antitrust and Financial Review solutions different from those set out in the guides wilf be acceptable if.  5.  Materials and Plant Protection  10.  General they provide a basis for the findings requisite to the issuance or continu ance of a permit or license by the Commission.


Copies of issued guides may be purchased from the Government Printing This guide was Issued after consideration of comments received from          Office at the current GPO price. Information on current GPO prices may the public, Comments and suggestions for improvements In these              be obtained by contacting the Superintendent of Documents, U.S.
pertinent to the development of the criteria in this guide. These criteria are divided into three categories that are associated with the levels of safety appropri ate for the radioactive contents being transported.


guides are encouraged at all times, and guides will be revised, as ap        Government Printing Office, Post Office Box 37082, Washington, DC
Table 1 in this guide identifies the radioactivity limits for each of the three categories. Tables 4, 5, and 6 in NUREG/CR-18152 (reproduced along with Table 3 in the Appendix to this guide) list the fracture tough ness criteria associated with each category. A qualita tive description of the margins of safety against brittle failure for each of the three categories is given in Ap pendix C to NUREG/CR-1815 (Ref. 2)
propriate, to accommodate comments and to reflect new Information or        20013-7082, telephone (202)275-2060 or (202)275-2171, experience.
Additional information regarding the basis for the criteria is contained in Appendix B of NUREG/
CR-1815 (Ref. 2)
Regulatory Position 1 endorses a portion of the criteria contained in Section 5 of NUREG/CR-1815.


Written comments may be submitted to the Regulatory Publications Branch, DFIPS, ADM, U.S. Nuclear Regulatory Commission, Washing Issued guides may also be purchased from the National Technical Infor mation Service on a standing order basis. Details on this service may be ton, DC 20555.                                                              obtained by writing NTIS, 5285 Port Royal Road, Springfield, VA 22,161.
These criteria identify material properties in accor dance with the standards specified in Tables 4, 5, and
6 of NUREG/CR-1815, as appropriate.


pertinent to the development of the criteria in this                          use of austenitic stainless steels. Since austenitic stain guide. These criteria are divided into three categories                        less steels are not susceptible to brittle failure at tem that are associated with the levels of safety appropri                        peratures encountered in transport, their use in con ate for the radioactive contents being transported.                            tainment vessels is acceptable to the staff and no tests Table 1 in this guide identifies the radioactivity limits                      are needed to demonstrate resistance to brittle fail for each of the three categories. Tables 4, 5, and 6 in                        ure.
For Category II and III containers, the highest nil ductility transition temperature (TNDT)
specified for the material in Table 3 of NUREG/CR-1815 (repro duced in the Appendix to this guide) may be used in lieu of conducting tests to determine the actual TNDT of the material.


NUREG/CR-18152 (reproduced along with Table 3 in the Appendix to this guide) list the fracture tough ness criteria associated with each category. A qualita NUREG/CR-3019, "Recommended Welding Cri tive description of the margins of safety against brittle                      teria for Use in the Fabrication of Shipping Contain failure for each of the three categories is given in Ap ers for Radioactive Materials" (Ref. 3), and NUREG/
Table 1 Category I
pendix C to NUREG/CR-1815 (Ref. 2).
Category II
                                                                              CR-3854, "Fabrication Criteria for Shipping Contain Additional information regarding the basis for the                       ers" (Ref. 4), also contain information applicable to criteria is contained in Appendix B of NUREG/                                  shipping containers, as does a related Regulatory CR-1815 (Ref. 2).                                                             Guide 7.12, "Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Contain Regulatory Position 1 endorses a portion of the                          ment Vessels with a Wall Thickness Greater than 4 criteria contained in Section 5 of NUREG/CR-1815.                             Inches (0.1 m) But Not Exceeding 12 Inches (0.3 These criteria identify material properties in accor                          m)" (Ref. 5).
Category III
dance with the standards specified in Tables 4, 5, and
Low Greater than Less than Specific
6 of NUREG/CR-1815, as appropriat
30,000 Ci or
30,000 Ci Activity greater than and less than
3,000 A,* or
3,000 A,
greater than and less than
3,000 A,-  
3,000 A,  
Special Greater than Between Less than Form
3,000 A,
3,000 A, and
30 A, and or greater than 30 A, and not less than
30,000 Ci greater than
30,000 Ci
30,000 Ci Normal Greater than Between Less than Form
3,000 A2 
3,000 A2 and
30 A2 or greater than 30 A2 and not and less than
30,000 Ci greater than
30,000 Ci
30,000 Ci
*Defined in 10 CFR 71.4 Although NUREG/CR-1815 (Ref. 2) addresses the use of ferritic steels only, it does not preclude the Mrhe following corrections should be made to the NUREG: Table 1, Category III revise to read "...Fine Grain Practice..."; Table 4, Crite ria .... third line "has ays a 70 ksi, either."; Figure 6, vertical scale should be "...0, 20, 40..."; Section 5.3.1, subsection 1, "By se lecting a normalized steel ...."
use of austenitic stainless steels. Since austenitic stain less steels are not susceptible to brittle failure at tem peratures encountered in transport, their use in con tainment vessels is acceptable to the staff and no tests are needed to demonstrate resistance to brittle fail ure.


====e.     ====
NUREG/CR-3019, "Recommended Welding Cri teria for Use in the Fabrication of Shipping Contain ers for Radioactive Materials" (Ref. 3), and NUREG/
CR-3854, "Fabrication Criteria for Shipping Contain ers" (Ref. 4), also contain information applicable to shipping containers, as does a related Regulatory Guide 7.12, "Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Contain ment Vessels with a Wall Thickness Greater than 4 Inches (0.1 m) But Not Exceeding 12 Inches (0.3 m)" (Ref. 5). 


==C. REGULATORY POSITION==
==C. REGULATORY POSITION==
For Category II and III containers, the highest nil ductility transition temperature (TNDT) specified for the material in Table 3 of NUREG/CR-1815 (repro                                    1. The criteria contained in Section 5 of duced in the Appendix to this guide) may be used in                            NUREG/CR-1815 (Ref. 2), other than for full-scale lieu of conducting tests to determine the actual                              destructive testing (5.1.4 and 5.2.4) and qualifying TNDT of the material.                                                        procedures for reduced stress levels (5.1.2), are ac ceptable to the NRC staff for assessing the fracture toughness of thin-wall base material (up to and in Table 1                                      cluding 4 inches (0.1 m)) ferritic steel containment vessels for the categories identified in Table 1 of this Category I        Category II          Category III        guide. In 5.1.2, only a value of a/Uyd equal to I is acceptable.
1. The criteria contained in Section  
 
5 of NUREG/CR-1815 (Ref. 2), other than for full-scale destructive testing (5.1.4 and 5.2.4) and qualifying procedures for reduced stress levels (5.1.2), are ac ceptable to the NRC staff for assessing the fracture toughness of thin-wall base material (up to and in cluding 4 inches (0.1 m)) ferritic steel containment vessels for the categories identified in Table 1 of this guide. In 5.1.2, only a value of a/Uyd equal to I is acceptable.
Low                                  Greater than        Less than Specific                              30,000 Ci or        30,000 Ci Activity                              greater than        and less than            2. A Category I container qualified in accor
                                      3,000 A,* or        3,000 A,            dance with this guide is acceptable for transporting greater than        and less than      either Category II or Category III radioactive materi
                                      3,000 A,-            3,000 A,            als. Similarly, a Category II container qualified in ac Special            Greater than      Between              Less than          cordance with this guide is acceptable for transporting Form              3,000 A,          3,000 A, and        30 A, and          Category III materials.


or greater than    30 A, and not        less than
2. A Category I container qualified in accor dance with this guide is acceptable for transporting either Category II or Category III radioactive materi als. Similarly, a Category II container qualified in ac cordance with this guide is acceptable for transporting Category III materials.
                  30,000 Ci          greater than        30,000 Ci                         


==D. IMPLEMENTATION==
==D. IMPLEMENTATION==
30,000 Ci Normal            Greater than      Between              Less than                The purpose of this section is to provide informa Form              3,000 A2          3,000 A2 and        30 A2              tion to applicants and licensees regarding the NRC
The purpose of this section is to provide informa tion to applicants and licensees regarding the NRC  
                  or greater than 30 A 2 and not          and less than staff's plans for using this regulatory guide.
staff's plans for using this regulatory guide.


30,000 Ci          greater than        30,000 Ci
Except in those cases in which an applicant or licensee proposes an acceptable alternative method for complying with specified portions of the Commis sion's regulations, the methods described in this guide (which reflects public comments) will be used by the NRC staff in evaluating base material for all applica tions for new package designs and all requests that existing package designs be designated as Type B(U)  
                                      30,000 Ci
or Type B(M) packages submitted after Septem ber 30, 1991.
*Defined in 10 CFR 71.4                                                            Except in those cases in which an applicant or licensee proposes an acceptable alternative method for complying with specified portions of the Commis Although NUREG/CR-1815 (Ref. 2) addresses                                sion's regulations, the methods described in this guide the use of ferritic steels only, it does not preclude the                      (which reflects public comments) will be used by the NRC staff in evaluating base material for all applica Mrhe following corrections should be made to the NUREG: Table 1,            tions for new package designs and all requests that Category III revise to read "...Fine Grain Practice..."; Table 4,Crite        existing package designs be designated as Type B(U)
ria .... third line "has ays a 70 ksi, either."; Figure 6, vertical scale should be "...0, 20, 40..."; Section 5.3.1, subsection 1, "By se        or Type B(M) packages submitted after Septem lecting a normalized steel ...."                                            ber 30, 1991.


7.11-2
7.11-2


REFERENCES
REFERENCES
    1. ASME Boiler and Pressure Vessel Code, Sec           ers for Radioactive Materials," NUREG/CR-3019,*
1. ASME Boiler and Pressure Vessel Code, Sec tion III, "Rules for Construction of Nuclear Power Plant Components," American Society of Mechanical Engineers, New York, updated frequently.
tion III, "Rules for Construction of Nuclear Power          U.S. Nuclear Regulatory Commission, March 1985.
 
2. W. R. Holman and R. T. Langland (under Lawrence Livermore National Laboratory contract to the NRC), "Recommendations for Protecting Against Failure by Brittle Fracture in Ferritic Steel Shipping Containers Up to Four Inches Thick," U.S. Nuclear Regulatory Commission, NUREG/CR-1815, *August
1981.
 
3. R. E. Monroe, H. H. Woo, and R. G. Sears (under Lawrence Livermore National Laboratory contract to the NRC), "Recommended Welding Cri teria for Use in the Fabrication of Shipping Contain- ers for Radioactive Materials," NUREG/CR-3019,*  
U.S. Nuclear Regulatory Commission, March 1985.


Plant Components," American Society of Mechanical Engineers, New York, updated frequently.                        4. L. E. Fischer and W. Lai (under Lawrence Livermore National Laboratory contract to the NRC),
4. L. E. Fischer and W. Lai (under Lawrence Livermore National Laboratory contract to the NRC),  
    2. W. R. Holman and R. T. Langland (under              "Fabrication Criteria for Shipping Containers,"
"Fabrication Criteria for Shipping Containers,"  
Lawrence Livermore National Laboratory contract to          NUREG/CR-3854,* U.S. Nuclear Regulatory Com the NRC), "Recommendations for Protecting Against          mission, March 1985.
NUREG/CR-3854,* U.S. Nuclear Regulatory Com mission, March 1985.


Failure by Brittle Fracture in Ferritic Steel Shipping Containers Up to Four Inches Thick," U.S. Nuclear                5. U.S. Nuclear Regulatory Commission, "Frac Regulatory Commission, NUREG/CR-1815, *August              ture Toughness Criteria of Base Material for Ferritic
5. U.S. Nuclear Regulatory Commission, "Frac ture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with a Wall Thickness Greater Than 4 Inches (0.1 m) But Not Exceeding 12 Inches (0.3 m)," Regulatory Guide  
1981.                                                      Steel Shipping Cask Containment Vessels with a Wall Thickness Greater Than 4 Inches (0.1 m) But Not
7.12,* May 1991.
    3. R. E. Monroe, H. H. Woo, and R. G. Sears            Exceeding 12 Inches (0.3 m)," Regulatory Guide (under Lawrence Livermore National Laboratory              7.12,* May 1991.


contract to the NRC), "Recommended Welding Cri              *Copies may be purchased from the National Technical Information teria for Use in the Fabrication of Shipping Contain-        Service, 5285 Port Royal Road, Springfield, VA 22161.
*Copies may be purchased from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161.


7.11-3
7.11-3


APPENDIX
APPENDIX
    Tables 3 through 6 from NUREG/CR-1815, "Recommendations for Protecting Against Failure by Brittle Fracture in Ferritic Steel Shipping Containers Up to Four Inches Thick," are reproduced here for the reader's convenience.
Tables 3 through 6 from NUREG/CR-1815, "Recommendations for Protecting Against Failure by Brittle Fracture in Ferritic Steel Shipping Containers Up to Four Inches Thick," are reproduced here for the reader's convenience.
 
TABLE 3.


TABLE 3.      NDT temperatures for steel plates.
NDT temperatures for steel plates.


NDT
NDT  
                        Group                                     Thickness               temperature                 ASTM
Group Thickness temperature ASTM  
  Group             treatment                                     (in.)                 range (*F)               specification I. PEARLITIC: Low and intermediate strength steels (oys = 30 to 70 ksi)
Group treatment (in.)  
                  A As rolled                                     0.625 to 3             0 to 70           A36, A516, A709,
range (*F)  
                                                                  3 to 4                 20 to 90           A442, A662 B Normalized (fine                             0.625 to 3             -50 to 10         A516, A442, A662, grain practice)                             3 to 4                 -30 to 30         A709 C Normalized (high                             0.625 to 3             -70 to -10         A441, A537, C.I 1, strength, low alloy)                         3 to 4                 -50 to 10         A533, A588, A736
specification I. PEARLITIC:  
  11. MARTENSITIC AND BAINITIC: High strength steels (47y3 = 80 to 120 ksi)
Low and intermediate strength steels (oys = 30 to 70 ksi)  
                  D Quenched and tempered                         0.625 to 4 a            -90 to -30b       A514, A517 (low alloy)
A As rolled  
                  E Quenched and tempered                         0.625 to 4             -160 to -80 b      HY-80, HY-100,
0.625 to 3  
                    (high alloy)                                                                           A-508-CL 4 & 5, A543 Ill. CRYOGENIC STEELS: (ays = 37 to 120 ksl at room temperature)
0 to 70  
                  F See ASTM specifications                       0.625 to 4             <-70OFc           A203 G See ASTM                                     0.625 to 4             <-100Fc           A353, A553, A645 aMaximum thickness depends on hardenability.
A36, A516, A709,  
3 to 4  
20 to 90  
A442, A662 B Normalized (fine  
0.625 to 3  
-50 to 10  
A516, A442, A662, grain practice)  
3 to 4  
-30 to 30  
A709 C Normalized (high  
0.625 to 3  
-70 to -10  
A441, A537, C.I 1, strength, low alloy)  
3 to 4  
-50 to 10  
A533, A588, A736  
11. MARTENSITIC AND BAINITIC: High strength steels (47y3 = 80 to 120 ksi)  
D Quenched and tempered  
0.625 to 4a
-90 to -30b A514, A517 (low alloy)  
E Quenched and tempered  
0.625 to 4  
-160 to -80b HY-80, HY-100,  
(high alloy)  
A-508-CL 4 & 5, A543 Ill. CRYOGENIC STEELS:  
(ays = 37 to 120 ksl at room temperature)  
F See ASTM specifications  
0.625 to 4  
<-70OFc A203 G See ASTM  
0.625 to 4  
<-100Fc A353, A553, A645 aMaximum thickness depends on hardenability.


bManufacturer must certify that the NDT temperature Is within this range.
bManufacturer must certify that the NDT temperature Is within this range.
Line 115: Line 209:
7.11-4
7.11-4


TABLE 4. Category I fracture toughness requirements and criteria for ferritic steels with yield strength no greater than 100 ksi.
TABLE 4.


Required degree      Safet*y                                          Very large margin of safety.
Category I fracture toughness requirements and criteria for ferritic steels with yield strength no greater than 100 ksi.


(-e Appeadh C)
Required degree Safet*y Very large margin of safety.
  Reqrueed amevnt of fracture toughme                                  Sufficient to arrest large cracks under dynamic loading; gemeral (see Sec. 5.1)                                                        yielding will precede fracture.


Thicknke   (B)
(-e Appeadh C)
      (I-.)                                                               Criteria for meeting toughness requirementsa
Reqrueed amevnt of fracture toughme Sufficient to arrest large cracks under dynamic loading; gemeral (see Sec. 5.1)
  0.625 to 40                                      
yielding will precede fracture.
 
Thicknke (B)  
(I-.)  
Criteria for meeting toughness requirementsa  
0.625 to 40  
* NDT temeratureb must be iss than a maximum value.
* NDT temeratureb must be iss than a maximum value.


See FIg. 3, and Secs. 5.1.1 and 5.1.2.
See FIg. 3, and Secs. 5.1.1 and 5.1.2.


Additlonally, if the steel has   y < 70 ksl, either: *
Additlonally, if the steel has y < 70 ksl, either: *  
                                                    0 5/9 in. thick DTr mast be greater than 400 ft-4b at upper shelf temperatures.
0 5/9 in. thick DTr mast be greater than 400 ft-4b at upper shelf temperatures.


See Sec. S.I.I.
See Sec. S.I.I.


Or
Or  
 
* CVd mist be greater than 45 ftl.b at upper sbelf temperatures.
* CVd mist be greater than 45 ftl.b at upper sbelf temperatures.


See See. 5.1.1.
See See. 5.1.1.


0.19 to 0.625                                    
0.19 to 0.625  
* Use DT Test E-604-80. 80% or greater shear fracture appearsace required at LST.
* Use DT Test E-604-80. 80% or greater shear fracture appearsace required at LST.


See See. 5.1.3.
See See. 5.1.3.


Or
Or  
                                                    "me DWTT Test E.-436 80% or greater Asear fracture appearance required at LST.
"me DWTT Test E.-436 80% or greater Asear fracture appearance required at LST.


See Sec. 5.1.3.
See Sec. 5.1.3.


0.025 to 0.19                                    
0.025 to 0.19  
* Use Notc     Tensile Teat E-33&
* Use Notc Tensile Teat E-33&  
                                                    Notch temnlle strength     > 1.0 at ISr.
Notch temnlle strength  
> 1.0 at ISr.


YW strenogth see sec 5.13.
YW strenogth see sec 5.13.


aFgnl scale destructive tesding a case-by-case basis may be weedas an alternate to requirements listed below. See Sec. 5.1.4.
aFgnl scale destructive tesding a  
case-by-case basis may be weed as an alternate to requirements listed below. See Sec. 5.1.4.


bNDT Is mea*lred according to ASTM E-208, or an equivalext NDT cam be establisbed by subtracting
bNDT Is mea*lred according to ASTM E-208, or an equivalext NDT cam be establisbed by subtracting 50*F from the midpoint of the  
                                                                                                            50*F from the midpoint of the
5/1 hi. DT eegy transition crve measured accordiag to ASTM E-604.
5/1 hi. DT eegy transition crve measured accordiag to ASTM E-604.


Line 166: Line 264:
dcv measured according to ASTM E-23.
dcv measured according to ASTM E-23.


*Editor's Note: This line should read, "Additionally, if the steel has orys &#x17d;                     70 ksi, either:" to cor rect a typographical error.
*Editor's Note: This line should read, "Additionally, if the steel has orys &#x17d;  
70 ksi, either:" to cor rect a typographical error.


7.11-5
7.11-5


TABLE 5. Category II fracture toughness requirements and criteria for ferritic steels with yield strength no greater than 100 ksi.
TABLE 5.
 
Category II fracture toughness requirements and criteria for ferritic steels with yield strength no greater than 100 ksi.


Required degree *I safety                                               Large margin of safety.
Required degree *I safety Large margin of safety.


(see Appendix C)
(see Appendix C)  
Required amount of fracture toughness                                   Sufficient to prevent fracture Initiation of cracks under dynamic (see Sec. 5.2)                                                         loading.
Required amount of fracture toughness Sufficient to prevent fracture Initiation of cracks under dynamic (see Sec. 5.2)  
loading.


Thickness (B)
Thickness (B)  
    (in.)                                                                 Criteria for meeting toughness requirementsa
(in.)  
0.625 to 4.0                                        
Criteria for meeting toughness requirementsa  
0.625 to 4.0  
* With full dynamic loading rates, NDT temperatureb must be less than a maximum value.
* With full dynamic loading rates, NDT temperatureb must be less than a maximum value.


Line 188: Line 291:
See Sec. 5.2.2.
See Sec. 5.2.2.


0.19 to 0.625                                         " Use DT Test E-644-80. 50% or greater shear fracture appearance required at LST.
0.19 to 0.625  
" Use DT Test E-644-80. 50% or greater shear fracture appearance required at LST.


See Sec. 5.2.3.
See Sec. 5.2.3.


Or
Or  
                                                      "0 Use DWTT Test   E-436. 50% or greater shear fracture appearance required at LST.
"0  
Use DWTT Test E-436. 50% or greater shear fracture appearance required at LST.


See Sec. 5.2.3.
See Sec. 5.2.3.


Or
Or  
 
* Use any normalized steel made to "Fine Grain Practice" or betterc.
* Use any normalized steel made to "Fine Grain Practice" or betterc.


See Sec. 5.2.3.
See Sec. 5.2.3.


Less than 0.19                                      
Less than 0.19  
* No requirements wben B is less than 0.19 in.
* No requirements wben B is less than 0.19 in.


Line 210: Line 314:
aFliI scale destructive testing on a case-by-case basis may be used as an alternate to requirements listed below. See Sec. 5.2.4.
aFliI scale destructive testing on a case-by-case basis may be used as an alternate to requirements listed below. See Sec. 5.2.4.


bNDT is measured according to ASTM E-208, or an equivalent NDT can be established by subtracting 50*F from the midpoint of the
bNDT is measured according to ASTM E-208, or an equivalent NDT can be established by subtracting 50*F from the midpoint of the  
  5/8 In. DT energy transition curve measured according to ASTM E-604 or the NDT temperature requirement can be met by selecting the maximum NDT temperature given in Fig. 1 or Table 3.
5/8 In. DT energy transition curve measured according to ASTM E-604 or the NDT temperature requirement can be met by selecting the maximum NDT temperature given in Fig. 1 or Table 3.


cSteei with an NDT temperature lower than steels made to a fine grain practice.
cSteei with an NDT temperature lower than steels made to a fine grain practice.
Line 219: Line 323:
TABLE 6. Category III fracture toughness requirements and criteria for ferrtitc steels with yield strength no greater than 100 ksi.
TABLE 6. Category III fracture toughness requirements and criteria for ferrtitc steels with yield strength no greater than 100 ksi.


Required degree of safety                                             Adequate margin of safety.
Required degree of safety Adequate margin of safety.


(we Appendix C)
(we Appendix C)  
Required amouet of fracture toughness                                 Sufficient to prevent fracture Initiation at minor defects typical of (see Sec. 5)                                                         good fabrication practices.
Required amouet of fracture toughness Sufficient to prevent fracture Initiation at minor defects typical of (see Sec. 5)  
good fabrication practices.


Thickoess (3)
Thickoess (3)  
    (I1.)                                                               Criteria for meetlig toghnmess requremets
(I1.)  
0.4 to 4.0                                        
Criteria for meetlig toghnmess requremets  
0.4 to 4.0  
* Without testing, ue any normalized steel made to "Fine Grain Prctice" or bettera.
* Without testing, ue any normalized steel made to "Fine Grain Prctice" or bettera.


See Sec. 5.3.1.
See Sec. 5.3.1.


Or
Or  
 
* Show that NDTh 4 10-F (B ; 0.625 in.).
* Show that NDTh 4 10-F (B ; 0.625 in.).
Or  
                                                    Or
 
* Test to show that DTc > 50 ft-lb at 10*F, with test specimen 0.625 in. thick.
* Test to show that DTc > 50 ft-lb at 10*F, with test specimen 0.625 in. thick.


Or
Or  
 
* Test to show that CVd > 15 ft-lb at 10*.
* Test to show that CVd > 15 ft-lb at 10*.
Or  
                                                    Or
 
* Without testing, use as-rolled steel, provided the welds have been stress relieved and inspected by nondestructive evaluation techniques.
* Without testing, use as-rolled steel, provided the welds have been stress relieved and inspected by nondestructive evaluation techniques.


Less than 0.4                                    
Less than 0.4  
* No requirements when B is less than 0.4 in.
* No requirements when B is less than 0.4 in.


Line 252: Line 354:
aStee with an NDT temperature lower than steels made to a fine grain practice.
aStee with an NDT temperature lower than steels made to a fine grain practice.


bNDT Is measured according to ASTM F,208, or an equivalent NDT can be established by subtracting 50*F from the midpoint of the
bNDT Is measured according to ASTM F,208, or an equivalent NDT can be established by subtracting 50*F from the midpoint of the  
5/8 in. DT energy transition curve measured according to ASTM E-604 or the NDT temperature requirement can be met by selecting the maximum NDT temperature given in Fig. I or Table 3.
5/8 in. DT energy transition curve measured according to ASTM E-604 or the NDT temperature requirement can be met by selecting the maximum NDT temperature given in Fig. I or Table 3.


Line 262: Line 364:


VALUE/IMPACT STATEMENT
VALUE/IMPACT STATEMENT
            A draft value/impact statement was published           A copy of the draft value/impact statement is avail with the draft of this guide when it was published for     able for inspection or copying for a fee in the Com public comment (Task DG-7001, July 1989). No               mission's Public Document Room at 2120 L Street changes were necessary, so a separate value/impact         NW, Washington, DC, under DG-7001.
A draft value/impact statement was published with the draft of this guide when it was published for public comment (Task DG-7001, July 1989). No changes were necessary, so a separate value/impact statement for the final guide has not been prepared.


statement for the final guide has not been prepared.
A copy of the draft value/impact statement is avail able for inspection or copying for a fee in the Com mission's Public Document Room at 2120 L Street NW, Washington, DC, under DG-7001.


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Latest revision as of 03:10, 17 January 2025

Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with Maximum Wall Thickness of 4 Inches (0.1 M)
ML003739413
Person / Time
Issue date: 06/30/1991
From:
Office of Nuclear Regulatory Research
To:
References
RG-7.011
Download: ML003739413 (8)


U.S. NUCLEAR REGULATORY COMMISSION

R E GUlaTORY

June 1991 GUIDE

OFFICE OF NUCLEAR REGULATORY RESEARCH

REGULATORY GUIDE 7.11 FRACTURE TOUGHNESS CRITERIA OF BASE MATERIAL

FOR FERRITIC STEEL SHIPPING CASK CONTAINMENT

VESSELS WITH A MAXIMUM WALL THICKNESS OF 4 INCHES (0.1 m)

(Previously issued as Drafts MS 144-4 and DG-7001)

A.

INTRODUCTION

Part 71, "Packaging and Transportation of Ra dioactive Material," of Title 10 of the Code of Fed eral Regulations requires that packages used to trans port radioactive materials withstand the conditions in

§ 71.71, "Normal Conditions of Transport," and

§ 71.73, "Hypothetical Accident Conditions."

In this guide, the terms packaging, shipping cask, and shipping container are used interchangeably.

The regulations require that accident conditions with an initial temperature as low as -20'F (-29°C)

be considered. At this temperature, several types of ferritic steels are brittle and subject to fracture. This guide describes fracture toughness criteria and test methods acceptable to the NRC staff for use in evalu ating Type B (U) and Type B (M)l ferritic steel ship ping cask containment vessel base material having a maximum thickness of 4 inches (0.1 m) and having a maximum static yield strength of 100 ksi (690 kPa).

The containment vessel is a major component of the containment system as defined in § 71.4 of 10 CFR

Part 71. This guide is applicable to the containment vessel only and not to other components of the pack age.

Alternative fracture toughness criteria and test methods may be used provided the applicant can

,'Type B(U) and Type B(M) packages are defined in 10 CFR 71.4.

USNRC REGULATORY GUIDES

Regulatory Guides are issued to describe and make available to the pub lie methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the staff in evaluating specific problems or postulated accidents, or to pro vide guidance to applicants. Regulatory Guides are not substitutes for regulations, and compliance with them Is not required. Methods and solutions different from those set out in the guides wilf be acceptable if.

they provide a basis for the findings requisite to the issuance or continu ance of a permit or license by the Commission.

This guide was Issued after consideration of comments received from the public, Comments and suggestions for improvements In these guides are encouraged at all times, and guides will be revised, as ap propriate, to accommodate comments and to reflect new Information or experience.

Written comments may be submitted to the Regulatory Publications Branch, DFIPS, ADM, U.S. Nuclear Regulatory Commission, Washing ton, DC 20555.

demonstrate that their use will ensure equivalent safety.

Any information collection activities mentioned in this regulatory guide are contained as requirements in 10 CFR Part 71, which provides the regulatory ba sis for this guide. The information collection require ments in 10 CFR Part 71 have been cleared under OMB Clearance No. 3150-0008.

B.

DISCUSSION

This guide presents fracture toughness criteria and test methods that can be used for evaluating ferritic steel containment vessel base material having a maximum wall thickness of 4 inches (0.1 m) with a maximum static yield strength of 100 ksi (690 kPa).

Section III of the ASME Boiler and Pressure Vessel Code (Ref. 1) contains requirements for mate rial fracture toughness; however, these requirements were developed for reactor components only and do not address hypothetical accident conditions appro priate for packaging (e.g., severe impact loads at low temperatures). Therefore, the code requirements are not directly applicable to shipping container design.

NUREG/CR-1815, "Recommendations for Pro tecting Against Failure by Brittle Fracture in Ferritic Steel Shipping Containers up to Four Inches Thick"

(Ref. 2), contains background and other information The guides are issued in the following ten broad divisions:

1. Power Reactors

2. Research and Test Reactors

3. Fuels and Materials Facilities

4. Environmental and Siting

5. Materials and Plant Protection

6. Products

7. Transportation

8. Occupational Health

9. Antitrust and Financial Review

10. General Copies of issued guides may be purchased from the Government Printing Office at the current GPO price. Information on current GPO prices may be obtained by contacting the Superintendent of Documents, U.S.

Government Printing Office, Post Office Box 37082, Washington, DC

20013-7082, telephone (202)275-2060 or (202)275-2171, Issued guides may also be purchased from the National Technical Infor mation Service on a standing order basis. Details on this service may be obtained by writing NTIS, 5285 Port Royal Road, Springfield, VA 22,161.

pertinent to the development of the criteria in this guide. These criteria are divided into three categories that are associated with the levels of safety appropri ate for the radioactive contents being transported.

Table 1 in this guide identifies the radioactivity limits for each of the three categories. Tables 4, 5, and 6 in NUREG/CR-18152 (reproduced along with Table 3 in the Appendix to this guide) list the fracture tough ness criteria associated with each category. A qualita tive description of the margins of safety against brittle failure for each of the three categories is given in Ap pendix C to NUREG/CR-1815 (Ref. 2).

Additional information regarding the basis for the criteria is contained in Appendix B of NUREG/

CR-1815 (Ref. 2).

Regulatory Position 1 endorses a portion of the criteria contained in Section 5 of NUREG/CR-1815.

These criteria identify material properties in accor dance with the standards specified in Tables 4, 5, and

6 of NUREG/CR-1815, as appropriate.

For Category II and III containers, the highest nil ductility transition temperature (TNDT)

specified for the material in Table 3 of NUREG/CR-1815 (repro duced in the Appendix to this guide) may be used in lieu of conducting tests to determine the actual TNDT of the material.

Table 1 Category I

Category II

Category III

Low Greater than Less than Specific

30,000 Ci or

30,000 Ci Activity greater than and less than

3,000 A,* or

3,000 A,

greater than and less than

3,000 A,-

3,000 A,

Special Greater than Between Less than Form

3,000 A,

3,000 A, and

30 A, and or greater than 30 A, and not less than

30,000 Ci greater than

30,000 Ci

30,000 Ci Normal Greater than Between Less than Form

3,000 A2

3,000 A2 and

30 A2 or greater than 30 A2 and not and less than

30,000 Ci greater than

30,000 Ci

30,000 Ci

  • Defined in 10 CFR 71.4 Although NUREG/CR-1815 (Ref. 2) addresses the use of ferritic steels only, it does not preclude the Mrhe following corrections should be made to the NUREG: Table 1, Category III revise to read "...Fine Grain Practice..."; Table 4, Crite ria .... third line "has ays a 70 ksi, either."; Figure 6, vertical scale should be "...0, 20, 40..."; Section 5.3.1, subsection 1, "By se lecting a normalized steel ...."

use of austenitic stainless steels. Since austenitic stain less steels are not susceptible to brittle failure at tem peratures encountered in transport, their use in con tainment vessels is acceptable to the staff and no tests are needed to demonstrate resistance to brittle fail ure.

NUREG/CR-3019, "Recommended Welding Cri teria for Use in the Fabrication of Shipping Contain ers for Radioactive Materials" (Ref. 3), and NUREG/

CR-3854, "Fabrication Criteria for Shipping Contain ers" (Ref. 4), also contain information applicable to shipping containers, as does a related Regulatory Guide 7.12, "Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Contain ment Vessels with a Wall Thickness Greater than 4 Inches (0.1 m) But Not Exceeding 12 Inches (0.3 m)" (Ref. 5).

C. REGULATORY POSITION

1. The criteria contained in Section

5 of NUREG/CR-1815 (Ref. 2), other than for full-scale destructive testing (5.1.4 and 5.2.4) and qualifying procedures for reduced stress levels (5.1.2), are ac ceptable to the NRC staff for assessing the fracture toughness of thin-wall base material (up to and in cluding 4 inches (0.1 m)) ferritic steel containment vessels for the categories identified in Table 1 of this guide. In 5.1.2, only a value of a/Uyd equal to I is acceptable.

2. A Category I container qualified in accor dance with this guide is acceptable for transporting either Category II or Category III radioactive materi als. Similarly, a Category II container qualified in ac cordance with this guide is acceptable for transporting Category III materials.

D. IMPLEMENTATION

The purpose of this section is to provide informa tion to applicants and licensees regarding the NRC

staff's plans for using this regulatory guide.

Except in those cases in which an applicant or licensee proposes an acceptable alternative method for complying with specified portions of the Commis sion's regulations, the methods described in this guide (which reflects public comments) will be used by the NRC staff in evaluating base material for all applica tions for new package designs and all requests that existing package designs be designated as Type B(U)

or Type B(M) packages submitted after Septem ber 30, 1991.

7.11-2

REFERENCES

1. ASME Boiler and Pressure Vessel Code, Sec tion III, "Rules for Construction of Nuclear Power Plant Components," American Society of Mechanical Engineers, New York, updated frequently.

2. W. R. Holman and R. T. Langland (under Lawrence Livermore National Laboratory contract to the NRC), "Recommendations for Protecting Against Failure by Brittle Fracture in Ferritic Steel Shipping Containers Up to Four Inches Thick," U.S. Nuclear Regulatory Commission, NUREG/CR-1815, *August

1981.

3. R. E. Monroe, H. H. Woo, and R. G. Sears (under Lawrence Livermore National Laboratory contract to the NRC), "Recommended Welding Cri teria for Use in the Fabrication of Shipping Contain- ers for Radioactive Materials," NUREG/CR-3019,*

U.S. Nuclear Regulatory Commission, March 1985.

4. L. E. Fischer and W. Lai (under Lawrence Livermore National Laboratory contract to the NRC),

"Fabrication Criteria for Shipping Containers,"

NUREG/CR-3854,* U.S. Nuclear Regulatory Com mission, March 1985.

5. U.S. Nuclear Regulatory Commission, "Frac ture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with a Wall Thickness Greater Than 4 Inches (0.1 m) But Not Exceeding 12 Inches (0.3 m)," Regulatory Guide

7.12,* May 1991.

  • Copies may be purchased from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161.

7.11-3

APPENDIX

Tables 3 through 6 from NUREG/CR-1815, "Recommendations for Protecting Against Failure by Brittle Fracture in Ferritic Steel Shipping Containers Up to Four Inches Thick," are reproduced here for the reader's convenience.

TABLE 3.

NDT temperatures for steel plates.

NDT

Group Thickness temperature ASTM

Group treatment (in.)

range (*F)

specification I. PEARLITIC:

Low and intermediate strength steels (oys = 30 to 70 ksi)

A As rolled

0.625 to 3

0 to 70

A36, A516, A709,

3 to 4

20 to 90

A442, A662 B Normalized (fine

0.625 to 3

-50 to 10

A516, A442, A662, grain practice)

3 to 4

-30 to 30

A709 C Normalized (high

0.625 to 3

-70 to -10

A441, A537, C.I 1, strength, low alloy)

3 to 4

-50 to 10

A533, A588, A736

11. MARTENSITIC AND BAINITIC: High strength steels (47y3 = 80 to 120 ksi)

D Quenched and tempered

0.625 to 4a

-90 to -30b A514, A517 (low alloy)

E Quenched and tempered

0.625 to 4

-160 to -80b HY-80, HY-100,

(high alloy)

A-508-CL 4 & 5, A543 Ill. CRYOGENIC STEELS:

(ays = 37 to 120 ksl at room temperature)

F See ASTM specifications

0.625 to 4

<-70OFc A203 G See ASTM

0.625 to 4

<-100Fc A353, A553, A645 aMaximum thickness depends on hardenability.

bManufacturer must certify that the NDT temperature Is within this range.

CThese steels are special cases. Each product should be tested by the DT test to determine the NDT temperature.

7.11-4

TABLE 4.

Category I fracture toughness requirements and criteria for ferritic steels with yield strength no greater than 100 ksi.

Required degree Safet*y Very large margin of safety.

(-e Appeadh C)

Reqrueed amevnt of fracture toughme Sufficient to arrest large cracks under dynamic loading; gemeral (see Sec. 5.1)

yielding will precede fracture.

Thicknke (B)

(I-.)

Criteria for meeting toughness requirementsa

0.625 to 40

  • NDT temeratureb must be iss than a maximum value.

See FIg. 3, and Secs. 5.1.1 and 5.1.2.

Additlonally, if the steel has y < 70 ksl, either: *

0 5/9 in. thick DTr mast be greater than 400 ft-4b at upper shelf temperatures.

See Sec. S.I.I.

Or

  • CVd mist be greater than 45 ftl.b at upper sbelf temperatures.

See See. 5.1.1.

0.19 to 0.625

  • Use DT Test E-604-80. 80% or greater shear fracture appearsace required at LST.

See See. 5.1.3.

Or

"me DWTT Test E.-436 80% or greater Asear fracture appearance required at LST.

See Sec. 5.1.3.

0.025 to 0.19

  • Use Notc Tensile Teat E-33&

Notch temnlle strength

> 1.0 at ISr.

YW strenogth see sec 5.13.

aFgnl scale destructive tesding a

case-by-case basis may be weed as an alternate to requirements listed below. See Sec. 5.1.4.

bNDT Is mea*lred according to ASTM E-208, or an equivalext NDT cam be establisbed by subtracting 50*F from the midpoint of the

5/1 hi. DT eegy transition crve measured accordiag to ASTM E-604.

CDT measured according to ASTM E-604.

dcv measured according to ASTM E-23.

  • Editor's Note: This line should read, "Additionally, if the steel has orys Ž

70 ksi, either:" to cor rect a typographical error.

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TABLE 5.

Category II fracture toughness requirements and criteria for ferritic steels with yield strength no greater than 100 ksi.

Required degree *I safety Large margin of safety.

(see Appendix C)

Required amount of fracture toughness Sufficient to prevent fracture Initiation of cracks under dynamic (see Sec. 5.2)

loading.

Thickness (B)

(in.)

Criteria for meeting toughness requirementsa

0.625 to 4.0

  • With full dynamic loading rates, NDT temperatureb must be less than a maximum value.

See Fig. 6 and Sec. 5.2.1.

  • With reduced loading rates, NDT temperature can be determined from Fig. 7.

See Sec. 5.2.2.

0.19 to 0.625

" Use DT Test E-644-80. 50% or greater shear fracture appearance required at LST.

See Sec. 5.2.3.

Or

"0

Use DWTT Test E-436. 50% or greater shear fracture appearance required at LST.

See Sec. 5.2.3.

Or

  • Use any normalized steel made to "Fine Grain Practice" or betterc.

See Sec. 5.2.3.

Less than 0.19

  • No requirements wben B is less than 0.19 in.

See See. 5.2.3.

aFliI scale destructive testing on a case-by-case basis may be used as an alternate to requirements listed below. See Sec. 5.2.4.

bNDT is measured according to ASTM E-208, or an equivalent NDT can be established by subtracting 50*F from the midpoint of the

5/8 In. DT energy transition curve measured according to ASTM E-604 or the NDT temperature requirement can be met by selecting the maximum NDT temperature given in Fig. 1 or Table 3.

cSteei with an NDT temperature lower than steels made to a fine grain practice.

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TABLE 6. Category III fracture toughness requirements and criteria for ferrtitc steels with yield strength no greater than 100 ksi.

Required degree of safety Adequate margin of safety.

(we Appendix C)

Required amouet of fracture toughness Sufficient to prevent fracture Initiation at minor defects typical of (see Sec. 5)

good fabrication practices.

Thickoess (3)

(I1.)

Criteria for meetlig toghnmess requremets

0.4 to 4.0

  • Without testing, ue any normalized steel made to "Fine Grain Prctice" or bettera.

See Sec. 5.3.1.

Or

  • Show that NDTh 4 10-F (B ; 0.625 in.).

Or

  • Test to show that DTc > 50 ft-lb at 10*F, with test specimen 0.625 in. thick.

Or

  • Test to show that CVd > 15 ft-lb at 10*.

Or

  • Without testing, use as-rolled steel, provided the welds have been stress relieved and inspected by nondestructive evaluation techniques.

Less than 0.4

  • No requirements when B is less than 0.4 in.

See Sec. 5.3.2.

aStee with an NDT temperature lower than steels made to a fine grain practice.

bNDT Is measured according to ASTM F,208, or an equivalent NDT can be established by subtracting 50*F from the midpoint of the

5/8 in. DT energy transition curve measured according to ASTM E-604 or the NDT temperature requirement can be met by selecting the maximum NDT temperature given in Fig. I or Table 3.

CDT measured according to ASTM E-604, for specimen thickness of 0.625 in.

dcv measured according to ASTM &-23.

7.11-7

VALUE/IMPACT STATEMENT

A draft value/impact statement was published with the draft of this guide when it was published for public comment (Task DG-7001, July 1989). No changes were necessary, so a separate value/impact statement for the final guide has not been prepared.

A copy of the draft value/impact statement is avail able for inspection or copying for a fee in the Com mission's Public Document Room at 2120 L Street NW, Washington, DC, under DG-7001.

UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 20555 OFFICIAL BUSINESS

PENALTY FOR PRIVATE USE, $300

FIRST CLASS MAIL

POSTAGE E FEES PAID

USNRC

PERMIT No. G-67

7.11-8