Regulatory Guide 1.130: Difference between revisions

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{{Adams
{{Adams
| number = ML070170053
| number = ML003740123
| issue date = 03/11/2007
| issue date = 10/31/1978
| title = Service Limits and Loading Combinations for Class 1 Plate-and-Shell-Type Supports
| title = Service Limits & Loading Combinations for Class 1 Plate-And-Shell-Type Component Supports
| author name = Dubouchet A
| author name =  
| author affiliation = NRC/NRO/DCIP, NRC/RES
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
| docket =  
| docket =  
| license number =  
| license number =  
| contact person = DuBouchet, A. NRO/DCIP/CCIB/CI, 415-2785
| contact person =  
| case reference number = DG-1169
| document report number = RG-1.130, Revision 1
| document report number = RG-1.130, Rev 2
| package number = ML070170046
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 9
| page count = 5
}}
}}
{{#Wiki_filter:The U.S. Nuclear Regulatory Commission (NRC) issues regulatory guides to describe and make available to the public methods that the NRC staff considers acceptable for use in implementing specific parts of the agencys regulations, techniques that the staff uses in evaluating specific problems or postulated accidents, and data that the staff need in reviewing applications for permits and licenses.  Regulatory guides are not substitutes for regulations, and compliance with them is not required.  Methods and solutions that differ from those set forth in regulatory guides will be deemed acceptable if they provide a basis for the findings required for the issuance or continuance of a permit or license by the Commission.
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION
 
Revision 1 October 1978 REGULATORY GUIDE  
This guide was issued after consideration of comments received from the public.  The NRC staff encourages and welcomes comments and suggestions in connection with improvements to published regulatory guides, as well as items for inclusion in regulatory guides that are currently being developed.
OFFICE OF STANDARDS DEVELOPMENT
 
Regulatory Guide 1.130  
The NRC staff will revise existing guides, as appropriate, to accommodate comments and to reflect new information or experience.  Written comments may be submitted to the Rules and Directives Branch, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
SERVICE LIMITS AND LOADING COMBINATIONS  
 
FOR CLASS 1 PLATE-AND-SHELL-TYPE COMPONENT SUPPORTS
Regulatory guides are issued in 10 broad divisions:  1, Power Reactors; 2, Research and Test Reactors; 3, Fuels and Materials Facilities;
*1
4, Environmental and Siting; 5, Materials and Plant Protection; 6, Products; 7, Transportation; 8, Occupational Health; 9, Antitrust and Financial Review;
and 10, General.
 
Requests for single copies of draft or active regulatory guides (which may be reproduced) should be made to the U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention: Reproduction and Distribution Services Section, or by fax to (301) 415-2289; or by email to Distribution@nrc.gov.
 
Electronic copies of this guide and other recently issued guides are available through the NRCs public Web site under the Regulatory Guides document collection of the NRCs Electronic Reading Room at http://www.nrc.gov/reading-rm/doc-collections/ and through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under Accession No. ML070170053.
 
U.S. NUCLEAR REGULATORY COMMISSION
March 2007 Revision 2 REGULATORY GUIDE
OFFICE OF NUCLEAR REGULATORY RESEARCH
REGULATORY GUIDE 1.130
(Draft was issued as DG-1169, dated October 2006)
SERVICE LIMITS AND LOADING COMBINATIONS
FOR CLASS 1 PLATE-AND-SHELL-TYPE SUPPORTS


==A. INTRODUCTION==
==A. INTRODUCTION==
General Design Criterion 2, Design Bases for Protection Against Natural Phenomena, of Appendix A, General Design Criteria for Nuclear Power Plants, to Title 10, Part 50, Domestic Licensing of Production and Utilization Facilities, of the Code of Federal Regulations (10 CFR Part 50)
General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena," of Appen dix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," requires that the design bases for structures, systems, and compo nents important to safety reflect appropriate combi nations of the effects of normal and accident condi tions with the effects of natural phenomena such as earthquakes. The failure of members designed to support safety-related components could jeopardize the ability of the supported component to perform its safety function.
(Ref. 1) requires that the design bases for structures, systems, and components important to safety reflect appropriate combinations of the effects of normal and accident conditions with the effects of natural phenomena such as earthquakes. The failure of members designed to support safety-related components and piping could jeopardize the ability of the supported component or piping to perform its safety function.


This guide delineates acceptable levels of service limits and appropriate combinations of loadings associated with normal operation, postulated accidents, and specified seismic events for the design of Class 1 plate-and-shell-type component and piping supports, as defined in Subsection NF of Section III
This guide delineates acceptable levels of service limits and appropriate combinations of loadings as sociated with normal operation, postulated accidents, and specified seismic events for the design of Class 1 plate-and-shell-type component supports as defined in Subsection NF of Section III of the American So ciety of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. 1 This guide applies to light water-cooled reactors.
of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Ref. 2).
This guide applies to light-water-cooled reactors.


This regulatory guide contains information collections that are covered by the requirements of
The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.
10 CFR Part 50 and that the Office of Management and Budget (OMB) approved under OMB control number 3150-0011.  The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information request or requirement unless the document displays a valid OMB control number.


1 Regulatory Guide 1.84, Design, Fabrication, and Materials Code Case Acceptability, ASME Section III (Ref. 3)
==B. DISCUSSION==
provides guidance for the acceptability of ASME Section III Code Cases and their revisions, including Code Cases N-71 and N-249.  Code Cases identified as Conditionally Acceptable Section III Code Cases are acceptable, provided that they are used with the identified limitations or modifications.
Load-bearing members classified as component supports are essential to the safety of nuclear power
* Lines indicate substantive changes from previous issue.


Rev. 2 of RG 1.130, Page 2
American Society of Mechanical Engineers Boiler and Pressure Vessel Codes Section 111, Division 1, 1977 Edition, including the
 
1977 Winter Addenda thereto. Copies of the Code may be ob tained from the American Society of Mechanical Engineers, United Engineering Center, 345 East 47th Street, New York, N.Y. 10017.
==B. DISCUSSION==
Background Load-bearing members classified as component and piping supports are essential to the safety of nuclear power plants because they hold components and piping in place during loadings associated with normal and upset plant conditions under the stress of specified seismic events, thereby permitting system components and piping to function properly. Load-bearing members also prevent excessive movement of components and piping during the loadings associated with emergency and faulted plant conditions combined with a specified seismic event or other natural phenomena, thereby helping to mitigate system damage. Component and piping supports are deformation-sensitive because large deformations can significantly change the stress distribution in the support system and its supported components and piping.


To provide a consistent level of safety, the ASME Code classification for component and piping supports should, as a minimum, be the same as that of the supported components and piping. This guide delineates levels of service limits and loading combinations, as well as supplementary criteria, for Class 1 plate-and-shell-type component and piping supports, as defined by NF-1212 of Section III of the ASME
plants because they retain components in place during loadings associated with normal and upset plant con ditions under the stress of specified seismic events, thereby permitting system components to function properly. They also prevent excessive component movement during the loadings associated with emer gency and faulted plant conditions combined with a specified seismic event or other natural phenomena, thereby helping to mitigate system damage. Compo nent supports are deformation-sensitive because large deformations in component supports may signifi cantly change the stress distribution in the support system and its components.
Code.  This guide does not address snubbers.


Subsection NF of Section III permits the use of three methods for the design of Class 1 plate-and- shell-type component and piping supports: (1) linear elastic analysis, (2) load rating, and
In order to provide a consistent level of safety, the ASME Boiler and Pressure Vessel Code classifica tion for component supports should, as a minimum, be the same as that of the supported components.
(3) experimental stress analysis.  For each method, the ASME Code delineates allowable stress or loading limits for various ASME Code service levels, as defined by NF-3113 and NCA-2142.4(b) of Section III, so that these limits can be used in conjunction with the resultant loadings or stresses from the appropriate plant conditions.  Because the ASME Code does not specify loading combinations, guidance is needed to provide a consistent basis for the design of supports.


Component and piping supports considered in this guide are located within seismic Category I
This guide delineates levels of service limits and loading combinations, as well as supplementary criteria, for Class 1 plate-and-shell-type component supports as defined by NF-1212 of Section III of the Code. Snubbers are not addressed in this guide.
structures and, therefore, are assumed to be protected against loadings from natural phenomena (or manmade hazards) other than the specified seismic events. Thus, only the specified seismic events need to be considered in combination with the loadings associated with plant conditions to develop appropriate loading combinations.  Loadings caused by any natural phenomena other than seismic events should be considered on a case-by-case basis.


1.
Subsection NF of Section III permits the use of three methods for the design of Class I plate-and shell-type component supports: (1) linear elastic analysis, (2) load rating, and (3) experimental stress analysis. For each method, the ASME Code de lineates allowable stress or loading limits for various Code service levels, as defined by NF-3113 and NCA-2142.2(b) of Section III, so that these limits can be used in conjunction with the resultant loadings or stresses from the appropriate plant conditions.


Design by Linear Elastic Analysis Tables 2A, 2B, 4, U, and Y-1 in Subpart 1 of Part D of Section II and Tables 1, 3, 4, and 5 of the latest accepted versions1 of ASME Code Cases N-71 and N-249 give the material properties when the linear elastic analysis method is used to design Class 1 plate-and-shell-type component and piping supports.  These tables list values at various temperatures for the design stress intensity S m, the minimum yield strength Sy, and the ultimate tensile strength Su.
Since the Code does not specify loading combina tions, guidance is needed to provide a consistent basis for the design of component supports.


Rev. 2 of RG 1.130, Page 3 NF-3522 and NF-3622 limit the primary stress for service levels A, B, and C to less than or equal to one-half the critical buckling strength of the component or piping support at temperature. F-1331.5(a)
Component supports considered in this guide are located within Seismic Category I structures and are USNRC REGULATORY GUIDES
limits the increase for service level D to two-thirds of the critical buckling strength of the component or piping support at temperature.  Because buckling prevents shakedown in a load-bearing member, it must be regarded as controlling for the level A through level D service limits. Also, buckling is the result of the interaction of the geometry of the load-bearing member and its material properties (i.e., elastic modulus E and minimum yield strength Sy).  Because both of these material properties change with temperature, calculation of the critical buckling stresses should use the values of E and S y of the support material at temperature.
Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C. 20556, Attention: Docketing and Regulatory Guides are issued to describe and make available to the public Service Branch.


Allowable service limits for bolted connections are derived on a different basis that varies with the size of the bolt.  For this reason, the increases permitted by NF-3221.2 and F-1332 of Section III do not directly apply to bolts and bolted connections.  For bolts, allowable increases for service levels B, C
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 broad divisions:
and D are specified in NF-3225.
ating specific problems or postulated accidents, or to provide guidance to applicants. Regulatory Guides are not substitutes for regulations, and corn-  


2.
===1. Power Reactors ===
6. Products pliance with them is not required. Methods and solutions different from those
2. Research and Test Reactors
7. Transportation set out in the guides will be acceptable if they provide a basis for the findings
3. Fuels and Materials Facilities
8. Occupational Health requisite to the issuance or continuance of a permit or license by the
4. Environmental and Siting
9. Antitrust and Financial Review Commission.


Design by Load Rating NF-3280 specifies load ratings for service level A, B, and C limits. F-1332.7 specifies the load rating for the service level D limit.
5. Materials and Plant Protection
10. General Requests for single copies of issued guides lwhich may tIe reproduced) or for Comments and suggestions for improvements in these guides are encouraged at placement on an automatic distribution list for single copies of future guides all times, and guides will be revised, as appropriate, to accommodate comments in specific divisions should be made in writing to the U.S. Nuclear Regulatory and to reflect new information or experience. This guide was revised as a result Commission, Washington, D.C. 20565, Attention: Director, Division of of substantive comments received from the public and additional staff review.


3.
Technical Information and Document Control.


Design by Experimental Stress Analysis Although II-1430 in Appendix II to Section III defines the test collapse load for the experimental stress analysis method, it does not delineate the methods design limits or various operating condition categories.  The interim method described in this guide remedies this deficiency.
therefore assumed to be protected against loadings from natural phenomena or man-made hazards other than the specified seismic events. Thus only the specified seismic events need to be considered in combination with the loadings associated with plant conditions to develop appropriate loading combina tions. When loadings caused by natural phenomena other than seismic events, such as the subsidence of the land surface as a result of large-scale ground water withdrawals exist, they should be specified in the Design Specification, and the loading combina tions reflecting the inclusion of these loadings should be reviewed.


4.
1. Design by Linear Elastic Analysis When the linear-elastic-analysis method is used to design Class I plate-and-shell-type component sup ports, material properties are given by Tables I-I. 1,
1-1.2, and 1-11.1 of Appendix I to Section III and Table I of the latest accepted version 2 of Code Case
1644. These tables list values for the design stress intensity Sm at various temperature


Large Deformations The design of component and piping supports is an integral part of the design of a system and its components and piping. A complete and consistent design is possible only when the interaction between the system, component, piping, and support is properly considered. When all four are evaluated on an elastic basis, the interaction is usually valid because individual deformations are small. However, if the design process uses plastic analysis methods, large deformations may occur that would result in substantially different stress distributions.
====s. Yet level D ====
service limits are determined by S., Sy, and S.. The load-rating method also requires the use of Su.


For the evaluation of level D service limits, Appendix F to Section III permits the use of plastic analysis methods in certain acceptable combinations for all four elements.  The selection of these acceptable combinations assumes that component and piping supports are more deformation-sensitive (i.e., their deformation in general will have a large effect on the stress distribution in the system and its components and piping).
The minimum yield strength S, at various temper atures could be found in Tables 1-2.1, 1-2.2, and
Because large deformations always affect stress distribution, care should be exercised even when using the plastic analysis method in the methodology combination approved in Appendix F.  This is especially important for identifying buckling or instability problems when the change of geometry should be considered to avoid erroneous results.
1-13.3 of Appendix I to Section III and Table 3 of the latest accepted version 2 of Code Case 1644 for the design of Class 1 plate-and-shell-type component supports, but values for the ultimate tensile strength S. above room temperature are not listed in Section III. The interim methods proposed by this guide should therefore ble used to obtain values of Su at temperature in order to provide a safe design margin.


Rev. 2 of RG 1.130, Page 4
While NF-3222.3 and F-1323.1(a) of Section III
5.
permit the increase of allowable service limits under various loading conditions, F-1370(c) limits the in crease to two-thirds of the critical buckling strength of the component support at temperature. However, NF 3211 (d) and NB 3220 do not specify the percent age of critical buckling strength for level A service limits. Since buckling prevents "shake-down"
in a load-bearing member, it must be regarded as control ling for the level A service limits, and F-1370(c)
must be regarded as controlling for the level D serv ice limits. Also, buckling is the result of the interac tion of the configuration at the load-bearing member and its material properties (i.e., elastic modulus E
and minimum yield strength S,). Because both of these material properties change with temperature, the critical buckling stresses should be calculated
2 Regulatory Guide 1.85, "Code Case Acceptability-ASME Sec tion III Materials," provides guidance for the acceptability of ASME Section III Code Cases and their revisions, including Code Case 1644. Supplementary provisions for the use of specified code cases and their revisions may also be provided and should be considered when applicable.


Function of the Supported System In selecting the level of service limits for different loading combinations, the designer should take into account the function of the supported system.  To ensure that systems for which the normal function is to prevent or mitigate the consequences of events associated with an emergency or faulted plant condition [e.g., the function of the emergency core cooling system (ECCS) during faulted plant conditions] will operate properly regardless of plant condition, the use of ASME Code Section III level A
with the values of E and S, of the component support material at temperature.
or B service limits of Subsection NF (or other justifiable limits provided by the Code) is appropriate.


6.
Allowable service limits for bolted connections are derived on a different basis that varies with the size of the bolt. For this reason, the increases permitted by NF-3222.3 and F-1323. 1(a) of Section III are not directly applicable to bolts and bolted connections.


Deformation Limits Because component and piping supports are deformation-sensitive load-bearing elements, satisfying the service limits of Section III will not automatically ensure their proper function. If stated in the ASME Code design specification, deformation limits may be the controlling criterion.  By contrast, if a particular plant condition does not require the function of a component or piping support, the stresses or loads resulting from the loading combinations under the particular plant condition do not need to satisfy the design limits for the plant condition.
2. Design by Load Rating When load-rating methods are used, Subsection NF
and Appendix F of Section III do not provide a level D load rating. This guide provides an interim method for the determination of the load rating for level D
limits.


7.
3. Design by Experimental Stress Analysis While the collapse load for the experimental stress-analysis method is defined by 11-1430 in Ap pendix II to Section III, the design limits for the experimental-stress-analysis method for various operating condition categories are not delineated.


Definitions Design Condition.  The loading condition defined by NF-3112 of Section III of the ASME Boiler and Pressure Vessel Code.
This deficiency can be remedied by the interim method described in this guide.


Operating Condition Categories. Categories of design limits for component and piping supports defined by NF-3113 of Section III of the ASME Code.
4. Large Deformations The design of component supports is an integral part of the design of a system and its components. A
complete and consistent design is possible only when system/component/component-support interaction is properly considered. When all three are evaluated on an elastic basis, the interaction is usually valid be cause individual deformations are small. However, if plastic analysis methods are used in the design proc ess, large deformations that would result in substan tially different stress distributions may occur.


Plant Conditions.  Operating conditions of the plant categorized as normal, upset, emergency, and faulted plant conditions.
For the evaluation of the level D, service limits, Appendix F to Section III permits the use of plastic analysis methods in certain acceptable combinations for all three elements. These acceptable combinations are selected on the assumption that component sup ports are more deformation-sensitive (i.e., their de formation in general will have a large effect on the stress distribution in the system and its components). 
Since large deformations always affect stress dis tribution, care should be exercised even if the plastic analysis method is used in the Appendix-F-approved methodology combination. This is especially impor tant for identifying buckling or instability problems, where the change of geometry should be taken into account to avoid erroneous results.


Normal Plant Conditions. Those operating conditions that occur in the course of system startup, operation, hot standby, refueling, and shutdown, with the exception of upset, emergency, or faulted plant conditions.
5. Function of the Supported System In selecting the level of service limits for different loading combinations, the designer must take into ac count the function of the supported system. To ensure that systems whose normal function is to prevent or mitigate consequences of events associated with an emergency or faulted plant condition (e.g., the func
130-2 I
I
11


Upset Plant Conditions.  Those deviations from the normal plant condition that have a high probability of occurrence.
tion of ECCS during faulted plant conditions) will operate properly regardless of plant condition, the Code level A or B service limits of Subsection NF
(which are identical) or other justifiable limits pro vided by the Code should be used.


Emergency Plant Conditions. Those operating conditions that have a low probability of occurrence.
6. Deformation Limits Since component supports are deformation sensitive load-bearing elements, satisfying the serv ice limits of Section III will not automatically ensure their proper function. Deformation limits, if specified by the Code Design Specification, may be the con trolling criterion. On the other hand, if the function of a component support is not required for a particu lar plant condition, the stresses or loads resulting from the loading combinations under the particular plant condition do not need to satisfy the design lim its for the plant condition.


Faulted Plant Conditions. Those operating conditions associated with postulated events of extremely low probability.
7. Definitions Critical Buckling Strength. The strength at which lateral displacements start to develop simultaneously with in-plane or axial deformations.


Service Limits. Stress limits for the design of component and piping supports, defined by Subsection NF
Design Condition. The loading condition defined by NF-3112 of Section III of the ASME Boiler and Pressure Vessel Code.
of Section III of the ASME Boiler and Pressure Vessel Code.


Levels of Service Limits. Four levels of service limits  A, B, C, and D  defined by Section III of the ASME Boiler and Pressure Vessel Code for the design of loadings associated with different plant conditions for components and piping and component and piping supports in nuclear power plants.
Emergency Plant Condition. Those operating con ditions that have a low probability of occurrence.


Rev. 2 of RG 1.130, Page 5 Operating-Basis Earthquake (OBE).  Seismic event defined in Appendix A, Seismic and Geologic Siting Criteria for Nuclear Power Plants, to 10 CFR Part 100, Reactor Site Criteria.
Faulted Plant Condition. Those operating condi tions associated with postulated events of extremely low probability.


Safe-Shutdown Earthquake (SSE).  Seismic event defined in Appendix A to 10 CFR Part 100.
Levels of Service Limits. Four levels (A, B, C, and D) of service limits defined by Section III of the Code for the design of loadings associated with dif ferent plant conditions for components and compo nent supports in nuclear power plants.


Specified Seismic Events. Operating-Basis Earthquake (OBE) and Safe-Shutdown Earthquake (SSE),
Normal Plant Condition. Those operating condi tions in the course of system startup, operation, hot standby, refueling, and shutdown other than upset, emergency, or faulted plant conditions.
defined above.


System Mechanical Loadings. The static and dynamic loadings developed by the system operating parameters  including deadweight, pressure, and other external loadings  and effects resulting from constraints of free-end movements, but excluding effects resulting from thermal and peak stresses generated within the component support.
Operating Basis Earthquake (OBE). As defined in Appendix A "Seismic and Geologic Siting Criteria for Nuclear Power Plants,"' to 10 CFR Part 100,  
"Reactor Site Criteria."
Operating Condition Categories. Categories of de sign limits for component supports as defined by NF-3113 of Section III of the ASME Code.


Ultimate Tensile Strength. Material property based on the engineering stress-strain relationship.
Plant Conditions. Operating conditions of the plant categorized as normal, upset, emergency, and faulted
,plant conditions.


Critical Buckling Strength. The strength at which lateral displacements start to develop simultaneously with in-plane or axial deformations.
Safe Shutdown Earthquake (SSE). As defined in Appendix A to 10 CFR Part 100.


2 If the function of a component or piping support is not required during a plant condition, satisfaction of the design limits of the support for that plant condition is not needed, provided excessive deflections or failure of the support will not result in the loss of function of any other safety-related system.
Service Limits. Stress limits for the design of com ponent supports as defined by Subsection NF of Sec tion III.


3 System mechanical loadings include all non-self-limiting loadings and the effects resulting from constraints of free-end displacements, but not the effects resulting from thermal or peak stresses generated within the component or piping support.
Specified Seismic Events. Operating Basis Earth quake and Safe Shutdown Earthquake.


4 Because component and piping supports are deformation-sensitive in the performance of their service requirements, satisfying these limits does not ensure the fulfilling of their functional requirements.  Any deformation limits specified by the design specification may be controlling and should be satisfied.
System Mechanical Loadings. The static and dynamic loadings that are developed by the system operating parameters, including dead weight, pres sure, and other external loadings, but excluding ef fects resulting from constraints of free-end move ments and thermal and peak stresses.


5 Because the design of component and piping supports is an integral part of the design of the system and the component and piping, the designer should make sure that methods used for the analysis of the system, component and piping, and support are compatible. The designer of component and piping supports should consider large deformations in the system or components and piping.
Ultimate Tensile Strength. Material property based on engineering stress-strain relationship.


Rev. 2 of RG 1.130, Page 6
Upset Plant Condition. Those deviations from the normal plant condition that have a high probability of occurrence.


==C. REGULATORY POSITION==
==C. REGULATORY POSITION==
The construction of ASME Code Class 1 plate-and-shell-type component and piping supports, except snubbers, which this guide does not address, should follow the rules of Subsection NF of Section III of the Code, as supplemented by the following stipulations:2
ASME Code Class 1 plate-and-shell-type compo nent supports except snubbers, which are not ad dressed in this guide, should be constructed to the rules of Subsection NF of Section III of the Code, as supplemented by the following: 3
1.
1. The classification of component supports should, as a minimum, be the same as that of the supported components.
 
The classification of component and piping supports should, as a minimum, be the same as that of the supported components and piping.
 
2.
 
The critical buckling strength should always limit the service limits for component and piping supports designed by linear elastic analysis.  The calculation of critical buckling strength should use material at temperature properties.  Critical buckling stresses for service level A, B, C, and D
limits should be maintained in accordance with NF-3522, NF-3622 and F-1332.5 for loadings combined according to Regulatory Position 3 of this guide.  Service limits related to critical buckling strength should not increase unless the ASME Code specifically allows such an increase.
 
3.


For component and piping supports subjected to the combined loadings of (1) the vibratory motion of the OBE and (2) system mechanical loadings3 associated with either the ASME Code design condition or normal or upset plant conditions, the design approach should be as follows: 4,
2. Values of Su at temperature, when they are not listed in Section III, should be estimated by Method 1, Method 2, or Method 3, as described below, on an interim basis until Section III includes such values. Values of S, at temperature listed by Tables 1-2.1, 1-2.2, and 1-13.1 of Appendix I and Table 3 of the latest accepted version1 of Code Case
5 a.
1644 of Section III may be used for the interim calculation.


Supports designed by the linear elastic analysis method should not exceed (1) the service limits of NF-3522 and NF-3622 for design loadings and level A and B service limits and
a. Method 1. This method applies to component support materials whose values of ultimate tensile strength at temperature have not been tabulated by their manufacturers or are not available.
(2) Regulatory Position 2 of this guide.


b.
S,, = u S,,r Syr where S. = ultimate tensile strength at temperature t to be used to determine the design limits Sur = ultimate tensile strength at room tem perature tabulated in Section III, Ap pendix I, or the latest accpeted version'
of Code Case 1644
3 If the function of a component support is not required during a plant condition, the design limits of the support for that plant con dition need not be satisfied, provided excessive deflections or failure of the support will not result in the loss of function of any other safety-related system.


Supports designed by the load-rating method should not exceed the load rating for level A or level B limits of NF-3280 of Section III.
1.130-3


c.
Sy = minimum yield strength at temperature t tabulated in Section III, Appendix I, or the latest accepted version2 of Code Case 1644 Syr = minimum yield strength at room tem perature, tabulated in Section III, Ap pendix I, or the latest accepted version 2 of Code Case 1644.


Supports designed by the experimental stress analysis method should not exceed the test collapse load determined by II-1430 of Section III divided by 1.7.
b. Method 2. Since the listed values of Sm at temperature in Section III will always be less than one-third of the corresponding values of ultimate strength Su at temperature, S. at temperature may be approximated by the value of
3 Si at the same temperature.


Rev. 2 of RG 1.130, Page 7
c. Method 3. This method applies to component support materials whose values of ultimate strength Su at temperature are available as tabulated by their manufacturers.
4.


The design of component and piping supports subjected to the system mechanical loadings4 associated with the emergency plant condition should adhere to the following design limits, except when the normal function of the supported system is to prevent or mitigate the consequences of events associated with the emergency plant condition (Regulatory Position 6 then applies):5,6 a.
Su Sur Su , but not greater than Sur Stur where Su= ultimate tensile strength at temperature t to be used to determine the design limits Sur = ultimate tensile strength at room tem perature tabulated in Section III, Ap pendix 1, or the latest accepted version2 of Code Case 1644
§u = ultimate tensile strength at temperature t tabulated by manufacturers in their catalogs or other publications Sur = ultimate tensile strength at room tem perature tabulated by manufacturers in the same publications.


Supports designed by the linear elastic analysis method should not exceed the service limits of NF-3522 and NF-3622 of Section III and Regulatory Position 2.
3. Service limits for component supports designed by linear elastic analysis should always be limited by the critical buckling strength. The critical buckling strength should be calculated using material at tem perature properties. A design margin of 2 for flat plates and 3 for shells should be maintained for loadings combined according to Regulatory Position  
4 of this guide. Service limits related to critical buckling strength should not be increased unless the Code specifically allows such an increase.


b.
4. Component supports subjected to the combined loadings of (a) the vibratory motion of the OBE and (b) system mechanical loadings4 associated with either (a) the Code design condition or (b) normal or
4 System mechanical loadings include all non-self-limiting load ings and do not include effects resulting from constraints of free end displacements and thermal or peak stresses.


Supports designed by the load-rating method should not exceed the load rating for level C limits of NF-3280 of Section III.
5Since component supports are deformation-sensitive in the per formance of their service requirements, satisfying these limits does not ensure the fulfilling of their functional requirements.


c.
Any deformation limits specified by the design specification may be controlling and should be satisfied.


Supports designed by the experimental stress analysis method should not exceed the test collapse load determined by II-1430 of Section III and divided by 1.3.
upset plant conditions should be designed as follows. 5-6 a. The service limits of (1) NF-3221.1 and NF
3221.2 for design loadings, (2) NF-3222 for level A
service limits, and (3) Regulatory .Position 3 of this guide should not be exceeded for component supports designed by the linear-elastic-analysis method.


5.
b. The load rating for level A limits or level B
limits of NF-3262.2 of Section III should not be ex ceeded for component supports designed by the load-rating method.


The design of component and piping supports subjected to the combined loadings of (1) the vibratory motion of the SSE, (2) the system mechanical loadings4 associated with the normal plant condition, and (3) the dynamic system loadings associated with the faulted plant condition should adhere to the following design limits, except when the normal function of the supported system is to prevent or mitigate the consequences of events associated with the faulted plant condition (Regulatory Position 6 then applies):5,6 a.
c. The collapse load determined by 11-1400 of Section III divided by 1.7 should not be exceeded for component supports designed by the experimental stress-analysis method.


Supports designed by the linear elastic analysis method should not exceed the service limits of F-1332 of Section III.
5. Component supports subjected to the system mechanical loadings4 associated with the emergency plant condition should be designed within the fol lowing design limits except when the normal function of the supported system is to prevent or mitigate the consequences of events associated with the emer gency plant condition (at which time Regulatory Po sition 7 applies):5"'
a. The service limits of NF-3224 of Section III  
and Regulatory Position 3 should not be exceeded for component supports designed by the linear-elastic analysis method.


b.
b. The load rating for level C limits of NF
3262.2 of Section III should not be exceeded for component supports designed by the load-rating method.


Supports designed by the load-rating method should not exceed the value of TL x 0.7 Su/Su
c. The collapse load determined by 11-1400 of Section III and divided by 1.3 should not be exceeded for component supports designed by the experimental-stress-analysis method.
*, where TL and Su* are defined according to F-1332.7 of Section III and Su is the ultimate tensile strength of the material at service temperature.


c.
6. Component supports subjected to the combined loadings of (a) the vibratory motion of SSE and (b)
the system mechanical loadings 4 associated with the normal plant condition and (c) the dynamic system loadings associated with the faulted plant condition should be designed within the following design limits except when the normal function of the supported system is to prevent or mitigate the consequences of events associated with the faulted plant condition (at which time Regulatory Position 7 applies):.5 a. The service limits of F-1323.1(a) and F-1370(c) of Section III should not be exceeded for
6Since the design of component supports is an integral part of the design of the system and the design of the component, the de signer must make sure that methods used for the analysis of the system, component, and component support are compatible (see Table F-1322.2-1 of Appendix F to Section I11). Large deforma tions in the system or components should be considered in the design of component supports.


Supports designed by the experimental stress analysis method should not exceed the test collapse load determined by II-1430.
1.130-4
11
11


d.
component supports designed by the linear-elastic analysis method.


If plastic methods are used for the design of supports, the combined loadings of Regulatory Position 5 should include loads such as constraints of free-end displacements.
b. The value of T.L. x 0.7 -&- should not be SI'
exceeded, where T.L. and Su are defined according to NF-3262.1 of Section III and S§, is the ultimate tensile strength of the material at service temperature for component supports designed by the load-rating method.


The design should not exceed the service limits of F-1340 of Section III.
c. The collapse load determined by 11-1400 and divided by 1.1 should not be exceeded for component supports designed by the experimental-stress-analysis method.


6.
d. If plastic methods are used for the design of component supports, the combined loadings of Reg ulatory Position 6 should include all loads such as thermal loads and constraints of free displacements, which contribute to expansion stress intensities, and the service limits of F-1324 and F-1370(c) of Sec tion III should not be exceeded.


The design of component and piping supports in systems for which the normal function is to prevent or mitigate the consequences of events associated with an emergency or faulted plant condition should adhere to the limits described in Regulatory Position 3 or other justifiable limits such as the level C or level D service limits provided by the ASME Code. The design specification should define these limits so that the function of the supported system will be maintained when the supports are subjected to the loading combinations described in Regulatory Positions 4 and 5.
7. Component supports in systems whose normal function is to prevent or mitigate the consequences of events associated with an emergency or faulted plant condition should be designed within the limits de scribed in Regulatory Position 4 or other justifiable limits such as the level C or level D service limits provided by the Code. These limits should be defined by the design specification so that the function of the supported system will be maintained when the sup ports are subjected to the loading combinations de scribed in Regulatory Positions 5 and 6.
 
Rev. 2 of RG 1.130, Page 8


==D. IMPLEMENTATION==
==D. IMPLEMENTATION==
The purpose of this section is to provide information to licensees regarding the NRC staffs plans for using this regulatory guide.  No backfitting is intended or approved in connection with the issuance of this guide.
The purpose of this section is to provide guidance to applicants and licensees regarding the NRC staff's plans for using this regulatory guide.
 
Except in those cases in which a licensee proposes or has previously established an acceptable alternative method for complying with specified portions of the NRCs regulations, the NRC staff will use the methods described in this guide to evaluate (1) submittals in connection with applications for construction permits, standard plant design certifications, operating licenses, early site permits, and combined licenses; and (2) submittals from operating reactor licensees who voluntarily propose to initiate system modifications that have a clear nexus with the subject for which guidance is provided herein.
 
REGULATORY ANALYSIS / BACKFIT ANALYSIS
The regulatory analysis and backfit analysis for this regulatory guide are available in Draft Regulatory Guide DG-1169, Service Limits and Loading Combinations for Class 1 Plate-and-Shell- Type Component Supports (Ref. 4).  The NRC issued DG-1169 in October 2006 to solicit public comment on the draft of this Revision 2 of Regulatory Guide 1.130.
 
6 All NRC regulations listed herein are available electronically through the Public Electronic Reading Room on the NRCs public Web site, at http://www.nrc.gov/reading-rm/doc-collections/cfr/.  Copies are also available for inspection or copying for a fee from the NRCs Public Document Room at 11555 Rockville Pike, Rockville, MD; the PDRs mailing address is USNRC PDR, Washington, DC 20555; telephone (301) 415-4737 or (800) 397-4209; fax (301)
415-3548; email PDR@nrc.gov.
 
7 Copies may be purchased from the American Society of Mechanical Engineers, Three Park Avenue, NewYork, NY
10016-5990; phone (212) 591-8500; fax (212) 591-8501; www.asme.org.
 
8 All regulatory guides listed herein were published by the U.S. Nuclear Regulatory Commission.  Where an accession number is identified, the specified regulatory guide is available electronically through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html.  All other regulatory guides are available electronically through the Public Electronic Reading Room on the NRCs public Web site, at http://www.nrc.gov/reading-rm/doc-collections/reg-guides/.  Single copies of regulatory guides may also be obtained free of charge by writing the Reproduction and Distribution Services Section, ADM, USNRC, Washington, DC 20555-0001, or by fax to (301) 415-2289, or by email to DISTRIBUTION@nrc.gov.  Active guides may also be purchased from the National Technical Information Service (NTIS) on a standing order basis.  Details on this service may be obtained by contacting NTIS at 5285 Port Royal Road, Springfield, Virginia 22161, online at http://www.ntis.gov, by telephone at (800) 553-NTIS (6847) or (703) 605-6000, or by fax to (703) 605-6900.  Copies are also available for inspection or copying for a fee from the NRCs Public Document Room (PDR), which is located at 11555 Rockville Pike, Rockville, Maryland; the PDRs mailing address is USNRC PDR, Washington, DC 20555-
0001.  The PDR can also be reached by telephone at (301) 415-4737 or (800) 397-4209, by fax at (301) 415-3548, and by email to PDR@nrc.gov.
 
9 Draft Regulatory Guide DG-1169 is available electronically under Accession #ML063000484 in the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html.
 
Copies are also available for inspection or copying for a fee from the NRCs Public Document Room (PDR), which is located at 11555 Rockville Pike, Rockville Maryland; the PDRs mailing address is USNRC PDR, Washington, DC
20555-0001.  The PDR can also be reached by telephone at (301) 415-4737 or (800) 397-4209, by fax at (301) 415-3548, and by email to PDR@nrc.gov.
 
Rev. 2 of RG 1.130, Page 9 REFERENCES
1.
 
U.S. Code of Federal Regulations, Title 10, Energy, Part 50, Domestic Licensing of Production and Utilization Facilities.6
2.
 
ASME Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Power Plant Components, Division I, 2001 Edition through the 2003 Addenda, American Society of Mechanical Engineers, New York, NY, 1992.7
3.


Regulatory Guide 1.84, Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, U.S. Nuclear Regulatory Commission, Washington, DC.8
Except in those cases in whicih the applicant pro poses an acceptable alternative method for complying with the specified portions of the Commission's reg ulations, the method described herein will be used in the evaluation of submittals for construction permit applications docketed after October 31, 1978. If an applicant wishes to use this regulatory guide in de veloping submittals for construction permit applica tions docketed on or before October 31,  
4.
1978, the pertinent portions of the application will be evaluated on the basis of this guide.


Draft Regulatory Guide DG-1169, Service Limits and Loading Combinations for Class 1 Plate- and-Shell-Type Component Supports, U.S. Nuclear Regulatory Commission, Washington, DC.9}}
1.130-5}}


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Latest revision as of 02:07, 17 January 2025

Service Limits & Loading Combinations for Class 1 Plate-And-Shell-Type Component Supports
ML003740123
Person / Time
Issue date: 10/31/1978
From:
Office of Nuclear Regulatory Research
To:
References
RG-1.130, Revision 1
Download: ML003740123 (5)


U.S. NUCLEAR REGULATORY COMMISSION

Revision 1 October 1978 REGULATORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

Regulatory Guide 1.130

SERVICE LIMITS AND LOADING COMBINATIONS

FOR CLASS 1 PLATE-AND-SHELL-TYPE COMPONENT SUPPORTS

  • 1

A. INTRODUCTION

General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena," of Appen dix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," requires that the design bases for structures, systems, and compo nents important to safety reflect appropriate combi nations of the effects of normal and accident condi tions with the effects of natural phenomena such as earthquakes. The failure of members designed to support safety-related components could jeopardize the ability of the supported component to perform its safety function.

This guide delineates acceptable levels of service limits and appropriate combinations of loadings as sociated with normal operation, postulated accidents, and specified seismic events for the design of Class 1 plate-and-shell-type component supports as defined in Subsection NF of Section III of the American So ciety of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. 1 This guide applies to light water-cooled reactors.

The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.

B. DISCUSSION

Load-bearing members classified as component supports are essential to the safety of nuclear power

  • Lines indicate substantive changes from previous issue.

American Society of Mechanical Engineers Boiler and Pressure Vessel Codes Section 111, Division 1, 1977 Edition, including the

1977 Winter Addenda thereto. Copies of the Code may be ob tained from the American Society of Mechanical Engineers, United Engineering Center, 345 East 47th Street, New York, N.Y. 10017.

plants because they retain components in place during loadings associated with normal and upset plant con ditions under the stress of specified seismic events, thereby permitting system components to function properly. They also prevent excessive component movement during the loadings associated with emer gency and faulted plant conditions combined with a specified seismic event or other natural phenomena, thereby helping to mitigate system damage. Compo nent supports are deformation-sensitive because large deformations in component supports may signifi cantly change the stress distribution in the support system and its components.

In order to provide a consistent level of safety, the ASME Boiler and Pressure Vessel Code classifica tion for component supports should, as a minimum, be the same as that of the supported components.

This guide delineates levels of service limits and loading combinations, as well as supplementary criteria, for Class 1 plate-and-shell-type component supports as defined by NF-1212 of Section III of the Code. Snubbers are not addressed in this guide.

Subsection NF of Section III permits the use of three methods for the design of Class I plate-and shell-type component supports: (1) linear elastic analysis, (2) load rating, and (3) experimental stress analysis. For each method, the ASME Code de lineates allowable stress or loading limits for various Code service levels, as defined by NF-3113 and NCA-2142.2(b) of Section III, so that these limits can be used in conjunction with the resultant loadings or stresses from the appropriate plant conditions.

Since the Code does not specify loading combina tions, guidance is needed to provide a consistent basis for the design of component supports.

Component supports considered in this guide are located within Seismic Category I structures and are USNRC REGULATORY GUIDES

Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C. 20556, Attention: Docketing and Regulatory Guides are issued to describe and make available to the public Service Branch.

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 broad divisions:

ating specific problems or postulated accidents, or to provide guidance to applicants. Regulatory Guides are not substitutes for regulations, and corn-

1. Power Reactors

6. Products pliance with them is not required. Methods and solutions different from those

2. Research and Test Reactors

7. Transportation set out in the guides will be acceptable if they provide a basis for the findings

3. Fuels and Materials Facilities

8. Occupational Health requisite to the issuance or continuance of a permit or license by the

4. Environmental and Siting

9. Antitrust and Financial Review Commission.

5. Materials and Plant Protection

10. General Requests for single copies of issued guides lwhich may tIe reproduced) or for Comments and suggestions for improvements in these guides are encouraged at placement on an automatic distribution list for single copies of future guides all times, and guides will be revised, as appropriate, to accommodate comments in specific divisions should be made in writing to the U.S. Nuclear Regulatory and to reflect new information or experience. This guide was revised as a result Commission, Washington, D.C. 20565, Attention: Director, Division of of substantive comments received from the public and additional staff review.

Technical Information and Document Control.

therefore assumed to be protected against loadings from natural phenomena or man-made hazards other than the specified seismic events. Thus only the specified seismic events need to be considered in combination with the loadings associated with plant conditions to develop appropriate loading combina tions. When loadings caused by natural phenomena other than seismic events, such as the subsidence of the land surface as a result of large-scale ground water withdrawals exist, they should be specified in the Design Specification, and the loading combina tions reflecting the inclusion of these loadings should be reviewed.

1. Design by Linear Elastic Analysis When the linear-elastic-analysis method is used to design Class I plate-and-shell-type component sup ports, material properties are given by Tables I-I. 1,

1-1.2, and 1-11.1 of Appendix I to Section III and Table I of the latest accepted version 2 of Code Case

1644. These tables list values for the design stress intensity Sm at various temperature

s. Yet level D

service limits are determined by S., Sy, and S.. The load-rating method also requires the use of Su.

The minimum yield strength S, at various temper atures could be found in Tables 1-2.1, 1-2.2, and

1-13.3 of Appendix I to Section III and Table 3 of the latest accepted version 2 of Code Case 1644 for the design of Class 1 plate-and-shell-type component supports, but values for the ultimate tensile strength S. above room temperature are not listed in Section III. The interim methods proposed by this guide should therefore ble used to obtain values of Su at temperature in order to provide a safe design margin.

While NF-3222.3 and F-1323.1(a) of Section III

permit the increase of allowable service limits under various loading conditions, F-1370(c) limits the in crease to two-thirds of the critical buckling strength of the component support at temperature. However, NF 3211 (d) and NB 3220 do not specify the percent age of critical buckling strength for level A service limits. Since buckling prevents "shake-down"

in a load-bearing member, it must be regarded as control ling for the level A service limits, and F-1370(c)

must be regarded as controlling for the level D serv ice limits. Also, buckling is the result of the interac tion of the configuration at the load-bearing member and its material properties (i.e., elastic modulus E

and minimum yield strength S,). Because both of these material properties change with temperature, the critical buckling stresses should be calculated

2 Regulatory Guide 1.85, "Code Case Acceptability-ASME Sec tion III Materials," provides guidance for the acceptability of ASME Section III Code Cases and their revisions, including Code Case 1644. Supplementary provisions for the use of specified code cases and their revisions may also be provided and should be considered when applicable.

with the values of E and S, of the component support material at temperature.

Allowable service limits for bolted connections are derived on a different basis that varies with the size of the bolt. For this reason, the increases permitted by NF-3222.3 and F-1323. 1(a) of Section III are not directly applicable to bolts and bolted connections.

2. Design by Load Rating When load-rating methods are used, Subsection NF

and Appendix F of Section III do not provide a level D load rating. This guide provides an interim method for the determination of the load rating for level D

limits.

3. Design by Experimental Stress Analysis While the collapse load for the experimental stress-analysis method is defined by 11-1430 in Ap pendix II to Section III, the design limits for the experimental-stress-analysis method for various operating condition categories are not delineated.

This deficiency can be remedied by the interim method described in this guide.

4. Large Deformations The design of component supports is an integral part of the design of a system and its components. A

complete and consistent design is possible only when system/component/component-support interaction is properly considered. When all three are evaluated on an elastic basis, the interaction is usually valid be cause individual deformations are small. However, if plastic analysis methods are used in the design proc ess, large deformations that would result in substan tially different stress distributions may occur.

For the evaluation of the level D, service limits, Appendix F to Section III permits the use of plastic analysis methods in certain acceptable combinations for all three elements. These acceptable combinations are selected on the assumption that component sup ports are more deformation-sensitive (i.e., their de formation in general will have a large effect on the stress distribution in the system and its components).

Since large deformations always affect stress dis tribution, care should be exercised even if the plastic analysis method is used in the Appendix-F-approved methodology combination. This is especially impor tant for identifying buckling or instability problems, where the change of geometry should be taken into account to avoid erroneous results.

5. Function of the Supported System In selecting the level of service limits for different loading combinations, the designer must take into ac count the function of the supported system. To ensure that systems whose normal function is to prevent or mitigate consequences of events associated with an emergency or faulted plant condition (e.g., the func

130-2 I

I

11

tion of ECCS during faulted plant conditions) will operate properly regardless of plant condition, the Code level A or B service limits of Subsection NF

(which are identical) or other justifiable limits pro vided by the Code should be used.

6. Deformation Limits Since component supports are deformation sensitive load-bearing elements, satisfying the serv ice limits of Section III will not automatically ensure their proper function. Deformation limits, if specified by the Code Design Specification, may be the con trolling criterion. On the other hand, if the function of a component support is not required for a particu lar plant condition, the stresses or loads resulting from the loading combinations under the particular plant condition do not need to satisfy the design lim its for the plant condition.

7. Definitions Critical Buckling Strength. The strength at which lateral displacements start to develop simultaneously with in-plane or axial deformations.

Design Condition. The loading condition defined by NF-3112 of Section III of the ASME Boiler and Pressure Vessel Code.

Emergency Plant Condition. Those operating con ditions that have a low probability of occurrence.

Faulted Plant Condition. Those operating condi tions associated with postulated events of extremely low probability.

Levels of Service Limits. Four levels (A, B, C, and D) of service limits defined by Section III of the Code for the design of loadings associated with dif ferent plant conditions for components and compo nent supports in nuclear power plants.

Normal Plant Condition. Those operating condi tions in the course of system startup, operation, hot standby, refueling, and shutdown other than upset, emergency, or faulted plant conditions.

Operating Basis Earthquake (OBE). As defined in Appendix A "Seismic and Geologic Siting Criteria for Nuclear Power Plants,"' to 10 CFR Part 100,

"Reactor Site Criteria."

Operating Condition Categories. Categories of de sign limits for component supports as defined by NF-3113 of Section III of the ASME Code.

Plant Conditions. Operating conditions of the plant categorized as normal, upset, emergency, and faulted

,plant conditions.

Safe Shutdown Earthquake (SSE). As defined in Appendix A to 10 CFR Part 100.

Service Limits. Stress limits for the design of com ponent supports as defined by Subsection NF of Sec tion III.

Specified Seismic Events. Operating Basis Earth quake and Safe Shutdown Earthquake.

System Mechanical Loadings. The static and dynamic loadings that are developed by the system operating parameters, including dead weight, pres sure, and other external loadings, but excluding ef fects resulting from constraints of free-end move ments and thermal and peak stresses.

Ultimate Tensile Strength. Material property based on engineering stress-strain relationship.

Upset Plant Condition. Those deviations from the normal plant condition that have a high probability of occurrence.

C. REGULATORY POSITION

ASME Code Class 1 plate-and-shell-type compo nent supports except snubbers, which are not ad dressed in this guide, should be constructed to the rules of Subsection NF of Section III of the Code, as supplemented by the following: 3

1. The classification of component supports should, as a minimum, be the same as that of the supported components.

2. Values of Su at temperature, when they are not listed in Section III, should be estimated by Method 1, Method 2, or Method 3, as described below, on an interim basis until Section III includes such values. Values of S, at temperature listed by Tables 1-2.1, 1-2.2, and 1-13.1 of Appendix I and Table 3 of the latest accepted version1 of Code Case

1644 of Section III may be used for the interim calculation.

a. Method 1. This method applies to component support materials whose values of ultimate tensile strength at temperature have not been tabulated by their manufacturers or are not available.

S,, = u S,,r Syr where S. = ultimate tensile strength at temperature t to be used to determine the design limits Sur = ultimate tensile strength at room tem perature tabulated in Section III, Ap pendix I, or the latest accpeted version'

of Code Case 1644

3 If the function of a component support is not required during a plant condition, the design limits of the support for that plant con dition need not be satisfied, provided excessive deflections or failure of the support will not result in the loss of function of any other safety-related system.

1.130-3

Sy = minimum yield strength at temperature t tabulated in Section III, Appendix I, or the latest accepted version2 of Code Case 1644 Syr = minimum yield strength at room tem perature, tabulated in Section III, Ap pendix I, or the latest accepted version 2 of Code Case 1644.

b. Method 2. Since the listed values of Sm at temperature in Section III will always be less than one-third of the corresponding values of ultimate strength Su at temperature, S. at temperature may be approximated by the value of

3 Si at the same temperature.

c. Method 3. This method applies to component support materials whose values of ultimate strength Su at temperature are available as tabulated by their manufacturers.

Su Sur Su , but not greater than Sur Stur where Su= ultimate tensile strength at temperature t to be used to determine the design limits Sur = ultimate tensile strength at room tem perature tabulated in Section III, Ap pendix 1, or the latest accepted version2 of Code Case 1644

§u = ultimate tensile strength at temperature t tabulated by manufacturers in their catalogs or other publications Sur = ultimate tensile strength at room tem perature tabulated by manufacturers in the same publications.

3. Service limits for component supports designed by linear elastic analysis should always be limited by the critical buckling strength. The critical buckling strength should be calculated using material at tem perature properties. A design margin of 2 for flat plates and 3 for shells should be maintained for loadings combined according to Regulatory Position

4 of this guide. Service limits related to critical buckling strength should not be increased unless the Code specifically allows such an increase.

4. Component supports subjected to the combined loadings of (a) the vibratory motion of the OBE and (b) system mechanical loadings4 associated with either (a) the Code design condition or (b) normal or

4 System mechanical loadings include all non-self-limiting load ings and do not include effects resulting from constraints of free end displacements and thermal or peak stresses.

5Since component supports are deformation-sensitive in the per formance of their service requirements, satisfying these limits does not ensure the fulfilling of their functional requirements.

Any deformation limits specified by the design specification may be controlling and should be satisfied.

upset plant conditions should be designed as follows. 5-6 a. The service limits of (1) NF-3221.1 and NF

3221.2 for design loadings, (2) NF-3222 for level A

service limits, and (3) Regulatory .Position 3 of this guide should not be exceeded for component supports designed by the linear-elastic-analysis method.

b. The load rating for level A limits or level B

limits of NF-3262.2 of Section III should not be ex ceeded for component supports designed by the load-rating method.

c. The collapse load determined by 11-1400 of Section III divided by 1.7 should not be exceeded for component supports designed by the experimental stress-analysis method.

5. Component supports subjected to the system mechanical loadings4 associated with the emergency plant condition should be designed within the fol lowing design limits except when the normal function of the supported system is to prevent or mitigate the consequences of events associated with the emer gency plant condition (at which time Regulatory Po sition 7 applies):5"'

a. The service limits of NF-3224 of Section III

and Regulatory Position 3 should not be exceeded for component supports designed by the linear-elastic analysis method.

b. The load rating for level C limits of NF

3262.2 of Section III should not be exceeded for component supports designed by the load-rating method.

c. The collapse load determined by 11-1400 of Section III and divided by 1.3 should not be exceeded for component supports designed by the experimental-stress-analysis method.

6. Component supports subjected to the combined loadings of (a) the vibratory motion of SSE and (b)

the system mechanical loadings 4 associated with the normal plant condition and (c) the dynamic system loadings associated with the faulted plant condition should be designed within the following design limits except when the normal function of the supported system is to prevent or mitigate the consequences of events associated with the faulted plant condition (at which time Regulatory Position 7 applies):.5 a. The service limits of F-1323.1(a) and F-1370(c) of Section III should not be exceeded for

6Since the design of component supports is an integral part of the design of the system and the design of the component, the de signer must make sure that methods used for the analysis of the system, component, and component support are compatible (see Table F-1322.2-1 of Appendix F to Section I11). Large deforma tions in the system or components should be considered in the design of component supports.

1.130-4

11

11

component supports designed by the linear-elastic analysis method.

b. The value of T.L. x 0.7 -&- should not be SI'

exceeded, where T.L. and Su are defined according to NF-3262.1 of Section III and S§, is the ultimate tensile strength of the material at service temperature for component supports designed by the load-rating method.

c. The collapse load determined by 11-1400 and divided by 1.1 should not be exceeded for component supports designed by the experimental-stress-analysis method.

d. If plastic methods are used for the design of component supports, the combined loadings of Reg ulatory Position 6 should include all loads such as thermal loads and constraints of free displacements, which contribute to expansion stress intensities, and the service limits of F-1324 and F-1370(c) of Sec tion III should not be exceeded.

7. Component supports in systems whose normal function is to prevent or mitigate the consequences of events associated with an emergency or faulted plant condition should be designed within the limits de scribed in Regulatory Position 4 or other justifiable limits such as the level C or level D service limits provided by the Code. These limits should be defined by the design specification so that the function of the supported system will be maintained when the sup ports are subjected to the loading combinations de scribed in Regulatory Positions 5 and 6.

D. IMPLEMENTATION

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

Except in those cases in whicih the applicant pro poses an acceptable alternative method for complying with the specified portions of the Commission's reg ulations, the method described herein will be used in the evaluation of submittals for construction permit applications docketed after October 31, 1978. If an applicant wishes to use this regulatory guide in de veloping submittals for construction permit applica tions docketed on or before October 31,

1978, the pertinent portions of the application will be evaluated on the basis of this guide.

1.130-5