Regulatory Guide 1.130: Difference between revisions

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{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION                                                                                                                               July 1977 REGULATORY GUIDE
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION
                                        OFFICE OF STANDARDS DEVELOPMENT
July 1977 REGULATORY GUIDE
                                                                        REGULATORY GUIDE 1.130
OFFICE OF STANDARDS DEVELOPMENT
                                                DESIGN LIMITS AND LOADING COMBINATIONS
REGULATORY GUIDE 1.130
                                                          FOR CLASS I PLATE-AND-SHELL-TYPE
DESIGN LIMITS AND  
                                                                          COMPONENT SUPPORTS
LOADING COMBINATIONS
FOR CLASS I PLATE-AND-SHELL-TYPE
COMPONENT SUPPORTS


==A. INTRODUCTION==
==A. INTRODUCTION==
conditions under the stress of specified seismic events, thereby permitting system components to General Design Criterion 2, "Design Bases for                                             function properly. They also prevent excessive corn- Protection Against Natural Phenomena," of Appen-                                               ponent movement during the loadings associated dix A, "General Design Criteria for Nuclear Power                                             with emergency and faulted plant conditions corn- Plants," to 10 CFR Part 50, "Licensing of Produc-                                             bined with a specified seismic eventvor other natural tion and Utilization Facilities," requires that the                                           phenomena, thereby helping ,t0:t mitigate system design bases for structures, systems, and components                                           damage. Component supports: are 'deformation- important to safety reflect appropriate combinations                                           sensitive because large deformations in component of the effects of normal and accident conditions with                                         supports may significantly"change the stress distribu- the effects of natural phenomena such as earth-                                               tion in the support, system and its 'components.
conditions under the stress of specified seismic events, thereby permitting system components to General Design Criterion 2, "Design Bases for function properly. They also prevent excessive corn- Protection Against Natural Phenomena," of Appen- ponent movement during the loadings associated dix A, "General Design Criteria for Nuclear Power with emergency and faulted plant conditions corn- Plants," to 10 CFR Part 50, "Licensing of Produc- bined with a specified seismic eventvor other natural tion and Utilization Facilities," requires that the phenomena, thereby helping ,t0:t mitigate system design bases for structures, systems, and components damage. Component supports: are 'deformation- important to safety reflect appropriate combinations sensitive because large deformations in component of the effects of normal and accident conditions with supports may significantly"change the stress distribu- the effects of natural phenomena such as earth- tion in the support, system and its 'components.


quakes. The failure of members designed to support safety-related components could jeopardize the                                                       NF- 1122 and NA-21346 f Section 111 of the ASME
quakes. The failure of members designed to support safety-related components could jeopardize the NF- 1122 and NA-21346 f Section 111 of the ASME
ability of the supported component to perform its                                             Boiler and:?resure Vesel Code imply that the clas- safety function.                                                                              sification' §6-f ;omp6nent supports should, as a limt a      miniium ebe                          the~same as that of the supported com- This guide delineates acceptable design limits and                                        pon  ,eroibti. Th'is should be considered as a requirement.
ability of the supported component to perform its Boiler and :?resure Vesel Code imply that the clas- safety function.


appropriate combinations of loadings associated with i*:i*`Z_1hisi!gdidle                        r                    e di    delineates design limits and loading corn- normal operation, postulated accidents, and specified "ib.i'ition s, in addition to supplementary criteria, for seismic events for the design of Class I pla-I'iiid.                                          'lass I plate-and-shell-type component supports as shell-type component supports as defined in                                                    d~fined by NF-1212 of Section II1. Snubbers installed desec tion NF of Section III of the America,:.'Socic*. of.02 for protection against seismic or dynamic loadings of Mechanical Engineers (ASME) Boilq,,;'and Prri                                                  other origins are not addressed in this guide.
sification' §6-f ;omp6nent supports should, as a limt a
miniium ebe the~same as that of the supported com- This guide delineates acceptable design limits and pon
,eroibti.


Vessel Code.' This guide applies to lighti-water"ooled reactors.                                                            '        ,
Th'is should be considered as a requirement.
                                B. DIPSIO
                                                                                              three methods for the design of Class I plate-and-
                                            *._ýSIO                                          shell-type component supports: (1) linear elastic Load-bearing menil                            uassified as component                      analysis, (2) load rating, and (3) experimental stress supports are                              t'    c sUety of nuclear power                      analysis. For each method, the ASME Code plants becau they                          air. ompon**n ts in place dur-                    delineates allowable stress or loading limits for s                                                                        various Code service level limits, as defined by NF-
ing a                 sa        cia" with normal and upset plant
                                                                                              3113 of Section III, so that these limits can be used in IAmen                  icity ~IcchanicaI Engineers Boiler and Pressure                      conjunction with the resultant loadings or stresses Vessel Co            Section ItI, Division 1. 1974 Edition, including the                    from the appropriate plant condition


====s. Since the====
appropriate combinations of loadings associated with r
1974 Wintc              ddenda thereto. Copies or the Code may be ob- tained from the American Society of Mechanical Engineers,                                     Code does not specify loading combinations, United Engineering Center. 345 East 47th Street, New York. N.Y.                              guidance is needed to provide a consistent basis for
e di i*:i*`Z_1hisi!gdidle delineates design limits and loading corn- normal operation, postulated accidents, and specified "ib.i'ition s, in addition to supplementary criteria, for seismic events for the design of Class I pla-I'iiid.
10017.                                                                                        the design of component supports.


USN RC REG ULA TORY G UIDES                                          Co,,,m-         'p, id h,
'lass I plate-and-shell-type component supports as shell-type component supports as defined in desec d~fined by NF-1212 of Section II1. Snubbers installed tion NF of Section III of the America,:.'Socic*. of.02 for protection against seismic or dynamic loadings of Mechanical Engineers (ASME) Boilq,,;'and Prri other origins are not addressed in this guide.
                                                                                                            1,t%                      ,,-r
                                                                                                                                        - 1 to I',   ,,  .(t r,.,,,v ,t tIN. C,               a ,',.u:.; N.


,,,,,,,ww                    ,, it,,
Vessel Code.' This guide applies to lighti-water"ooled reactors.
  R egulaltio y G u iJes ate l  isw ed to describe ari ,natlt available to the tiublic m ethods  latriry C o m inlh.. $1Ol .                 rniir ,
                                                                                                                                                  n    D C '. - 7 7 Wv.,r A ii~r        lt,,,rr l ri.  'Iirv) ..,Stl                "
  accCptalltle to the NRC stall at implleenhln(g **ecilc parts of the Commission's              W-r'h.


egulalti tns. to delineate technrta le,$usedJ h the staff in evalualing specific tproblem %  The tuirh-              isculii rt i
'
                                                                                                                  .i', ks.,41              r hr      i  .l t[b',Ir lt,    *Iiv.....'..
,
  or postulated accidents. or to iprovide guidiance to applicant$. nfjijulmaly Guides ate no l substitute% for regulalion $0and comnpliince with them ,s nut rrs uired.              1. Plvi%*    Al    .ic  tIor                                          G tr,,to..l Methods anti solutions different ftrm those set Out in the guides will be accetl.            2.  Aeaorch a*dl Tint R-y,'nS                                          7. Tr.Iait,4.iiitIiimi able it lhey trovide a 11.bis fot the findings requisite to the issuance or conlittuance      3,  Fuels anti hlat..riAs Frcililei,                                   8. Occiplalruail i)lAtih Of i Pcermilt Of license hy the Comm ission.                                                 4.  Env lrr*nmrnrfri      t , ,rin Stirng                            9. Aii        rlritiR awvur "
B. DIPSIO
                                                                                                5.   Material* and Planrt i'r*illt                                          G ,ril
*._ýSIO
                                                                                                                                                                        1rn *0O.
Load-bearing menil uassified as component supports are t '  
c sUety of nuclear power plants becau they air. ompon**n ts in place dur- ing a
sa s
cia"
with normal and upset plant IAmen icity
~IcchanicaI Engineers Boiler and Pressure Vessel Co Section ItI, Division 1. 1974 Edition, including the
1974 Wintc ddenda thereto. Copies or the Code may be ob- tained from the American Society of Mechanical Engineers, United Engineering Center. 345 East 47th Street, New York. N.Y.


Comments and Sug-estions for irmp~rovement% ir% these guides ire encouglied at all times, a nd guides will be revisedl iat ali roorirate, to accommodate comments and            Reou-.sis          *ia-qfel*o cnpimii ,, in rsui        tafi hofust          ih TIvIv..011ýria~iV
10017.
                                                                                                                                                                                        1W                    W fill iitII:. "
  to re lecIe new information of exrw ience.        Hnwev'r. com m ents on this guid ei, I    ,'ient or, ai, auto .atlic unI $t1ii l                        hiafor sirlrlr cu
                                                                                                                                                          #oil                  " 11it! i l lt U'v    ri .d. in          ltwIi le- ecerveet within aboul It o months ,afterits issu lince.will ti- ptarticullarl y ais lul in  dlvision%shoul              firiii. rrle      in i tinr      it)t til hl! .' . N -l.l., Dtei.Ii.itory C...rrn              0a
                                                                                                                                                                                                                            . ..    ,
  evaluating the need tot an vlitly revision.                                                  Walringtrn, O.C.                    2D555, A*tentinnir: D.,,:rltr, tv.,iiam                        OJM,.urrrrt Cr,,llrul.


Most of the component supports considered in this          2. Design by Load Rating guide are located within containment.. They are therefore assumed to be protected against loadings                When load-rating methods are used, Subsection from natural'phenomena or man-made hazards other              NF and Appendix F of Section Ill do not provide a than the specified seismic events for ordinary nuclear          faulted condition load rating. This deficiency should
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 delineates allowable stress or loading limits for various Code service level limits, as defined by NF-
* power plants and the wave motion for floating                  be provided for by the interim method described in nuclear power plants. Thus only the appropriate                this guide.
3113 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 combinations, guidance is needed to provide a consistent basis for the design of component supports.


loadings from natural phenomena and the specified seismic events or wave motions need to be considered          3. Design by Experimental Stress Analysis in combination with the loadings associated with plant conditions to develop appropriate loading com-               While the collapse load for the experimental-stress- binations.                                                     analysis method is defined by 11.1430 in Appendix 1I
USN RC REG ULA TORY G UIDES
                                                                  to Section IIt, the design limits for the experimental- stress-analysis method for variovs operating condi- I. Design by Linear Elastic Analysis                          tion categories are not delineated. This deficiency can be remedied by the interim method described in this guide.
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to
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When the linear-elastic-analysis method is used to design Class I plate-and-shell-type component sup-            4. Large Deformations ports, material properties are given by Table I-11.1 of Appendix I to Section III and Table I of Code Case                The design of component supports is an integral
,, it,,
  1644.5. These tables list values for the design stress        part of the design of a system and its components. A
R egulaltio y G u iJes l ate isw ed to describe ari ,natlt available to the tiublic m ethods latriry C o m inlh.. $1Ol .
  intensity Sm at various temperatures. Yet faulted              complete and consistent design is possible only when condition category design limits are determined by              system/component/component-support interaction Sm, Sy. and Su. The load-rating method also requires            is properly considered. When all three are evaluated the use of Su.                                                  on an elastic basis, the interaction is usually valid because individual deformations are small. However, if plastic analysis methods are used in the design The minimum yield strength Sy at various                    process, large deformations that would result in sub- temperatures could be found in Table 1-13.1 of Ap-              stantially different stress distributions may occur.
rniir ,  
'.  
-
7 A ii~r lt,,,rr l ri.


pendix I to Section III and Table 3 of Code Case
' Iirv) ..,Stl n D C
  1644.5 for the design of Class I plate-and-shell-type            For the evaluation of the level D service limits, Ap- component supports, but values for the ultimate ten-            pendix F to Section Ill permits the use of plastic sile strength S. above room temperature are not                analysis methods in certain acceptable combinations listed in Section Ill. An interim method should                for all three elements. These acceptable combinations therefore be used to obtain values of Su .at                  are selected on the assumption that component sup- temperature in order to provide a safe design margin.          ports are more deformation-sensitive (i.e., their deformation in general will have a large effect on the While NF-3224 and F-1323.1(a) of Section Ill per-          stress distribution in the system and its components).
7 Wv.,r
  mit the increase of allowable stresses under various loading conditions, F-1370(c) limits the increase to               Since large deformations always affect stress dis- two-thirds of the critical buckling strength of the            tribution, care should be exercised even if the plastic component support at temperature. Since buckling                analysis method is used in the Appendix-F-approved prevents "shake-down" in a load-bearing member, it              methodology combination. This is especially impor- must be regarded as controlling for the level A service        tant for identifying buckling or instability problems, limits and F-1370(c) must be regarded as controlling            where the change of geometry should be taken into for the level D service limits. Also, buckling is the          account to avoid erroneous results.
"
accCptalltle to the NRC stall at implleenhln(g **ecilc parts of the Commission's W-r'h.


result of the interaction of the configuration at the load-bearing member and its material properties (i.e.,         5. Function of the Supported System elastic modulus E and minimum yield strength Sy).                 In selecting design limits for different loading com- Because both of these material properties change              binations, the function of the system and its supports with temperature, the critical buckling stresses should must be taken into account. If a support's service is be calculated with the values of E and Sy of the com-          required by the normal function of the supported ponent support material at temperature.                         system during any plant operating condition, the design limits for the normal-operating-condition Allowable design limits for bolted connections are          category or some other justifiable design limits derived on a different basis that varies with the size of      should be used to evaluate the effect of all loading the bolt. For this reason, the increases permitted by          combinations during that specific plant operating NF-3224 and F-1323.1(a) of Section III are not                  condition. This will ensure the proper functioning of directly applicable to bolts and bolted connections.            safety-related systems, such as the injection of the
egulalti tns. to delineate technrta le,$ usedJ
                                                            1.130-2
h the staff in evalualing specific tproblem %
The tuirh-  
.i', isculi i rt hr ks.,41 i r i
.l t[b',  
Ir lt,
*Iiv.....'..
or postulated accidents. or to iprovide guidiance to applicant$. nfjijulmaly Guides ate no l substitute% for regulalion $0 and comnpliince with them ,s nut rrs uired.


Emergency Core Cooling System (ECCS) under the                     Ultimate Tensile Strength. Material property based action of a Loss-of-Coolant Accident (LOCA) and a              on engineering stress-strain relationship.
1. Plvi%*
Al
.ic tIor G tr,,to..l Methods anti solutions different ftrm those set Out in the guides will be accetl.


0 Safe Shutdown Earthquake (SSE) during the faulted plant condition.                                                   Upset Plant Condition, Those deviations from the normal plant condition that have a high probability of occurrence.
2. Aeaorch a*dl Tint R-y,'nS
7. Tr.Iait,4.iiitIiimi able it lhey trovide a 11.bis fot the findings requisite to the issuance or conlittuance
3, Fuels anti hlat..riAs Frcililei,  
8. Occiplalruail i)lAtih Of i Pcermilt Of license hy the Comm ission.


===6. Deformation Limits ===
4. Env lrr*nmrnrfri ,
t ,rin Stirng
 
===9. Aii rlriti R ===
awvur
"
5. Material* and Planrt i'r*illt
1rn *0O.
 
G ,ril Comments and Sug-estions for irmp~rovement% ir% these guides ire encouglied at all times, a nd guides will be revisedl iat ali roorirate, to accommodate comments and Reou-.sis
*ia l*o
-qfe cnpimii ,, in rsui tafi ho fust h
i TIv Iv..011ýria~iV
1W
W fill iit II:.
"
to re lec Ie new information of exrw ience.
 
Hnwev'r. com m ents on this guid ei, I
,'ient or, ai, auto t
.alic unI $t1ii l hia
#oil for sirlrlr
"
cu 11it! i l lt U'v ri
.d. in ltwIi le- ecerveet within aboul It o months
,after its issu lince. will ti- ptarticullarl y ais lul in dlvision% shoul firi ii. rrle in i tinr it) t l hl!
ti
.' . N -l.l., Dtei.Ii.itory C...rrn
. ..
0a
,
evaluating the need tot an vlitly revision.
 
Walringtrn, O.C.
 
2D555, A*tentinnir:
D.,,:rltr, tv.,iiam OJ M,.urrrrt Cr,,llrul.
 
Most of the component supports considered in this guide are located within containment.. They are therefore assumed to be protected against loadings from natural'phenomena or man-made hazards other than the specified seismic events for ordinary nuclear
*
power plants and the wave motion for floating nuclear power plants. Thus only the appropriate loadings from natural phenomena and the specified seismic events or wave motions need to be considered in combination with the loadings associated with plant conditions to develop appropriate loading com- binations.
 
I. 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 Table I- 11.1 of Appendix I to Section III and Table I of Code Case
1644.5. These tables list values for the design stress intensity Sm at various temperatures. Yet faulted condition category design limits are determined by Sm, Sy. and Su. The load-rating method also requires the use of Su.
 
The minimum yield strength Sy at various temperatures could be found in Table 1-13.1 of Ap- pendix I to Section III and Table 3 of Code Case
1644.5 for the design of Class I plate-and-shell-type component supports, but values for the ultimate ten- sile strength S. above room temperature are not listed in Section Ill. An interim method should therefore be used to obtain values of Su .at temperature in order to provide a safe design margin.
 
While NF-3224 and F-1323.1(a) of Section Ill per- mit the increase of allowable stresses under various loading conditions, F-1370(c) limits the increase to two-thirds of the critical buckling strength of the component support at temperature. Since buckling prevents "shake-down" in a load-bearing member, it must be regarded as controlling for the level A service limits and F-1370(c) must be regarded as controlling for the level D service limits. Also, buckling is the result of the interaction of the configuration at 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, the critical buckling stresses should be calculated with the values of E and Sy of the com- ponent support material at temperature.
 
Allowable design 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-3224 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 Ill do not provide a faulted condition load rating. This deficiency should be provided for by the interim method described in this guide.
 
3. Design by Experimental Stress Analysis While the collapse load for the experimental-stress- analysis method is defined by 11.1430 in Appendix 1I
to Section IIt, the design limits for the experimental- stress-analysis method for variovs operating condi- tion 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 because individual deformations are small. However, if plastic analysis methods are used in the design process, large deformations that would result in sub- stantially different stress distributions may occur.
 
For the evaluation of the level D service limits, Ap- pendix F to Section Ill 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 deformation 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 design limits for different loading com- binations, the function of the system and its supports must be taken into account. If a support's service is required by the normal function of the supported system during any plant operating condition, the design limits for the normal-operating-condition category or some other justifiable design limits should be used to evaluate the effect of all loading combinations during that specific plant operating condition. This will ensure the proper functioning of safety-related systems, such as the injection of the
1.130-2
 
0
Emergency Core Cooling System (ECCS) under the action of a Loss-of-Coolant Accident (LOCA) and a Safe Shutdown Earthquake (SSE) during the faulted plant condition.
 
6. Deformation Limits Since component supports are deformation- sensitive load-bearing elements, satisfying the design 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 par- ticular plant condition, 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.
 
7. Definitions Critical Buckling Strength. The strength at which lateral displacements start to develop simultaneously with in-plane or axial deformations.
 
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.
 
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 to 10 CFR Part 100.
 
Operating Condition Categories. Categories of design 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.
 
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 non-self-limiting loadings, but ex- cluding effects resulting from constraints of free-end movements 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==
==C. REGULATORY POSITION==
Since component supports are deformation- sensitive load-bearing elements, satisfying the design            All ASME Code Class I plate-and-shell-type com- limits of Section III will not automatically ensure          ponent supports except snubbers, which are not ad- their proper function. Deformation limits, if specified      dressed in this guide, should be constructed to the by the Code Design Specification, may be the con-            rules of Subsection NF of Section 111, as sup- trolling criterion. On the other hand, if the function        plemented by the following:2 of a component support is not required for a par- ticular plant condition, the stresses or loads resulting          1. The classification of component supports from the loading combinations under the particular            should, as a minimum, be the same as that of the sup- plant condition do not need to satisfy the design              ported components.
All ASME Code Class I plate-and-shell-type com- ponent supports except snubbers, which are not ad- dressed in this guide, should be constructed to the rules of Subsection NF of Section 111, as sup- plemented by the following:2
1. The classification of component supports should, as a minimum, be the same as that of the sup- ported components.


limits for the plant condition.
2. Values of Su at temperature, when they are not listed in Section III, should be estimated by either Method 1, Method 2, or Method 3, as described below on an interim basis until Section I1I includes such values. Values of Sv at temperature listed by Tables 1-1.1, 1-1.2, andl-11.1 of Appendix I and Table 3 of the latest approved version of Code Case
1644 of Section III may be used for the interim calculation.


2. Values of Su at temperature, when they are not listed in Section III, should be estimated by either
a. Method I. This method applies to component support materials whose values of ultimate strength Su at temperature have been tabulated by their manufacturers in catalogs or other publications.
  7. Definitions                                                  Method 1, Method 2, or Method 3, as described Critical Buckling Strength. The strength at which            below on an interim basis until Section I1I includes lateral displacements start to develop simultaneously          such values. Values of Sv at temperature listed by with in-plane or axial deformations.                            Tables 1-1.1, 1-1.2, andl-11.1 of Appendix I and Table 3 of the latest approved version of Code Case Emergency Plant Condition. Those operating con-              1644 of Section III may be used for the interim ditions that have a low probability of occurrence.              calculation.


Faulted Plant Condition. Those operating condi-                   a. Method I. This method applies to component tions associated with postulated events of extremely            support materials whose values of ultimate strength low probability.                                                Su at temperature have been tabulated by their manufacturers in catalogs or other publications.
Su =S.ur Ž
, but not greater than Sur ur where Su = ultimate tensile strength at temperature t to be used to determine the design limits Sur =ultimate tensile strength at room temperature tabulated in Section 111, Ap- pendix I, or Code Case 1644 S= ultimate tensile strength at temperature t tabulated by manufacturers in their catalogs or other publications S
= ultimate tensile strength at room temperature tabulated by manufacturers in the same publications.


Normal Plant Condition, Those operating condi- tions in the course of system startup, operation, hot                Su =S.ur Ž            , but not greater than Sur standby, refueling, and shutdown other than upset,                                    ur emergency, or faulted plant conditions.                        where Su = ultimate tensile strength at temperature t Operating Basis Earthquake (OBE). As defined in                            to be used to determine the design limits Appendix A to 10 CFR Part 100.                                        Sur =ultimate tensile strength at room Operating Condition Categories. Categories of                              temperature tabulated in Section 111, Ap- design limits for component supports as defined by                            pendix I, or Code Case 1644 NF-3113 of Section III of the ASME Code.                              S= ultimate tensile strength at temperature t tabulated by manufacturers in their Plant Conditions.Operating conditions of the plant                        catalogs or other publications categorized as normal, upset, emergency, and faulted plant conditions.                                                    S = ultimate tensile strength at room temperature tabulated by manufacturers Safe Shutdown Earthquake (SSE). As defined in                              in the same publications.
b, Method 2. This method applies to component support materials whose values of ultimate tensile strength at temperature have not been tabulated by their manufacturers in any catalog or publication.


Appendix A to 10 CFR Part 100.                                        b, Method 2. This method applies to component support materials whose values of ultimate tensile Specified Seismic Events. Operating Basis Earth-           strength at temperature have not been tabulated by quake and Safe Shutdown Earthquake.                           their manufacturers in any catalog or publication.
S
Sy u
-Sur S
_____
____yr
- 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.


S          Sy System Mechanical Loadings. The static and                            _____          u____yr
1.130-3
                                                                                                -Sur    S
  dynamic loadings that are developed by the system operating parameters, including dead weight, pres-            - If the function of a component support is not required during a sure, and other non-self-limiting loadings, but ex-            plant condition. the design limits of the support for that plant con- dition need not be satisfied. provided excessive deflections or cluding effects resulting from constraints of free-end        failure of the support will not result in the loss of function of any movements and thermal and peak stresses.                      other safety-related system.


1.130-3
.whete Su. = ultimate tensile strength at. temperature t to be used to determine the design limits Sur= ultimate tensile strength at room temperature tabulated in Section HIl, Ap- pendix 1, or Code Case 1644 Sy = minimum yield strength at temperature t tabulated in Section II1, Appendix 1, or Code Case 1644
=yr minimum yield strength at room temperature, tabulated in Section 111, Ap- pendix 1, or Code Case 164z c. Method 3. 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, Su at temperature may be
*
replaced by the value of 3 Sm at the same temperature.
 
3, Design 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 temperature material properties. A design margin of 2 for flat plates and 3 for shells should be maintained for l loadings combined according to Regulatory Posi- tions 4 and 5 of this guide. Design limits related to critical buckling strength should not be increased un- less the Code specifically allows such an increase.
 
4. Component supports subjected to the most adverse combination of the vibratory motion of the OBE. or the appropriate wave motion and system mechanical loadings ' associated with either the Code design condition or the normal or upset plant condi- tions should be designed with the following limits:4'5 a. The stress limits of (I) NF-3221.1 and NF-
3221.2 for design condition loadings, (2) NF-3222 for normal and upset operating condition loadings, and
(3) Regulatory Position 3 of this guide should not be exceeded for component supports designed by the linear-elastic-analysis method.
 
SSys.tem mechanical loadings include all non-scif-limiting loadings and do not include effects resulting from constraints of free-end displacements and thermal or peak stresses.


.whete                                                                            b. The normal condition load rating or the upset condition load rating of NF-3262.2 of Section III
Since component supports are deformation-sensitive in the performance or 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.
            Su. = ultimate tensile strength at. temperature t                should not be exceeded for component supports to be used to determine the design limits                 designed by the load-rating method.


Sur= ultimate tensile strength at room temperature tabulated in Section HIl, Ap-                        c. The collapse load determined by 11-1400 of pendix 1, or Code Case 1644                                Section III divided by 1.7 should not be exceeded for component supports designed by the experimental- Sy = minimum yield strength at temperature t                      stress-analysis method.
' Since the design of component supports is an integral part of the design of the system and the design of the component, the designer must make sure that methods used for the analysis of the system.


tabulated in Section II1, Appendix 1, or Code Case 1644                                                5. The limits in Regulatory Position 4 or some other justifiable design limits should not be exceeded minimum yield strength at room
component, and component support are compatible (see Table F-
                =yr                                                          by those component supports whose service is re- temperature, tabulated in Section 111, Ap-                quired by the normal function of the supported pendix 1, or Code Case 164z                                system during emergency or faulted plant conditions.
1322.2-1 of Appendix F to Section I11). Large deformations in the system or components should be considered in the design of com- ponent supports.


c. Method 3. Since the listed values of Sm at                        6. Component supports subjected to the most temperature in Section III will always be less than                        adverse combination of system mechanical loadings'
b. The normal condition load rating or the upset condition load rating of NF-3262.2 of Section III
  one-third of the corresponding values of ultimate                          associated with the emergency plant condition should
should not be exceeded for component supports designed by the load-rating method.
*  strength Su at temperature, Su at temperature may be                        be designed within the following design limits: 1-1
*  replaced by the value of 3 Sm at the same temperature.                                                                      a. The stress limits of NF-3224 of Section III
                                                                              and Regulatory Position 3 should not be exceeded for
        3, Design limits for component supports designed                      component supports designed by the linear-elastic-


* by linear elastic analysis should always be limited by                     analysis 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.


the critical buckling strength. The critical buckling strength should be calculated using temperature                                  b. The emergency condition load rating of NF-
5. The limits in Regulatory Position 4 or some other justifiable design limits should not be exceeded by those component supports whose service is re- quired by the normal function of the supported system during emergency or faulted plant conditions.
  material properties. A design margin of 2 for flat                        3262.2 of Section III should not beexceeded for com- plates and 3 for shells should be maintained for                          ponent supports designed by the load-rating method.


lloadings combined according to Regulatory Posi- tions 4 and 5 of this guide. Design limits related to                            c. The collapse load determined by 11-1400 of critical buckling strength should not be increased un-                    Section III and divided by 1.3 should not be exceeded less the Code specifically allows such an increase.                      for component supports designed by the experimental-stress-analysis method.
6. Component supports subjected to the most adverse combination of system mechanical loadings'
associated with the emergency plant condition should be designed within the following design limits: 1-1 a. The stress 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.


4. Component supports subjected to the most adverse combination of the vibratory motion of the                          7. Component supports subjected to the most OBE. or the appropriate wave motion and system                            adverse combination of the vibratory motion of SSE
b. The emergency condition load rating of NF-
    mechanical loadings ' associated with either the Code                    or the appropriate wave motion and system design condition or the normal or upset plant condi-                      mechanical loadings3 associated simultaneously with tions should be designed with the following limits:4'5                      the faulted plant condition and the upset plant condi- tion should be designed within the following design a. The stress limits of (I) NF-3221.1 and NF-                     limits:4 -"
3262.2 of Section III should not beexceeded for com- ponent supports designed by the load-rating method.
  3221.2 for design condition loadings, (2) NF-3222 for normal and upset operating condition loadings, and                              . a. The stress limits of F-1323.1(a) and F-1370(c)
  (3) Regulatory Position 3 of this guide should not be                      of Section Ilf should not be exceeded for component exceeded for component supports designed by the                            supports designed by the linear-elastic-analysis linear-elastic-analysis method.                                            method.


SSys.tem mechanical loadings include all non-scif-limiting loadings            b. The value of T.L. x 0.7O-should     not be ex- and do not include effects resulting from constraints of free-end                                            Su displacements and thermal or peak stresses.
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.


Since component supports are deformation-sensitive          in the       ceeded, where T.L. and Su are defined according to performance or their service requirements, satisfying these limits         NF-3262.1 of Section HI and SL is the ultimate ten- does not ensure the fulfilling of their functional requirements. Any      sile strength of thematerial at service temperature for deformation limits specified by the design specification may be            component supports designed by the load-rating controlling and should be satisfied.                                      method.
7. Component supports subjected to the most adverse combination of the vibratory motion of SSE
or the appropriate wave motion and system mechanical loadings3 associated simultaneously with the faulted plant condition and the upset plant condi- tion should be designed within the following design limits:4-"
.a. The stress limits of F-1323.1(a) and F-1370(c)
of Section Ilf should not be exceeded for component supports designed by the linear-elastic-analysis method.


' Since the design of component supports is an integral part of the design of the system and the design of the component, the designer              c. The collapse load determined by 11-1400 ad- must make sure that methods used for the analysis of the system.
b. The value of T.L. x 0.7O -should not be ex- Su ceeded, where T.L. and Su are defined according to NF-3262.1 of Section HI and SL is the ultimate ten- sile strength of thematerial at service temperature for component supports designed by the load-rating method.


component, and component support are compatible (see Table F-
c. The collapse load determined by 11-1400 ad- justed according to the provisions of F-1370(b) of Section III should not be exceeded for component supports designed by. the experimental-stress-analysis method.
                                                                              justed according to the provisions of F-1370(b) of
    1322.2-1 of Appendix F to Section I11). Large deformations in the          Section III should not be exceeded for component system or components should be considered in the design of com-            supports designed by. the experimental-stress-analysis ponent supports.                                                          method.


1.130-4
1.130-4


==D. IMPLEMENTATION==
==D. IMPLEMENTATION==
sion's regulations, the method described herein will The purpose of this section is to provide guidance      be used in the evaluation of submittals for construc- to applicants and licensees regarding the NRC staff's      tion permit applications docketed after April i, 1978.
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 the applicant proposes an acceptable alternative method for com- plying with the specified portions of the Commis- sion's regulations, the method described herein will be used in the evaluation of submittals for construc- tion permit applications docketed after April i, 1978.


If an applicant wishes to use this regulatory guide in plans for using this regulatory guide.                    developing submittals for construction permit ap- Except in those cases in which the applicant            plications docketed on or before April 1, 1978, the proposes an acceptable alternative method for com-        pertinent portions of the application will be evaluated plying with the specified portions of the Commis-          on the basis of this guide.
If an applicant wishes to use this regulatory guide in developing submittals for construction permit ap- plications docketed on or before April 1, 1978, the pertinent portions of the application will be evaluated on the basis of this guide.


1.130-5}}
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Revision as of 00:17, 11 January 2025

Design Limits and Loading Combinations for Class 1 Plate-and-Shell-Type Component Supports
ML13350A267
Person / Time
Issue date: 07/31/1977
From:
NRC/OSD
To:
References
RG-1.130
Download: ML13350A267 (5)


U.S. NUCLEAR REGULATORY COMMISSION

July 1977 REGULATORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 1.130

DESIGN LIMITS AND

LOADING COMBINATIONS

FOR CLASS I PLATE-AND-SHELL-TYPE

COMPONENT SUPPORTS

A. INTRODUCTION

conditions under the stress of specified seismic events, thereby permitting system components to General Design Criterion 2, "Design Bases for function properly. They also prevent excessive corn- Protection Against Natural Phenomena," of Appen- ponent movement during the loadings associated dix A, "General Design Criteria for Nuclear Power with emergency and faulted plant conditions corn- Plants," to 10 CFR Part 50, "Licensing of Produc- bined with a specified seismic eventvor other natural tion and Utilization Facilities," requires that the phenomena, thereby helping ,t0:t mitigate system design bases for structures, systems, and components damage. Component supports: are 'deformation- important to safety reflect appropriate combinations sensitive because large deformations in component of the effects of normal and accident conditions with supports may significantly"change the stress distribu- the effects of natural phenomena such as earth- tion in the support, system and its 'components.

quakes. The failure of members designed to support safety-related components could jeopardize the NF- 1122 and NA-21346 f Section 111 of the ASME

ability of the supported component to perform its Boiler and :?resure Vesel Code imply that the clas- safety function.

sification' §6-f ;omp6nent supports should, as a limt a

miniium ebe the~same as that of the supported com- This guide delineates acceptable design limits and pon

,eroibti.

Th'is should be considered as a requirement.

appropriate combinations of loadings associated with r

e di i*:i*`Z_1hisi!gdidle delineates design limits and loading corn- normal operation, postulated accidents, and specified "ib.i'ition s, in addition to supplementary criteria, for seismic events for the design of Class I pla-I'iiid.

'lass I plate-and-shell-type component supports as shell-type component supports as defined in desec d~fined by NF-1212 of Section II1. Snubbers installed tion NF of Section III of the America,:.'Socic*. of.02 for protection against seismic or dynamic loadings of Mechanical Engineers (ASME) Boilq,,;'and Prri other origins are not addressed in this guide.

Vessel Code.' This guide applies to lighti-water"ooled reactors.

'

,

B. DIPSIO

  • ._ýSIO

Load-bearing menil uassified as component supports are t '

c sUety of nuclear power plants becau they air. ompon**n ts in place dur- ing a

sa s

cia"

with normal and upset plant IAmen icity

~IcchanicaI Engineers Boiler and Pressure Vessel Co Section ItI, Division 1. 1974 Edition, including the

1974 Wintc ddenda thereto. Copies or 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.

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 delineates allowable stress or loading limits for various Code service level limits, as defined by NF-

3113 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 combinations, guidance is needed to provide a consistent basis for the design of component supports.

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Most of the component supports considered in this guide are located within containment.. They are therefore assumed to be protected against loadings from natural'phenomena or man-made hazards other than the specified seismic events for ordinary nuclear

power plants and the wave motion for floating nuclear power plants. Thus only the appropriate loadings from natural phenomena and the specified seismic events or wave motions need to be considered in combination with the loadings associated with plant conditions to develop appropriate loading com- binations.

I. 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 Table I- 11.1 of Appendix I to Section III and Table I of Code Case

1644.5. These tables list values for the design stress intensity Sm at various temperatures. Yet faulted condition category design limits are determined by Sm, Sy. and Su. The load-rating method also requires the use of Su.

The minimum yield strength Sy at various temperatures could be found in Table 1-13.1 of Ap- pendix I to Section III and Table 3 of Code Case

1644.5 for the design of Class I plate-and-shell-type component supports, but values for the ultimate ten- sile strength S. above room temperature are not listed in Section Ill. An interim method should therefore be used to obtain values of Su .at temperature in order to provide a safe design margin.

While NF-3224 and F-1323.1(a) of Section Ill per- mit the increase of allowable stresses under various loading conditions, F-1370(c) limits the increase to two-thirds of the critical buckling strength of the component support at temperature. Since buckling prevents "shake-down" in a load-bearing member, it must be regarded as controlling for the level A service limits and F-1370(c) must be regarded as controlling for the level D service limits. Also, buckling is the result of the interaction of the configuration at 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, the critical buckling stresses should be calculated with the values of E and Sy of the com- ponent support material at temperature.

Allowable design 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-3224 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 Ill do not provide a faulted condition load rating. This deficiency should be provided for by the interim method described in this guide.

3. Design by Experimental Stress Analysis While the collapse load for the experimental-stress- analysis method is defined by 11.1430 in Appendix 1I

to Section IIt, the design limits for the experimental- stress-analysis method for variovs operating condi- tion 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 because individual deformations are small. However, if plastic analysis methods are used in the design process, large deformations that would result in sub- stantially different stress distributions may occur.

For the evaluation of the level D service limits, Ap- pendix F to Section Ill 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 deformation 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 design limits for different loading com- binations, the function of the system and its supports must be taken into account. If a support's service is required by the normal function of the supported system during any plant operating condition, the design limits for the normal-operating-condition category or some other justifiable design limits should be used to evaluate the effect of all loading combinations during that specific plant operating condition. This will ensure the proper functioning of safety-related systems, such as the injection of the

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0

Emergency Core Cooling System (ECCS) under the action of a Loss-of-Coolant Accident (LOCA) and a Safe Shutdown Earthquake (SSE) during the faulted plant condition.

6. Deformation Limits Since component supports are deformation- sensitive load-bearing elements, satisfying the design 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 par- ticular plant condition, 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.

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

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.

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 to 10 CFR Part 100.

Operating Condition Categories. Categories of design 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.

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 non-self-limiting loadings, but ex- cluding effects resulting from constraints of free-end movements 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

All ASME Code Class I plate-and-shell-type com- ponent supports except snubbers, which are not ad- dressed in this guide, should be constructed to the rules of Subsection NF of Section 111, as sup- plemented by the following:2

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

2. Values of Su at temperature, when they are not listed in Section III, should be estimated by either Method 1, Method 2, or Method 3, as described below on an interim basis until Section I1I includes such values. Values of Sv at temperature listed by Tables 1-1.1, 1-1.2, andl-11.1 of Appendix I and Table 3 of the latest approved version of Code Case

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

a. Method I. This method applies to component support materials whose values of ultimate strength Su at temperature have been tabulated by their manufacturers in catalogs or other publications.

Su =S.ur Ž

, but not greater than Sur ur where Su = ultimate tensile strength at temperature t to be used to determine the design limits Sur =ultimate tensile strength at room temperature tabulated in Section 111, Ap- pendix I, or Code Case 1644 S= ultimate tensile strength at temperature t tabulated by manufacturers in their catalogs or other publications S

= ultimate tensile strength at room temperature tabulated by manufacturers in the same publications.

b, Method 2. This method applies to component support materials whose values of ultimate tensile strength at temperature have not been tabulated by their manufacturers in any catalog or publication.

S

Sy u

-Sur S

_____

____yr

- 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.

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.whete Su. = ultimate tensile strength at. temperature t to be used to determine the design limits Sur= ultimate tensile strength at room temperature tabulated in Section HIl, Ap- pendix 1, or Code Case 1644 Sy = minimum yield strength at temperature t tabulated in Section II1, Appendix 1, or Code Case 1644

=yr minimum yield strength at room temperature, tabulated in Section 111, Ap- pendix 1, or Code Case 164z c. Method 3. 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, Su at temperature may be

replaced by the value of 3 Sm at the same temperature.

3, Design 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 temperature material properties. A design margin of 2 for flat plates and 3 for shells should be maintained for l loadings combined according to Regulatory Posi- tions 4 and 5 of this guide. Design limits related to critical buckling strength should not be increased un- less the Code specifically allows such an increase.

4. Component supports subjected to the most adverse combination of the vibratory motion of the OBE. or the appropriate wave motion and system mechanical loadings ' associated with either the Code design condition or the normal or upset plant condi- tions should be designed with the following limits:4'5 a. The stress limits of (I) NF-3221.1 and NF-

3221.2 for design condition loadings, (2) NF-3222 for normal and upset operating condition loadings, and

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

SSys.tem mechanical loadings include all non-scif-limiting loadings and do not include effects resulting from constraints of free-end displacements and thermal or peak stresses.

Since component supports are deformation-sensitive in the performance or 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.

' Since the design of component supports is an integral part of the design of the system and the design of the component, the designer 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 deformations in the system or components should be considered in the design of com- ponent supports.

b. The normal condition load rating or the upset condition load rating 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 divided by 1.7 should not be exceeded for component supports designed by the experimental- stress-analysis method.

5. The limits in Regulatory Position 4 or some other justifiable design limits should not be exceeded by those component supports whose service is re- quired by the normal function of the supported system during emergency or faulted plant conditions.

6. Component supports subjected to the most adverse combination of system mechanical loadings'

associated with the emergency plant condition should be designed within the following design limits: 1-1 a. The stress 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 emergency condition load rating of NF-

3262.2 of Section III should not beexceeded for com- ponent 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.

7. Component supports subjected to the most adverse combination of the vibratory motion of SSE

or the appropriate wave motion and system mechanical loadings3 associated simultaneously with the faulted plant condition and the upset plant condi- tion should be designed within the following design limits:4-"

.a. The stress limits of F-1323.1(a) and F-1370(c)

of Section Ilf should not be exceeded for component supports designed by the linear-elastic-analysis method.

b. The value of T.L. x 0.7O -should not be ex- Su ceeded, where T.L. and Su are defined according to NF-3262.1 of Section HI and SL is the ultimate ten- sile strength of thematerial at service temperature for component supports designed by the load-rating method.

c. The collapse load determined by 11-1400 ad- justed according to the provisions of F-1370(b) of Section III should not be exceeded for component supports designed by. the experimental-stress-analysis method.

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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 which the applicant proposes an acceptable alternative method for com- plying with the specified portions of the Commis- sion's regulations, the method described herein will be used in the evaluation of submittals for construc- tion permit applications docketed after April i, 1978.

If an applicant wishes to use this regulatory guide in developing submittals for construction permit ap- plications docketed on or before April 1, 1978, the pertinent portions of the application will be evaluated on the basis of this guide.

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