ML20151V798

Reg Guide 1.87,Rev 1, Guidance for Const of Class 1 Components in Elevated-Temp Reactors (Supplement to ASME Section III Code Cases 1592,1593,1594,1595 & 1596)

ML20151V798
Person / Time
Issue date:	06/30/1975
From:	NRC OFFICE OF STANDARDS DEVELOPMENT
To:
References
REGGD-01.087, REGGD-1.087, NUDOCS 8808230008
Download: ML20151V798 (4)

Text

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Revision 1 U.S. NUCLEAR REGULATORY COMMISSION June 1975 REGULATORYGU DE OFFICE OF STANDARDS DEVELOPMENT W

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? r,f REGULATORY GUIDE 1.87 T ' ; -

i4 :a GUIDANCE FOR CONSTRUCTION' OF CLASS 1 COMPONENTS h h.N IN ELEVATED TEMPERATURE REACTORS (SUPPLEMENT TO ASME SECTION 111 CODE CASES 1592,1593,1594,1595, AND 1596) dpQ n

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.,7g%ihi A, INTRODUCTION B. DISCUSSION Md Section 50.55a, "Codes and Standards," of 10 CFR M' ^y g The rules for construction of nuclear components Part 50, "Ucensing of Prodt.ction and Utilization Facihties." requires, in part, that structures, systems, gisen in Section 111 of the ASME Boiler and Pressure Vessel Code, including Class I nuclear components h.i W,*-)>

M and components be designed, fabrica'd, erected, tested, that are covered in Subsectwn NB of Section 111, apply and inspected to quality standards enmensurate with to components at temperatures where creep effects are M9-the importance of the safety functions to be performed. insignificant. Material behavior considerations are j 'J t General Design Crit,rion 1, "Quality Standards and limited to either clastic or clastic plastic response, which, Records," of Apperidix A,8 "General Design Criteria for in effect, provides protection against only time. ?h&* ?.;l- 4 Nuclear Power Plants," to 10 CFR Part 50 permits use independent failure modes such as ductile rupture, gross kf 4, of reeognized codes and standards, provided they are distortion, and fatigue. gy n, identitied and evaluated to determine applicability, The service temperatures and load conditions for ty n adequacy, and sufficiency and are supplemented or llTGRs, LM FBRs, and GCFPRs are such that j,y 4 s modified as necessary to ensure a qmlity product in 19 jg heping with the required safety function. This gutde time dependent phenomena such as creep and relaxation j. *. ]

describes interim licensing Fuldelines to aid applicants in are important. Subsection NB of Section ill does not y(y implementing these requirements with respect to ASME pmside adequate guidance for construction of y . . ;.

Class I components operating at elevated temperatures, components subject to elevated temperature service. > v q.

This guide applies to high temperature gas-cooled Therefore, as an interim step, the ASME l'as developed -

4 reactors (llTGRs), liquitmetal fast breeder reactors five Code Cases (1592,~ 1593,1594,1595, and 1596) to y %([ ,

(LM FB Rs), and gas-cooled fast breeder reactors provide guidance in this area. Code Cases 1593,1594, 9,'

(GCFBRs).

1595, and 1596 were approved on November 5,1973, as interpretations of the ASME Boiler and Pressure Vessel f.[k_ 3 Code. Code Case 1592 was approved on April 29, 1974 4' p,{y.k,  :

'As defined in Section lit of the American Socety of ~'V$

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Mechanical F ngmeets Botler and Pressure Venel Code (ASME These Code Cases cover design, fabrication and BAPV Code), construction is an all-inclusive term comprisinF installation, examination, testing, and protection against 2.T materials. deugn, fat rication, examination, testmg, inspecuon, and certification required in the manufacture and installation verpressure. They reflect both time independent and i! -4

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of components. time-dependent material properties and structural 7%

' Appendh A to 10 CI R Part 50 is directly app 1Kable to behavior (clastic and inelastic) by considering the following modes of failure:

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water-cooled nuclear pow er ptants; howewr, as indkated in that appendh, the General Design Cntena are conudered applicable to other types of nuclear power units and are 1. Ductile rupture from short term loadings

htended to provide guMance in establishing principal enteria for nach other units. 2. Creep rupture from long term loadings; USNRC REGULATORY GUlDES c +=.au p..se w eei u ene sece . , es i*e c ==, a . u s wewe, p,';,7;,c; ~~ *"- - a e >= ^" ~~ o~'"" -a

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_ 3. Creep fatigue failure; tion of accepted construction practices. Ilowever. --

} certain aspects of testing and oserpressure protection 1 4. Gross distortion due to incremental ccIlapse and relatise to test liquids and "noncritical" component ratcheting; protection need further clarification as indicated in the

{m regulatory position of this guide. *Wi

5. loss of function due to excessive deformation; MM

'Q 1 These code cases were developed to supplement

6. Buckling due to short term loadmp; Subsection N B, "Requirements for Class 1 (9E y Components," of Section 111 of the ASME B&PV Code. pf,Y;)

T 7. Creep buckling due to long term loadings. In some instances, they also refer to use of other ASME Cy . >-

rules such as Appendix E,"Minimum Bolt Cross Section 4,9 L

I Consideration of these co,aplex failure modes serves as a basis for deselopir.g design methods and piocedures to Area." Appendix F, "Rules for Evaluation of Faulted Conditions," Subsection NF, "Component Supports," I h .:

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, provide adequate protection throughout a reactor and Subsection NG, "Core Support Structures." These g 9 3.

lifetime of 30 to 40 years. referenced rules do not include consideration of ele- Q ?,(p i sated temperature or time degendent effects during serv. A y The Code Cases under discussion utilize recently ice life. Therefore, the use of Appendices E or F, h Y t acquired information on material behavior, extended use Subsections NF or NG, or other portions of Section !!! 4 g of accepted practice, and special consideration of of the ASME ll&PV Code should be justified with g safetyelated aspects of the nuclear system to establish espect to applicabi;ity for elevated temperature service --

i rules of construction for components in eleva ted- when used with these Code Cases. Some representatise t- temprature senice. These rules estabbsh procedures areas of concern are repeated stress relaxation, dynamic E that are consistent with current knowiedge and the state load considerations, deformation limits, and irradiation E

5 of the art effects. (Uf W .,

A Code Case 1592 presents rules for component design A note of caution is also raised concerning Code Case g$

E and includes data on matenal properties. The complex reference to Articles in Subsection NB of Section ill of E influence of temperature, environment, and geometry on the ASME B&pV Code. The primary problem is that k material properties and structural behavior for extended literal comphance with a specific Ccde Case could

- time periods requires evaluation of component design by possibly introduce unintended construction practices by I analytical techniques. Although present knowledge is referring to a certain Article in Subsection NB that has 7 sufficient to design with a high probability of safe subsequently been superseded by another Code Case. As senice, it will be necessary for component designs to an example, Code Case 1593 (in the Reply to Inquiry)

=. consider and accommodate inservice inspection and refers to fabrication and installation in accordance with p suneillance programs. The intent, within the context of the rules of Section 111, Article NB-4000. Subparagraph E this guide, is to establish that potential, access and NB 4223.1 of that Article subsequently references Table g coupon test material needs for both inspection and NB 3642.1 1 which in turn refers to subparagraph surveillance programs should be considered at the NB 3641.1 of Article NB 3000, flowever, for Class 1 component design stage, components in elevated temperature service, Code Case 1592 has replaced Article NB 3000 and,in the process, z The provision to consider insenice inspection and the requirements of Table NB 3642.1 1 and sub-g surveillance test programs at the design stage will allow paragraph NB-3641.1 were changed. This illustrates systematic monitoring of component and material that compliance with one Code Case may inadvertently behavior. This approach will help to detect and assess conflict with another Code Case. Therefore, care should y accumulation of damage, excessive deformation, - be exercised to determine that referenced Articles in l incipient failure, or possibl? energistic effects of Subsection NB are consistent with all applicable Code elevated temperature, load conditions, and environment Cases and the supplements of thc regu'atory position of [J on materials and components during a design life of 30 this guide.

to 40 years. Additionally, the limited material response data base (tensile, creep, stress rupture, fatigue, etc.) and The rules in Appendix !! of Section 111 of the ASME y E lack of prototypical senice experience will also be B&PV Code permit component acceptance by means of a augmented by results from ongoing research programs. experimental stress analysis in lieu of analytical I E techniques. Code Case 1592 tstablishes intent to extend E Construction aspects associated with fabrication and this concept to permit acceptance of elevated-

[ installation s examination, testing, and overpressure temperature components by experimental analysis.

7 protection are covered in Code Cases 1593,1594,1595, Iktailed guidelines have not been provided;therefore,it and 1596, respectively. These rules generally account for will be necessary to document test procedures and potential safety-related problems during elevated- acceptance criteiis for experimental analysis of com-temperature unice by invoking more stringent applica- ponents to be t> sed in elevated temperature senice.

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inelastic analysis should be included in the PSAR. All D

l C. REGULATORY POSITION The requirements of Code C:ses 1592,"Section 111, Class ! Components in Elevated Temperature Senice,"

computer programs used should be identified and sufficiently-desenbed in the PSAR with respect to those portions utilized to identify basic theory, assumptions, 1593, "Fabrication and installation of Elevated constitutise relations, extent of verincation, limitations, l

Tem $rature Components, Section 111, Class 1," 1594, and justification of applicability, including validation of "Examination of Elevated Temperature Components, computer models and modeling techniques.

Section 111, Class 1," 1595, "Testing of Elevated Temperature Components, Section 111, Class 1," and b. Identification of whether the strength properties l 1596, "Protection Against Overpressure of Elevated used in analysis are minimum, average, or maximum Temperature Components, Section 111, Class 1," will be should be included in the PSAR for each part of the used with Section til of the ASME Boiler and Pressure analysis, except where the properties are specified by, or Vessel Code, including Addenda, .a evaluating are an integral part of, the analytical method %here an

+ appheations for construction permits, as supplemented option exists, the use of minimum, average, or maximum by the following: strength properties relative to critical failure modes, I damage laws, and deformation limits should be justified on the basis of increased safety. If the material property

1. Generalitems- data gnen in the Code Case are inadequate (including alteration or extrapolation) for design evaluation of all

a. All Sve Code Cases should be invoked, where modes of failure, the appropriate properties used in applicable, for components in high temperature design should be documented and justined in the PSAR.

gas-cooled reactors, liquid metal fast breeder reactors. This material data base, together with a description of and gassooled fast breeder reactors. the methods used to account for environmental effects throughout design life, should be documented in the

b. These Code Cases may be used in conjunction PSAR.

with Subsection NB of Section 111 of the ASME Boiler and Pressure Vessel Code. When other portions of

c. The acceptability criteria applied as stram,Section I!! such as Appendices E and F and Subsections deformation, and fatigue limits pursuant to 3250 should NF and NG are use-! with these Code Cases, justification be censonant with the rules of Appendix T of this Code of the bases relative to elevated temperature appli-cability should be submitted in the Preliminary Safety Case. When any acceptability enteria or material pr perties are invoked as alternatives to the rules of Analdis Report (PSAR).

Appendix T, the affected areas (material, parts, e mp nents, systems, etc.) should be identified, and if the requested justification and documentation are not available at the time the PSAR is submitted, they justification for such rules should be documented in the

( PSA R.

should be included in a subsequent submittal, and the PSAR should contain a prcliminary discussion of bases and approaches to be utilized and should reference the d. A full description of the buekhng analysis appropriate regulatory position paragraph of this guide pursuant to T 1500 should be documented in the PSAR. I such as C.I.b for this item. This procedure should be This should sbo include the following:

implemented for all paragraphs of this guide that request submittal ofinformation in the PSAR. (1) Indication of the margin for a design factor on load applied throughout service hfe, in addition to the

c. Component designs should accommodate the suggested end oflife design factor in Table T 1520-1.

I required inservice inspection and surveillance programs for material or component integrity. Representatiie (2) Justification that a process is purely environmental factors should consider the compatibility strain controlled and not combined with load-controlled of the coolant such as sodium, helium, eir, and or significant clastic followup when the strain controlled contaminants; irradiation effects that might induce design factor in Table T-15201 is used.

ductility loss; and aging resulting from prolonged i

exposure to elevated temperature. (3) Description of the methods used to determine the minimum stress strain curve suggested in T 1520(c).

2. Code Case 1592 e. The intent of Appendix 11 (ASME B&PV Code) rules should be used for guidance when design is justified l a. A description of analysis methods and delineation by experimental analysis. A description of procedures I of areas that have been subjected to elastic analysis or used for experimental analysis, the evaluation techniques, and acceptance criteria should be included in j

• Lines in&cate nutss:anuve changen frem previous asiuc. the PS AR.

l .h 7 3 1 - - _ _ _ _ _ __

/3 Code Case 1593 "nonciitical" pursuant to 7110(a)(4) and 7110(b). The evaluation techniques and acceptance criteria used te i All Articles of Subsection NB referencedin this Code justify designation as a "noncritical" component should l Case should be applied in a manner consistent with all also be included.

applicable elevated. temperature Code Cases and the corresponding supplementc in the regulatory position of b. All Articles of Subsection ND referenced in this this guide. Code Case should be applied in a inanner consistent with all applicable elevated tempertture Code Cases and the

4. Code Case 1594 corresponding supplements in the regulatory position of I

this Fuide.

l All Articles of Subsection NB referenced in this Code l Case should be applied in a manner consistent with all c. The potential overpressure due to failure of a applicable elevated. temperature Code Cases and the system component in 7121(d) should include corresponding supplements in the regulatory position of . consideration of pressure from an adjacent system by this guide, leaks or chemical reaction or both.

5. Code Case 1595 d. For those reacters using liquid sodium as the coolant, a description of the methods used to determine

a. The "nonhazardous liquid" in 6212(a) should be overpressure resulting from possible shock loads nonhazardous relative to possible reactions between mentioned in 7122 should appear in the Oserpressure residual test hquid and the normal coolant fluid and Protection Report. This should include a definition of nonhazardous with respect to deleterious effects to the what constitutes rapid valve closure relative to component (material) such as corrosion by either the pressure wave velocity and valve closing time. A test liquid or a liuid created by reaction of test liquid description of how the pressure shock and momentum and cc -. ant. Appropriate posttest procedures that ensure change effects have been accounted for with respect to l p.ver draining and drying may be instituted in some pressure relief, piping design, and support systems l instances where a potential test liquid would be should also be included.

I excluded from use because of the aforementioned effects. When a test liquid is considered "nonhautdous" D. IMPLEMENTATION as a result of such prescribed posttest procedures, the I posttest procedures should be documented in the PSAR The purpose of this section is to provide information and included as part of the Data Report Form required to applicants and licensees regarding the NRC staffs

( by NA.o400 of the ASME B&PV Code. All areas subject plans for utilizing this regulatory guide.

to these procedures should be identified in the PSAR.

Except in those instances in which the applicant l

b. All Articles of Subsection NB referenced in this proposes an alternatise method for complying with l Code Case should be applied in a manner consistent with specified portions of the Commission's regulations, the l all appheable elevated. temperature Code Cases and the method described herein will be used in the evaluation l corresponding supplements in the regulatory position of of submittals for construction permit appbcations this guide. docketed after January 1,1976.

6. Code Case 1596 If an applicant wishes to use this regulatory guide in developir.g submittals for apphcations docketed on or

a. The Overpressure Protection Report should before January 1,1976, the pertinent portions of the indicate those components considered to be application will be evaluated on the basis of this guide.

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