ML20083L898
| ML20083L898 | |
| Person / Time | |
|---|---|
| Issue date: | 04/30/1984 |
| From: | Serkiz A Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| REF-GTECI-A-01, REF-GTECI-PI, TASK-A-01, TASK-A-1, TASK-OR NUREG-0800, NUREG-0800-03.9.3-R1, NUREG-800, NUREG-800-3.9.3-R1, SRP-03.09.03, SRP-3.09.03, NUDOCS 8404170399 | |
| Download: ML20083L898 (11) | |
Text
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NUREG-0800 (Formerly NUREG.75/067)
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U.S. NUCLEAR REGULATORY COMMISSION Q1gj',i STANDARD REVIEW PLAN f
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OFFICE OF NUCLEAR REACTOR REGULATION t
v Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants 4'
Section No. 3.9.3 Revision No. No Change Appendix No. A to SRP Section 3.9.3 Revision No. 1 Branch Tech. Position N/A Revision No.
N/A Date issued April 1984 s
FILING INSTRUCTIONS j
I PAGES TO BE REMOVED NEW PAGES TO BE INSERTED PAGE NUMBER DATE PAGE NUMBER DATE Appendix A Rev. O July 1981 Appendix A Rev. 1 April 1984 to SRP Section to SRP Section l
3.9.3 3.9.3 3.9.3-12 3.9.3-12 thru thru 3.9.3-20 3.9.3-20 B404170399 840430 PDR NUREG 0000 R PDR
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The U.S. Nuclear Regulatory Commission's Standard Review Plan, NUREG-0000, prepared by the Office of Nuclear Reactor Regulation,is available for sale by the National Technical Information Service, Springfield. VA 22161.
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APPENDIX A STANDARD REVIEW PLAN SECTION 3.9.3 STRESS LIMITS FOR ASME CLASS 1, 2, AND 3 COMPONENTS AND COMPONENT SUPPORTS OF SAFETY-RELATED SYSTEMS AND CLASS CS CORE SUPPORT STRUCTURES UNDER SPECIFIED SERVICE LOADING COMBINATIONS A.
INTRODUCTION Nuclear power plant components and supports are subjected to combinations of loadings derived from plant and system operating conc'itions, natural phenomena, postulated plant events, and site-related hazards.
Section III, Division 1 of the ASME Code (hereafter referred to as the Code) provides specific sets of design and service stress limits that apply to the pressure retaining or structural integrity of components and supports when subjected to these loadings.
The design and service stress limits specified by the Code do not assure, in themselves, the operability of components, including their supports, to perform the mechanical motion required to fulfill the component's safety function.
Certain of the service stress limits specified by the Code (i.e.,
level C and D) may not assure the functional capability of components, including their supports, to deliver rated flow and retain dimensional stability.
Since the combination of loadings, the selection of the applicable design and service stress limits appropriate to each load combination and the proper consideration of operability is beyond the scope of the Code; and the treatment of functional capability, including collapse and deflection limits, is not adequately treated by the Code for all situations, such factors must be evaluated by designers and appropriate information developed for inclusion in the Design Specification or other referenced documents.
Applicants require guidance with regard'to the selection of acceptable design and service stress limits associated with various loadings and combinations thereof, resulting from' plant and system operating conditions and design basis events,' natural phenomena, and site-related hazards. The relationship and application of the terms " design conditions," " plant operating conditions,"
" system operating conditions," and the formerly used term " component operating conditions," now characterized by.four levels of. service stress limits, have not been. clearly understood by applicants and their subcontractors.
For example, under the " faulted plant or' system condition"-(e.g.. due to LOCA within the reactor coolant pressure boundary), the emergency core cooling
. system (ECCS) should be designed to operate and deliver rated flow for an extended period of time to assure the safe shutdown of the plant. -Although the
" plant condition" is termed " faulted," components in the functional ECCS must perform the safety function under a specified set of-service loadings which-includes those resulting from the specified plant postulated events. <The.
selection of ' level "D'.' (related to the " faulted" condition) service stress limits for this system,' based solely on the supposition that all components may use this limit for a postulated event resulting in the faulted plant condition cannot be justified, unless system operability is also demonstrated.
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This appendix is necessary to improve consistency and' understanding of the basic approach in the selection of load combinations applicable 'to safety-related systems and to establish acceptable relationships between plant postulated events, plant and' system operating conditions, component'and, 3.9.3-12 Rev.1 - April 1984.
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l component support design, and service stress limits, functional capability, and operability.
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DISCUSSION l
Current reviews of both standardized plants and custom plants have indicatad the need for additional guidance to reach acceptable design conclusions in the following areas:
(1) Relationship between certain plant postulated events, plant and system operating conditions, resulting loads and combinations thereof, and appropriate design and service stress limits for ASME Class 1, 2 and 3 components and component supports and Class CS core support structures.
(2) Relationship of component operability assurance, functional capability, and allowable design and service stress limits for ASME Class 1, 2, and 3 components and component supports.
The Code provides five categories of limits applicable to design and service loadings (design, level A, level B, level C, and level D). The Code rules provide for structural integrity of the pressure retaining boundary of a component and its supports, but specifically exclude the subject of component operability and do not directly address functional capability.
The types of j
loadings to be taken into account in designing a component are specified in the Code, but rules specifying how the loadings, which result from postulated O
events and plant and system operating conditions, are to be combined and what stress level is appropriate for use with loading combinations are not specified in the Code.
It is the responsibility of the designer to include all this information in the Code required Design Specification of each component and i
support.
C.
POSITION Effective with the 1977 Edition, the-Code provides design stress. limits and four sets'of service stress limits for all classes of components, component supports, and core support structures.
The availability;of such design and service stress limits within the Code requires that the MEB review and deter--
mine maximum acceptable design and service' stress limits which may be used with specified loads, or combinations thereof, for components and component supports of: safety-related systems (refer to definition in Table III) and. core support structures.
This appendix provides guidance for dealing with the components and component.
supports of safety-related systems and. core' support structures:in~the following.
areas:
(1). Consideration ~of design loadings and limits.
(2) Consideration of service loading combinations resulting'from postulated.
events and the designation of acceptable. service limits.' -
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(3) Consideration of piping functional capability and operability of active pumps and valves under service loading combinations resulting from
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postulated events.
(4) Applicability of the appendix to components, component support structures, and core support structures and procedures for compliance.
1.0 ASME CLASS 1, 2, AND 3 COMPONENTS AND COMPONENT SUPPORTS OF SAFETY-RELATED SYSTEMS AM') CLASS CS CORE SUPPORT STRUCTURES 1.1 Design Considerations and Design Loadings ASME Code Class 1, 2, and 3 components, component supports, and class CS core support structures shall be designed to satisfy the appropriate sub-sections of the Code in all respects, including limitations on pressure, and the requirements of this appendix.
Component supports that are intended to restrain either force and displacement or anchor movement shall be designed to maintain deformations within appropriate limits as specified in the component support Design Specifications.
Design loadings shall be established in the Design Specification.
The design limits of the appropriate subsection of the Code shall not be exceeded for the design loadings specified.
- 1. 2 Service Loading Combinations The identification of individual loads and the appropriate combination of these loads (i.e., sustained loads, loads due to system operating transients SOT, OBE, SSE, LOCA, DBPB, MS/FWPB and their dynamic effects) shall be in accordance with Section 1.3.
The appropriate method of combination of these loads shall be in accordance with NUREG-0484,
" Methodology foi Combining Dynamic Loads" (Reference 9).
1.3 Service Conditions 1.3.1 Service limit A Class 1, 2, and 3 components, component supports, and Class CS core support structures shall meet a service limit not greater than Level A when subjected to sustained loads resulting from normal plant / system operation.
1.3.2 Service Limit B l
Class 1, 2, and 3 components, component supports, and Class CS core support structures shall meet a service limit not greater than Level B when subjected to the appropriate combination of loadings resulting from 1
(1) sustained loads, (2) specified plant / system operating transients (SOT), and (3) the OBE.
1.3.3 Service Limit C (a) Class 1, 2, and 3 components, component supports, and Class CS ccre support strtctures shall meet a service limit not greater than Level 3.9.3-14 Rev. 1 - April 1984
C when subjected to the appropriate combination of loadings resulting from (1) sustained loads, and (2) the DBPB.
(b) The DBPB includes loads from the postulated pipe break, itself, and also any associated system transients or dynamic effects resulting j
from the postulated pipe break.
1.3.4 Service Limit 0 (a) Class 1, 2, and 3 components, component supports, and Class CS core support structures shall meet a service stress limit not greater than i
Level D when subjected to the appropriate combination of loadings resulting from (1) sustained loads, (2) either the DBPB, MS/FWPB, or LOCA, and (3) and SSE.
(b) The DBPB, MS/FWPB, and LOCA include loads from the postulated pipe breaks, themselves, and also any associated system transients or dynamic effects resulting tros the postulated pipe breaks. Asymme-l tric blowdown loads on PWR primary systems shall be incorporated per NUREG-0609 (Reference 10).
i 2.0 OPERABILITY AND FUNCTIONAL CAPABILITY 2.1 Active Pumps and Valves SRP Section 3.10 (Reference 4) shall demonstrate that the pump or valve, as supported, can adequately sustain the designated combined service loadings _at a stress level at least equal to the specified service limit, and can perform its safety function.without impairment.
Loads produced by the restraint of free end displacement and anchor point motions shall be r
included.
2.2 Snubbers-l The operability requirements specified for mechanical and hydraulic l
snubbers installed on safety-related systems is subject to review by the staff. When snubbers are used, their need shall be clearly established and their design criterin presented.
2.3 ~ Functional Capability-The design of Class 1, 2, and-3 piping components ~shall include a functional capability assurance program. -This program shall demonstrate that the piping components, as supported, can retain sufficient dimen-sional stability at service conditions so as not to impair the system's functional capability._-The program may be based on tests, analysis,~or a combination of tests and analysis.
3.0 TABLES.
3.1_ Table I summarizes the requirements _of this appendix for use with'ASME g
Class 1,12, and 3 components, component supports, and Class-CS core support structures. The table illustrates plant events,, system operating
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1 conditions, service loading combinations, and service stress limits and should always be used in conjunction with the text of this appendix.
3.2 Table II defines all the terms used in this appendix.
4.0 PROCEDURES FOR COMPLIANCE 4.1 Design Specification and Safety Analysis Report (a) The design options provided by the Code and related design criteria specified in the Code required Design Specification for ASME Class 1, 2, and 3 components, component supports, and Class CS core support structures should be summarized in sufficient detail in the Safety Analysis Report of the application to permit comparison with this Appendix.
(b) The presentation in the PSAR should specify and account for all design and service loadings, method of combination, the designation of the appropriate design and service stress limits (including primary and secondary stresses, fatigue consideration, and special limits on pressure when appropriate) for each loading combination presented, and the provisions for functional capability.
(c) The presentation in the FSAR should indicate how the criteria in Sections 1 and 2 of this appendix have been implemented.
(d) The staff may request the submission of the Code required Design Documents such as Design Specifications, Design Reports, Load Capacity Data Sheets, or other related material or portions thereof to establish that the design criteria, the analytical methods, and functional capability satisfy the guidance provided by this appendix.
This may include information provided to, and received from, component and support manufacturers.
As an alternative to the applicant submitting these documents, the staff may require them to be made available for review at the applicant's or vendor's office.
i 4.2 Use with Regulatory Guides The information and requirements contained in this appendix supersede those in the October 1973 version of Regulatory Guide 1.67 and the May 1973 version of Regulatory Guide 1.48.
Regulatory Guides 1.124 and 1.130 on Class 1 linear and Class 1 plate and shell component support structures are to be supplemented by this appendix.
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TABLE I Allowable Service Stress Limits for Specified Service Loading Combinations for ASME Class 1 Components and Class CS Support Structures System Service Service Stress Plant Event 2 Operating Conditions Loading Combination,4 Limit 1
1.
Normal Operation Normal Sustained Loads A
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Plant / System Operating Upset Sustained Loads + SOT + OBE B3 Transients (SOT) + OBE 3.
DBPB Emergency Sustained Loads + DBPB C3 w
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MS/FWPB Faulted Sustained Loads + MS/FWPB D3 w 5 Faulted Sustained Loads + DBPB or D3 h
. DBPB or MS/FWPB + SSE MS/FWPB + SSE 6.
LOCA Faulted Sustained Loads + LOCA D3 7.
Faulted Sustained Loads + LOCA + SSE D3 NOTE:
1The appropriate method of. combination is subject to review and evaluation.
Refer to Section 1.2.
2 Refer to Table II for definition of terms.
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3In addition to. meeting the specified service stress limits for given load combinations, operability and functional capability must also be demonstrated as discussed in Subsection 2.0 of this appendix and in SRP Section 3.10.
g 4These events must be considered in the pipe stress analysis and pipe support design process when specified in the ASME Code-required Design Specification. The Design Specification shall define the load and specify the applicable Code Service Stress Limit.
For clarification, it should be noted g
that the. potential for water' hammer and water (steam) hammer occurrence should also be given proper g
consideration in the development of. Design Specifications.
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TABLE II DEFINITION OF TERMS Active Pumps and Valves - A pump or valve which must perform a mechanical motion in order to shut down the plant or mitigate the consequences of a postulated event.
Safety and relief valves are specifically included.
Component and Support Functional Capability - Ability of a component, including its supports, to deliver rated flow and retain dimensional stability when the design and service loads, and their resulting stresses and strains, are at prescribed levels.
Component and Support Operability - Ability of an active component, including its support, to perform the mechanical motion required to fulfill its designated safety function when the design and service loads, and their resulting stresses and strains, are at prescribed levels.
DBPB - Design Basis Pipe Breaks - Those postulated pipe breaks other than a LOCA or MS/FWPB.
This includes postulated pipe breaks in Class 1 branch lines that result in the loss of reactor coolant at a rate less than or equal tc the capability of the reactor coolant makeup system.
This condition includes loads from the postulated pipe breaks, itself, and also any associated system transients or dynamic effects resulting from the postulated pipe break.
Design Limits - The limits for the design loadings provided in the appropriate subsection of Section III, Division 1, of the ASME Code.
Design Loads - Those pressures, temperatures, and mechanical loads selected as the basis for the design of a component.
Functional System - That configuration of components which, irrespective of ASME Code Class designation or combination of ASME Code Class designations, performs a particular function (i.e., each emergency core cooling system performs a single particular function and yet each may be comprised of some components which are ASME Class 1 and other components which are ASME Code Class 2).
LOCA - Loss-of-Coolant Accidents - Defined in Appendix A of 10 CFR Part 50 as "those postulated accidents that result from the loss of reactor coolant, at a rate in excess of the capabilit:, of the reactor coolant makeup system, from breaks in the reactor coolant pressure boundary, up to and including a break equivalent in size to the double-ended rupture of the largest pipe of the i
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This condition includes the loads from the postulated pipe break, itself, and (V
also any associated system transients or dynamic effects resulting from the postulated pipe break.
MS/FWPB - Main Steam and Feedwater Pipe Breaks - Postulated breaks in the main steam and feedwater lines.
For a BWR plant this may be considered as a LOCA event depending on the break location.
This condition includes the loads from the postulated pipe break, itself, and also any associated system transients or dynamic effects resulting from the postulated pipe break.
OBE - Operating Basis Earthquake - Defined in Section III (d) of Appendix A of 10 CFR Part 100 as "that earthquake which, considering the regional and local geology and seismology and specific characteristics of local subsurface material, could reasonably be expected to affect the plant site during the operating life of the plant.
It is that earthquake which produces the vibratory ground motion for which those features of the nuclear power plant, necessary for continued operation without undue risk to the health and safety of the public, are designed to remain functional."
This condition includes the loads from the postulated seismic event, itself, and also any associated system transients or dynamic effects resulting from the postulated seismic event.
pi Piping Components - These items of a piping system such as tees, elbows, bends, pipe and tubing, and branch connections constructed in accordance with v
the rules of Section III of the ASME Code.
Postulated Events - Those postulated natural phenomena (i.e., OBE, SSE),
postulated site hazards (i.e., nearby explosion), or postulated plant events (i.e., DBPB, LOCA, MS/FWPB) for which the plant is designed to survive without undue risk to the health and safety of the public.
Such postulated events may also be referred to as design basis events.
SSE - Safe Shutdown Earthquake - Defined in Section III(c) of Appendix A of 10 CFR Part 100 as "that earthquake which is based upon an evaluation of the maximum earthquake potential considering the regional and local geology and I
seismology and specific characteristics of local subsurface material.
It is l
the earthquake.which produces the maximum vibratory ground motion for which certain structures, systems, and components are designed to remain functional.
These structures, systems, and components are those necessary to assure:
(1) The integrity of the reactor coolant pressure boundary.
(2) The capability to shut down the reactor and maintain it in a safe shutdown condition, or (3).The capability to prevent or mitigate the consequences of accidents which could result -in potential offsite exposures comparable to the guideline."
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This condition includes the loads from the postulated seismic event, itself, and also any associated system transients or dynamic effects resulting from the postulated seismic event.
Service Limits - The four limits for the service loading as provided in the appropriate subsection of Section III, Division 1, of the ASME Code.
Service Loads - Those pressure, temperature, and mechanical loads provided in the Design Specification.
S0T - System Operating Transients - The transients and their resulting mechanical responses due to dynamic occurrences caused by plant or system operation.
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O1 3.9.3-20 Rev.1 - Aprf1 1984
l NUREG-0800 (Formerly NUREG 75/087) p aroo
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U.S. NUCLEAR REGULATORY COMMISSION
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1 STANDARD REVIEW PLAN OFFICE OF NUCLEAR REACTOR REGULATION l
Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants t
l Section No. 3.9.4 Revision No. 2 i
Appendix No. N/A Revision No. N/A Branch Tech. Position N/A Revision No.
N/A Date issued April 1984 l
FILING INSTRUCTIONS PAGES TO BE REMOVED NEW PAGES TO BE INSERTED PAGE NUMBER DATE PAGE NUMBER DATE 3.9.4-1 Rev. 1 July 1981 3.9.4-1 Rev. 2 April 1984 thru thru 3.9.4-8 3.9.4-9
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M The U.S. Nuclear Regulatory Commission's Standard Review Plan. NUREG-0000, prepared by the i
Office of Nuclear Reactor Regulation. is available for sale by the National Technical Information Service. Springfield, VA 22161.
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