ML20090D307
| ML20090D307 | |
| Person / Time | |
|---|---|
| Site: | 05000601 |
| Issue date: | 06/30/1984 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML19273A237 | List: |
| References | |
| NUDOCS 8407180186 | |
| Download: ML20090D307 (5) | |
Text
3.0 DESIGN OF STRUCTURES, COMPONENTS. E0VIPMENT. AND SYSTEMS i
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3.1 CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA g-i'
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i This section briefly outlines the General Design Criteria (GDC) applicable to the reactor coolant system of the Westinghouse Advanced Pressurized Water l
Reactor (WAPWR) per Title 10, Code of Federal Regulations, Part 50 (10CiR50),
Appendix A, " General Design Criteria for Nuclear Power Plants".
As presented in this section, each criterion is listed to denote applicability to the the
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reactor coolar.t system (see Table 3.1-1).
i A detailed discussion of the compliance with each criterion is provided in r
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RESAR-SP/90 PDA Module 7, " Structural / Equipment Design".
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TABLE 3.1-1 GDC APPLICABLE TO RCS l
Criterion Title O
1 Quality standards and records.
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Design bases for protection against natural phenomena 3
Fire protection 4
Environmental and missile design bases 5
Sharing of structures, systems and components l
10 Reactor design 13 Instrumentation and control i
14 Reactor coolant pressure boundary l
15 Reactor coolant system design l
19 Control room i
30 Quality of reactor coolant pressure boundary Fracture prevention of reactor coolant pressure boundary 31 32 Inspection of reactor coolant pressure boundary 44 Cooling water 45 Inspection of Cooling Water System f
46 Testing of Cooling Water System
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54 Piping systems penetrating containment 55 Reactor coolant pressure boundary penetrating containment I
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l 3.2 CLASSIFICATION OF STRUCTURES. COMPONENTS. AND SYSTEMS i
Certain structures, components, and systems of the RCS are important to safety because they:
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a.
Assure the integrity of the reactor coolant pressure boundary, i
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Assure the capability. to shut down the reactor and maintain it in a safe condition.
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Assure the capability to prevent or mitigate the consequences of acct-(
dents which could result in potential offsite exposures comparable to j
l the guideline exposures of 10 CFR 100.
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Contain or may contain radioactive material.
The purpose of this section is to classify structures, systems, and components r
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according to the importance of the item in order to provide reasonable assur-P ance that the facility can be operated without undue risk to the health and l.
saf ety of the public.
Table 3.2-1 delineates each of the items in the plant
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l which fall under the above-mentioned categories and the respective associated l
classification that the NRC, ANS, and industrial codes committees have devel-i oped.
Each of the classification categories in Table 3.2-1 is addressed in the following sections.
I The classification of specific piping runs and valves in these runs is pro-O vided in the RCS flow diagrams contained in this module.
Instrumentation and electrical equipment required to shut down the plant or mitigate an accident which is associated with the RCS will be classified as 1E (or Safety Class 3 A
per ANS 51.1) and identified in the appropriate module.
Additional information regarding the classification of structures, components, and systems is pr'ovided in RESAR-SP/90 PDA Mcdule 7
" Structural / Equipment l
O Design".
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P 3.2.1 Seismic Classification Seismic' classification criteria are set forth in 10 CFR 100 and supplemented I
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All components classified as Safety Class 1, 2, or 3 (classifications are as defined by Reference 1) are seismic Category I.
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Seismic Category I structures, components, and systems are designed to withstand the Safe Shutdown Earthquake (SSE) and other applicable load combinations, as discussed in RESAR-SP/90 PDA Module 3
" Introduction and l
Site" and Module 7,
" Structural / Equipment Design".
Seismic Category I structures are sufficiently isolated or protected from the other structures to f
ensure that their integrity is maintained.
t 3.2.2 System Ouality Group Classification l
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.The compcnents are classified according to their importance to safety, as dictated by service and functional requirements and by the consequences of their failure.
The quality assurance requirements and code requirements for l
the RCS meet the intent of Regulatory Guide 1.26.
3.2.3 Safety Classes j
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Table 3.2-1 lists the safety class assigned to applicable systems and components in accordance with ANS 51.1 (Ref. 1).
The criteria (of Ref.1) are used in the plant design to provide an added degree of assurance that the
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plant is designed, constructed, and operated without undue risk to the health and safety of the public.
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3.2.4 References 1.
" Nuclear Saf ety Criteria for the Design of Stationary Pressurized Water l
Reactor Plants," ANS-51.1, November 1983.
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CLASSIFICATION OF STRUCTURES, SYSTEMS, AND COMPONENTS V
FOR THE REACTOR COOLANT SYSTEM Principi1 Con-ANSI Safety Quality Code struction Codes Seismic em/ om onent location Class Assurance Class and Standards Category Reactor Vessel IC 1
Note 1 1
ASME III I
Stean Generators-Primary IC 1
Note 1 1
ASME III I
Secondary IC 2
Note 1 2
ASME III I
Lussurizer IC 1
No?e 1 1
ASME III I
Reactor Coolant Pumps IC 1
Note 1 1
A5ME III I
Pressurizer Relief Tank IC 3
Note 2 3
ASME III I
Piping IC/0C 1/2/3 Note 1/2 1/2/3 ASME III I
Valves IC/0C 1/2/3 Note 1/2 1/2/3 ASME III I
Meet, " Quality Control System Requirements,' Westinghouse QCS-1, which 1
satisfies requirements of 10CFR50, Appendix B,
Quality Assurance Criteria.
Meets " Quality Control System Requirements," Westinghouse QCS-2, which N te 2 satisfies requirements of 10CFR50, Appendix B.
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