ML20135J073
| ML20135J073 | |
| Person / Time | |
|---|---|
| Site: | 05000601 |
| Issue date: | 08/31/1985 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML19273A537 | List:
|
| References | |
| NUDOCS 8509250192 | |
| Download: ML20135J073 (5) | |
Text
1.0 INTRODUCTION
AND GENERAL DESCRIPTION OF PLANT
1.1 INTRODUCTION
l The Westinghouse Electric Corporation
.(hereinafter referred to as Westinghouse) has developed this Reference Safety Analysis Report (RESAR-SP/90) for the Westinghouse Advanced Pressurized Water Reactor (WAPWR) as. part of. its continuing ef forts toward design and licensing standardization of nuclear power plants.
RESAR-SP/90 is a standard safety analysis report submitted initially for Preliminary Design Approval (PDA) in accordance with Appendix 0, " Standardization.of Design; Staf f Review of Standard Designs," to Part 50 of Title 10 of the Code of Federal Regulations (hereinaf ter referred to as 10CFR).
The ultimate objective is to obtain a Final Design Approval j
(FDA) of RESAR-SP/90 followed by a
rulemaking proceeding and design certification.
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WAPWR-WM 1.0-1 AUGUST, 1985 2993e:1d
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i 1.2 GENERAL PLANT DESCRIPTION i
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l.2.2 Principal Desian Criteria i
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j RESAR-SP/90 is designed to comply with 10 CFR Part 50, Appendix A,
" General l
l Design Criteria for Nuclear Power Plants."
The specific applications of l
General Design Criteria to RESAR-SP/90 a r'e discussed in Section 3.1 of RESAR-SP/90 Module 7
" Structural / Equipment Design".
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1 1.6 MATERIAL INCORPORATED BY REFERENCE The WAPWR Waste Management Design Module incorporates, by reference, certain topical reports.
The topical reports, listed in Table 1.6-1, have been filed previously in support of other Westinghouse applications.
The legend for the review status code letter follows:
A U.S.
Nuclear Regulatory Commission review complete; USNRC l
acceptance letter issued.
AE -
U.S.
Nuclear Regulatory Commission accepted as part of the Westinghouse emergency core cooling system (ECCS) evaluation model j
only; does not constitute acceptance for any purpose other than i
for ECCS analyses.
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Submitted to USNRC as background information; no undergoing formal USNRC review.
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On file with USNRC: older generation report with current validity; j
not actively under formal USNRC review, i
Actively under formal USNRC review.
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1 ABLE 1.6-1 MATERIAL INCORPORATED BY REFERENCE l
Westinghouse SAR Topical Revision Section Submitted Review I
l ReDort No.
Title
_ Number Reference to the NRC Status 1
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i WCAP-8253 Source Term Data for Westinghouse Rev. 1 11.1 2/76 B
Pressurized Water Reactors l
CAP-8370 Westinghouse Water Reactor Divi-Rev. 9A 17.1 2/81 A
l sions Quality Assurance Plan Amend. 1 i
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l.8 CONFORMANCE WITH THE STANDARD REVIEW PLAN In accordance with 10CFR50.34(g), Table 1.8-1 of each PDA module identifies and evaluates deviations from the acceptance criteria of those sections of the NRC Standard Review Plan (NUREG-0800) pertinent to the subject module.
No deviations have been identified for.this module.
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