ML20213F702

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Nonproprietary Chapter 1, Introduction & General Description of Plant, of RESAR-SP/90 Westinghouse Advanced PWR Module 13, Auxiliary Sys
ML20213F702
Person / Time
Site: 05000601
Issue date: 10/31/1986
From:
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML19292G244 List:
References
NUDOCS 8611170036
Download: ML20213F702 (6)


Text

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1.0 INTRODUCTION

AND GENERAL DESCRIPTION OF PLANT

1.1 INTRODUCTION

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 efforts 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; Staff Review of Standard Designs," to Part 50 of Title 10 of the Code of Federal Regulations (hereinaf tnr referred to as 10CFR). The ultimate objective is to obtain a Final Design Approval (FDA) of RESAR-SP/90 followed by a rulemaking proceeding and design certification.

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WAPWR-AS 1.1-1 OCTOBER, 1986 5539e:1d 8611170036 861029 PDR ADOCK 05000601 K

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i 1.2 GENERAL PLANT DESCRIPTION t

i 1.2.2 Principal Design Criteria RESAR-SP/90 is designed to comply with 10 CFR Part 50, Appendix A " General

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Design Criteria for Nuclear Power Plants." The specific applications of General Design Criteria to RESAR-SP/90 are discussed in Section 3.1 of l

RESAR-SP/90 Module 7, " Structural / Equipment Design.

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WAPWR-AS 1.2-1 OCTOBER, 1986 i

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i 1.6 MATERIAL INCORPORATED BY REFERENCE I

The WAPWR Radiation' Protection Module incorporates, by reference, certain topical reports. The topical reports, listed in Table 1.6-1, have been filed O

previously in support of other Westinghouse applications.

The legend for the review status code letter follows:

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U.S. Nuclear Regulatory Commission review complete; USNRC acceptance letter issued.

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U.S. Nuclear Regulatory Commission accepted as part of the Westinghouse emergency core cooling system (ECCS) evaluation model only; does not constitute acceptance for any purpose other than for ECCS analyses.

B Submitted to USNRC as background information; no undergoing formal USNRC review.

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0 On file with USNRC: older generation report with current validity; i

not actively under formal USNRC review, i

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U Actively under formal USNRC review, i

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O WAPWR-AS 1.6-1 OCTOBER, 1986 5539e:1d

TABLE 1.6-1 MATERIAL INCORPORATED BY REFERENCE Westinghouse SAR Topical Revision Section Submitted Review Report No.

Title Number Re!'erence to the NRC Statu WCAP-8370 Westinghous'e Water Reactor Divi-Rev. 9A 17.1 2/81 A

sions Quality Assurance Plan Amend. 1 O

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O WAPWR-AS 1.6-2 OCTOBER, 1986 5539e:1d

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i 1.8 CONFORMANCE WITH THE STANDARD REVIEW PLAN

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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

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NRC Standard Review Plan (NUREG-0800) pertinent to the subject module.

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Table 1.8-1 provides this list for the " Auxiliary Systems."

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WAPWR-AS 1.8-1 OCTOBER, 1986 i

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TABLE 1.8-1 STANDARD REVIEW PLAN DEVIATIONS O

SRP Acceptance Criteria Deviation Section SRP 12.3 The design of the fuel pit 9.1.1.5 12.4 racks precludes criticality 9.1.2.5 Describe the radiation instru-under all postulated normal mentation that will be used to and accident conditions. There-meet the criticality accident fore, criticality monitors, monitoring requirements of as required by 10 CFR 70.24 70.24 of 10 CFR Part 70 for and Regulatory Guide 8.12, are storage area for new fuel.

not needed.

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l WAPWR-AS 1.8-2 OCTOBER, 1986 5539e:1d

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