ML19260C587

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Amend 1 to Preliminary Design Approval PDA-7 for Westinghouse SAR-35 NSSS Std Design
ML19260C587
Person / Time
Site: 05000545
Issue date: 12/21/1979
From: Vassallo D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19260C586 List:
References
NUDOCS 8001080060
Download: ML19260C587 (3)


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WESTINGHOUSE ELECTRIC COMPANY DOCKET NO. STN 50-545 REFERENCE SAFETY ANALYSIS REPORT (RESAR-35 NUCLEAR STEAM SUPPLY SYSTEM STANDARD DESIGN)

PRELIMINARY DESIGN APPROVAL (PDA)

Preliminary Desian Aoproval No. PDA-7 Amendment No. 1 (1) The Westinghouse Electric Corporation has submitted to the Nuclear Regulatory Commission's (NRC) staff for its review a proposed standardized preliminary design for major portions of a nuclear power reactor of the type described in 10 CF'. 50.22. The preliminary design is described in the Westinghouse Electric Corporation Standard Safety Analysis Report, RESAR-3S, along with 15 amendments thereto (hereinafter collectively referred to as RESAR-35).

(2) RESAR-35 contains preliminary design information in accordance with 10 CFR Part 50 Appendix 0, paragraph 3, for the nuclear steam supply system portion of a pressurized water reactor nuclear power plant, which encompasses the reactor coolant system, emergency core cooling system, reactor control and protection systems, engineered safety features actuation system, chemical and volune control system, boron recycle system, residual heat removal system, fuel handling equipment, and related systems and features. The RESAR-3S reference design is designed to operate at a core thermal power level of 3411 megawatts.

(3)

The RESAR-35 reference design has been reviewed by the '!RC staff and by the Advisory Comittee on Reactor Safeguards (ACRS). The results of the NRC staff evaluation of the RESAR-35 reference design are presented in the Safety Evaluation Rep' rt (SER), NUREG-0104, dated Decenber 1976.

The ACRS comments are set forth in its letter of July 14, 1976 (Appendix C of the SER).

1701 305 8001080 dh

2 (4) Based on its review, and the findings set forth in Section 19 of the SER, the NRC staff has concluded that, subject to the conditions set forth herein, the information provided in RESAR-3S with respect to the major portions of the preliminary design encompassed by RESAR-35, as described in paragraph 2 above, complies with the requirements of 10 CFR Part 50, Appendix 0 and is acceptable for incorporation by reference in applications for construction permits.

In accordance with 10 CFR Part 50, Appendix 0, subject to the conditions set fort,h herein and in Appendix 0, the approved design shall be utilized and relied upon by the staff and the ACRS in their review of any individual facility license applicatio which incorporates by reference the approved design, unless there exists significant new informttion which substantially affects the determination set forth in this Preliminary Design Approval or other good cause.

(5) RESAR-3S and the RESAR-3S reference design are acceptable for use as a reference design for construction permit applications:

-(a) for facilities to be located at sites whose characteristics conform to the envelope of site parameters postulated for the preliminary design of the RESAR-3S reference design, which are set forth in RESAR-35, provided that (b) the design of pcrtions of the balance of plant which interface with the approved design shall conform to the safety-related interface requirements set forth in RESAR-35 and in the SER.

(6)

(a) This Preliminary Cesign Approval is subject to the satisfactory resolution of the matter of reactor conidown using only safety-grade systems.

(b) The status on this matter shall be addressed in applications for construction permits referencing RESAR-3S and will be considered in the staff review of such applications.

(7) This Preliminary Design Approval is subject to the satisfactory and timely submission of further information concerning the matters of (a) anticipated transients without scram, (b) seismic and environmental qualification of electrical equipment, and (c) fire protection.

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. (8 ) This Preliminary Design Approval is subject to a review by the Nuclear Regulatory Cornission staff to confim the adequacy of the Westinghouse Electric Corporation responses to the PDA-7 extension review matters contained in Amendments 14 and 15 to the RESAR-3S Safety Analysis Report and any additional licensing requirements resulting from our review of the accident at Three Mile Island, Unit 2 on March 28, 1979. Such a review would be conducted after the Nuclear Regulatory Commission staff it infomed by a utility-applicant that it intends to reference the RESAR-3S design in a construction pemit application filed after December 30, 1979.

Such a review would be scheduled for completion prior to the tendering of the utility application.

(9 ) This Preliminary Design Approval and all applications for construction pemits incorporating it by reference, are subject to all applicable provisions of the Atomic Energy Act of 1954, as amended, and the rules and regulations and Orders o.f the Comission now or hereafter in effect.

(10)

This Preliminary Design Approval does not constitute a cocmitment to issue a pemit or license or in any way affect the authority of the Comission, Atomic Safety and Licensing Appeal Board, Atenic Safety and Licensing Boards and other presiding officers in any proceeding under Subpart G of 10 CFR Part 2.

(11)

This Preliminary Design Approval is effective as of its date of issuance and shall expire on December 30, 1981 unless earlier superseded by the issuance of a Final Design Approval for the RESAR-3S reference design, or unless extended by the NRC staff. The expiration of this PDA on December 30, 1981 shall not affect the use of this PDA for reference in any construction pemit application docketed prior to such date.

FOR THE hUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Acting Director Division of Project Management Office of Nuclear Reactor Regulation Date of Issuance:

DEC 3 1 1979 1701 307