ML20153A923

Preliminary Design Approval PDA-13 for Westinghose Elec RESAR-414 Nuc Steam Supply Sys Standard Design

ML20153A923
Person / Time
Site:	05000572
Issue date:	11/14/1978
From:	Boyd R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20153A912	List: ML20153A918 ML20153A923 NUREG-0491, Notice of Issuance of SER NUREG-0491 & Preliminary Design PDA-13 for Nuc Steam Supply Sys Portion of Nuc Pwr Plant as Described in Westinghouse Rept RESAR-414. W/O NUREG-0491
References
NUDOCS 7811290006
Download: ML20153A923 (3)

Text

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WESTINGHOUSE ELECTRIC CORPORATION DOCKET NO. STN 50-572 REFERENCE SAFETY ANALYSIS REPORT (RESAR-414 NUCLEAR STEAM SUPPLY SYSTEM STANDARD DESIGN)

PRELIMINARY DESIGN APPROVAL (PDA)

Preliminary Design Approval No. PDA-13

l. The Westinghouse Electric Corporation has submitted a proposed standardized preliminary design for the nuclear steam supply system of a nuclear power reactor of the type described in 10 CFR 50.22 to the Nuclear Regulatory Commission (NRC) staff for its review.

The preliminary design is described in Westinghouse Electric Corporation Standard Safety Analysis Report, RESAR-414, along with 19 amendments thereto (herinafter collectively referred to as RESAR-414).

2. RESAR-414 contains prel)minary design information in accordance with 10 CFR Part 50 Appendix 0, p=raph 3, for the nuclear steam supply system portion of a pressuri: der reactor nuclear power plant, which encompasses the rea: tor . ant system, emergency core cooling system, reactor control systems, integrated reactor protection and engineered safety features actuation system, chemical and volume control system, boron recycle system, residual heat removal system, fuel handling equipment, and related systems and features. The RESAR-414 reference system design is designed to operate at a core thermal power level of 4100 megawatts but, in accordance with Regulatory Guide 1.49, " Power Levels of Nuclear Power Plants," the application for the Preliminary Design Approval was based on a core thermal power level of 3800 megawatts.

3. The RESAR-414 reference system design has been reviewed by the NRC staff and by the Advisory Comittee on Reactor Safeguards (ACRS). The results of the NRC Staff evaluation of the RESAR-414 reference system design are presented in the Safety Evaluation Report (SER), NUREG-0491 dated November 1978. The ACRS comments are set forth in its letter of August 10, 1978 (Appendix E of the SER).

4. Based on its review, and the findings set forth in Section 19 of the SER, the NRC staff has concluded that, subj':ct to the conditions set forth herein, the information provided in RESAR-414 with respect to the portions of the preliminary design encompassed by RESAR-414, 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 l-

'811290006

with 10 CFR Part 50, Appendix 0, subject to the conditions set forth 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 construction permit application which incorporates by reference the approved design, unless significant new information which substantially affects the determination set forth in this Preliminary Design Approval, or other good cause is present.

5. RESAR-414 and the RESAR-414 reference system design are acceptable for use as a reference system design for construction permit applications for facilities to be located at sites whose characteristics conform to the envelope of site parameters postulated fer the preliminary design of the RESAR-414 reference system design, which are set forth in RESAR-414, provided that the design of portions of the balance of plant which interface with the approved design shall conform to the safety-related interface requirements set forth in RESAR-414 and in the SER.

6. This Preliminary Design Approval is subject to the satisfactory and timely completion of the development and verification test programs described in Table 1-3 of the SEh and is subject to the requirements for utility-applicants referencing RESAR-414 identified in Appendix F and elsewhere throughout the SER.

7. This Preliminary Design Approval and all applications for construction permits 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 of the Commission now or hereafter in effect.

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

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9. This Preliminary Design Approval is effective as of its date of issuance and shall expire on November 14, 1983, unless superseded earlier by the issuance of a Final Design Approval for the RESAR-414 reference system design or extended by the NRC staff. This expiration of this PDA on November 14, 1983, shall not affect the use of this PDA for reference in any construction permit application docketed prior to such date.

FOR THE NUCLEAR REGULATORY COMMISSION er S. B Direct r Division Of Project Manageme Office of Nuclear Reactor Regulation Date of Issuance:

November 14, 1978