View source for 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

{{Adams
| number = ML20153A907
| issue date = 11/14/1978
| title = 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
| author name = Varga S
| author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| addressee name = 
| addressee affiliation = 
| docket = 05000572
| license number = 
| contact person = 
| document report number = NUDOCS 7811290003
| title reference date = 11-14-1978
| package number = ML20153A912
| document type = FEDERAL REGISTER NOTICES, TEXT-CODE OF FEDERAL REGULATIONS
| page count = 4
}}

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MRC PITPIJO DOCU7JENT DOOM UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKETNO.STN50-572lh WESTINGHOUSE ELECTRIC CORPORATION REFERENCE SAFETY ANALYSIS REPORT (RESAR-414 NUCLEAR STEAM SUPPLY-SYSTEM STANDARD DESIGN)
NOTICE OF ISSUANCE OF A SAFETY EVALUATION REPORT AND PRELIMINARY DESIGN APPROVAL                          ,
Notice is hereby given that the Staff of the Nuclear Regulatory Commission (the NRC Staff) has issued a Safety Evaluation Report (SER) dated November 1978, and a Preliminary Design Approval No. PDA-13 dated November 14, 1978, for the nuclear steam supply system portion of a nuclear power plant as described in the Westinghouse Electric Corporation Reference Safety Analysis Report (RESAR-414). RESAR-414 was reviewed by the NRC Staff pursuant to Appendix 0 to 10 CFR Part 50.
RESAR-414 contains preliminary safety-related design information for the nuclear steam supply system portion of a pressurized water reactor nuclear power plant which includes the reactor coolant system, emergency core cooling system, reactor control systems, integrated reactor protection and engineered safety features actuation system,          r 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 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.
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The SER documents the results of the Staff's review and evaluation       i of RESAR-414, including Amendments 1 through 19 thereto. 'The SER addresses    !
l           the comments of the Advisory Comittee on Reactor Safeguards (ACRS) as reflected in its report to the Commission, dated August 10, 1978. A copy of the ACRS report is included as Appendix E to the SER.
PDA-13 provides NRC Staff approval of the preliminary nuclear steam supply system design described in RESAR-414, including Amendments 1             l through 19 and described and evaluated in Sections 1 through 19 of the SER.
By the issuance of PDA-13, the NRC Staff has determined that the i
!           design is acceptable for referencing in utility applications for l
construction permits. RESAR-414 and the RESAR-414 reference system design, subject to the conditions of PDA-13, shall be utilized by and relied upon by the NRC Staff and the ACRS in their review of 1
facility license applications for construction permits incorporating the RESAR-414 nuclear steam supply system preliminary standard design             i l
by reference, unless significant new information which substantially              l affects the determinations in PDA-13, or other good cause is present.
Issuance of PDA-13 and the Staff's Safety Evaluation Report does not      i l
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 I

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officers in any proceeding under Subpart G of 10 CFR Part 2. This action only approves the preliminary design of a nuclear steam supply system for use for reference purposes in applications for permits to construct a nuclear power plant. It does not authorize the con-struction or operation of any nuclear power plant or any other facility.
The environmental impacts associated with any facility proposed to be constructed utilizing the. approved reference system design will be considered in accordance with the Commission's regulations in 10 CFR Part 51.
PDA-13 is effective as of its date of issuance and shall expire on November 14, 1983, unless superseded earlier by issuance of an appropriate Final Design Approval for the RESAR-414 nuclear steam supply system standard design. The expiration of PDA-13 on November 14, 1
1983, shall not affect use of PDA-13 for reference in any construction permit application docketed prior to such date.
A copy of (1) the Preliminary Design Approval No. PDA-13 dated          l November 14,1978;(2) the report of the Advisory Committee on Reactor Safeguards dated August 10,.1978; (3) the NRC Staff's Safety Evaluation Report (NUREG-0491), dated November 1978; (4) the Westinghouse Electric Corporation Reference Safety Analysis Report, and Amendments 1 through 19 thereto; and (5) WASH-1341, the Commission's " Programmatic Information for the Licensing of Standardized Nuclear Power Plants," dated August 1974, (which also ' includes the Standardization Policy issued on March 5,1973),
as further augmented by NUREG-0427, " Review of the Connission Program      -
for Standardization of Nuclear Power Plants and Recommendations

to Improve Standardization C'oncepts" and the Commission Policy Statement on August 22,.1978 are available for public inspection at the Commission's Public Document Room at 1717 H Street, N. W., Washington D. C. -20555.
A copy of,PDA-13 may be abtained upon request. The request should be addressed to the U. ".. Nuclear. Regulatory Commission, Washington',
D. C. 20555, Attention: Director, Division of Project Management.                         1 Copies of~the Safety Evaluation Report (Document No. NUREG-0491) or of NUREG-0427 may be purchased at current rates from the National Technical Information Service, Department of Commerce, 5285 Port Royal Road, Springfield, Virginia 22161.
Dated at Bethesda, Maryland, this 14th day of November 1978.
FC   THE NUCLEAR RE             ATORY COMMISSION gtevenA.Vaga.         ,
Light Water Reactors Br u
blef No. 4 Division of Project Management l
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