ML20070L506
| ML20070L506 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 07/13/1994 |
| From: | Russell W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070F169 | List: |
| References | |
| NUDOCS 9407180218 | |
| Download: ML20070L506 (2) | |
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DOCKET NO.52-001 GE NUCLEAR ENERGY (GE)
U.S. ABWR STANDARD DESIGN FINAL DESIGN APPROVAL (FDA)
PURSUANT TO 10 CFR PART 52. APPENDIX 0 (1)
GE has submitted to the Nuclear Regulatory Commission's (NRC) staff, for its review, a standardized design for a major portion of a nuclear power facility of the type described in 10 CFR Section 50.22.
GE's standard design is described in the U.S. ABWR Standard Safety Analysis Report (SSAR), including Amendments 1 through 35 thereto.
(2)
The SSAR contains design information required by 10 CFR Part 52, Appendix 0, Paragraph 3, for a standard design.
The U.S. ABWR standard design, whose scope is defined in SSAR Section 1.1.2, is for a nuclear power facility with a rated reactor core power level of 3926 megawatts thermal.
(3)
The NRC staff and the Advisory Committee on Reactor Safeguards (ACRS) have reviewed the U.S. ABWR standard design. The findings of the staff's evaluation of the U.S. ABWR standard design are presented in the Final Safety Evaluation Report (FSER), dated June 1994.
The ACRS reported on the application for design certification in a letter dated April 14, 1994 (see Chapter 21 of the FSER), as required by 10 CFR Section 52.53.
(4)
Based on its review and the findings given in the FSER, the staff concludes that the information provided in the SSAR, with respect to the U.S. ABWR standard design as described in paragraph 2 above, complies with the requirements of 10 CFR Part 52, Appendix 0.
(5)
The U.S. ABWR standard design is acceptable for use as a reference design for construction permit and operating license applications and combined license applications for facilities that are located at sites whose characteristics are within the envelope of site parameters given in the SSAR, and the out-of-scope portions of the plant that interface with the approved design conform to the interface requirements given in the SSAR.
(6)
This FDA and all applications for operating licenses incorporating it by reference, are subject to all applicable provisions of the Atomic Energy Act, as amended, and the rules and regulations and orders of the Commis-sion now or hereafter in effect.
9407180218 940713 PDR ADDCK 05200001 A
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. (7)
This FDA does not constitute a commitment to issue a permit, design certification, or license, or in any way affect the authority of the Commission, the Atomic Safety and Licensing Board, and other presiding officers, in any proceeding pursuant to 10 CFR Part 2.
(8)
This FDA is effective as of its date of issuance and will expire on July i3, 1999, unless extended by the staff. The expiration of this FDA shall not affect its use in applications docketed before such date.
Dated in Rockville, Maryland, this 13 day of July 1994.
FOR THE NUCLEAR REGULATORY COMMISSION hh Tl William T. Russell, Director Office of Nuclear Reactor Regulation I
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