ML20210J359
| ML20210J359 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 08/11/1997 |
| From: | Collins S NRC (Affiliation Not Assigned) |
| To: | Quirk J GENERAL ELECTRIC CO. |
| Shared Package | |
| ML20210J365 | List: |
| References | |
| NUDOCS 9708180055 | |
| Download: ML20210J359 (4) | |
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-August 11,'1997 Mr. Joseph-Quirk ABWR Certification Program Manager
' GE Nuclur Energy--
'175 Curtner Avenue, Mail Code-782 San Jose,. California 95125
Dear;Mr. Quirk:
This letter transmits,a revised final design approval (FDA) for the U.S.
advanced boiling-water reactor (ABWR) standard design, pursuant to Appendix 0 of 10 CFR Part 52. This FDA supersedes.the FDAs. issued on July 13 and November 23, 1994. The FDA allows the ABWR standard ' design to be referenced in an application for a construct son permit or operating license pursuant to
'10 CFR Part 50, or in an application for a combined license pursuant to 10 CFR Part.52.
The duration of this FDA conforms with the duration of the design certification rule for the U.S. ASWR design.
Sincerely, 1
Originalsignedb)r SamuelJ. Collins Samuel J. Collins, Director Office of Nuclear Reactor Regulation Docket No.52-001
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FDA for U.S. ABWR standard design
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i Mr. Joseph Quirk
. Docket No. 52-001-GE Nuclear Energy l l
cc: Mr. Steven A. Hucik Mr. Ronald Simard, Director GE Nuclear Energy Advanced Reactor Programs 175 Curtner Avenue, Mail Code 782
-Nuclear Energy Institute San Jose,-CA 95125 1776 Eye Street, N.W.
Suite 300 Mr. Rob Wallace Washington, DC 20086 GE Nuclear Energy 1299 Pennsylvania Ave., N.W.
Mr. B. A. McIntyre
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Suite.1100 Advanced Plant Safety & Licensing 4
Washington, D.C.
20004 Westinghouse Electric Corporation Eu rgy Systems Business Unit
= Director, Criteria & Standards Divistor:
Box 355 Office of Radiation Programs Pittsburgh, PA 15230 U.S. Environmental Protection Agency 401 M. Street, S.W.
Mr. Joseph R. Egan Washington, DC 20460 Egan & Associate:;, P.C.
2300 N Street, N.W.-
Mr. Sterling Franks Washington, DC C0037-1138 U. S. Department of Energy NE-42
-Barton Z. Cowan, Esq.
Washington, DC 20585 Eckert Seamans Cherin & Mellott d Floor
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A DOCKET NO.52-001 GE: NUCLEAR ENERGY (GE)
U.S. ABWR STANDARD DESIGN i-f)NAL DESIGN APPROVAL (FDA) l PURSUANT TO 10 CFR PART 52. APPENDIX 0 (1) GE has submitted to the Nuclear Regulatory Commission (NRC) staff, for its review, a standardized design for a major portion of a nuclear power facility of the type described in 10 CFR 50.22. GE's standard design is described in the U.S. ABWR Standard Safety Analysis Report (SSAR),
including Amendments I through 37 (Revision 9) thereto.
i (2) The SSAR contains design information required by 10 CFR Part 52, Appen-dix 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 Reacter Safeguards (ACRS) i 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 July 1994 (NUREG-1503) and Supplement No. I to NUREG-1503 dated May 1997. The ACRS reported on the application for design certification in letters dated April 14, 1994, and August 15, 1996, as required by 10 CFR Section 52.53.
(4) On the basis of its review and the findings reported in the FSER and the supplement.thereto, the staff concludes that the infcrmation 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 tha cut-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.
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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 officers In sny proceeding pursuant to 10 CFR Part 2.the Atomic Safety and L (8) This FDA is effective as of its date of issuance and will expire on June 11, 2012, unless extended by the staff, and supersedes previous FDAs for the U.S. ABWR design. The ex)f ration of this FDA shall not affect its use in applications docketed >efore such date.
Dated in Rockville, Maryland, this 11thday of August 11, 1997.
4 FOR THE NUCLEAR REGULATORY COMMISSION a ue -c.
c) tor Office of Nuclear Reactor Regulation 4
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