ML20249C160

From kanterella
Jump to navigation Jump to search
Transmits Revised Fda for Sys 80+ Design,Per App O of 10CFR52.Duration of Fda Conforms W/Duration of Design Certification Rule for Sys 80+ Std Design
ML20249C160
Person / Time
Site: 05200002
Issue date: 06/24/1998
From: Collins S
NRC (Affiliation Not Assigned)
To: Matzie R
ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
Shared Package
ML20249C161 List:
References
NUDOCS 9806260130
Download: ML20249C160 (4)


Text

_ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _

e ,

June 24, 1998 Dr. Regis A. Matzie Vice President, Nuclear Systems ABB-Combustion Engineering, Inc, P.O. Box 500 2000 Day Hill Road Windsor, CT 06095-050 y.

Dear)d. Matzie This letter transmits a revised final design approval (FDA) for the System 80+c..JEid design, issued pursuant to Appendix 0 of 10 CFR Part 52. This FDA supersedes the FDAs issued on July 26 and November 23,1994. The FDA allows the System 80+ design to be referenced in an application for a construction 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 System 80+ standard design.

Sincerely, Gijsblsignedby SW11U81.I.Colline Samuel J. Collins, Director Office of Nuclear Reactor Regulation Docket No.52-002

Enclosures:

1. FDA for the System 80+

standard design

2. Federal Reoister Notice cc w/ encl: See next page _ _ _

plSTRIBUTION: h F N YIIF Docket File PDST R/F .

PUBLIC JNWilson SCollins/FMiraglia,0-12 G18 DScaletti 4 JRoe Tounv g JMoore,0-15 B18 ACRS (11) .

4f ,}

l 9006260130 990624 e ADOCK 05200002 PDR A PM ,

uvvvMcNI NAMt-: A:CETRAN.JNW *See previous concurrence Ta receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure " " = Copy with attachment / enclosure "N" = No copy is OFFICE . SPA:PDST:DRPM , OGC l D:PDST:DRPM D (A)((DEPM pn QA8Eyf l NAME JNWilson:sW# RWeisman F- TRQuay SM JWRoe D$JCollins

~

DATE 05/ t1/98 V/) "

05/11/98 05/ O/98 05h-l /98 d6T&/98 OFFICIAL RECORD COPY 45 j Sse. /W OCl y(

o

ABB-Combustion Engineering, Inc. Docket No.52-002 cc: Mr. C. B. Brinkman, Manager Mr. B. A. McIntyre Washington Nuclear Operations Advanced Plant Safety & Licensing ABB-Combustion Engineering, Inc. Westinghouse Electric Corporation 12300 Twinbrook Parkway, Suite 330 Energy Systems Business Unit Rockville, MD 20852 Box 355 Pittsburgh, PA 15230 Mr. Stanley E. Ritterbusch, Manager .

Standard Plant Licensing ABB-Combustion Engineering Post Office Box 500 1000 Prospect Hill Road Windsor, CT 06095-0500 Mr. Sterling Franks U.S. Department of Energy NE-42 Washington, DC 20585 Mr. Joseph R. Egan, Esquire Egan & Associates, P.C.

2300 N Street, NW., Suite 600 Washington, DC 20037-1128 Mr. Emest L. Blake, Jr.

Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW.

Washington, DC 20037 Mr. Russ Bell Senior Project Manager, Programs Nuclear Energy Institute 1776 i Street, NW.

Suite 300 Washington, DC 20006-3708 Barton Cowan, Esq.

Ecker1 Seamans, Cherin & Mellot 600 Grant Street 42nd Floor

. Pittsburgh, PA 15219 l

I 1

s* p DOCKET NO.52-002 ABB-COMBUSTION ENGINEERING. INC. (ABB-CE)

SYSTEM 80+ STANDARD DESIGN FINAL DESIGN APPROVAL (FDA)

PURSUANT TO 10 CFR PART 52. APPENDIX O (1) ABB-CE 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. ABB-CE's System 80+ standard plant design is described in the Combus-tion Engineering Standard Safety Analysis Report- Design Certification (CESSAR-DC),

including Amendments A through X thereto.

(2) The CESSAR-DC contains design information required by 10 CFR Part 52, Appendix O, Paragraph 3, for a standard design. The System 80+ standard design, whose scope is defined in CESSAR-DC Section 1.1.1, is for a nuclear power facility with a rated reactor core power level of 3914 megawatts thermal.

(3) The NRC staff and the Advisory Committee on Reactor Safeguards (ACRS) have reviewed the System 80+ standard design. The findings of the staff's evaluation of the System 80+

standard design are presented in the Final Safety Evaluation Report (FSER), dated August 1994 (NUREG-1462) and Supplement No.1 to NUREG 1462, dated May 1997.

The ACRS reported on the application for design codification in a letter dated May 11, 1994, as required by 10 CFR 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 information in the CESSAR-DC, with respect to the l System 80+ standard design as described in paragraph 2 above, complies with the l requirements of 10 CFR Part 52, Appendix O.

(5) The System 80+ standard design is acceptable for use as a reference design for construc-tion 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 CESSAR-DC, and the out-of scope portions of the plant that interface with the approved design conform to the interface requirements given in CESSAR-DC.

(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, 3 regulations, and orders of the Commission now or hereafter in effect. l l

I Enclosure 1

s*  ;,

l l (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 Par 12.

(8) This FDA is effective on the date of issuance and will expire on June 20,2012, unless extended by the staff, and supersedes previous FDAs for the System 80+ standard design.

The expiration of this FDA shall not affect its use in applications docketed before such date.

3 Dated in Rockville, Maryland, thid day of JVMt 1998.

FOR THE NUCLEAR REGULATORY COMMISSION k ector Office of Nuclear Reactor Regulation

.._____.________-__w