ML20239A148
| ML20239A148 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 09/03/1998 |
| From: | Collins S NRC (Affiliation Not Assigned) |
| To: | Mcintyre B WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| Shared Package | |
| ML20239A150 | List: |
| References | |
| NUDOCS 9809080268 | |
| Download: ML20239A148 (4) | |
Text
(
l September 3, 1998 l
Mr. Bri:n A. McIntyrs, M: nag:r Adv:nced Pl nt Saf:ty end Licensing
)
Energy Systems Business Unit Westinghouse Electric Company l
P.O. Box 355 l
Pittsburgh, PA 15230-0355
SUBJECT:
MNAL DESIGN APPROVAL (FDA) FOR AP600 1
Dear Mr. McIntyre:
This letter provides the FDA for the AP600 standard nuclear reactor design (Enclosure 1) and the Nuclear Regulatory Commission's (NRC's) Notice of Issuance of an FDA (Enciosure 2).
j This FDA allows the AP600 design to De referenced in an application for a construction permit i
or operating license under 10 CFR Part 50, or an application for a combined license under 1
Issuance of this FDA signifies completion of the technical review phase of Westinghouse's application for certification of the AP600 design. The NRC staff performed its technical review l
of the AP600 Standard Safety Analysis Report, Probabilistic Risk Assessment, and Tier 1 Material in accordance with the standards for review of design certification applications set forth in 10 CFR 52.48 that were applicable and technically relevant to the AP600 design or were modified by the exemptions identified in the NRC's final safety evaluation report (FSER). On the basis of its evaluation and independent analyses, as described in the FSER, the NRC staff concludes that Westinghouse's application for design certification meets the applicable portions of 10 CFR 52.47 and the review standards set forth above. In addition, the AP600 design is ready for the rulemaking phase, subject to satisfactory completion of the AP600 design control document (DCD). Therefore, the NRC staff and Advisory Committee on Reactor Safeguards will utilize the AP600 DCD and will rely on it in the rulemaking (administrative review) phase of the design certification process pursuant to 10 CFR 52.51.
The duration of this FDA is for 5 years, in accordance with the Commission's Standardization
[l Policy of August 1978, and the intent of 10 CFR Part 52. If the AP600 design is subsequently certified, then this FDA will be updated, as needed, to conform to any changes resulting from the design certification rulemaking and will be in effect for the duration of the design certification pp) rule. If you have questions on this document, please contact Jerry N. Wilson at 301-415-3145.
Sincerely, nma _
- C ' -. < ; ;':;{ N original signed by:
9909090268 990903 Samuel J. Collins, Director PDR ADOCK 05200003 Office of Nuclear Reactor Regulation E
PDR Docket No.52-003 DISTRIBUTION.
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Enclosures:
As stated PUBLIC JRoe DMatthews TQuay cc w/encis: See next page JNWilson JMoore,0-15 B18 DOCUMENT NAME: A:\\FDA-LTR.JNW To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with cttachment/ enclosure "N" = No copy A
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Mr. Brian A. McIntyre Docket No.52-003 Westinghouse Electric Corporation AP600 cc:
Mr. H. A. Sepp -
Mr. Russ Bell Advanced Plant Safety & Licensing Senior Project Manager, Programs Westinghouse Electric Corporation Nuclear Energy Institute Energy Systems Business Unit 17761 Street, NW P.O. Box 355 Suite 300 Pittsburgh, FA 15230 Washington, DC 20006-3706 Ms. Susan Fanto Ms. Lynn Connor Advanced Plant Safety & Ucensing Doc-Search Associates Westinghouse Electric Corporation Post Office Box 34 Energy Systems Business Unit Cabin Johc. MD 20818 P.O. Box 355 Pittsburgh, PA 15230 Dr. Craig D. Sawyer, Manager
~ Advanced Reactor Programs Mr. Sterling Franks GE Nuclear Energy U.S. Department of Energy 175 Curtner Avenue, MC-754 NE-50 San Jose, CA 95125 19901 Germantown Road Germantown, MD 20874 Mr. Robert H. Buchholz GE Nuclear Energy Mr. Frank A. Ross 175 Curtner Avenue, MC-781 U.S. Department of Energy, NE-42 San Jose, CA 95125 Office of LWR Safety and Technology 19901 Germantown Road Barton Z. Cowan, Esq.
Germantown, MD 20874 Eckert Seamans Cherin & Mellott 600 Grant Street 42nd Floor Mr. Charies Thompson, Nuclear Engineer Pittsburgh, PA 15219 AP600 Certification NE-50 Mr. Ed Rodwell, Manager 19901 Germantown Road PWR Design Certification Germantown, MD 20874 Electric Power Research Institute 3412 Hillview Avenue Mr. Robert Maiers, P.E.
Palo Alto, CA 94303 Pennsylvania Department of Environmental Protection Bureau of Radiation Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 i
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DOCKET NO.52-003 I
AP600 STANDARD DESIGN FINAL DESIGN APPROVAL (FDA)
PURSUANT TO 10 CFR PART 52. APPENDlX O (1)
Westinghouse Electric Company has submitted to the Nuclear Regulatory Commission's (NRC's) 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. Westinghouse's standard design is described in the AP600 Standard Safety Analysis Report (SSAR), including Revisions 1 through 25, thereto, and the AP600 Probabilistic Risk Assessment (PRA), including Revisions 1 through 13, thereto.
(2)
The SSAR and its references contain design information required by 10 CFR Part 52, Appendix O, Paragraph 3, for a standard plant design. The AP600 standard design, whose scope is defined in SSAR Section 1.8, is a nuclear power facility with a rated reactor core power level of 1933 megawatts thermal.
(3)
The NRC staff and the Advisory Committee on Reactor Safeguards (ACRS) have reviewed the AP600 standard design. The findings of the staff's evaluation of the AP600 standard design are presented in the Final Safety Evaluation Report (FSER), dated September 1998 (NUREG-1512). The ACRS reported on the application for design certification in a letter dated July 23,1998, as required by 10 CFR Section 52.53.
l (4)
On the basis of its review and the findings reported in the FSER, the staff concludes that the information in the SSAR and PRA, with respect to the AP600 design described in paragraph 2 above, complies with the requirements of 10 CFR Part 52, Appendix O.
(5)
The AP600 standard design is acceptable for use as a reference design for construction l
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.
l (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 tne rules, regulations, and orders of the Commission now or hereafter in effect. In addition, licensees who reference the AP600 standard design shall comply with the operational requirements in the SSAR, including the technical specifications and availability controls in Chapter 16 of the SSAR.
t (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 Part 2.
2-d (8)
This FDA is effective on the date it is issued and will expire on September 3,2003, unless the NRC staff extends the date. The expiration of the FDA shall not affect its use in applications docketed before such date.
Dated in Rockville, Maryland, this day of September 1998.
FOR THE NUCLEAR REGULATORY COMMISSION c
r Office of Nuclear Reactor Regulation 4
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