ML20210J534
| ML20210J534 | |
| Person / Time | |
|---|---|
| Site: | 05000447 |
| Issue date: | 09/22/1986 |
| From: | Bernero R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210J400 | List: |
| References | |
| NUDOCS 8610010170 | |
| Download: ML20210J534 (4) | |
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NO. STN 50-447 GENERAL ELECTRIC COMPANY GENERAL ELECTRIC STANDARD SAFETY ANALYSIS REPORT (GESSAR II BWR/6 NUCLEAR ISLAND DESIGN)
NOTICE OF ISSUANCE OF AMENDMENT NO. 2 TO FINAL DESIGN APPROVAL NO. FDA-1 Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has issued Amendment No. 2 to FDA-1, the Final Design Approval for the BWR/6 Nuclear Island design described in the General Electric Standard Safety Analysis Report GESSAR II. FDA-1, which was issued by the NRC staff on July 27, 1983 (48 FR 35050), permitted the GESSAR II design to be referenced in utility applications for operating licenses for those plants that referenced the Preliminary Design Approval for the GESSAR-238 Nuclear Island design (PDA-1) at the construction permit stage.
Amendment No. I to FDA-1 which was issued on August 9, 1985, removed the constraint on the forward referenceability of the GESSAR II. design and permitted it to be referenced in new construction permit (CP) and operating license (0L) applications as provided for by Paragraph B.3.b(1) of the Com-mission's " Policy Statement on Severa Reactor Accidents Regarding Future Designs and Existing Plants" (50 FR 32138). Paragraph B.3.b(1), however, prohibits the issuance of a CP or OL to an application that references the design until successful completion of the severe accident revien. Amendment No. 2 to FDA-1 documents the completion of the staff's and the ACRS's review of 8610010170 860922 PDR ADOCK 05000447 A
o GESSAR II for the severe accidents concerns described in paragraph B.2. of the Commission's policy statement.
GESSAR II contains final safety-related design information for the nuclear island portion of a BWR/6 boiling water reactor type nuclear power plant which includes the nuclear steam supply system (NSSS), engineered safety feature systems, reactor building (including shield building and Mark III containment),
auxiliary. building, control building, radwaste building, fuel handling building, and related systems and structures. The BWR/6 Nuclear Island reference design is for a facility which would operate at a core thermal power level of 3730 megawatts (1269 megawatts electrical, nominal net).
The GESSAR II design was reviewed by the NRC staff pursuant to Appendix 0 to 10 CFR Part 50. The Safety Evaluation Report (SER), NUREG-0979, dated April 1983 and Supplements 1 throu;h 5 thereto dated July 1983, November 1984, January 1985, July 1985, and May 1186, respectively, document the results of the NRC staff's review and evaluation of the GESSAR II design including Amendments 1 through 21 thereto. The SER also addresses the comments of the Advisory Committee on Reactor Safeguards (ACRS) as reflected in its reports to the Commission dated June 15, 1983, and January 14, 1986. A copy of the ACRS's reports are included as Appendix F to SER Supplement I and Appendix H to SER Supplement 5.
Based on its review, the NRC staff has concluded, subject to the con-ditions set forth in Amendment 2 to FDA-1, that the information provided in GESSAR II complies with the requirements of 10 CFR Part 50, Appendix 0, and with Paragraphs B.2 and B.3.b(1) of the Commission's " Policy Statement on 3evere Reactor Accidents Regarding Future Designs and Existing Plants," and
. is acceptable for incorporation by reference in utility applications for con-struction pennits and operating licenses. Amendment 2 allows a CP or OL to be issued to applicants who reference the GESSAR II design without further staff or ACRS review of those portions of the design covered by FDA-1.
Issuance of Amendment No. 2 to FDA-1 does not constitute a commitment to issue a pennit 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 officers in any proceeding under Subpart G of 10 CFR Part 2.
This action only approves the design of a facility for use for reference purposes in applications for construction pennits and operating licenses for nuclear power plants.
It does not authorize the operation of any nuclear power plant or any other facility. The environmental impacts associated with any facility proposed to be operated utilizing the approved reference design will be considered in accordance with the Connission's regulations in 10 CFR Part 51.
The Final Design Approval as amended is effective as of its date of issuance and shall expire on September 22, 1991, unless extended by the NRC staff. The expiration of the Final Design Approval on September 22, 1991, shall not affect its use in licensing applications docketed prior to such date.
For further details with respect to this action, see (1) Amendment No. 2 to FDA-1 and Attachment A thereto; (2) the NRC staff's Safety Evaluation Report, NUREG-0979, dated April 1983 and Supplements 1 through 5 thereto, dated July 1983, November 1984, January 1985, July 1985, and May 1986, respectively; (3) the reports of the Advisory Committee on Reactor Safeguards dated June 15, 1983 and January 14,1986;(4) the General Elect.ric Standard Safety Analysis Report GESSAR II
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..a o and Amendments 1 through 21 thereto; and (5) the Commission's " Policy Statement on Severe Reactor Accidents regarding Future Design and Existing Plants." These documents 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 Amendment No. 2 to FDA-1 and Attachment A thereto may be obtained upon request to the U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, Attention: Director, Division of BWR Licensing. Copies of the Safety Evaluation Report and Supplements (NUREG-0979) may be purchased through the U.S. Government Printing Office by calling (202) 275-2060 or by writing to the U.S. Government Printing Office, P.O. Box 37082, Washington, D.C.
200313-7082. Copies may also be purchased from the National Technical Information Service, U.S. Department of Comerce, 5285 Port Royal Road, Springfield, Virginia 22161.
nd Dated at Bethesda, Maryland, this 22 day of September 1986.
FOR THE NUCLEAR REGULATORY COMMISSION Robert M. Bernero, Director Division of BWR Licensing Office of Nuclear Reactor Regulation
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