ML20134A582
| ML20134A582 | |
| Person / Time | |
|---|---|
| Site: | 05000447 |
| Issue date: | 08/09/1985 |
| From: | Thompson H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20134A554 | List: |
| References | |
| NUDOCS 8508150348 | |
| Download: ML20134A582 (4) | |
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/ %, UNITED STATES
. , ,8 g NUCLEAR REGULATORY COMMISSION 3 ;* wAsmNGTON,0. C. 20555 l
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i f - t UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NO. STN 50-447 T ,
- - GENERAL ELECTRIC COMPANY GENERAL ELECTP.IC STANDARD SAFETY ANALYSIS REPORT f
(GESSAR II BWR/6 NUCLEAR ISLAND DESIGN)
NOTICE OF ISSUANCE OF AMENDMENT NO. I'T0 h "-
FINAL DESIGN APPROVAL NO. FDA-1
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Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has issued Amendment No. I to FDA-1, the Final Design
"' Approval for the BWR/6 Nuclear Island design described in the General i Electric Standard Safety Analysis Report GESSAR II. FDA-1, which was issued by the NRC staff on July 27,1983(48FR35050),permittedtheGESSARII design to be referenced in utility applications for, cperating licenses for those plants that referenced the Preliminary Design Approval for the GESSAR-238 Nuclear Island design (PDA-1) at the construction permit stage.
. Amendmert No. I to FDA-1 removes the present constraint on the forward .
- referenceability of the GESSAR II design ed pemits it to be referenced in new construction permit and operating license applications as provided by Paragraph B.3.b of the Commission's ' Policy Statement on Severe Reactor Accidents Regarding Future Designs and Existing Plants" (50 FR 32138).
GESSAR II contains final safety-related design information for the nuclear f island portion of a BWR-6/ Mark III containment boiling water reactor type nuclearpowerplantwhichincludesthenuclearsteamsupplysystem(NSSS),
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2-engineered safety feature systems, reactor building (including s.hield building and containnenti, auxiliary building, control building, radwaste building, fual handling building, and related systems and structures. The BWR/6 Nuclear Island reference design is for a facility which would operate at a ccre thermal power level of 3730 megawatts (1269 megawatts electrical, nominal net).
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The GESSAR II design was reviewed by the NRC staff pursuant te Appendix _
'blo10CFRPart50. The Safety Evaluation Report (SER), NUPEG-0979, dated
,. April 1983 and Supplement I thereto dated July 1983 document the results of the NRC staff's review and evaluation of the GESSAR II design including Amendments 1 through 16 thereto. The SER also addresses the coments of the Advisory Comittee on Reactor Safeguards (ACRS) as reflected in its report to the Comission dated June 15, 1983. A copy of the ACRS' report is included to a' Appendix F to SER Supplement 1.
Based on its review, the NRC staff has concluded, subject.to the conditions set forth in Amendment 1 to FDA-1, that the information provided in GESSARiI complies with the requirements of 10 CFR Part 50, Appendix 0, and -
with Paragraph B.3.b(1) of the Comission's " Policy Statement on Severe Reactor' Accidents Regarding Future Designs and Existing Plants," and is acceptable for incorporation by reference in utility applicatiers for ennstruction permits and operating licenses. Upon completion of NRC Staff
, and ACRS review for severe accident considerations, this Final Design Approval will be further amended. -
Issuance of Amendment No. I to FDA-1 does not constitute a commitment to issue a pemit or license, or in any way affect the authority of the
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Comission, Atomic Safety and Licensing Appeai Board, Atomic Safety and Licensire Poards 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 pemits ard operating licenses for nuclear power plants. It does not authorize the operation of any nuclear power plant or any other facility. The envircemental impacts
- associated with any facility proposed to be operated utilizing the approved -
- re erence design will be considered in accordance with the Comission's
. - regulations in 10 CFR Part 51.
The Final Design Approval as amended is effective as of its date of issuance and shall be further amended at the completion of the severe accident review described in Paragraph 6(c) therein to implement the results of that review.
- For further details with respect to this action, see (1) Amendment No. I to FDA-1 and. Attachment A thereto; (2) the NRC staff's Safety Evaluatinn Peport, NUREG-0979, dated April 1983 and Supplement 1 thereto, dated July 1983; (3)'the rep 6rt of the Advisory Comittee on Reactor Safeguards dated June 15,'
1983; (4) the General Electric Standard Analysis Report GESSAR II and Amendments 1 throuch 16 thereto; and (5) the Commission's " Policy Statenent on Severe Reactor Accidents regarding Future Desiqn 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
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-4 Amendment No. I to FDA-1 and Attachmert A thereto may be obtained upon request to the U. S. Nuclear Regulatory Corrission, Washington, D.C. '20355,
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Attention: Director, Division of Licensing. Copiesof_theSafeTyEvaluation Report and Supplement I thereto may be purchased by celling (202) 275-2060 or (202)275-2171 or by writing to the Superintendent of Documents U. S.
Government Printing Office, Post Office Box 37082 Washington, D. C.
j s. 20013-7982.
Dated at E thesda, Maryland, this 9th day of August,1985.
FOR THE NUCLEAR REGULATORY COMMISSION l
Hg L. Thomps r, irector D sion of Licensin Office of Nuclear Reactor Regulation e
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