ML20126F491

Forwards Proposed Amend 1 to FDA-1 for GESSAR-II BWR/6 Nuclear Island Design,For Review.Amend Prepared in Anticipation of Final Commission Action on Severe Accident Policy Statement.Comments Requested by 850614

ML20126F491
Person / Time
Site:	05000447
Issue date:	06/07/1985
From:	Thomas C Office of Nuclear Reactor Regulation
To:	Sherwood G GENERAL ELECTRIC CO.
References
NUDOCS 8506170503
Download: ML20126F491 (7)

Text

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June 7, 1985 Docket No. 00007447 Dr. Glenn G. Sherwood, Manager Safety & Licensing Operations fluclear Power Systens Division General Electric Corrpany 175 Curtner Avenue, Mail Code 682 San Jose, California 95125

SUBJECT:

RE00EST FOR COMMENTS ON AMEilDMENT 1 TO FDA-1, GESSAR II Enclosed for your review and comnent is the proposed amendrent to FDA-1 for your BPR/6 Nuclear Island Design, GESSAR II. Amendment No. I to FDA-1 has been prepared in anticipation of final Commission action on the Severe Accident Policy Statement. As allowed by the Severe Accident Policy Statement, Amendment No. I will remove the constraints identified in FDA-1 to allow the GESSAR II design to be referenced in new CP and OL applications.

Please provide your coninents by June 14, 1985. If you have any questions regarding this request please contact Dino Scaletti at (301) 492-9787.

The proposed amendme0t was previously given to nenbers of your staff.

Sincerely, Original signed by Cecil 0. Thomas, Chief Standardization and Special Projects Branch Division of Licensing

Enclosure:

As stated cc: See next page DISTRIBUTION:

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• s.,...../ June 7, 1985 Docket No. 00007447 Dr. Glenn G. Sherwood, Manager Safety & Licensing Operations Nuclear Power Systems Division General Electric Company 175 Curtner Avenue, Mail Code 682 San Jose, California 95125

SUBJECT:

REQUEST FOR COMMENTS ON AMENDMENT 1 TO FDA-1, GESSAR II .

Enclosed for your review and comment is the proposed amendment to FDA-1 for your BWR/6 Nuclear Island Design, GESSAR II. Amendment No. I to FDA-1 has been prepared in anticipation of final Commission action on the Severe Accident Policy Statement. As allowed by the Severe Accident Policy Statement, Amendment No. I will remove the constraints identified in FDA-1 to allow the GESSAR II design to be referenced in new CP and OL applications.

Please provide your coments by June 14, 1985. If you have any ouestions regarding this request please contact Dino Scaletti at (301) 492-9787.

The proposed amenchent was previously given to members of your staff.

Sincerely, eE? 0.  %::  :

Cecil 0. Thomas, Chief Standardization and Special Projects Branch Division of Licensing

Enclosure:

As stated cc: See next page l

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GESSAP TI 00007447 General Electric Company ATTN: Glenn G. Sherwood,tianager Safety A Licensing Operation iluclear Power Systems Division 175 Curtner Avenue, Mail Code 682 San Jose, California 95125 cc: Mr. Pudolph Villa, Manager BWR Standardization General Electric Company 175 Curtrer Avenue San Jose, California 95114 Mr. L. Gifford, Manager Regulatory Operations Unit .

General Electric Company 7910 Woodmont Avenue Bethesda, Maryland 20814 Director, Criteria & Standards Division Office of Padiation Programs U. S. Environmental Protection Agency 401 M Street, S.W.

Washington, D.C. 20460 L. M. Mills, Chief Regulatory Staff Tennessee Valley Authority Bldg. 400, CST 11-C Chattanooga, Tennessee 37201 Mr. Daniel F. Giessing Division of Nuclear Regulation and Safety Office of Converter Reactnr Deployment, NE-12 Office of Nuclear Energy Washington, D.C. 20545 l

GEt!ERAL ELECTRIC COMPANY DOCKET NO. STN 50 a47 GESSAR II BWR/6 NUCLEAR ISLAND DESIGN FIflAL DESICf' APPPOVAL (FDA)

Final Design Approval No. FDA-1 Amendment No. 1 (1) The Generel Electric Company (GE) has submitted to the Nuclear Regulatory Commission's (NRC) staff for its review a standardized final design for ma,ior portions of a nuclear power reactor of the type described in.

10 CFR 50.?2. The design is described in the General Electric Standard Safety Analysis Report, GESSAR II, including Amendments 1 through 16 thereto.

(2) GESSAP II contains final design information in eccordance with 10 CFR Part 50, Appendir 0, Paragraph 3, for the nuclear island portion of a BWR-6/ Mark III containment boiling water reactor nuclear power plant, which encompasses the nuclear steam supply system (NSSS), engineered safety feature s and containment)ystems,

, auxiliary reactor building,building control(includino the shield build-building, radwaste building ing, fuel handling building, and related systems and structures. The which would operate at a GESSAR core thermalII power reference levelc'esign of 3730 is for a facility (1269 megewatts electrical, megawatts nominal net).

(3) The GESSAR II reference desion has been reviewed by the NRC staff and by the Advisory Comittee on Reactor Safeguards (ACRS). The results of the NRC staff evaluation of the GESSAR II reference design are presented in the Safety Evaluation Report (SER), NUREG-0979, dated April 1983 and SER Supplement I dated July 1983. The ACRS comments are set forth in its letter of June 15, 1983 (Appendix F of the SER Supplement 1).

(4) Based on its review and the findings set forth in Section 21 of the SER, the NRC staff has concluded that subject to the conditions set forth herein, the information provided in GESSAR II with respect to the major portions of the final design encompassed by GESSAR II, as 3

described in paragraph 2 above, complies with the requirements of 10 CFP Pert 50, Appendix 0 and paragraph B.3.b(1) of the Comission's

" Policy Statement on Severe Reactor Accidents Regarding Future Desion and Existing Plants" ( FR ) and is acceptable for incorporation by reference in individual facility applications for construction pemits and operating licenses. In accordance with 10 CFR Part 50, Appendix 0, subject to the conditions set forth herein and in Appendix 0, the approved design shall he utilized and relied upon by the staff and-the ACRS in their reviews of any individual facility license application which incorporates by reference the approved design unless there exists significant new infomation which substantially affects the determina-tion set forth in this Final Design Approval or other good cause.

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(5) The BWR/6 Nuclear Island design described in GESSAR II is acceptable for usa as e reference design for construction permit and operating i license applications which are to be located at sites whose charecter-istics corfcrm to the envelope of site parameters postulated for the BWR/6 Nuclear Island Design which are set forth in GESSAR II and NUREG-0979 provided that the balance-of-plant which interface with the approved design conforns to the safety-related interface requirements set forth in GESSAP II and NUREG-0979.

(6) (a) The RWR/6 Nuclear Island design is acceptable for use as a reference i design for construction permit and operatino license applications except for those features of the design which are specified in Attachment A hereto. These design features must be satisfactorily resolved to conform to the NRC staff's reouiremerts described in NUREG-0979. To the extent that the General Electric Company subsecuently resolves these issues and ~

modifies GESSAR II to conform to the staff requirements, the conditions shall be modified accordingly. If c11 the issues are resolved to conform to the staff requirements, these corditions in Attachment A will be deleted. All of the issues in Attachment A must be satisfactorily resolved prior to the NPC issuing a construction permit or an operating license for a facility referencing the GESSAP II design.

(h) In addition to the conditions specified in Attachment A, there are certain issues identified in Section 1.9 of SER Supplement 1. which are confirmetery in nature. These are issues that have essentially been re-solved to the staff's safisfaction although some additionel information mey be required of GE. It will be necessary for GE to submit the additional information in sufficient time to allow the staff to confirm its cerclusions prior to issuing a construction pernit or an operatino license for a facility referencing the GESSAR II design.

(c) The GESSAR II reference design is still under review by the NRC staff and the ACPS for the severe accident considerations described in the Commission's Severe Accident Policy Statement. This review must be completed and the criteria stated in Section B.2 of the Severe Accident Policy Statement must be satisfied prior to the NRC issuing a construction permit or en operating license for a facility referencing the GESSAR II design.

(7) This Final Design Approval and all applications for construction permits and operating licenses incorporating it by reference, are sub,iect to all applicable provisions of the Atomic Energy Act, as amended, and the rules and regulations and Orders of the Commission now or hereafter in effect.

(8) This Final Design Approval does not constitute a connitment to issue a permit or license or in any way affect the authority of the Commission, Atnmic 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.

(9) This Final Design Approvel as amended is effective as of its date of issuance. .The staff shall further amend the Final Design Approval upon the completion of the severe accident review described in Paragraph 6(c) above to implement the results of that review.

FOR THE NUCLEAR REGULATORY COMMISSION i

Huoh L. Thompson, Jr., Director Division of Licensing Office of Nuclear Reactor Regulation

Attachment:

Attachment A - Conditions of FDA-1 Date of Issuance:

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ATTACHEMENT A GESSAR-II BWR/6 NUCLEAR ISLAND DESIGN DOCKET NO. STN 50-447 CONDITIONS OF FDA-1 WHICH INCORPORATF NilCLEAR REGULATORY COMPISSION STAFF POSITIONS TPA' IDENTIFY REQUIREMENTS DIFFERENT FROM THOSE NOTED IN GESSAR II SER Section Where Staff Positions

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Condition No. Design Feature are Discussed

1. Post Accident Monitoring 7.5.2 Instrumentation

2. Humphrey Issuar 6.?

Dated:

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