ML20134A573
| ML20134A573 | |
| Person / Time | |
|---|---|
| Site: | 05000447 |
| Issue date: | 08/09/1985 |
| From: | Thompson H Office of Nuclear Reactor Regulation |
| To: | GENERAL ELECTRIC CO. |
| Shared Package | |
| ML20134A554 | List: |
| References | |
| NUDOCS 8508150345 | |
| Download: ML20134A573 (4) | |
Text
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i . e GENERAL ELECTRIC COMPANY 3
DOCKET NO. STN 50-447' GESSAR II BWR/6 NUCLEAR ISLAND DESIGN s
FINAL DESIGN APPp0 VAL (FDA)
Final Design Approifal No.'FDA-1 Amendment No. 1 (1) The General Electric Company (GE) has submitted to the Nuclear Regulatory Comission's (NRC) staff for its review a standardized final design for major portions of _a nuclear power reactor of the type described in 10 CFR 50.22. 'The design is described in the General Electric Standard 1 Safety Analysis-Report, GESSAR II, including Amendments 1 through 16
~thereto.
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2 (2) GESSAR II contains final design infonnation in accordance with 10 CFR Part 50, Appendix 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 i i safety feature s l~- -and containment)ystems,
, auxiliaryreactor building, building (including control building,the shield building radwaste build-ing, fuel handling building, and related system', and structures. The which would operate at a 4 GESSAR core themalIIpower reference level ofdesign 3730 megawatts is for a facility (1269 negawatts electrical, nominal net). ;
(3) The GESSAR II reference design has been reviewed by the NRC staff and l
by.the Advisory Committee 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 l _ , Supplement 1). ,
(4) Based on its review and the findings set forth in Section 21 of the j 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
- . described in paragraph 2 above, complies with the requirements of 10 l CFR Part 50, Appendix 0 and Paragraph B.3.b(1) of the Commission's-
" Policy Statement on Severe Reactor Accidents Regarding Future Design and Existing Plants" (50 FR 32138) and is acceptable for incorporation by reference in individual facility applications for construction pennits and operating licenses. In accordance with 10 CFR Part 50, j Appendix 0, subject to the conditions set forth herein and in Appendix 0, j the approved design shall _be utilized and relied upon by the Ttaff and i
the ACPS in their reviews of any individual facility license application which incorporates by reference the approved design unless there exists significant new information which substantially affects the detemina-
_ tion set forth in this Final Design Approval or other good cause.
8508150345 850809 PDR ADOCK 05000447 A PDR _
, (5) The BWR/6 Nuclear Island desion described in GESSAR II is acceptable for use as a reference design #ce construction permit and 'ophrating 4 license applications which are to be located at sites whose character-istics conform to the envelope of site parameters postulatedTfor the BWR/6 Nuclear Island design which are set forth in GESSAR II and NUREG-0979 provided that the balance-of-plant which interfaces with the approved design conforms to the safety-related interface requirements
- set forth in GESSAR II and NUREG-0979.
4 (6) (a) The BWR/6 Nuclear Island design is acceptable for use as a reference design for construction permit and operating 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 requirements described in NUREG-0979. To the extent that the General Electric Company subsequently resolves these issues and modifies GESSAR II to confom to the staff requirements, the conditicns '
shall be modified accordingly. If all the issues are resolved to conform 4
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to the steff requirements, these conditions in Attachment A will be 4
deleted. All of the issues in Attachment A must be satisfactnrily !
resolved prior to the NRC issuing a construction pemit or an operatino !
, license for a facility referencing the GESSAR II design. l 3 . i (b) In addition to the conditions specified in Attachment A, there are certain issues identified in Section 1.9 of SER Supplement I which are confimatory in nature. These are issues that have essentielly been re-
! solved to tha staff's safisfaction although some additional information
- may be required of GE. It will be necessary for GE to sutuit the additional infometion in sufficient time to allow the staff to confirm its conclusions prior to issuing a construction pemit or an operating 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 ACRS for the severe accident considerations described in .
l r ~ the Commission's Severe Accident Policy Statement. This review must i be completed and the criteria stated in Section B.2 of the Severe l facident Policy Statement must be satisfied prior to the NRC issuing a construction pemit or an operating license for a facility referencing the GESSAR II' design.
I (7) This Final Design Approval and all applications for construction pemits and operating licenses incorpor.iting it by reference, are subject 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.
l (8) This Final Design Approval does not constitute a comitment to issue a permit or license or in any way affect the authority of the Comission, i
Atomic Sefety and Licensing Appeal Board, Atomic Safety and Licensing Boards and other presiding officers in any proceeding under Subpart G
- of 10 CFP. Part P.
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1 (9) This Final Design Approval as amended is effective as of itssdate of issuance. The staff shall further amend the Final Des-;gn Approvel upon the completion of the severe accident review described in Paeagraph 6(c) above to implement the results of that review. _
FOR THE NUCLEAR REGULATORY COMMISSION 4{ .
Hu L. Thonpso Jr Director Di sion of Licensi Office of fluclear Reactor Regulation
Attachment:
Attachment A - Conditions of FDA-1
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Date of Issuance: August 9, 1985 l
d e
d 4
-4 ATTACHEMENT A GESSAR-II RWR/6 NUCLEAR ISLAND DESIGN DOCKET NO. STN 50-447 ~I i
- CONDITIONS OF FDA-1 WHICH INCORPORATE NUCLEAR REGULATORY COMMISSION STAFF POSITIONS THAT IDENTIFY RE0llIREMENTS DIFFERENT FROM THOSE NOTED IN GESSAR II
- - SER Section Where _
Staff Positions Condition No. Design Feature are Discussed
- 1. Post Accident Monitoring 7.5.2 Instrumentation
- 2. Humphrey Issue > 6.2 i
Dated: August 9, 1985
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