ML20210J464
| ML20210J464 | |
| Person / Time | |
|---|---|
| Site: | 05000447 |
| Issue date: | 09/22/1986 |
| From: | Bernero R Office of Nuclear Reactor Regulation |
| To: | GENERAL ELECTRIC CO. |
| Shared Package | |
| ML20210J400 | List: |
| References | |
| NUDOCS 8610010154 | |
| Download: ML20210J464 (4) | |
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GENERAL ELECTRIC COMPANY DOCKET N0. STN 50-447 GESSAR II BWR/6 NUCLEAR ISLAND DESIGN FINAL DESIGN APPROVAL (FDA)
Final Design Approval No. FDA-1 Amendment No. 2 (1) The General Electric Company (GE) has submitted to the Nuclear Regulatory Commission'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 Safety Analysis Report, GESSAR II, including Amendments 1 through 21 thereto. -
(2) GESSAR II contains final design information in accordance with 10 CFR Part 50, Appendix 0, Paragraph 3, for the nuclear island portion of a BWR/6 boiling water reactor nuclear power plant which encompasses the nuclear steam supply system (NSSS), engineered safety feature systems, reactor building (including the shield building and Mark III containment),
auxiliary building, control building, radwaste building, fuel handling building, and related systems and structures. The GESSAR II reference design level of is for amegawatts 3730 facility (which 1269would operate megawatts at a core electrical, thermal nominal power net).
(3) The GESSAR II reference design has been reviewed by the NRC staff and by the Advisory Committee on Reactor Safeguards (ACRS). The results of the NRC staff evaluation of the GESSAR II reft:rence design are presented in the Safety Evaluation Report (SER), NUREG-0979, dated April 1983 and SER Supplements 1 through 5 dated July 1983, November 1984, January 1985, July 1985 and May 1986, respectively. The ACRS's comments are set forth in its letters of June 15, 1983 and January 14, 1986 (Appendices F and H of SER Supplement 1 and Supplement 5, respectively).
(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 described in paragraph 2 above, complies with the requirements of 10 CFR Part 50, Appendix 0 and the criteria and procedural requirements identified in ParagraphsB.2andB.3.b(1)oftheCommission's" Policy 5tatementonSevere Reactor Accidents Regarding Future Design and Existing Plants" (50 FR 32138) and is acceptable for incorporation by reference in individual facility applications for construction permits 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 be utilized
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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 information which substantially affects the determination set forth in this Final Design Approval or other good cause.
(5) The BWR/6 Nuclear Island design described in GESSAR II is acceptable for use as a reference design for construction permit and operating license applications which are to be located at sites whose characteristics conform 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 interfaces with the approved design conforms to the safety-related interface requirements set forth in GESSAR II and NUREG-0979.
(6) (a) The BWR/6 Nuclear Island design is acceptable for use as a reference design for construction pemit 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 conform to the staff requirements, the conditions shall be modified accordingly. If all the issues are resolved to conform to the staff requirements, these conditions in Attachment A will be deleted. All of the issues in Attachment A must be satisfactorily resolved prior to the NRC issuing a construction permit or an operating license for a facility referencing the GESSAR II design.
(b) In addition to the conditions specified in Attachment A, there are certain issues identified in Section 1.9 of SER Supplement No. 5 which are confirmatory in nature. These are issues that have essentially been .
resolved to the staff's satisfaction although some additional information may 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 conclusions prior to issuing a construction permit or an 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 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.
(8) This Final Design Approval does not constitute a commitment to issue a permit or license or in any way affect the authority of the Comission, 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.
(9) This 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 this Final Design Approval on September 22, 1991, shall not affect its use in license applications docketed prior to such date.
FOR THE NUCLEAR REGULATORY COMMISSION
.v Robert M. Bernero, Director Division of BWR Licensing Office of Nuclear Reactor Regulation
Attachment:
Attachment A - Conditions of FDA-1 Date of Issuance: September 22, 1986 1
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ATTACHMENT A GESSAR-II BWR/6 NUCLEAR ISLAND DESIGN DOCKET NO. STN 50-447 CONDITIONS OF FDA-1 WHICH INCORPORATE NUCLEAR REGULATORY COMMISSION STAFF POSITIONS THAT IDENTIFY REQUIREMENTS 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 Issues 6.2
- 3. Relay Chatter 15.6.2.3(1.5)
- 4. Dedicated Power Supply 15.6.3.4.4(1) to Hydrogen Ignitor System
- 5. Final Design and Seismic 15.6.3.4.4(2)
Upgrade to UPPS 6, 10-Hour Station Batteries 15.6.3.4.4(3) and Charger Dated: September 22, 1986
.