ML20199D532
| ML20199D532 | |
| Person / Time | |
|---|---|
| Site: | 05000447 |
| Issue date: | 06/11/1986 |
| From: | Scaletti D Office of Nuclear Reactor Regulation |
| To: | Sherwood G GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 8606200368 | |
| Download: ML20199D532 (7) | |
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=in 80 -Y 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
Dear Dr. Sherwood:
SUBJECT:
REQUEST FOR COMMENTS ON AMENDMENT 2 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. 2 to FDA-1 has been prepared to document the completion of the staff _'s and ACRS's review of GESSAR II for the severe accident concerns described in paragraphs B.2 and B.3.b(1) of the Comission's Severe Accident Policy Statement.
Amendment No. 2 removes the constraints on. issuing construction'rermits and
. operating licenses to applicants who reference the GESSAR II desi;n.
Please provide your comments by June 20, 1986..If you have any questions regarding this request please contact me at (301) 492-8208. The proposed amendment was previously given to members of your staff.
Sincerely, Mh 8606200368 860611 PDR ADOCK 0500 7
A Dino C SMmi, P@d Mme-Standardization and Special Projects Directorate Division of PWR Licensing-B
Enclosure:
As stated cc: See next page l
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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
Dear Dr. Sherwood:
SUBJECT:
REQUEST FOR COMMENTS ON AMENDMENT 2 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. 2 to FDA-1 has been prepared to document the completion of the staff's and ACRS's review of GESSAR II for the severe accident concerns described in paragraphs B.2 and 8.3.b(1) of the Comission's Severe Accident Policy Statement.
Amendment No. 2 removes the constraints on issuing construction permits and operating licenses to applicants who reference the GESSAR II design.
Please provide your comments by June 20, 1986.
If you have any questions regarding this request please contact me at (301) 492-8208. The proposed amendment was previously given to members of your staff.
i Sincerely, D
0.
Dino C. Scaletti, roject Manager Standardization and Special i
l Projects Directorate Division of PWR Licensing-B
Enclosure:
As stated l
l cc: See next page
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GENERAL ELECTRIC COMPANY I
DOCKET NO. STN 50-447 GESSAR II BWR/6 NUCLEAR-ISLAND DESIGN FINAL DESIGN APPROVAL (FDA) 4 Final Design Approval No. FDA-1 l
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.
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-(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, i
reactor building (including the shield building and Mark III containment),
i auxiliary building, control building, radwaste building, fuel handling building, and related systems and structures. The GESSAR II reference design is for a facility (which would operate at a core thermal power level of 3730 megawatts 1269 megawatts electrical, nominal net).
(3). The GESSAR II reference design has been reviewed by the NRC staff and by i
the Advisory Committee on Reactor Safeguards (ACRS). The resGlts of the i
l NRC, staff evaluation of the GESSAR II reference design are presented in the Safety Evaluation Report (SER), NUREG-0979, dated April 1983 and SER
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Supplements 1 through 5 dated July 1983 November 1984 January 1985, July 1985 and May 1986, respectively. The ACRS' comments are set forth i
in its letters of June 15, 1983 and January 14, 1986 (Appendices F and H ofSERSupplement1andSupplement5,respectively).
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'(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 requiremerts identified in Paragraphs B.2 and B.3.b(1) of the Comission's " Policy Statement on Severe i
Reactor Accidents Regarding Future Design and Existing Plants" (50 FR i
32138) and is acceptable for incorporation by reference in icdividual facility applications for construction permits and operatir; licenses.
In accordance with 10 CFR Part 50 Appendix 0, subject tc the conditions set forth herein and in Appendix 0..the approved design shall be utilized O
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ll 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 i
use as a reference design for construction pemit 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 i
to the safety-related interface requirements set forth in GESSAR II and NUREG-0979.
l (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 l
that the General Electric Company subsequently resolves these issues and modifies GESSAR II to conform to the staff requirements, the conditions l
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 l
for a facility referencing the GESSAR II design.
l (b). In addition to the conditions specified in Attachment A, there are l
certain issues identified in Section 1.9 of the SER and its Supplements l
which are confirmatory in nature. These are issues that have essentially been resolved to the staff's satisfaction although some additional infor-1 mation 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 Connission, Atomic Safety and Licensing Appoal Board, Atomic Safety and Licensing Boards and other presiding officers in any proceeding under Subpart G
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l of 10 CFR Part 2.
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. (9) This Final Design Approval as amended is effective as of its date of issuance and shall expire on June
,1991, unless extended by the NRC staff. The expiration of this Final Design Approval on June
, 1991, shall not effect its use in license applications docketed prior to such date.
FOR THE NUCLEAR REGULATORY COMMISSION Robert M. Bernero, Director Division of BWR Licensing Office of Nuclear Reactor Regulation
Attachment:
Attachment A - Conditions of FDA-1 Date of Issuance: June
, 1986 l
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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: ' June
, 1986 9
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GESSAR II Docket No. STN 50-447 cc: Mr. Rudolph Villa, Manager BWR Standardization General Electric Company 175 Curtner 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 Radiation 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 Reactor Deployment, NE-12 Office of Nuclear Energy Washington, D.C.
20545 I
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