ML20154Q661
| ML20154Q661 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/13/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20154Q664 | List: |
| References | |
| NUDOCS 8603210242 | |
| Download: ML20154Q661 (8) | |
Text
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punuqjb UNITED STATES v
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NUCLEAR REGULATORY COMMISSION g
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COMMONWEALTH EDIS0N COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 OUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 License No. DPR-29 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications for amendment by Comonwealth Edison Company (the licensee) dated October 2, 1984 and October 29, 1985, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Comission; i
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-29 is hereby amended to read as follows:
8603210242 060313 PDR ADOCK 05000254 P
, (2) Technical Soecifications The Technical Specifications contained in Appendices A and 8, as revised throuah Amendment No. 93, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Soecifications.
3.
This license amendment is effective as of the date of its issuance.
FORTHENUCLEARREGULAf0RYf0MMISSION l
3 w
John
. Zwolinski, Director BWR o,iect Directorate #1 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 13, 1986.
l
ATTACHMENT TO LICENSE AMENDMENT NO.g3 FACILITY OPERATING LICENSE N0. DPR-29 DOCKET NO. 50-254 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
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Amendment i;o. 90,93
QUAD CITIES DPR-29 5.0 DESIGN FEATURES 5.1 Site The Quad Cities Station, which consists of a tract of land of approximately 404 acres, is located about 3 miles north of Cordova, Illinois, Rock Island County, Illinois. The tract is situated in portions of Sections 7, 8, 17, and 18 of Township 20 North, Range 2 East.
5.2 Reactor A.
The core shall consist of not more than 724 fuel assemblies.
B.
The reactor core shall contain 177 cruciform-shaped control rods. The control material shall be boron carbide powder (B4 ) compacted to C
approximately 70% of theoretical density or hafnium metal.
5.3 Reactor Vessel The reactor vessel shall be as described in Table 4.1.1 of the SAR. The applicable design codes shall be as described in Table 4.1.1 of the SAR.
5.4 Containment A.
The principal design parameters and applicable design codes for the primary containment shall be as given in Table 5.2.1 of the SAR.
B.
The secondary containment shall be as described in Section 5.3.2 of the SAR, and the applicable codes shall be as described in Section 12.1.1.3 of the SAR.
C.
Penetrations to the primary containment-and piping passing through such penetrations shall be designed in accordance with standards set forth in Section 5.2.2 of the SAR.
5.5 Fuel Storage A.
The new fuel storage facility shall be such that the Kerr dry is less than 0.90 and flooded is less than 0.95.
B.
The Kerr of the spent fuel storage pool shall be less than or equal to 0.95.
5.6 Seismic Design The reactor building and all contained engineered safeguards are designed for the maximum credible earthquake ground motion with an acceleration of 24% of gravity. Dynamic analysis was used to determine the earthquake acceleration application to the various elevations in the reactor building.
5.0-1 Amendment No. 79,93 1
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