ML20126F235
| ML20126F235 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/30/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co, Iowa Illinois Gas & Electric Company |
| Shared Package | |
| ML20126F237 | List: |
| References | |
| DPR-30-A-087 NUDOCS 8506170408 | |
| Download: ML20126F235 (4) | |
Text
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UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION L
.j WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS XNU ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE M
/
Amendment No. 87 License No. DPR-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Comonwealth Edison Company (the licensee) dated October 2, 1984, as supplemented May 29, 1985, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. 'There is reasonable assurance (1) that the activities authorized 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 Commission'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 3.B of Facility Operating License No. DPR-30 is hereby amended to read as follows:
1 8506170408 850530 PDR ADOCK 05000265 P
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 87, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 30, 1985 T
9 ATTACHMENT TO LICENSE AMENDMENT NO. 87 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET NO. 50-765 Revise the Appendix A Technical Specifications by removing page 5.0-1 and inserting revised page 5.0-1.
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e i
4 QUAD CITIES OPR-30 i
5.0 DESIGN FEATURES
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i 5.1 Site 4
The Quad Cities Station, which consists of a tract of land of approximately 404 a
l 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
]
f A.
The core shall consist of not more than 724 fuel assentlies.
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B.
The reactor core shall contain 177 cruciform-shaped control rods. The l
control material shall be boron carbide powder (B C) compacted to 4
l L approximately 70% of theoretical density or hafnium metal.
5.3 Reactor Vessel l
The reactor vessel shall be as described in Table 4.1.1 of the SAR. The l
applicable design codes shall.be as described in Table 4.1.1 of the SAR.
l 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.
fi B.
The secondary containment shall be as described in Section 5.3.2 of the i
i SAR, and the applicable codes shall be as described in Section 12.1.1.3 of the SAR.
i
..e C.
Penetrations to the primary containment and piping passing through such
{w penetrations shall be designed in accordance with standards set forth in Section 5.2.2 of the SAR.
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5.5 Fuel Storage A.
The new fuel storage facility shall be such that the Keff dry is less than 0.90 and flooded is less than 0.95.
i B.
The Keff 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.
Amendment No. 87 5.0-1
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