ML20054G047
| ML20054G047 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/09/1982 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20054G048 | List: |
| References | |
| NUDOCS 8206210018 | |
| Download: ML20054G047 (8) | |
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D UNITED STATES
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N NUCLEAR REGULATORY COMMISSION yE WASHINGTON. D. C. 20555 ky#
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COMMONWEALTH EDISON COMPANY AND IOWA-ILLINDIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 QUAD CITIES STATION UNIT NO. 1 AMENDMEST TO FACILITY OPERATING LICENSE Amendment No. 79 License No. DPR-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated March 26,1R81 as supplemented, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regu-lations 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 Commission; C.
There is reasonable assurance Ol that the activities authorized by this amendment can Se conducted without endangering the health g and safety of the puSlic, and Oi) that such activities will be conducted in compitance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common 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 Specifi-cations as indicated in the attachment to this license amendment and paragraph 3.B of Facility License No. DPR-29 is hereby amended to read as follows:
o 8206210018 820609 PDR ADOCK 05000254 P
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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 79, 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 Thomas M. Novak, Assistant Director for Operating Reactors
- Diviston of Ltcensing Attachinent:
Changes to the Technical Specifications Date of Issuance: June 9, 1982 ee
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ATTACHMENT TO LICENSE ~ AMENDMENT'NO. 79 FACILITY OPERATING LICENSE'NO. DPR-29 DOCKET NO. 50-254 Revise the Appendix "A" Technical Spectfications by removing page 5.0-1 and replacing with the attached revtsed page 5.0-1.
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QUAD-CITIES DPR-29 5.0 DESIGN FEATURES 5.1 Site The Quad-Cities Station, which consists of a tract ofland 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 power (B C) compacted to approximately 70% of theoretical density.
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5.3 Reactor Vessel The reactor vessel shall be as described in Table 4.1.1 of the S AR.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
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given in Table 5.2.1 of the SAR.
B.
He 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.
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5.5 Fuel Storage A.
The new fuel storage facility shall be such that the K,, dry is less than 0.90 and flooded is less than 0.95.
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B.
The K,, of the spent fuel storage pooI shall be less than or equal to 0.95.
f 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.
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Amendment No. 79 5.o _ t
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UNITED STATES f
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NUCLEAR REGULATORY COMMISSION
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A E WASHINGTON D. C. 20555 o
COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS AND ELECTRIC COMPANY -
DOCKET NO. 50-265 QUAD' CITIES STATION UNIT NO. 2 AMENDMENT TO FACILITY' OPERATING' LICENSE Amendment No.73 License No. DPR-30 1.
The Nuclear Regulatory Commtssion (.the; Commission 1 has found that:
A.
The application for amendment by tihe Commonwealth Edison Company (the licenseel dated March 26, 1981 as supplemented, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Actl and the Commission's rules and regulations j
set forth in 10 CFR Chapter I; l
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B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations. of the Commission;
- t. I There is reasonable assurance (il that the activities authorized Sy tftis amendment can Se conducted without endangering the health and safety of the public, and (11).that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; l
and i
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 Specifi-cations as indicated in the attachment to this license amendment and paragraph 3.B of Facility License No. DPR-30 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices-A and B, as revised through Amendment No. 73, are hereEy incorporated in the license.
The licensee shall operate the factitty in accordance with the Technical Specifications.
3.
This license amendment _is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORT COMMISSION W'
Thomas M. Novak, Assistant Director for Operating Reactors
. Divtsion of Licensing Attac hment:
Changes to the Technical Specifications Date of Issuance:
June 9,1982
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ATTACHMENT TO LICENSE ~ AMENDMENT'NO. 73 FACILITY bPERATING LICENSE'NO. DPR-30 DOCKET NO 50-265 Revise the Appendix "A" Technical Spectftcations by removing page 5.Q-1 and replacing witfi. t'ie attacfied revised page 5.0-1.
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QUAD-CITIES DPR-30 5.0 DESIGN FEATURES 5.1 Site The Quad Cities Station, which consists of a tract ofland of approximately 404 acres. is located about 3 miles north of Cordova Illinois, Rock Island Cou~nty, Illinois. The tract is situated in portions of Sectioni 7,8.17, and 18 of Township 20 North Range 2 East.
5.2 Reactor A.
He core shall consist of not more than 724 fuel assemblies.
B.
He reactor core shall contain 177 cruciform-shaped control rods. The control material shall be boron carbide power (B.C) compacted to approximately,70% of theoretical density.
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.
He 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 enetrations to the primary containment and piping passing through such penetrations shall be designed 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 K,, dry is less than 0.90 and flooded is less than 0.95.
l B.
The K,, 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 cred'ible carthquake ground motion with an acceleration of 24% of gravity. Dynamic analysis was used to determine the carthquake I
acceleration application to the various elevations in the reactor building.
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Amendment No. 73 5.0 - 1
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