ML20210A546
| ML20210A546 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 05/01/1987 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210A551 | List: |
| References | |
| NPF-37-A-007, NPF-66-A-007 NUDOCS 8705050110 | |
| Download: ML20210A546 (6) | |
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WASHINGTON, D. C. 20655 NUCLEAR REGULATORY COMMISSION 3*
z COMMONWEALTH EDISON COMPANY DOCKET N0. STN 50-454 BYRON STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 7 License No. NPF-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonw'ealth Edison Company (the licensee) dated January 6, 1987, supplemented March 4 and March 23, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) 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 Commission; 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 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby amended to read as follows:
P-
_2 (2) Technical Specifications The Technical Specifications contained in Appendix (NUREG-1113),
as revised through Amendment No. 7 and revised by Attachment 2 to NPF-60, and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-37, dated February 14, 1985, are hereby incorporated into this license. contains a revision to Appendix A which is hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance..
FOR THE NUCLEAR REGULATORY COMMI S N V
Utm H
Daniel R. Muller, Director Project. Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Enclosure:
Changes to the Technical Specifications Date of Issuance: May 1, 1987 i
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COMMONWEALTH EDIS0N COMPANY DOCKET NO. STN 50-455 BYRON STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 7 License No. NPF-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonw'ealth Edison Company (the licensee) dated January 6,1987, supplemented March 4 and March 23, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) 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 Commission; C.
There is reasonable assurance (1) 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 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-66 is hereby amended to read as follows:
. (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 7 and the Environment Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FORTHENUCLEARREGULATORYCOMMISyl 3 p/
Y44 Daniel R. Muller, Director Project-Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Enclosure:
Changes to the Technical Specifications Date of Issuance:
May 1, 1987 4
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WASHINGTON. D. C. 20555
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ATTACHMENT TO LICENSE AMENDMENT NO. 7 AND 7 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. STN-50-454 AND STN 50-455 Revise Appendix A as follows:
Remove Pages Insert Pages 5-3*
5-3*
5-4 5-4 1
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DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4, except that limited substitution l
of fuel rods by filler rods consisting of Zircaloy-4 or stainless steel or by i
vacancies may be made if justified by a cycle specific reload analysis.
Each I
fuel rod shall have a nominal active fuel length of 144 inches.
The initial t
core loading shall have a maximum enrichment of less than 3.20 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.0 weight percent U-235.
CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 53 full-length and no part-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber material.
All control rods shall be hafnium, clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE i
5.4.1 The Reactor Coolant System is designed and shall be maintained:
a.
In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for nomal degradation pursuant to the applicable Surveillance Requirements, 1
b.
For a pressure of 2485 psig, and c.
For a temperature of 650*F, except for the pressurizer which is 680*F.
VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 12,257 cubic feet at a nominal T,yg of 588.4*F.
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5.5 METEOROLOGICAL TOWER LOCATION i
5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
O BYRON - UNITS 1 & 2 5-4 AMENDMENT NO. 7
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