ML20247B707
| ML20247B707 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 03/17/1989 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20247B713 | List: |
| References | |
| NPF-37-A-025, NPF-66-A-025 NUDOCS 8903300011 | |
| Download: ML20247B707 (7) | |
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COMMONWEALTH EDISON COMPANY DOCKET N0. 50-454 BYRON STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 25 License No. NPF-37 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the i
licensee) dated September 3, 1986, supplemented November 7 and 1
November 24, 1986, complies 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 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 l
l 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 Specifica-I tions as indicted in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. NPF-37 is hereby amended to read as follows:
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J (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 25 and the Environmental Protection Plan con-tained in Appendix B, both of which are attached hereto, are herehy 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 COMMISSION M
Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications O
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'i COMMONWEALTH EDISON COMPANY DOCKET NO. 50-455 BYRON STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 25-l License No. NPF-66 e
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~1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the l
licensee) dated September 3, 1986, supplemented November 7 and-November 24, 1986, complies with the standards and requirements ci 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, th'e 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'
- l conducted in conpliance with the Commission's regulations; 1
D.
The issuance of 'his amendment will not be inimical.to the common defense and sect ity or to the health and safety of the public;.and I
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commiss!.n'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:
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(2) Technical Specifications The Technical Specifications contained in Appendix A (NUREG-1113),
as revised through Amendment No. 25 and revised by Attachment-2 to NPF-60, and the Environmental Protection Plan contained in Appendix B, both of which are attached to License No. NPF-37, dated February 14, 1985, are hereby incorporated into this license. Attachment 2 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 COMMISSION
,3 Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications l
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ATTACHMENT TO LICENSE AMENDMENT NOS. 25 AND 25 FACILITY OPERATING LICENSE NOS. NPT-37 AND NPF-66 DOCKET NOS. 50-454 AND 50-455 Revise. Appendix A as follows:
Remove Pages Insert Pages 5-5 5-5 5-Sa b
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DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 5 6.1.1 The spent fuel storage racks are designed and shall.be maintained with:
a.
Ak equivalent to less than or equal to 0.95 when flooded with eff unborated water, which includes a conservative allowance for uncer-tainties as described in Section 9.1 of the FSAR.
This is based on spent fuel storage in Region 2 with enrichments and burnup in accord-ance with Figure 5.6-1 or in a checkerboard pattern; and b.
A nominal 10.32 inch north-south and 10.42 inch east-west, center-to-center distance between fuel assemblies placed.in Region 1 spent fuel storage racks and a nominal 9.03 inch center-to-center distance f
bet'.aen fuel assemblies placed in Region 2 spent fuel storage. racks.
j 5.6.1.2 The k f r new fuel for the first core loading stored dry in the eff spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 423 feet 2 inches.
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 2870 fuel assemblies.
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5.7 COMP 0NENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
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BYRON - UNITS 1 & 2 5-5 Amendment No. 25
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FIGURE 5.6-1 MINIMLH BURNUP VERSUS INITIAL Eh1ICHMEh7 FOR REGION 2 STORAGE BTRON - UNITS I & 2 5-Sa Amendment No. 25
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