ML20247B688
| ML20247B688 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 07/17/1989 |
| From: | Shemanski P Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20247B693 | List: |
| References | |
| NPF-37-A-030, NPF-66-A-030, NPF-72-A-019, NPF-77-A-019 NUDOCS 8907240179 | |
| Download: ML20247B688 (12) | |
Text
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-454 BYRON STATION, UNIT 1 AfiENDMENT TO FACILITY OPERATING LICENSE Amendment No. 30
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License No. NPF-37 I.
The Nuclear Regulatcry Comission (the Comission) has found that:
A.
The application for amendment b." Comonv:ealth Edison Company (the licensee)datedMay 22, 1989, 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 prov4sions of the Act, and the rules end regulations of the Comission; C.
There is reasonab;c 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 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.Specifica-tion as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby j
amended to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appendix A as revised thiough Amendment No. 30 and the Environmental 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.
FOR THE NUCLEAR REGULATORY COMMISSION.
Paul C. Shemanski, Acting Director Project Directorate III-2 Division of Reactor Projects. III, IV, V and Special Projects
Attachment:
. Changes to the Technical Specifications Date of Issuance: July 17, 1989
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COMMONWEALTH EDISON COMPANY-o DOCKET NO. 50-455 BYRON STATION, UNIT 2
- AMENDMENT-TO FACILITY OPERATING LICENSE-Amendment No. 30 License No. NPF-66' 1.
- e Nuclear Regul6 tory Comission (the Comission) has found that:
'A..
The application for amenoment by Commonwealth Edison Company (the licensee) dated May. 22, 1989, 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 Comission; C.
Thereisreasonableassurance(1).thattheactivitiesauthorizedby 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 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions 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 (2) Technical Specifications The Technical Specifications contained in Appendix A'(NUREG-1113), as revised through Amendment No. 30 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 amendnent is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION hC 5
1 Paul C. Shemanski, Acting Director Project Direct 9 rate III-2 Division of Reactor Projects - III, IV, Y and Special Projects Atta-hment:
Changes to the Technical Specifications Date of Issuance:
July 17, 1989 I
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.AND 30 ATTACHMENT TO LICENSE AMENDMENT NOS. 30 FACILITY CPERATING LICENSE NOS. NPF-37'AND NPF-66 DOCKET N05. 50-454 AND 50-455 Revise Appendix A'as follows:
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DESIGN FEATURES 5.3' REACTOR CORE FUEL ASSEMBLIES -
l 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 vacancies may be made if justified by a cycle specific reload analysis.
Each fuel rod shall have a nominal active fuel length of 144 inches.
The initial core loa' ding 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. :The-enrichment of any reload fuel design shall be determined to be acceptable for storage in either the spent fuel pool or the new fuel _ vault.
Such acceptance criteria shall be based on the results of the CRITICALITY ANALYSIS OF BYRON AND BRAIDWOOD STATION FUEL STORAGE RACKS.
CONTROL R0D 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 absc'ber material.
All control rods shall be hafnium, silver-indium-cadmium, or a mixture of both types.
All control rods shall be clad with stainless steel tubing.
. DESIGN PRESSURE AND TEMPERATURE 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 normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and c.
For a temperature of 650 F, except for the pressurizer which is 680 F.
VOLUME i
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.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
AMENDMENT NO. 30 BYRON - UNITS 1 & 2 5-4
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l COMMONWEALTH EDISON COMPANY DOCKET NO. 50-456 BRAIDWOOD STATION, UNIT 1 AMENDMENTT0]ACILITYOPERATINGLICENSE Amendment No. 19 License No. NPF 1.
The Nucicar Regulatory Commission (the Cor.nission) has found that:
A.
The. application for amendment by Correonwealth Edison Corapany (the licensee) dated May 22, 1989, complies with the standarcs and requirements cf the Atomic Energy Act of 1954, as amended (the Act) and the Conaission'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 Connission; 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, ar.d (ii) that such activities will te conducted in compliance with the Consission'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 amendme t is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirements have i
been satisfied.
l 2.
Accordingly, the license is amended by changes to the Technical Specifica-tion at indicated in the attachment to this license amendment, and paragr o 2.C.(2) of Facility Operating License No. NPF-72 is hereby amendec to read as follows:
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(2) Technical Specifications-r The Technical Specifications contained in Appendix A as revised through Amendment No.19 and the Environmental-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.
FOR THE NUCLEAR REGULATORY COMMISSION
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Paul C. Shemanski, Acting Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: July 17, 1989 I
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-457 BRAIDWOOD STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 19 License No. NPF-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee)datedMay 22, 1989, 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 cperate in conformity with the application, the provisions of the Act, and the rules and regulations of the -
Commission; C.
Thereisreasonableassurance(i)thattheactivitiesauthorizedby 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 r,ct 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-tion as indicated in the attachment to this license amendment, and para-l graph 2.C.(2) of Facility Operating License No. NPF-77 is herevy amended to read as follows:
2 (2)-TechnicalSpecifications' The Technical Specifications contained in Appendix A as revised through Amendment No. 19 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No.
NPF-72, dated July 2, 1987, 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.
FOR THE NUCLEAR REGULATORY COMMISSION (5
Paul C. Shemanski, Acting Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: July 17, 1989 i
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t ATTACHMENT TO LICENSE AMENDMENT NO3.19 ' AND' 19
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'AND FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77:
' DOCKET NOS. 50-456 AND'50-457 Revise Appendix A as follows:
Remove Pages Insert Pages.
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.u DES'GN 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 substitu-tion of fuel rods by filler rods consisting of Zircaloy 4.or stainless steel or by vacancies may be made'if justified by a cycle specific' reload analysis.
'Each fuel rod shall have a nominal active fuel length of 144 inches.
The initial 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.
The enrichment of any reload fuel design shall be determined to be acceptable for storage.in either the spent fuel pool or the new fuel.
. vault.
Such acceptance criteria shall be based on the results of the CRITICALITY ANALYSIS OF BYRON AND BRAIDWOOD STATION FUEL STORAGE RACKS.
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, silver-indium-cadmium, or a mixture of both types.
All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 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 normal' degradation pursuant to the applicable Surveillance Requirements, 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.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
BRAIDWOOD - UNITS 1 & 2 5-4 Amendment No. 19
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