ML20205C846
| ML20205C846 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 03/24/1987 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205C853 | List: |
| References | |
| NUDOCS 8703300278 | |
| Download: ML20205C846 (6) | |
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UNITED STATES l.
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DUKE POWER COMPANY DOCKET N0. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Araendment No. 68 License No. NPF-9 1.
The Nuclear Regulatory Conmission (the Comission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duk'e Power Company (the licensee) dated October 13, 1986, and a supplement filed January 21, 1987, comply with the standards and requirements.of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth in l
10 CFR Chapter I; i
B.
The facility will operate in conformity with the application, as amended, the provisions'of the Act, and the rules and regulations of the Comission; j
C.
There is reasonable assurance (1) that the activities authorized by i
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 set forth in 10 CFR
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Chapter I; 5
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 l
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.
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Accordingly, the_ license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
(2)_ Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.68, are hereby incorporated into the 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Darl Hood, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: March 24, 1987 f/
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DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No. NPF-17 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by the Dukb Power Company (the licensee) dated October 13, 1986, and a supplement filed January 21, 1987, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations set forth in 10 CFR Chapter I; 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 hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment Nm,49, are hereby incorporated into the 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Darl Hood, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
-Technical Specification Changes Date of Issuance: March 24, 1987 li #
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ATTACHMENT TO LICENSE AMENDMENT NO. 68 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT NO. 49
' FACILITY OPERATING LICENSE NO. NPF-17 DOCKET N0. 50-370 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains vertical lines indicating the areas of change.
Amended Page 5-6 I
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f DESIGN FEATURES V
5.2.1.2 REACTOR BUILDING I
i a.
Nominal annular space = 5 feet.
.b.
Annulus nominal volume.= 427,000 cubic feet.
c.
Nominal outside height (measured from top of foundation base to the top of the dome) = 177 feet.
d.
Nominal inside diameter = 125 feet.
e.
Cylinder wall minimum thickness = 3 feet.
f.
Dome minimum thickness = 2.25 feet.
g.
Dome inside radius = 87 feet.
I DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment is designed and shall be maintained for a maximum internal pressure of 15.0 psig and a temperature of 250*F.
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5.3 REACTOR CORE i
FUEL ASSEMBLIES 1
~5.3.1 The core shall contain 193 ' fuel assemblies with each fuel assembly con-taining 264 fuel rods clad with Zircaloy-4, except that limited substitutions of fuel rods by filler rods consisting of Zircaloy-4 or stainless steel, or by vacancies, may be made in peripheral fuel assemblies if justified by cycle-specific reload analyses.
Each fuel rod shall have a nominal active fuel lengt,h of 144 inches and contain a maximum total weight of 1766 grams uranium.
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.
l CONTROL ROD ASSEMBLIES' i
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. The nominal values of absorber material for Unit 1 control rods shall be 80% silver,15% indium, and 5% cadmium.
The nominal values of absorber material for Unit 2 control rods shall be 100%
boron carbide (B C) for 102 inches and 80% silver, 15% indium, and 5% cadmium 4
-for the 40-inch tip.
All control rods shall be clad with stainless steel tubing.
f McGUIRE - UNITS 1 and 2 5-6 Amendment No. 68 (Unit 1)
Amendment No. 49 (Unit 2)
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