ML20079L990
| ML20079L990 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 10/31/1991 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079L993 | List: |
| References | |
| NUDOCS 9111070223 | |
| Download: ML20079L990 (6) | |
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UNITED STATES i
NUCLEAR REGULATORY COMMISSION k\\
WASHINo10N D C. 205t4 DilKE POWER C0f4PANY DOCKET NO. 50-369, ficGillRE HllCLEAR STATION, UNIT 1 AftENDMEtiT TO FACILITY CPERATING LICENSE Anordment No. 127 1.icense No. NPF-9 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the ficGuire Nuclear Station, Unit 1 (the facility) Facility Operatino by the Duke Power Company (the licensee) License No. NPF-9 filed dated April 18, 1991, complies with the standards and equirements 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 oserate in conformity with the application, the provisions of t1e 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 endancering 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 it D.
The issuance of this amendrent will not be inimical to the common dtfense 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 requiremente have been satisfied.
9111070PP3 911031 PDR ADOCK 05000369 P
,a i 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph ?.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained v Appendix A, as revised through Amendment flo.127, re hereby asorporated into the license.
3 Tne licensee shail 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.
F03 THE NUCLEAR REGULATORY COMM'SSION l
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David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-1/11 Office of Nuclear Reactor Reculation
Attachment:
Technical Specification Changes Date of Issuance October 31, 1991
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DUKE ffWER COMPANY DOCKET NO. 50-370 14cGt!!RE NtlCLEAR STATION, llNIT 2 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No.109 License No. NPF-17 1.
The Nuclear Regulatory Commission (the Commission) has found that:
%e app (lication for amendment to the ficGeire huclear Station,the f acility) Fac A.
Ibit 2 by the Duke Power Company (the licensee) dated April 18, 1991, complies with t standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter it 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 autho,*ized by this amendment can be conducted without endangering the health and safe " of the public, and (ii) that such activities will be conducteo in cc..yliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
Tne issuance of this amendnent 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 Commi:sion's regulations and all applicable requirements have been satisfied.
l 2
2.
Accordingly, the license is herehy amended by page 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-17 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.109, are hereby inc.orporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and tne Environmental Protection Plan.
3.
This license anendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY C0tiMISS10N W rt }{
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w David B. Matthews, Director -
Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Spet.ification Changes Date of Issuance: October 31, 1991 I
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ATTACHMENT TO LICENSE AMENDMENT NO.127 FAC1LITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDitENT N0.109 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. ine revised page is identified by Amendment nurber and contains vertical lines indicating the areas of change.
Remove Page insert Page 5-6 5-6
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DESIGN FEATURES 5.2.1.2 REACTOR BUILDING 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.
DESIGNPRESSUREANDTEMPERATQE 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.
- 5. 3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembl I
nominally containing 264 fuel rods clad with Zircaloy-4,* except that su stitu-tions of fuel rods by filler rods consisting of Zircaloy-4 or stainless steel, or by vacancies, may be made in luel assemblies if justified by_ cycle-specific reload analyses using NRC-approved methodology.
Should more than 30 rods in the core, or 10 rods in any assembly, be replaced per refueling, a special report describing the number of rods replaced will be submitted to the Commission pursuant to Specification 6.9.2 within 30 days after cycle startup.
Each fuel rod shall have a nominal active fuel length of 144 inches.
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 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 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.
- dcGuire Unit 1 will use two demonstration assemblies in cycles 8, 9, and 10.
These assemblies will contain > 30 fuel rods each which are clad with a zirconium-based alloy other than Zircaloy-4, as described in BAW-2133P.
Amendment No.127(Unit 1)
McGUIRE - UNITS 1 and 2 5-6 Amendment No.109(Unit 2)