ML20151M632
| ML20151M632 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/28/1988 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151M637 | List: |
| References | |
| NUDOCS 8808050261 | |
| Download: ML20151M632 (6) | |
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'o UNITED STATES NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555
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DUKE POWER COMPAllY N_0RTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.
DOCKET N0. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 50 License No. NPF-35 1.
The Nuclear Regulatory Comission (the Cnmission) has found that:
The app (lication for amendment to the Catawba Nuclear Station,the facility A.
Unit 1 by the Duke Power Company (the licensee) dated February 5,1988, as superseded by a letter dated April 1, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules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 (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 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 l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and oil 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 tc this license amendment, and Paragraph 2.C.(2) of facility Operating License No. NPF-35 is hereby amended to read as follows:
1 (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment tio. 50, 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 Tile NUCLEAR REGULATORY COMMISS10ll Original signed by:
David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II Attachment-Technical ification Chances Date of Issuance: July 28, 1988 0FFICIAL RECORD COPY pY
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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. NPF-52 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for acendment to the Catawba Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-52 filed by the Duke Power Company (the licensee) dated February 5,1988, as superseded by a letter dated April 1, 1988, complies 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) tnat 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 Corrraission'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 Comission'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 atuchments to this license anendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-52 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
43, 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 amen / ment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY C0f't11SSION Original signed by:
David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II
Attachment:
Technical Specification Changes Date of Issuance: July 28, 1988 0FFICIAL RECORD COPY
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4 ATTACHMENT TO LICENSE AllENDMENT NO. 50 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET N0. 50-413 AND 1
TO LICENSE AMENDMENT NO. 43 FACILITY OPERATING LICENSE !!0. NPF-52 DOCKET NO. 50-414 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Artendment number and contains a vertical line indicating tha area of change.
Amended Page 5-6 l
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DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment vessel is designed and shall be maintained for a maximum internal pressure of 15 psig and a temperature of 328 F.
5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly nominally containing 264 fuel rods clad with Zircaloy-4, except that substitu-tions of fuel rods by filler rods consisting of Zircaloy-4 or stainless steel, or by vacancies, may be made in fuel 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 commis-sion 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 with a maximum enrichment tolerance of i 0.05 weight percent U-235.
CONTROL R00 ASSEMBLIES 5.3.2 The core shall contain 53 full-length control rod assemblies.
The full-length control rod assemblies shall contain a nominal 142 inches of absorber material of which 102 inches shall be 100% boron carbide and remaining 40-inch tip shall be 80% silver, 15% indium, and 5% cadmium.
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 l
of the FSAR, with allowance for normal degradation oursuant to
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the applicable Surveillance Requirements, b.
For a pressure a 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 12,040 i 100 cubic feet at a nominal T,yg of 525 F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown in Figure 5.1-1.
CATAWBA - UNITS 1 & 2 5-6 Amendment No. 50 (Unit 1)
Amendment No. 43 (Unit 2)
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