ML20044B294
| ML20044B294 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/13/1990 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20044B295 | List: |
| References | |
| NUDOCS 9007180307 | |
| Download: ML20044B294 (6) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
- ' e 3-wasniwoTow, o. c. 20sn DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76~
License No. NPF-35 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company acting for itself, North Carolina Electric Membership)CorporationandSaludaRiverElectricCooperative,-.Inc.,
(licensees dated February 7,'1990, as supplemented April 12, 1990, 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, 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 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.
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Accordingly, the license is hereby 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-35 is hereby amended to read as follows:
Technical' Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 76, 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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David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-l/II Office of Nuclear Reactor Regulation Attachnent:
Technical Specification Changes
-Date of. Issuance:
July 13, 1990
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l UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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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 l
Amendment No. 70 License No. NPF-52 l
L 1.
The Nuclear Regulatory Comission (the Comissien) has found that:-
L A.
The application for amendment to the Catawba Nuclear Station, Unit 2'
-(the facility) Facility Operating License No. NPF-52-filed by the Duke Power Company acting for itself, North Carolina Municipal-Power Agency No I and Piedmont Municipal Power Agency (licensees) dated February 7,1990, as supplemented April 12, 1990, complies with as amended (the Act)quirements of the Atomic Energy Act of 1954, the standards and re, and the Comission's rules and regulations as set forth in 10 CFR Chapter I;.
l B.
The facility will' operate in-conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 i
L conducted in compliance with the Comission's regulations set forth l-in 10 CFR Chapter I; l-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.
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1 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, tadParagraph2.C.(2)ofFacilityOperatingLicenseNo.NPF-52ishereby 0 mended to read as follows:
g cal Specifications
'he Technical Specifications contained in Appendix A, as revised through Amendment No.. 70, are hereby incorporated into the license. The licensee 1
shall operate the facility in accordance with the Technical Specifications l
and the Environnental Protection Plan.
l" 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION b1 avid B. Matthews, Diredor y
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Project Directorate 11-3 Division of Reactor Projects-I/11 Office of Nuclear Reactor. Regulation
Attachment:
'i Technical Specification Changes E
Date of Issuance: July 13, 1990 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 76 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 A,Np TO LICENSE AMEN 0 MENT NO. 70
_ FACILITY OPERATitlG LICENSE NO. NPF-52 DOCKET 110. 50-414 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
Remove Page Insert Page 5-6 5-6
I OfSIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment vessel is designed and shall be maintained for a maximum internal pressure o! 15 psig and a temperature of 328'F.
5.3 REACTORCORj FUEL ASSEMBLIES l
5.3.1 TN core shall contain 193 fuel assemblies with each fuel assembly nomina 1*y containing 264 fuel rods clad with Zircaloy-4, except that substitu-r tions of fuel rods by filler rods consisting of Zirceloy-4 or stainless steel, or by vacancies, may be made in fuel assemblies if justified by cycle-specific reload analyses using NRC-approved methodology.
ShN1d 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 phyr,1 cal 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 1 0.05 weight percent U-235.
CONTROL ROD 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.
For Units I and 2, all control rods shall be clad with stainless steel tubing, except for Unit 2, a maximum of one Rod Cluster Control Assembly may have Inconel clad control rods.
5.4 REACTOR COOLANT SYSTEM l
DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
l a.
In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant tc 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 l
680 F.
VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 12.040 1 100 cubic feet at a nominal T,yg of 525'F.
5.5 METEOROLOGICAL TOWER LOCATION l
5.5.1 The meteorological tower shall be located as shown in Figure 5.1-1.
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CATAWBA - UNITS 1 & 2 5-6 Amendment No.76 (Unit 1)
Amendment No.70 (Unit 2)
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