ML20247K260
| ML20247K260 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/23/1989 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247K267 | List: |
| References | |
| NUDOCS 8906010258 | |
| Download: ML20247K260 (6) | |
Text
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og UNITED STATES q.
NUCLEAR REGULATORY COMMISSION '
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DUKE POWER COMPANY NCRTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA' RIVER ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY CPERATING LICENSE Amendment No. 64 License No. NPF-35 1.
The Nuclear Regulatory Comission (the Commission) 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 P0wer Company acting for itself, North Carolina Electric Membership) Corporation and Saluda River Electric Cooperative, Inc.,
(licensees dated April 6, 1989, as. supplemented April 21, 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 as set forth in 10 CFR Chapter 1; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
Thereis'reasonableassurance(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 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 r'ablic;.and j
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.
8906010258 890523 PDR ADOCK 05000413 P
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1 2.
Accordingly, the license is hereby amendeo by page changes to the Technical Specifications as indicated in the attachments to this-license amendnent, and Paragraph 2.C.(2) of. Facility Oper3 ting License No.. NPF-35 is hereby anende+ to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 64, 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 hy e-David B. Matthews, Director Project Directorate 11-3
. Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: tiay 23,1989
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UNITED STATES'
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. NUCLEAR REGULATORY _ COMMISSION
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_ WASHINGTON, D. C. 20555
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DUKE PO!!ER COMPA!1Y.
y NORTH CAROLINA til'NICIPAL POWER AGENCY t;0.1-PIEDFONT MUNICIPAL POWER AGENCY-DOCKET NO. 50-414 CATAWBA NUCLEAP STATION, Uf!IT 2 AMENOMENT TO FACILITY OPERATING LICENSE i
Amendment tio. 58 License No. NPF-52 1.
The' Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the. Catawba Nuclear Station, Unit'2 (the facility) Fa.cility Operating License No. NPF-52 filed by -the Duke Power Company acting for itself, North Caro'.ina Municipal Power Agency No. I and Piedmont Municipal Power Agency, (licensees) dated April 6,.1989, as supplemented April 21, 1989, complies with the standards and requirements of the Atomic Energy. Act of 1914, as amended:(the' Act), and the Comission's rules and reguiricions 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 (i) that the. activities authorized by this amendirent can be conducted without. endangering the health and safety of the public, and (fi) 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 amencynent will not be i timical to the comron defense and security or to the health end safety of the ;:ublic; 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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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-52 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 58, 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 C0>711SSION 6
David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation Attachnent:
Technical Specification Changes Date of Issuance: flay 23,1989
1 ATTACHMENT TO LICENSE AMENDMENT NO. 64 FACILITY OPERATING LICENSE NO.~NPF L DOCKET N0. 50-413 Asp TO LICENSE AMENDMENT NO. 58 FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. Sfd14, l
Replace the following page of the Appendix "A" Technical Specifications with
- the enclosed page. The revised page is identified by Amendment nurter and f
contains a vertical line indicating the area of change.
Amended Page 5-6 1
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)
1 1
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 R0D 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 Unit 1, all control rods shall be clad with stainless steel tubing.
For Unit'2, all control rods, except for the control rods in one Rod Cluster Control Assembly (RCCA), shall be clad with stainless steel tubing.
The remaining Rod Cluster Control Assembly control rods shall be clad with Inconel.
5.4 REAC70R 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 FSM, with ailowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure a 2485 psig, and c.
For a temperature of 650 F, except for the pressuriz9r which is 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 f 525"F.
avg 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. 64 (Unit 1)
Amendment No. 58 (Unit 2)