ML20092J627
| ML20092J627 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/18/1995 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20092J629 | List: |
| References | |
| NUDOCS 9509220258 | |
| Download: ML20092J627 (6) | |
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-' t UNITED STATES p-g
,j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 2006H001 i
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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.
135 License No. NPF-35 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, i
Unit 1 (the facility) Facility Operating License No. NPF-35 filed
]
by the Duke Power Company, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated June 17, 1993, as supplemented July 5,1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and thd 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 cl.n 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 accordar.ce with 10 CFR Part 5.1 of the Comission's regulations and all applicable requirements have been satisfied.
I 6
9509220258 950918 PDR ADOCK 05000413 p
- 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 2.C.(2) of Facility Operating License No.
NPF-35 is hereby amended to read as follows:
i Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 135, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
Duke Power Company 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 and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION v
Herbert N. Berkow, Dire
'o r Project Directorate II-2 Division of Reactor Projects - I/II Of fice of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes 4
Date of Issuance: September 18, 1995 4
h i
p au:vq S1 UNITED STATES p*
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.j LCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20066 4001 49.....,o DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY N0. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 129 License No. NPF-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
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 June 17, 1993, as supplemented July 5, 1995, complies with the 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 I; 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 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 Commission'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 Commission's regulations and all applicable requirements have been satisfied.
4
. 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 2.C.(2) of Facility Operating License No.
NPF-52 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.129
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Duke Power Company 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 and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Herbe rkow, Direct Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes
]
Date of Issuance:
September 18, 1995 j
i
ATTACHMENT TO LICENSE AMENDMENT NO. 135 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AliD TO LICENSE AMENDMENT NO. 129 FACILITY OPERATING LICENSE NO. NPF-52
. DOCKET NO. 50-414 Replace the following page of the Appendix "A" Technical Specifications with
. the enclosed page. The revised pages are identified by Amendment number and contains vertical lines indicating the areas of change.
Remove Paae Insert Pace 5-6 5-6 i
f 4
DESIGN' FEATURES PESIGN 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.
l 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor shall contain 193 fuel assemblies.
Each assembly shall consist of a matrix of cylindrical zircaloy clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide as fuel material.
l Limited substitutions of zirconium alloy or stainless steel filler rods for.
fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be used.
Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff-approved ccdes and methods, and shown by tests or analyses to comply with all fuel safety design bases.. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions.
Reload
. fuel shall be similar in physical design to the initial core loading and shall have a maximum nominal enrichment of 5.0 weight percent U-235 with a maximum tolerance of i.05 weight percent U-235.
l CONTROL ROD ASSEMBLIE1~
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 shal1~ be 100% boron carbide and remaining 40-inch tip shall be 80% silver, 15% indium, and 5% cadmium.
For Units 1 and 2, all cpntrol 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.
14 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
I a.
In accordance with the code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, l
b.
For a pressure of 2485 psig, and i
c.
For a temperature of.650*F, except_for the pressurizer which is 680*F.
VOLUME f
.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, of 525'F.
5.5 METEOROLOGICAL TOWER 10 CATION 5.5.1 The meteorological tower shall be located as shown in Figure 5.1-1.
CATAWBA - UNITS'1 AND 2 5-6 Amendment No.135 (Unit 1)
Amendment No.129 (Unit 2)
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