ML20096G272
| ML20096G272 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/22/1996 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20096G276 | List: |
| References | |
| NUDOCS 9601250086 | |
| Download: ML20096G272 (6) | |
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NUCLEAR RECULATORY COMMISSION 4
WASHINGTON, D.C. 20665-0001 DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION. UNIT 1 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
141 License No. NPF-35 1.
The Nuclear Regulatory Commission (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 Powcr Company, acting for itself, North Carolina Electric Membership Ccrporation and Saluda River Electric Cooperative, Inc. (licensees), dated August 8, 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 (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 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.
9601250086 960122 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:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.141
, 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 l
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 1
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'Dl#7 Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: January 22, 1996 l
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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 4001
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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL FOWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY QQEET NO. 50-414 j
CATAWBA NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 135 License No. NPF-52 1.
The Nuclear Regulatory Comission (the Comission) has found that:
i 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 August 8,1995, 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; R.
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 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 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.
. 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:
1 Technical Snecifications 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 f71 Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation 1
Attachment:
Technical Specification Changes Date of Issuance:
January 22, 1996 1
i ATTACHMENT TO LICENSE AMENDMENT NO.
141 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND TO LICENSE AMENDMENT NO.135 FACILITY OPERATING LICENSE tet Of-11 DOCKET NO. 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 vertical lines indicating the areas of change.
Remove Paae Insert Paae 3/4 4-31 3/4 4-31 s
TABLE 4.4-4 (Continued)
I&BLE NOTATIONS Until the specific activity of the Reactor Coolant System is restored within its limits.
Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor was last subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.
A gross radioactivity analysis shall consist of the quantitative measurement of the total specific activity of the reactor coolant except for radionuclides with half-lives less than 10 minutes and all radiciodines. The total specific activity shall be the sum of the beta-gamma activity in the sample within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after the sample is taken and extrapolated back to when the sample was taken.
Determination of the contributors to the gross specific activity shall be based upon those l
energy peaks identifiable with a 95% confidence level.
The latest available data may be used for pure beta-emitting radionuclides.
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- A radiochemical analysis for E shall consist of the quantitative measurement of the specific activity for each radionuclide, except for l
radionuclides with half-lives less than 10 minutes and all radiciodines, i
which is identified in the reactor coolant.
The specific activities for these individual radionuclides shall be used in the determination of E for the reactor coolant sample. Determination of the contributors to E shall be based upon those energy peaks identifiable with a 95% confidence level.
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CATAWBA - UNITS 1 & 2 3/4 4-31 Amendment No. 141 (Unit 1)
Amendment No. 135 (Unit 2) 1