ML20097E280
| ML20097E280 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 02/05/1996 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20097E286 | List: |
| References | |
| NUDOCS 9602130424 | |
| Download: ML20097E280 (6) | |
Text
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[k Aq UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001
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DUKE POWER COMPANY QOCKET NO. 50-369 McGUIRE NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 164 License No. NPF-9 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility), Facility Operating License No. NPF-9 filed by the Duke Power Company (licensee) dated November 2,1994, as supplemented November 16 and December 14, 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.
9602130424 960205 PDR ADOCK 05000369 P
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Accordingly, the license is hereby amended by deleting Appendix B, Environmental Protection Plan, and revising Paragraph 2.C.(2) of Facility Operating License No. NPF-9 to read as follows:
(2) Technical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 164, are hereby incorporated into this.
license. The licensee shall operate the facility in accordance with the Technical Specifications.
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 Y
Herbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Revised License Condition 2.C.(2)
Date of Issuance; February 5, 1996
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(3)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, i
possess and use at.any time any byproduct, source and special nuclear material a sealed neutron sources for reactor startup, 3
sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;
)
(4)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, 1
possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or l
associated with radioactive apparatus or components; and
)
(5)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70 to posses, but not separate, such byproduct and special nuclear materials as may be produced by the operation of McGuire Nuclear Station, j
Units 1 and 2.
i i
(6)
Pursuant to.the Act and 10 CFR Parts 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Power Company Training 3
j and Technology Center.
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C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (100%
power).
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.164, are hereby incorporated into this license. The licensee shall operate the facility in accordarce with the Technical Specifications.
Amendment No. 164
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555-0001 i
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DUKE POWER COMPANY l
DOCKET No. 50-370 McGUIRE NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 146 License No. NPF-17 1.
lhe Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility), Facility Operating License No. NPF-17 filed by the Duke Power Company (licensee) dated November 2,1994, as supplemented November 16 and December 14, 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 safaty 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.
l i 2.
Accordingly, the license is hereby amended by deleting Appendix B, Environmental Protection Plan, and revising Paragraph 2.C.(2) of l
Facility Operating License No. NPF-17 to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 146, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This iscense 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 WY
~
Herbert N. Berkow, Director 7
Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Revised License Condition 2.C.(2)
Date of Issuance:
February 5, 1996 i
J
. (6)
Pursuant to the Act and 10 CFR Part 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Power Company Training and Technology Center.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Comission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (100%
power) in accordance with the conditions specified herein and in Attachment I to this license. The preoperational tests, startup tests and other items identified in Attachment I to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.146, are hereby incorporated into license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Antitrust Conditions The licensee shall comply with the antitrust conditions delineated in Appendix C to this license; (4)
Thermal Sleeyn (Section 3.9.2 of SSER #6)*
By December 31, 1983, the licensee siall provide, for NRC staff review and approval, justification for continued operation with the seven thermal sleeves removed from selected locations in the reactor coolant system; i
The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Amendment No. 146