ML15113A239
| ML15113A239 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/27/1986 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duke Power Co |
| Shared Package | |
| ML15113A240 | List: |
| References | |
| DPR-38-A-150, DPR-47-A-150, DPR-55-A-147 NUDOCS 8609090497 | |
| Download: ML15113A239 (8) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 150 License No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated September 24, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations 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; 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.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-38 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.150, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8609090497 860827 PDR ADOCK 05000269 P
_PDR
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- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jo F. Stolz, Director (Po Project Directorate 6
~i vision of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance: August 27, 1986
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.150 License No. DPR-47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated September 24, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and.regulations 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; 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.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.3 of Facility Operating License No. DPR-47 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.150, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION J h
. Stolz, Director Project Directorate Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance: August 27, 1986
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 147 License No. DPR-55
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated September 24, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations 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; 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 e
.51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-55 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.147, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION oh F. Stol z, Director W Project Directorate 6 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance: August 27, 1986
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 150 TO DPR-38 AMENDMENT NO. 150 TO DPR-47 AMENDMENT NO. 147 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Replace the following page of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by amendment numbers and contains vertical lines indicating the area of change.
Remove Page Insert Page 5.3-1 5.3-1
5.3 REACTOR Specification 5.3.1 Reactor Core 5.3.1.1 The reactor core contains approximately 93 metric tons of slightly enriched uranium dioxide pellets. The pellets are encapsulated in Zircaloy-4 tubing to form fuel rods.
The reactor core is made up of 177 fuel assemblies, all of which are prepressurized with Helium. (1) 5.3.1.2 The fuel assemblies shall form an essentially cylindrical lattice with an active height of 142 in. and an equivalent diameter of 128.9 in. (2) 5.3.1.3 There are 61 full-length control rod assemblies (CRA) and 8 axial power shaping rod assemblies (APSR) distributed in the reactor core as shown in FSAR Figure 4.3-3. The full-length CRA and the APSR shall conform to the design described in the FSAR or reload report. (1) 5.3.1.4 Initial core and reload fuel assemblies and rods shall conform to design and evaluation described in the FSAR.
5.3.2 Reactor Coolant System 5.3.2.1 The design of the pressure components in the reactor coolant system shall be in accordance with the code requirements.
(3) 5.3.2.2 The reactor coolant system and any connected auxiliary systems exposed to the reactor coolant conditions of temperature and pressure, shall be designed for a pressure of 2,500 psig and a temperature of 650 0F. The pressurizer and pressurizer surge line shall be designed for a temperature of 670 0F. (4) 5.3.2.3 The maximum reactor coolant system volume shall be 12,200 ft3.
REFERENCES (1) FSAR Section 4.2.2 (2) FSAR Section 4.3.1, and Table 4.3-1 (3) FSAR Section 5.2.3.1 (4) FSAR Section 5.2.1 Amendment No. 150, 150 & 147 5.3-1