ML17342A604
| ML17342A604 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 07/14/1986 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17342A605 | List: |
| References | |
| NUDOCS 8607220728 | |
| Download: ML17342A604 (6) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
'I FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT PLANT UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 117 License No.
DPR-31 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power and Light Company (the licensee) dated April 15, 1986, 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 reauirements 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-31 is hereby amended to read as follows:
2607220722 2607>g PDR ADOCK 05000250 P
2
{B} Technical S eci~ications The Technical Specifications contained in Appendix A and B, as revised through Amendment No. 117, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications'.
This license amendment is effective as of the date of issuance and shall be implemented within 60 days of issuance.
'OR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
Ju]y ] 4 1/86 Lester S. Rubenstein, Director PMR Project Directorate ¹2 Division of PMR Licensing-A Office of Nuclear Reactor Regulation
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT PLANT UNIT NO.
4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. ill License No.
DPR-41 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power and Light Company (the licensee) dated April 15, 1986, 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 3.8 of Facility Operating License No.
DPR-41 is hereby amended to read as follows:
2 (8)
Technical S ecifications The Technical Specifications contained in Appendix A and B, as revised through Amendment No. 111, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately and shall be implemented within 60 days of issuance FOR THE NUCLEAR REGULATORY COMMISSION oP~~
Lester S. Rubenstein, Director PWR Project Directorate b'2 Division of PMR Licensing-A Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July ]4, 19Q6
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 117 FACILITY OPERATING LICENSE NO.
DPR-31 AMENDMENT NO. ~>>
FACILITY OPERATING LICENSE NO.
DPR-41 DOCKET NO. 50-250 AND 50-251 Revise Appendix A as fo11ows:
Remove Pa es 5.2-1 Insert Pa es 5.2-1
5.2 REACTOR CORE 1 ~
The reactor core contains approximately 71 metric tons of uranium in the form slightly enriched uranium dioxide pellets.
The pellets are encapsulated in
'Zircaloy - 0 tubing to form fuel rods.
The reactor core is made up of 157 fuel assemblies.
Each fuel assembly contains 200 fuel rods.
2.
The average enrichment of the initial core is a nominal 2.50 weight percent of U-235.
Three fuel enrich'nents are used in the initial core.
The highest enrichment is a nominal 3.10 weight percent of U-235.
3.
Reload fuel willhe similar in design to the initial core.
5.
Burnable poisons are in the form of rod clusters which are located in vacant rod cluster control guide tubes, or integral to the fuel design and are used for reactivity and/or power distribution control.
There are 05 full-length RCC assemblies and 8 partial-length" RCC assemblies in the reactor core.
The full-length RC.
assemblies contain a 100 inch length of silver-indium-cadmium alloy clad with the stainless steel.
The partial-length>>
RCC assemblies contain a 36 inch length of silver-indium-cadmium alloy with the remainder of the stainless steel sheath filled with A1203.
The design of the Reactor Coolant System comolies with the code requirements.
2.
All piping, components and supporting structures of the Reactor Coolant System are designed to Class I requirements and have been designed to withstand:
a.
The design seismic ground acceleration, 0.05g acting in the horizontal and 0.033g acting in the vertical planes simultaneously, with stress maintained within code allowable working stresses.
b.
The maximum potential seismic ground acceleration, 0.15g, acting in the horizontal and 0.10g acting in the vertical directions simultaneously with no loss of function.
3.
The nominal liquid volume of the Reactor Coolant System, at rated operating conditions, is 9088 cubic feet.
>> Any r ference to oart-length rods no longer applies after the part-length rods are removed from the reactor.
5.2-1 Amendment Nos.117 and 111