ML17219A282
| ML17219A282 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/22/1986 |
| From: | Thadani A Office of Nuclear Reactor Regulation |
| To: | Florida Power & Light Co |
| Shared Package | |
| ML17219A283 | List: |
| References | |
| DPR-67-A-076 NUDOCS 8701060409 | |
| Download: ML17219A282 (5) | |
Text
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t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POMER 5 LIGHT COMPANY DOCKET NO. 50-335 ST.
LUCIE PLANT UNIT NO.
1 AYENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76 License No.
DPR-67 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power 8 Light Company, (the licensee) dated October 17, 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 securit'y 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.
t' PDR ADOCu 8 8701060409 OS000a3S~
2 C
2.
Accordingly, Facility Operating License No. DPR-67 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 2.C.(2) to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A
and 8, as revised through Amendment No. 76
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
Attachment:
Changes to the Technical Specifications FOR THE NUCLEAR REGULATORY COt1tiISSION Ashok C
Thadani, Director PWR Project Directorate 88 Division of PWR Licensing-B Date of Issuance:
December 22, 1986
ATTACHMENT TO LICENSE AMENDMENT NO.
TO FACILITY OPERATING LICENSE NO. DPR-67 DOCKET NO. 50-335 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 area of change.
The corresponding overleaf page is also provided to maintain document com-pleteness.
Remove Paae 5-4 Inser t Paae 5-4
FIGURE 5.1-2 (De 1 e ted)
ST.
LUCIE - UNIT 1 5-3 Amendment No, 5 9
DESIGN FEATURES 5.2.1.2 SHIELD BUILDING a.
Minimum annular space
= 4 feet.
b.
Annulus nominal volume
= 543,000 cubic feet.
C.
Nominal outside height (measured from top of foundation base to the top of the dome)
= 230.5 feet.
d.
Nominal inside diameter
= 148 feet.
e.
Cylinder wall minimum thickness
= 3 feet.
f.
Dome minimum thickness
= 2.5 feet.
g.
Dome inside radius
= 112 feet.
DESIGN PRESSURE AND TEMPERATURE 5.2.2 The containment vessel is designed and shall be maintained for a maximum internal pressure of 44 psig and a temperature of 264'F.
PENETRATIONS 5.2.3 Penetrations through the containment structure are designed and shall be maintained in accordance with the original design provisions contained in Sections 3.8.2.1.10 and 6.2.4 of the FSAR with allowance for normal degrada-tion pursuant to the applicable Surveillance Requirements.
5.3 REACTOR CORE FUEL ASSE/1BLIES 5.3.1 The reactor core shall contain 217 fuel assemblies with each fuel assembly containing a maximum of 176 fuel rods clad with Zircaloy-4.
Each fuel rod shall have a nominal active fuel length of between 134.1 and 136.7 inches and contain a maximum total weight of 2250 grams uranium.
Individual fuel assemblies shall contain fuel rods of the same nominal active fuel length.
The initial core loading shall have a maximum enrichment of 2.83 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading.
5.3.2 Except for special test as authorized by the NRC, all fuel assemblies under control element assemblies shall be sleeved with a sleeve"design previously approved by the NRC.
ST(.
LUCIE - UNIT 1
5-4 Amendment No. Q,Q, 76