ML17219A252
| ML17219A252 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/01/1986 |
| From: | Thadani A Office of Nuclear Reactor Regulation |
| To: | Florida Power & Light Co |
| Shared Package | |
| ML17219A253 | List: |
| References | |
| DPR-67-A-075 NUDOCS 8612100195 | |
| Download: ML17219A252 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER
& LIGHT COYiPANY DOCKET NO. 50-335 ST.
LUCIE PLANT UNIT NO.
1 AHENDYiENT TO FACILITY OPERATING LICENSE Amendment No. 75 License No.
DPR-67 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power 5 Light Company, (the licensee) dated July 8, 1986, as supplemented by letter dated October 6, 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.
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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 B, as revised through Amendment No.
75
, 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.
FOR THE NUCLEAR REGULATORY COMMISSION c PigA
~2~~'shok
.'hadani, Director PWR P
ject Directorate k'8 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 1,
1986
ATTACHMENT TO LICENSE AMENDMENT NO.
75 TO FACILITY OPERATING LICENSE NO.
DPR-67 DOCKET NO. 50-335 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pa es 5-5 5-6 Insert Pa es 5-5 5-6
DESIGN FEATURES CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 73 full length and no part length control element assemblies.
The control element assemblies shall be designed and maintained in accordance with the original design provisions, contained in Section
- 4. 2. 3.2 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.
1 The reactor coolant system is designed and shall be maintained:
a ~
In accordance with the code requirements specified in Section
- 5. 2 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and C.
For a temperature of 650'F, except for the pressurizer which is 700'F.
VOLUflE
- 5. 4.2 The total water and steam volume of the reactor coolant system is 11,100 180 cubic feet at a nominal T
of 567'F.
5.5 EMERGENCY CORE COOLING SYSTEMS a
5.5.1 The emergency core cooling systems are designed and shall be main-tained in accordance with the original design provisions contained in Section 6.3 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.6 FUEL STORAGE CRITICALITY 5.6.l.a The spent fuel storage racks are designed and shall be maintained with:
l.
A k equivalent to less.than or equal to 0.95 with the sto Fge poo'l filled with unborated water, which includes the conservative assumptions as described in Section 9. 1 of the FSAR.
ST.
LUCIE - UNIT 1
5-5 Amendment No. lg,27, 75
DESIGN FEATURES CRITICALITY Continued 2.
A center-to-center distance of not less than 12.53 inches between fuel assemblies placed in the storage racks.
3.
A boron concentration greater than or equal to 1720 ppm.
In addition, fuel in the storage pool shall be a U-235 enrichment of less than or equal to 4.0 weight percent.
b.
The new fuel storage racks, are designed for dry storage of unirradiated fuel assemblies having a U-235 enrichment less than or equal to 4.,0 weight percent, while maintaining a
k ff of less than or equal to 0.98 under the most reactive condition.
DRAINAGE 5.6.2 The fuel pool'is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 56 feet.
CAPACITY 5.6.3 The spent fuel pool is designed and shall be maintained with a storage capacity limited to no more than 728 fuel assemblies.
- 5. 7 SEISMIC CLASSIFICATION 5.7.1 Those structures, systems and components identified as seismic Class I
in Section 3.2. 1 of the FSAR shall be designed and maintained to the original design provisions contained in Section 3.7 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.8 METEOROLOGICAL TOWER LOCATION 5.8.1 The meteorological tower location shall be as shown on Figure 5.1-1.
5.9 COMPONENT CYCLE OR TRANSIENT LIMITS 5.9.1 The components identified in Table 5.9-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.9-1.
ST.
L'UCIE - UNIT 1
5-6 Amendment No. V.22.2E.H.