ML17221A718
| ML17221A718 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/05/1988 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17221A719 | List: |
| References | |
| NUDOCS 8804130337 | |
| Download: ML17221A718 (6) | |
Text
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+k*kk UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POllER I'IGHT COMPANY POCKET NO. 50-335 ST.
LIJCIE PLANT IINIT NO.
1 AMFNPMENT TO FACILITY OPERATING LICENSE Amendment No. 92 License No.
DPR-67 1.
The Nuclear Reoulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power II Light Company, (the licensee) dated January PO,
- 1988, cnmplies with the standards and requirements of the'tomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set fnrth in 10 CFR Chapter I; B.
The facility will the provisions of the Commission; operate in conformity with the application, the Act, and the rules and regulations of C.
There is reasonable assurance (i) that the activities author ized by this amendment can be conducted without endangerino the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Cow ission's regulations; D.
The issuance of this amendment will not he inimical to the common defense and security nr to the health and safetv 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 satis ied.
880m>S03SV 8S0O05 PDR ADOCK 05000335 P,,',
PDR e,,j" r'
2.
Accordingly, Facility Operating License No.
DPR-67 is amended by changes to the Technica>
Specificatinns 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. 92
, are hereby incorporated in the l'.cense.
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 RFAULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 5, 1988 H rbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
M
ATTACHMENT TO LICENSE AMENDMENT NO. 92 TO FACILITY..OPERATING LICENSE NO.
DPR-67 DOCKET NO. 50-335 Replace the following page o< the Appendix "A" Technical Specifications with the enclosed pages.
The revised page is identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document com-pleteness.'P 5-6 Insert Paqes 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 0 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.
avg 5.5 EMERGENCY CORE COOLING SYSTEMS
- 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 ff equivalent to less than or equal to 0.95 when flooded witli unborated water, which includes a conservative allowance of 0.0065 hk for uncertainties.
ST.
LUCIE - UNIT 1
5-5 Amendment No. gg,g7, 7$,
91
DESIGN FEATURES CRITICALITY (Continued 2.
A nominal 10.12 inches center to center distance between fuel assemblies in Region 1 of the storage racks and a nominal 8.86 inches center to center distance between fuel assemblies in Region 2 of the storage racks.
3.
A boron concentration greater than or equal to 1720 ppm.
4.
Neutron absorber (boraflex) installed between spent fuel assemblies in the storage racks in Region 1 and Region 2.
b.
Region 1 of the spent fuel storage racks can be used to store fuel which has a'U-235 enrichment less than or equal to 4.5 weight percent.
Region 2
can be used to store fuel which has achieved sufficient burnup such that storage in Region 1 is not required.
The initial enrichment vs. burnup requirements of Figure 5.6-1 shall be met prior to storage of fuel assemblies in Region 2.
Freshly discharged fuel assemblies may be moved temporarily into Region 2 for purposes of fuel assembly inspection and/or repair, provided that the configuration-is maintained in a checkerboard pattern (i.e., fuel assemblies and empty locations aligned diagonally).
Following such inspection/repair activities, all such fuel assemblies shall be removed from Region 2 and the requirements of Figure 5.6-1 shall be met for fuel storage.
c.
The new fuel storage racks are designed for dry storage of unirradiated fuel assemblies having a U-235 enrichment less than or equal to 4.5 weight percent, while maintaining a
k 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 1706 fuel assemblies.
5.7 SEISJ1IC 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 Requirement.
ST.
LUGIE - UNIT 1 5-6 Amendment No. J7,gg,gg,gg, 7P. M, 92