ML17215A640
| ML17215A640 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 10/16/1984 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17215A641 | List: |
| References | |
| NUDOCS 8411140467 | |
| Download: ML17215A640 (7) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER 5 LIGHT COMPANY, ET AL.
DOCKET NO. 50-389 ST.
LUCIE PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
7 License No. NPF-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power 5 Light Company, et al., (the licensee) dated March 13, 1984, 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 Commissioy
'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.
84ii1404b7 84i016 PDR ADOCK 05000389 P
'DR
I
2.
Accordingly, Facility Operating License No. NPF-16 is amended by changes to the Technical Specifications as indicated in the Attach-ment to this license amendment, by amending paragraph 2.C.2, and by adding a
new paragraph 2.C.(19) to read as follows:
2-Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised -through Amendment No.
7
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
(19) Prior to storing extended burnup fuel in the modified spent fuel pool (greater than 38,000 Mw-days/Metric ton) the licensee must submit and obtain approval of a new analysis that addresses the potential of large. gap releases for the extended burnup fuel.
3.
This-license amendment is effective as of the date of its issuance.
Attachment:
Changes to the Technical Specifications Date of Issuance:
October I6,
]9Q4 f.OR THE NUCLEAR REGULATORY COMMISSION E/
~PE r Mc, James R. Miller, Chief Operating Reactors Branch P3 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO. 7 FACILITY OPERATING LICENSE NO.
NPR-16 DOCKET NO. 50-389 Remove and 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.
The corresponding overleaf pages are provided to maintain document completeness.
Remove 5 4 Insert 5-4 5-4a (new)
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.
1 The r'eac&r core shall contain 217 fuel assemblies with each fuel assembly containing 236 fuel rods clad with Zircaloy-4.
Each fuel rod shall have a nominal active fuel length of 136.7 inches and contain a maximum total weight of 1698.5 grams uranium.
The initial core loading shall have a maximum enrichment of 2.73 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 3.70 weight percent U-235.
CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 83 full-length control element assemblies and no part-length control element assemblies.
5.4 REACTOR COOLANT SYSTEM I
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 Qith allowance for normal degradation pursuant of 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.
ST.
LUCIE - UNIT 2
. DESIGN FEATURES VOLUME 5,4.2 The total water and steam volume of the reactor coolant system is 10,931
+ 275 cubic feet at a nominal T
of 572'F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5; 1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY 5.6.T a.
The spent fuel storage racks are designed and shall be maintained with:
DRAINAGE ff equi val ent to 1 ess than or equal to 0. 95 when flooded wit3 unborated water, which includes a conservative allowance of 0.024 dk ff for Total Uncertainty.
eff A nominal 8.96 inch center-to-center distance between fuel assemblies placed in the storage racks.
3.
A boron concentration greater than or equal to 1720 ppm.
Region I can be used to store fuel which has a U-235 enrichment less than or equal to 4.5 weight percent.
Region II can be used to store fuel which has achieved sufficient burnup such that storage in Region I 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 II.
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 f of less than or equal to 0.98 under the most reactive conditi5(.
5.6.2 The spent fuel storage 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 storage pool is designed and shall be maintained with a storage capacity limited to no more than 1076 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
ST'.
LUCIE-UNIT 2 Amendment No.
x 30,000 I
3LK BURNUP REQUIRED FOR STORAGE IN REGION II LU C9,
~; 20,000 CQ V)
Ch 10,000 Ul BURNUP = (lli200)
X (ENRICHHENT M/0)
-13,900 1.5 2.0 2.5 30 3S 40 4.5 5.0 INITIAL U-235 ENRICHMENT, 1/0 FIGURE 5 6-1 INITIAL ENRICHMENT YS BURNUP REQUIREMENTS FOR STORAGE OF FUEL ASSEHBLIES IN REGION II ST.
LUC I E UNIT 2 5-,4A AMENDHENT NO, 7