ML17354A762
| ML17354A762 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 01/09/1998 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17354A761 | List: |
| References | |
| NUDOCS 9801220101 | |
| Download: ML17354A762 (5) | |
Text
ATTACHMENT 3 to L-97-317 MARKED-UP TECHNZCAL SPECZFZCATZONS CHANGES Page 5-4 Page 6-22 980i220iOi 980i09 W
~an aaaCX OSOOOaioj P
PDRQ
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEHBLIES I<sF RT 5.3. 1 The core shall contain 157 fuel assemb mbl containing 204 fuel rods clad with'Zircaloy-
, except that replacement of fuel rods by fil~er rods consisting of stainless
- steel, or by vacant rod positions, may be made in fuel assemblies if justified by cycle-specific reload analysis using NRC"approved methodology.
The reactor core contains approximately 71 metric tons of uranium in the form of natural or slightly enriched uranium dioxide pellets.
Each fuel rod shall have a nominal active fuel length of 144 inches.
Should more than 30 individual rods in the core, or 10 fuel rods in any fuel assembly, be replaced per refueling, a Special Report discussing the rod replacements shall be submitted to the Commission within 30 days after
- cycle startup, CONTROL ROO ASSEHBLIES 5.3.2 The core shall contain 45 full-length control rod assemblies.
The full"length control rod assembTies shall contain a nominal 142 inches of absorber material.
The absorber material shall be silver, indium, and cadmium.
All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM OESIGN PRESSURE ANO TEMPERATURE
- 5. 4. 1 The Reactor Coolant System is designed and shall be maintained:
a.
- In accordance with the Code requirements specified in Section
- 4. 1 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
C.
For a pressure of 2485 psig
+ iX, and For a temperature of 650'F, except for the pressurizer which is 6800F.
VOLUME 5.4.2 The nominal water and steam volume of the Reactor Coolant System is 9343 cubic feet at a nominal T
of 574.2'F.
avg
- 5. 5 HETEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological towers shall be located as shown on Figure 5.1-1.
TURKEY POINT - UNITS 3
& 4 5-4, l(
AHENOMENT NOS137 ANO 132
rQS ERT' 4
Addendum 2. Revision 1 (proprietary),
Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code:
Safety Injection in the Broken Loop and Improved Condensation Model
. October 1995.*
WCAP-12945-P, "Westinghouse Code Qualification Document For Best Estimate LOCA
- Analysis, Volumes I-V. June 1996.~
USNRC Safety Evaluati'on Report. Letter from R.
C. Jones (USNRC) to N. J.
Liparulo (W). "Acceptance for Referencing of the Topical Report WCAP-12945(p)
'Westinghouse Code Qualification Document for Best Estimate Loss of Coolant Analysis..'une
- 28. 1996.~
Letter dated June 13.
1996.
from N. J. Liparulo (g) to Frank R. Orr (USNRC).
"Re-Analysis Work Plans Using Final Best Estimate Methodology."**
The analytical methods used to determine Rod Bank Insertion Limits and the All Rods Out position shall be those previously reviewed and approved by the NRC in:
1.
"Westinghouse Reload Safety Evaluation Methodology," July 19B5.
The ability to calculate the COLR nuclear design parameters are demonstrated in:
1.
Florida Power
& Light Company Topical Report NF-TR-95-01.
Nuclear Physics Methodology for Reload Design of Turkey Point
& St. Lucie Nuclear Plants Topical Report NF-TR-95-01 was approved by the NRC for use by Florida Power
& Light Company in:
Safety Evaluation by the Office of Nuclear Reactor Regulations Related to Amendment No.
174 to Facility Operating License DPR-31 and Amendment No.
168 to Fa'cility Operating License DPR-41," Florida Power
& Light Company Turkey Point Units 3 and 4. Docket Nos.
50-250 and 50-251.
The AFD. FQ(Z).
F<H. K(Z). and Rod Bank*Insertion Limits shall be determined such that all applicable limits of the safety analyses are met.
The CORE OPERATING LIMITS REPORT. including any mid-cycle revisions or supplements thereto.
shall be provided upon issuance.
for each
. reload cycle. to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector, unless otherwise approved by the Commission.
J'.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report as stated in the Specifications
.within Sections 3.0. 4.0, or 5.0.
- This reference is only to be used subsequent to NRC approval.
- As evaluated in NRC Safety Evaluation dated TURKEY POINT - UNITS 3
& 4 6-22 AMENDMENT NOS'195 AND189
or ZZRLO 7.
WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report,"
S.
L. Davidson and T. L. Ryan, April 1995
0
,1 a
ap, i
li