ML080430648
| ML080430648 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 02/22/2008 |
| From: | NRC/NRR/ADRO/DORL/LPLII-2 |
| To: | |
| Mozafari B, NRR/ADRO/DORL, 415-2020 | |
| Shared Package | |
| ML080430644 | List: |
| References | |
| TAC MD6096, TAC MD6097 | |
| Download: ML080430648 (9) | |
Text
Applicable provisions of the Act and of the rules, regulations, and orders of the, Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
A. Maximum Power Level FPL is authorized to operate the facility at steady state reactor core power levels not in excess of 2700 megawatts (thermal).
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 204 are hereby incorporated in the renewed license. FPL shall operate the facility in accordance with the Technical Specifications.
Appendix B, the Environmental Protection Plan (Non-Radiological), contains environmental conditions of the renewed license. If significant detrimental effects or evidence of irreversible damage are detected by the monitoring programs required by Appendix B of this license, FPL will provide the Commission with an analysis of the problem and plan of action to be taken subject to Commission approval to eliminate or significantly reduce the detrimental effects or damage.
C. Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on March 28, 2003, describes certain future activities to be completed before the period of extended operation. FPL shall complete these activities no later than March 1, 2016, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement as revised on March 28, 2003, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following issuance of this renewed license. Until that update is complete, FPL may make changes to the programs described in such supplement without prior Commission approval, provided that FPL evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
D. Sustained Core Uncovery Actions Procedural guidance shall be in place to instruct operators to implement actions that are designed to mitigate a small-break loss-of-coolant accident prior to a calculated time of sustained core uncovery.
Renewed License No. DPR-67 Amendment No. 204
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE 3/4.4.6 CONTAINMENT SYSTEMS 3/4.6.1 CO NTAINM ENT VESSEL ................................................................................... 3/4 6-1 Containm ent Vessel Integrity .............................................................................. 3/4 6-1 Containm ent Leakage ......................................................................................... 3/4 6-2 Containm ent Air Locks .................................................................................... 3/4 6-10 Internal Pressure ............................................................................................... 3/4 6-12 Air Tem perature ................................. ,1.............................................................. 3/4 6-13 Containm ent Vessel Structural Integrity ............................................................ 3/4 6-14 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS ......................................... 3/4 6-15 Containm ent Spray and Cooling System s ........................................ 3/4 6-15 Spray Additive System .......................... .......................................................... 3/4 6-16a 3/4.6.3 CO NTAINM ENT ISO LATIO N VALVES ............................................................ 3/4 6-18 3/4.6.4 DELETED ......................................................................................................... 3/4 6-23 DELETED ....................................................................................... ................. 3/4 6-24 DELETED .................................................................................................... 3/4 6-25 3/4.6.5 VACUUM RELIEF VALVES .............................................................................. 3/4 6-26 I
3/4.6.6 SECO NDARY CO NTAINM ENT ........................................................................ 3/4 6-27 Shield Building Ventilation System ................................................................... 3/4 6-27 Shield Building Integrity ................................................................................... 3/4 6-30 Shield Building Structural Integrity .................................................................... 3/4 6-31 3/4.7 PLANT SYSTEMS 3/.4.7.1 TURBINE CYCLE ............................................................................................... 3/4 7-1 Safety Valves ...................................................................................................... 3/4 7-1 Auxiliary Feedwater System ............................................................................... 3/4 7-4 Condensate Storage Tank ................................................................. 3/4 7-6 Activity ...................... ............................................................................. 3/4 7-7 Main Steam Line Isolation Valves ....................................................................... 3/4 7-9 ST. LUCIE - UNIT 1 VI Amendment No. 27, 434-,4-34, 204
DELETED ST. LUCIE - UNIT 1 3/4 6-23 Amendment No. 89, 204
DELETED ST. LUCIE - UNIT 1 3/4 6-24 TAendrment No. 204
DELETED ST. LUCIE - UNIT 1 3/4 6-25 Amendment No. 464, 204
neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; D. Pursuant to the Act and 10 CFR Parts 30, 40, and 70, FPL to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and E. Pursuant to the Act and 10 CFR Parts 30,-40, and 70, FPL to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
- 3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission's regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
A. Maximum Power Level FPL is authorized to operate the facility at steady state reactor core power levels not in excess of 2700 megawatts (thermal).
Commencing with the startup for Cycle 16 and until the Combustion Engineering Model 3410 Steam Generators are replaced, the maximum reactor core power shall not exceed 89 percent of 2700 megawatts (thermal) if:
- a. The Reactor Coolant System Flow Rate is less than 335,000 gpm but greater than or equal to 300,000 gpm, or
- b. The Reactor Coolant System Flow Rate is greater than or equal to 300,000 gpm AND the percentage of steam generator tubes plugged is greater than 30 percent (2520 tubes/SG) but less than or equal to 42 percent (3532 tubes/SG).
This restriction in maximum reactor core power is based on analyses provided by FPL in submittals dated October 21, 2005 and February 28, 2006, and approved by the NRC in Amendment No. 145, which limits the percent of steam generator tubes plugged to a maximum of 42 percent (3532 tubes) in either steam generator and limits the plugging asymmetry between steam generators to a maximum of 600 tubes.
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 151 are hereby incorporated in the renewed license. FPL shall operate the facility in accordance with the Technical Specifications.
Renewed License No. NPF-16 Amendment No. 151
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CO NTAINM ENT INTEG RITY ..................................................................... 3/4 6-1 CO NTAINM ENT LEAKAG E ....................................................................... 3/4 6-2 CO NTAINM ENT AIR LO CKS .................................................................... 3/4 6-9 INTER NA L PR ESS U R E .......................................................................... ,3/4 6-11 A IR TE MP ERA TU R E ............................................................................... 3/4 6-12 CONTAINMENT VESSEL STRUCTURAL INTEGRITY ......................... 3/4 6-13 CONTAINMENT VENTILATION SYSTEM .............................................. 3/4 6-14 3/4.6.2, DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY AND COOLING SYSTEMS ............................. 3/4 6-15 IO DINE REM OVAL SYSTEM .................................................................. 3/4 6-17 3/4.6.3 CONTAINMENT ISOLATION VALVES ............................................................ 3/4 6-19 3/4.6.4 DELETED D E L E T E D ................................................................................................. 3/4 6 -24 D E L E T E D .................................................................................................. 3/4 6-2 5 3/4.6.5 VACUU M RELIEF VALVES .............................................................................. 3/4 6-26 3/4.6.6 SECONDARY CONTAINMENT SHIELD BUILDING VENTILATION SYSTEM ......................................... 3/4 6-27 SHIELD BUILDING INTEGRITY ............................................................. 3/4 6-30 SHIELD BUILDING STRUCTURAL INTEGRITY ............. ....................... 3/4 6-31 ST. LUCIE - UNIT 2 VII Amendment No. 70, 151
DELETED ST. LUCIE - UNIT 2 3/46-24 ST.
UCIE-UIT23/4 No. 2-7, 151
-24Amendment
DELETED ST. LUCIE - UNIT 2 3/4 6-25 Amendment No. 151