Text

Proposed Tech Specs,Incorporating Administrative Changes
	ML17228A891
Person / Time
Site:	Saint Lucie
Issue date:	10/27/1994
From:	; FLORIDA POWER & LIGHT CO.
To:	;
Shared Package
ML17228A892	List: ML17228A891; ML17309A751;
References
	NUDOCS 9411020151
	Download: ML17228A891 (112)
	v • d • e

St. Lucie Unit 1 and Unit 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments Administrative U date ATTACHMENT 3 ST ~ LUCIE UNIT 1 MARKED-UP TECHNICAL SPECIFICATION PAGES INDEX SECTION 3 4 Pages Ia Pages 3/4 2-2 III 3/4 3-22 IV 3/4 3-25 V 3/4 3-37 VI 3/4 3-44 VII 3/4 3-45 IX 3/4 3-51 X 3/4 3-52 XI 3/4 3-53 XII 3/4 3-54 XIII 3/4 3-56 XIV 3/4 4-27 XV 3/4 7-10 3/4 11-1 BASES SECTION 2 BASES SECTION 3 4 Page B 2-7 Pages B 3/4 7-1 B 3/4 11-1 94ii02015i 94i027 PDR ADOCK 05000335 P

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INDEX QEF IH IT IONS SECTION PAGE 1.23 Process Control Program (PCP)................... 1-5 1.24 Purge - Purg>ng........................ 1-5 1.25 Rated Thermal Power.................... 1-6 1.26 Reactor Trip System Response Time......,. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

1.27 Reportable Event . 1-6 1.28 Shield Building Integrity........................ 1-6 1.29 Shutdown Margin...................... 1-6 1.30 Site Boundary. 1-6 1 .31 Source Check.......................................... 1-6 1.32 Staggered Test Basis................................ 1-7 1.33 Thermal Power.................. 1-7 1.34 Unidentified Leakage........................ ~ .. 1-7 1.35 Unrestricted Area.................... 1-7 1.36 Unrodded Integrated Radial Peaking Factor - Fr...... .. . 1-7 1.37 DELETED 1-7 FYepeeIey Hollo. TIoh ~ ~ I ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t e e CY tlom t No deS ST. LUCIE - UNIT 1 Ia Amendment No. SN,ND, EE~y

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREHENTS SECTION PAGE 3 4. 0 APPL I CAB ILITY . 3/4 0-1 3 4.1 REACTIVITY CONTROL SYSTEMS 3/4. 1. 1 BORATION CONTROL Shutdown Margin - T, ) 200'F 3/4 Ee le ~

Shutdown Margin - T,, ~ 200'F 3/4 1-3 Boron Dilution 3/4 1-4 Moderator Temperature Coefficient . 3/4 1-5 Minimum Temperature For Criticality . 3/4 1-7 3/4.1.2 BORATION SYSTEMS 3/4 1-8 Flow Paths - Shutdown . . 3/4 1-8 Flow Paths - Operating 3/4 1-10 Charging Pumps - Shutdown . 3/4 1-12 Charging Pumps - Operating 3/4 1-13 Boric Acid Pumps - Shutdown . . . . 3/4 1-14 Boric Acid Pumps - Operating 3/4 1-15 Borated Water Sources - Shutdown 3/4 1-16 Borated Water Sources - Operating . 3/4 1 Qll~i 3/4. 1.3 MOVABLE CONTROL ASSEHBLIES 3/4 1-20 Full Length CEA Position 3/4 1-20 Position Indicator Channels . 3/4 1-24 CEA Drop Time..... 3/4 1-26 Shutdown CEA Insertion Limit 3/4 1-27 Regulating CEA Insertion Limits 3/4 1-28 ST. LUCIE - UN!T 1 Amendment No. 77,

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INDEX LIMITING CONDITIONS fOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3 4. 2 POWER DISTRIBUTION L I HITS 3/4.2.1 LINEAR HEAT RATE................................... 3/4 2-1 3/4.2.2 DELETED 3/4 2-6 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR F ........ 3/4 2-9 3/4.2.4 AZIMUTHAL POWER .........;......... .......

TILT Tq' 3/4 2-11 3/4.2.5 DNB PARAMETERS.............................. ....... 3/4 2-13 3 4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION................. 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.... ...................... ........ 3/4 3-9 3/4.3.3 MONITORING INSTRUMENTATION......................... 3/4 3-21 Radiation Monitoring.. . .......................... 3/4 3-21 Incore Detectors................................... 3/4 3-25

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-'Accident Monitoring Instrumentation.. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3 41 Explosive Gas Monitoring Instrumentation........... 3/4 3-50 3 4.4 REACTOR COOLANT SYSTE 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION...... 3/4 4-1 3/4.4.2 SAFETY VALVES - SHUTDOWN........................... 3/4 4-2 3/4.4.3 SAFETY VALVES OPERATING.......................... 3/4 4-3 ST. LUCIE UNIT 1 IV

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INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3/4.4.4 PRESSURIZER.........................................,.. 3/4 4-4 3/4.4.5 STEAM GENERATORS....................................... 3/4 4-5 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE......................... 3/4 4-12 Leakage Detection Systems............... 3/4 4-12 Reactor Coo1ant System Leakage.......... 3/4 4-14 3/4.4.7 CHEMISTRY..."........................................... 3/4 4-15 3/4.4.8 SPECIFIC ACTIVITY.................-.....,............... 3/4 4-17 3/4.4.9 PRESSURE/TEMPERATURE LIMITS............................ 3/4 4-21 Reactor Coo1ant System.................. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 4-21 Pressurizer............ ~ ....... ~ ~ .- ~ ~ ~ - ~

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3/4 4-25 3/4.4.10 STRUCTURAL INTEGRITY................................... 3/4 4-26 r4SHK H l)'L) Components............... ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ 3/4 4 26 ppn ~ ~ ~ ~ ~ ~ ~ ~

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3/4.4.12 PORV BLOCK VALVES..................... 3/4 4-58 3/4.4.13 POWER OPERATED RELIEF VALVES.......... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 4 59 3/4.4.14 REACTOR COOLANT PUMP - STARTING........................ 3/4 4-60 3/4.4.15 REACTOR COOLANT SYSTEM VENTS............................ 3/4 4-61 3 4.5 EMERGENCY CORE COOLING SYSTEMS ECCS 3/4.5.1 SAFETY INJECTION TANKS................................. 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS ~ Tayg > 325 Fe ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 5 3 3/4.5.3 ECCS SUBSYSTEMS Tayg < 325 F ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .~ i ~ ~ ~ ~ ~ ~ ~ 3/4 5 7 3/4.5.4 REFUELING WATER TANK................................... 3/4 5-8 ST. LUCIE-UNIT 1 Amendment No. gg, Pg, ~,

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3/4. 6 CONTAINMENT SYSTEMS 3/4.6.1 CONTAINMENT VESSEL..................... 3/4 6-1 Containment Vessel Integrity......................... 3/4 6-1 Containment Leakage.................................. 3/4 6-2 Containment Air Locks..............., ................ 3/4 6-10 Internal Pressure.....................-.....-...... " 3/4 6-12 A lr Temperature........................ ~ ~ ~ ~ ~ i ~ ~ ~ ~ ~ ~ ~ ~ 3/4 6-13 Containment Vessel Structural Integrity 3/4 6-14 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS... 3/4 6-15 Containment Spray System............... 3/4 6-15 Spray Additive System.................. 3/4 6-16a Containment Cooling System............. 3/4 6-17.

3/4.6.3 CONTAINMENT ISOLATION VALVES........... 3/4 6-18 3/4.6.4 COMBUSTIBLE GAS CONTROL................ 3/4 6-23

'ydrogen Analyzers................... " 3/4 6-23 Electric Hydrogen Recombiners - W ..... 3/4 6-24 3/4.6.5 VACUUM RELIEF VALVES................... 3/4 6-26 3/4.6.6 SECONDARY CONTAINMENT...'............. ~... ~ ~ - ~ ~ ~ ' ~ - ~ 3/4 6-27 Shield Building Ventilation System..... 3/4 6-27 Shield Building Integrity.............. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 6-3O

~hield Building Structural Integrity.'." 3/4 6-31 3/4.7 PLANT SYSTEHS 3/4.7.1, TURBINE CYCLE ......................;.........-...-..'fety 3/4 7-1 S Valves........................................ 3/4 7-1 Auxiliary Feedwater System............ 3/4 7-4 Condensate Storage Tank..-... ..

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~ - ~ ~ ~ ~ om INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3/7.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION....... 3/4 7-13 3/4.7.3 COMPONENT COOLING MATER SYSTEM........................ 3/4 7-14 3/4.7.4 INTAKE COOLING WATER SYSTEM........................... 3/4 7-16 3/4.7o5 ULTIMATE HEAT SINK.................................... 3/4 7-18 3/4.7.6 FLOOD PROTECTION...................................... 3/4 7-19 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM............. 3/4 7-20 3/4.7.8 ECCS AREA VENTILATION SYSTEM.......................... 3/4 7-24 3/4.7.9 SEALED SOURCE CONTAMINATION........................... 3/4 7-27 r

3/4.7;10 SNUBBERS.............................................. 3/4 7-29 Fire u ression Water System................. ...... 3/4 7-Fire Hose Stations.. ........ ............. .. .... 3/4 7-4 Yard Fire Hydran Hydrant ouses............ 3/4 7-S e er'ystems................................ ... 3/4 7-4 c EFRA ~N~~RR ~ o o ~ o o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o o o ~ o ~ ~

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3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C.. SOURCES.......................................... 3/4 8-1 0 Peratl ng o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 8 1 l

S hutdown o ~ ~ ~ ~ ~ o o ~ ~ ~ o ~ o o o o o o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 3/4 8 7 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS..................... 3/4 8-8 A.C. Distribution - Operating. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 8 8 A.C. Distribution - Shutdown .. 3/4 8-9 D.C. Distribution - Operating......................... 3/4 8-10 D.C. Distribution - Shutdown.......................... 3/4 8-13 ST. LUCIE - UNIT 1 VII Amendment Nn. ES. AN, P8

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INDEX BASES SECTION PAGE 3/4.0 APPLICABILITY .................................. 8 3/4 O-l 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATIOH CONTROL . .... . . ............... ........

~ 8 3/4 l-l 3/4.1.2 BORATION SYSTEMS......,.......,. ... . , . . . . 8 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES ........; ................. 8 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LIttEAR HEAT RATE ...... ............................ 8 3/4 2-1.

3/4.2.2 ~H+fto.................. 8 .3/4 2-1 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKIHG FACTOR - F ......... 8 3/4 2-1 3/4.2.4 AZIMUTHAL POttEP, TILT .......... ~ ~ ~ 8 3/4 2-1 3/4.2. 5 OHB PARAMETERS ............................... 8 3/4 2-2 3/4'. 3 IHSTRUt1EN TATIOH 3/4.3.1 and 3/4.3.2 PROTECTIVE. AND ENGINEERED SAFETY FEATURES IHSTRUt!ENTATION ..................... 8 3/A 3-1 3/4.3.3 MONITORING INSTRUMEiNTATION ................ 8 3/4 3-1 ST. LUCIE - UNIT 1 IX Amendment Ho.

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INDEX BASES SECTION PAGE 3 4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION.......... 8 3/4 4-1 3/4.4.2 and 3/4.4.3 SAFETY VALVES.............................. 8 3/4 4-1 3/4.4.4 PRESSURIZER. ~ .......- -. ... ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 3/4 4-2 3/4.4.5 STEAM GENERATORS....................................... 8 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE......................... 8 3/4 4-4 3/4.4.7 C HEMISTRYo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 3/4 4-4 3/4.4.8 SPECIFIC ACTIVITY............... ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 3/4 4 5

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3/4.4o9 PRESSURE/TEMPERATURE LIMITS..... 8 3/4 4 6 3/4 4 10 STRUCTURAL INTEGRITY a ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 3/4 4-12 3/4.4.11 0 ELETED ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3 3/4 4-13 3/4.4.12 PORV BLOCK VALVES...................................... 8 3/4 4-14 3/4.4.13 POWER OPERATED RELIEf VALVES and 3/4.4.14 REACTOR COOLANT PUMP - STARTING......... ~

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' ~~~~ ~ ~ ~ ~ ~ ~ 8 3/4 4 15 3/4.4.15 REACTOR COOLANT SYSTEM VENTS........................... 8 3/4 4-15 3 4.5 EMERGENCY CORE COOLING SYSTEMS ECCS 3/4.5.1 SAFETY INJECTION TANKS................................. 8 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS............................. 8 3/4 5-1 3/4.5.4 REFUELING WATER RAG TANK STf................ 8 3/4 5-2 geist'/4.

6 CONTAINMENT SYSTEMS 3/4.6.1 CONTAINMENT VESSEL..................................... 8 3/4 6-1 3/4.6. 2 DEPRESSURIZATION AND COOLING SYSTEMS................... 8 3/4 6-2 3/4.6.3 . CONTAINMENT ISOLATION VALVES........................... 8 3/4 6-3 3/4.6.4 COMBUSTIBLE GAS CONTROL...........-.......--.........-. 8 3/4 6-3 3/4.6. 5 VACUUM RELIEF VALVES.........................;......... 8 3/4 6-4 3/4.6.6 SECONDARY CgNTAINMENT........;..............-..... ..... 8 3/4 6-4 ST. LUCIE -.UNIT 1 X Amendment No. 27, N, N,98'

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INDEX BASES SECTION PAGE 3/4.9.9 CONTAINMENT ISOLATION SYSTEM ....... 8 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND STORAGE POOL WATER LEVEL .................-.......... 8 3/4 9-2 3/4.9.12 FUEL POOL VENTILATION SYSTEM - FUEL STORAGE 8 3/4 9-3 3/4.9.13. SPENT FUEL CASK CRANE ...................,........... 8 3/4 9-3 3/4.9.14 DECAY TIME - STORAGF POOL ........................... 8 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN ..................................... 8 3/4 10-1 3/4.10.2 GROUP LIMITS .................................

HEIGHT, INSERTION AND POWER DISTRIBUTION 8 3/4 10-1 3/4.10.3 DELETED 3/4.10.4 DELETED 3/4.10.5 CENTER CEA MISALIGNMENT . .. . . . . .. . . 8 3/4 10-1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 ~8&9 ~ttf ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 ~ ~ ~ \ ~ ........... 8 3/4 ll-l 8 +,>(.c.$ &'A.aside a$ Netvl tf~FBHBRS ... 8 3/4 11 S +. ( i. g . g GAS cAA5 Hrth'S b&B-RAB%6A ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ \ ~ ~ .......... 8 3/4 11-5 3/4.12.-1 MONITORING OGRE ............... -............. 8 3/4 12-1

/4.12.2 LAND USE C 0 ......... 8 3/4 12-2 BQRAT4RY-MMPAM4QN-PROGRA ST. LUCIE - UNIT 1 XII Amendment No. P, gP,/g7,

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INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE E xclusion Area............................................ 5-1 Low Population Zone.... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ d ~ ~ ~ ~ ~ ~ ~ ~ 5,1 Flood Control.......... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ V~ ~ ~ ~ ~ ~ d ~ ~

5. 2 CONTAINMENT C onff- 1 guratl on ~ d ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

5-1 Design Pressure and Temperature........................... 5-4 P enetrations............................................:. 5-4 5.3 REACTOR CORE F uel Assemblies........................................... 5-4 Control Element Assemblies................................ 5-5 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature........................... 5-5 V ol ume e ~ ~ ~ ~ ~ ~ d ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5-5 5.5 EMERGENCY CORE COOLING SYSTEMS............................ 5-5 5.6 FUEL STORAGE vrizicaiiry................................................ 5-5 Drainage..................................................

5.7 SEISMIC CLASSIFICATION.................................... 5-6 5.8 METEOROLOGICAL TOWER LOCATION............................. S ~~

5d9 COMPONENT CYCLE OR TRANSIENT LIMITS....................... S qQ~

ST. LUCIE - UNIT 1 XIII II d

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jADEX ADMINISTRATIVE CONTROLS S~C 'ON PAGE I

5. 1 RESPONSIBILITY ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-1 6.2 ORGANIZATION

(.2.1 ONSITE AND OFFSITE ORGANIZATI~N ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 1 6.2.2 UNIT STAFF.....,........

6.2.3 SHIFT TECHNICAL AOVISOR..................................... 6-5 6.3 UNIT STAFF UALIFICATIONS................................... 6-6 6.4 T RAININGo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

6.5 REVIEW ANO AUDIT

6. 5.1 FACILITY REVIEW GROUP functl on o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 6 C omposition................................................. 6-6 A lternates.................................................. 6-7 Meeting Frequency.......................... ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 7 uorumo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 6 7 Responsibilities............................................ 6-7 A uthorsty................................................... 6-8 R ecords.....................................................,6-8 6.5.2 COMPANY NUCLEAR REVIEW BOARO F Uncti on ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 6 9 C omposition................................................. 6-9 A lternates......,........................................... 6-9 Consultants........ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 6 10 Meeting Frequency.. ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Q uorum...................................................... 6-10 R eviBI ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 6 10 A udits...................................................... 6-11 A uthorsty.........................., ,, 4 'W 19 R ecords..................................................... 6-12 ST. LUCIE - UNIT 1 XIV Amendment No. Q,

INOEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.6 REPORTABLE EVENT ACTION................................. 6-12 6.7 SAFETY LIMIT VIOLATION.................................. 6-12 6.8 PROCEDURES AND PROGRAMS................................. 6-13

6. 9 REPORTING RE U IREMENTS 6.9.1 ROUTINE REPORTS....................................... 5 @>

Startup Report ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5-15+

Annual Reports............................. 6-16 Monthly Operating Reports.................. 6-16 a Annual Radioactive Effluent Release Report. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-17 Annual Radiological Environmental Operating Report.... 6-18 6.9.2 SPECIAL REPORTS.............-.......................... 6-19

6. 10 RECORD RETENTION........................................ 6-20 6.11 RADIATION PROTECTION PROGRAM............................ 6-21 6.12 HIGH RADIATION AREA..................................... 6-22

6. 13 PROCESS CONTROL PROGRAM................................. 6-23 6.14 OFFSITE DOSE CALCULATION MANUAL.......................... 6-23 ST. LUCIE UNIT 1 XV 4 d t N

t LIMITING SAFETY SYSTEM SETTINGS BASES Thermal Mar in Low Pressure The Thermal Margin/Low Pressure trip is provided to prevent operation when the ONBR is less than the'NBR limit. I The trip is initiated whenever the reactor coolant system pressure signal drops below either 1887 psia or a computed value as described below, whichever is higher. The computed value is a function of the higher of dT power or neutron power, reactor inlet temperature. the number of reactor coolant pumps operating and the AXIAL SHAPE INOEX. The minimum value of reactor coolant flow rate, the maximum AZIMUTHAL POWER TILT and the maximum CEA deviation permitted for continuous operation are assumed in the generation of this trip function. In addition, CEA group sequencing in accordance with Specifications 3.1.3.5 and 3.1.3.6 is assumed. Finally, the maximum insertion of CEA banks which can occur during any anticipated operational occurrence prior to a Power Level-High trip is assumed.

The Thermal Margin/Low Pressure trip setpoints include appropriate qV allowances for equipment response time, calculational and measur ent uncer-tainties, and processing error. A further allowance included to compensate for the time delay associated with providing effective termina-tion of the occurrence that exhibits the most rapid decrease in margin to the DNBR 1 imi t.

As etric Steam Generator Transient Protective Tri Function ASGTPTF The ASGTPTF consists of Steam Generator pressure inputs to the TM/LP calculator, which causes a reactor trip when the difference in pressure between the two steam generators exceeds the trip setpoint. The ASGTPTF is designed to provide a reactor trip for those events associated with secondary system mal-functions which resul t in asymmetric primary loop coolant temperatures. The most limiting event is the loss of load to one steam generator caused by a single main steam isolation valve closure.

The equipment trip setpoint and allowable values are calculated to account for instrument uncertainties, and will ensure a trip at or before reaching ',the analysis setpoint. if ST. LUCIE - UNIT 1 B 2-7 Amendmen t No . 27, P 3, fN

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POWER DISTRIBUTION LIMITS SURVEILLANCE RE UIREMENTS Continued C. Verifying that the AXIAL SHAPE INDEX is maintained within the allowable limits of Figure 3.2-2, where 100 percent of maximum allowable power represents the maximum THERMAL POWER allowed by the following expression:

MxN where:

1. M is the maximum allowable THERMAL POWER level for the existing Reactor Coolant Pump combination.

2. N is the maximum allowable fraction of RATED THERMAL POWER T

as determined by the F curve of Figure 3.2-3.

4.2.1.4 Incore Detector Monitorin S stem - The incore detector monitor-ing system may be used for monitoring the core power distribution by verifying that the incore detector Local Power Density alarms:

a ~ Are adjusted to satis'fy the requirements of the core power distribution map which shall be updated at least once per 31 days of accumulated operation in MODE l.

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b. Have their alarm setpoint adjusted to less than or equal to the limits. shown on Figure 3.2-1 when the following factors are appropriately included in the setting of these alarms:

l. A measurement-calculational uncertainty factor of 1.07,

2. An engineering uncertainty factor of 1.03,

3. A THERMAL POWER measurement uncertainty factor of 1.02.

incore NJf the~ system becomes inoperable, reduce power to M x N within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and monitor linear heat rate in accordance with Specification 4.2.1.

ST. LUCI E - UNIT 1 3/4 2-2 Amendment No. 77, 27. 32.58& "<

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1. AREA HONITORS

a. Fuel Storage Pool Area g 15 mR/hr 10 10 mR/h) 13

b. Containment (CIS) 3 6 g 90 mR/hr 1 - 10 mR/hr 16

c. Containment Area - Hi 1, 2, 3 & 4 5 10 R/hr 1 10 R/hr Range

2. PROCESS HONITORS

a. Containment LO - lO cpm

i. Gaseous Activity RCS Leakage Detection 1, 2, 3 & 4 Not Applicable ii. Particulate Activity RCS Leakage Detection 1, 2, 3 & 4 Not Applicable 14

b. Fuel Storage Pool Area 6

>O-tO cpr Ventilation System

i. Gaseous Activity 10

" 10 QCi/cc 12 ii. Particulate Activity 1- 10 cpm 12

With fuel in the storage pool or building.

- With irradiated fuel in the storage pool or whenever there is fuel movement within the pool or crane O operation with loads over the storage pool.

- - The Alarm Setpoints are determined and set in accordance with requirements of the Offsite Dose Calculation Hanual.

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INSTRUMENTATION INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3 ~ 2 The incore detection system shall be OPERABLE with:

a. At least 75K of all incore detector locations, and

b. A minimum of two quadrant symmetric incore detector locations per core quadrant.

An OPERABLE incore detector location shall consist of a fuel assembly contain-ing a fixed detector string with a minimum of three OPERABLE rhodium detectors.

APPLICABILITY: When the incore detection system is used for:

a. Recalibration of the excore axial flux offset detection system,

b. Monitoring the AZIMUTHAL POWER TILT,

c. Calibration of the power level neutron flux channels, or

d. Monitoring the linear heat rate.

ACTION:

With the incore detection system inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.2 The incore detection system shall be demonstrated OPERABLE:

$ 15 CHAaYs5.

a. By performance of a CHANNEL CHECK within 7 et@

~ prior to, its Fgggtoosl:f 84~0%5%60 8'f 1. Recalibration of the excore axial flux offset detection Hi gatv, system,

2. Monitoring the linear heat rate pursuant to Specification 4.2.1.

ST LUCI E - UNIT 1 3/4 3-25 Amendment No. dy, pt t~>YE

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deleted from the Technical Specifications.

ST. LUCIE - UNIT I 3/4 3-37 Amendment No. ~4-,84

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TABLE 4.3-7 ACCIDENT HONITORING INSTRUHENTATION SURVEILLANCE RE IREHENTS CHANNEL CHANNEL INSTRUHENT CHECK CALIBRATION Pressurizer Water Level

2. Auxiliary Feedwater Flow Rate

3. Reactor Coolant System Subcooling Margin Monitor

4. PORV Position Indicator

5. PORV Block Valve Position Indicator

6. Safety Valve Indi cator

7. Incore Thermocouples PoSiklorl

8. Containment Sump Mater Level (Narrow Range)

9. Containment Sump Mater Level .=. R

10. Reactor Vessel Level Monitoring System ll. Containment Pressure R

0 C $

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pages 3/4 3-46 through 3/4 3-49 (Amendment No. 123) have been i deleted from the Technical Specifications.

ST. LUCIE - UNIT 1 3/4 3-45 AMENDMENT NO. $ 9. SH i

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TABLE 3.3-13 EXPLOSIVE GAS MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. WASTE GAS DECAY TANKS EXPLOSIVE GAS MONITORING SYSTEM

a. Oxygen Monitors TABLE NOTATION

During waste gas system operation.

ACTION 1 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, oper ation of this system may continue for up to 30 days provided samples of Oa are analyzed by the

'I lab gas partitioner at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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TABLE 4.3-9 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS CHANNEL HODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CIIECK CAEIEEAIIOK IEEI ~RE OIIIEO

1. WASTE GAS DECAY TANKS EXPLOSIVE GAS HONITORING SYSTEM

a. Oxygen Monitor 0(I)

b. Oxygen monitor (alternate) g(l)

TA LE NOTATION

During waste gas holdup system operation.

(1) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. One volume percent oxygen, balance nitrogen, and

.2- Four volume percent oxygen, balance nitrogen.

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Ouring waste ga tern operation.

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1. MASTE GAS DECAY TANKS E IVE GAS MONITORING SYS

a. Oxygen nitor Q(I) xygen Monitor (alternate) 0(I) ll2ggINE4. TNS ldfoR%KCenL Wo WE. ~/< >-5~

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During wast dup system operation.

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REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS (Continued)

,Pages 3/4 4-28 through 3/4 4-55 (Amendment No. 90), and Pages 3/4 I4-56 through 3/4 4-57 (Amendment No. 80) have been deleted from Ithe Technical Specifications.

ST. LUC IE - UNIT 1 3/4 4-27 Amendment No. P6

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Pages 3/4 7-11 through 3/4 7-12 (Amendment No. 86) have been deleted from the Technical Specifications.

ST. LUCIE - UNIT 1 3/4 7-10 Amendment Nn.P

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ST. LUG IE - UNIT 1 3/4 11-1 AMENDMENT NO.SH

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3/4.7 PLANaT SYSTEMS BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES

)'io g of The OPERABILITY of the main steam line code safety valves ensures t4at the second r s stem pressure will be limited to within its desi n ressure of 'uring the most severe anticipated system opera-tional transient. The maximum relieving capacity is associated with a turbine trip from 100% RATED THERNL POWER coincident with an assumed loss of condenser heat sink (i.e., no steam bypass to the condenser).

The specified valve lift settings and relieving capacities are in accordance with the requirements of Section III of the ASt<E Boiler and Pressure Code, 1971 Edition and ASME Code for Pumps and Valves, Class II.

The total relieving capacity for all valves on all of the steam 'lines is 12.88 x:10s Ibs/hr which is 102.8 percent the tote'I secondary steam flow of 12.04 x 106 lbs/hr at 100K RATED THERNL POWER. A minimum of 2 OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for removing decay heat.

STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in secondary system steam flow and THERfQL POWER required by the reduced reactor trip settings of the Power Level-High channels. The reac'tor tri p setpoi nt reductions are derived on the following bases:

For two loop operation SP

(")- (

x (106.5) nial where:

SP reduced reactor trip setpoint in percent of RATED THERMAL POWER maximum number of inoperable safety valves per steam line ST. LUCI E - UNIT 1 B 3/4 7-1 221st sa saa n~ t I,IO

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3 4.11 RADIOACTIVE EFFLUENTS BASES Pages B 3/4 11-2 through B 3/4 11-3 (Amendment No. 123) have been

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ST. LUG I E - UNIT 1 B 3/4 11-1 Amendment No. 59, ~

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St. Lucie Unit 1 and Unit 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments Administrative U date ATTACHMENT 4 ST ~ LUCZE UNIT 2 MARKED-UP TECHNICAL SPECIFICATION PAGES INDEX SECTION 3 4 Pages V Pages 3/4 3-4 VIII 3/4 3-15 X 3/4 3-16 XIV 3/4 3-27 XVI 3/4 3-30 XVIII 3/4 3-43 XXI 3/4 3-44 XXIII 3/4 3-48 XXIV 3/4 3-54 XXV 3/4 3-55 3/4 3-56 3/4 3-57 3/4 3-59 3/4 11-1 BASES SECTION 3 4 Pages B 3/4 5-2 B 3/4 11-1

INOEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3 4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE........... 3/4 2-1 3/4.2.2 TOTAL PLANAR RADIAL PEAKING FACTOR - F 3/4 2-7 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR F ........... 3/4 2-9 3/4.2.4 AZIMUTHAL POWER TILT.................................. 3/4 2-13 3/4.2.5 DNB PARAMETERS............................-........-.. 3/4 2-14 3 4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION.................... 3/4 3-1 No'%/4. 3. 2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM QiS eAAgCF-INSTRUMENTATION............................. ........ 3/4 3-11

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RADIATION MONITORING INSTRUMENTATION.................. 3/4 3-24

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INCORE DETECTORS....................-....... 3/4 3-30

~( 68. MEIRAR6 o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

INSTRUMENTATION........................ 3/4 3-35 METEOROLOGICAL REMOTE SHUTDOWN INSTRUMENTATION....................... 3/4 3-38 ACCIDENT MONITORING INSTRUMENTATION .. 3/4 3-41 bkl4LO!%4ttllfLZIIS4ltlllEH'WFM LOOSE-PART DETECTION INSTRUMENTATION........ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3 47 EXPLOSIVE GAS MONITORING INSTRUMENTATION.............. 3/4 3-53 3/4.3.4 TURBINE OVERSPEED PROTECTION.......................... 3/4 3-60 3 4.4 REACTOR COOLANT SYSTEM 3/4.4. 1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION.................. 3/4 4-1 HOT STANDBY.................................. 3/4 4-2 HOT SHUTDOWN.......................................... 3/4 4-3 COLD SHUTDOWN (LOOPS FILLED)................. 3/4 4-5 COLD SHUTDOWN (LOOPS NOT FILLED):............ 3/4 4.-6 ST. LUC IE UNIT 2 Amendment No /

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4. 7. 1 TURBINE CYCLE 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 MAIN FEEDWATER LINE ISOLATION VALVES. 3/4 7-10 ATMOSPHERIC DUMP VALVES........... 3/4 7-u.

3/4. 7. 2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION......... 3/4 7-12 3/4.7. 3 COMPONENT COOLING WATER SYSTEM.... 3/4 7-13 3/4.7. 4 INTAKE COOLING WATER SYSTEM..... 3/4 7-14 3/4. 7. 5 ULTIMATE HEAT SINK. 3/4 7-15 3/4. 7. 6 FLOOD PROTECTION. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 7-16 3/4.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM.......... 3/4 7-17 3/4.7.8 ECCS AREA VENTILATION SYSTEM...... 3/4 7-20 3/4.7.9 SNUBBERS 3/4 7-21 3/4.7.10 SEALED SOURCE CONTAMINATION....... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 7-28 E SUPPRES&N~kTE~STE ................

+5'HOSTS'ION o ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

NR0- DRANTSMNB-HYDRA~OS U

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ \ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

4T 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8. 1 - A.C. SOURCES 0 PE RATING o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

' ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 8-1 S HUTDOWN o ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ s ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 8-9 C/

ST. LUCIE - UNIT 2 VIII .

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE EXPLOSIVE GAS MIXTURE....... ...... .............. 3/4 11-14 GAS STORAGE TANKS..................... 3/4 11-15 ST. LUCIE UNIT 2 Amendment No

P.~.ft,A 4 >

'0

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INOEX BASES ~

SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4. 7. 1 TURBINE CYCLE B 3/4'7-1 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION....:.. B 3/4 7"4 3/4.7.3 COMPONENT COOLING WATER SYSTEM. ~ . ~... ~...... B 3/4 7"4 3/4.7.4 INTAKE COOLING WATER SYSTEM................... B 3/4 7-4 3/4.7. 5 ULTIMATE HEAT SINK....... ' ~ - ~ - - - - ~ ~ ~: ~ ~ ~ ~ ~ B 3/4 7-5 3/4.7. 6 FLOOD PROTECTION........ ~ ......... B 3/4 7-5 3/4.7. 7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM. B 3/4 7-5 3/4.7.8 ECCS AREA VENTILATION SYSTEM. B 3/4 7"5 3/4.7. 9 S NUBBE RS o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 7-6 3/4. 7. 10 SEALED SOURCE CONTAMINATION..... B 3/4 7-7 3/4.8 EI ECTRICAL POWER SYSTEMS 3/4.8. 1, 3/4.8. 2 and 3/4.8. 3 A. C. SOURCES, D. C. SOURCES and ONSITE POWER DISTRIBUTION SYSTEMS B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES B 3/4 8'-3 3/4. 9 REFUELING OPERATIONS 3/4. 9. 1 BORON CONCENTRATION................................... B 3/4 9"1 3/4. 9. 2 INSTRUMENTATION.. B 3/4 9-1 3/4.9. 3 DECAY TIME......................... B 3/4 9-1 3/4. 9.4 CONTAINMENT BUILDING PENETRATIONS.. B 3/4 9-1 3/4.9. 5 'OMMUNICATIONS B 3/4 9-1 ST. LUCIE -

P UNIT 2 XIV ~/IN'u.

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INDEX BASES SECTION PAGE

)A@$ 3/4. 11 RADIOACTIVE EFFLUENTS PW

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~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 3/4 ll-9', t~.c.c cygne sloRAt'E 'NIKE B 3/4 11-5 3/4. 12. 1 M TTOfHNG-PRO RAN. B 3/4 12-3/4. 12.2 LAND USE SU B 3/4 12-3 ORY COMPARISON PROGRAM...

0 ST. LUCIE " UNIT 2 XVI ~ex/jun t ho.

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INDE'0MIHISTRATIYE CONTROLS iECTIQN PAGE

6. 1 RESPONSIBILITY

6. 2 ORGANIZATION. 6-1

6. 2. 1 Ot/SITE Ati0 OFFSITE ORGANIZATION.~ 6-1 y

6. 2. 2 UNIT STAFF.. ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

6. 2. 3 INOEPENOENT SAFETY ENGINEERING GROUP.

FUNCTION......... ~ ~ 6-6 COMPOS ITIOH............. 6-6 RESPONSIBILITIES ..

AUTHORITY... 6-6 RECOROS........ 6"6

6. 2. 4 SHIFT TECHNICAL AOVISOR.............................,.....

6. 3 UNIT STAFF UALIFICATIONS................................... 6-6 6 4

~ TRAIN!NGo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ * ~ ~ ~ ~ ~ \ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ 6-7 6.5 REVIEW ANO AUOIT................................. 6-7

6. 5. 1 FACILITY 'REVIEW GROUP..... 6-7 FUNCTION............... 6-7 COMPOSITION............ ~ ~ 0 ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-7 A LTERNATES................................. 6-7 MEETING FRE)UENCY.............. -........ -..... - . 6-8 QUORUM................. ~ 1 ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-8 RESPONSIBILITIES....... ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-8 AUTHORITY.. ~ ............................. 6-9 R ECORD5 t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

6-9 ST. LUCIE - UNIT 2 XVIII Amendnent 'No-

f'

~Nf'X LIST QF'IGURES ee s s s 8 s + g g g s s s s s s s s s 8 8 s 0 s s s s s s s s 8 ee ee s 8 5 s s s s s s s s 8 s R s s 0 8 s 5 s s s s 4 g g m g g g s g g g g g g g

~FG~R PAG 2.1-1 REACTOR CORE THERMAL MARGIN SAFETY LIMIT LINES FOUR REACTOR COOLANT PUHPS OPERATING......,........,..... 2-3 2.2-1 LOCAL POMER DENSITY - HIGH TRIP SETPOINT PART 1 (FRACTION OF RATED THERMAL POWER VERSUS gR~)............. 2-7 2.2-2 LOCAL POWER DENSITY - HIGH TRIP SETPOINT PART 2 (gR) VERSUS Yi).......................................... 2-8 Fo 2 3 THERMAL MARGIN/LOM PRESSURE TRIP SETPOINT PART 1

( Yi VERSUS Ai)........................................... 2-9

2. 2-4 THERMAL MARGIN/LOM PRESSURE TRIP SETPOINT PART 2 (FRACTION OF RATED THERMAL POMER VERSUS gRi)............. 2-10 B 2.1-1 AXIAL POWER DISTRIBUTION FOR THERMAL MARGIN SAFETY LIMITS..............-............................ B 2-2 3.1-1 MINIMUM BORIC ACID STORAGE TANK VOLUHE AS A FUNCTION OF STORED BORIC ACID CONCENTRATION...................... 3/4 1-15 T

3.1-1a ALLOMABLE TIHE TO REALIGN CEA VS INITIAL F~............. 3/4 1-19a 3.1-2 CEA INSERTION LIMITS VS THERMAL POMER MITH FOUR REACTOR COOLANT PUMPS OPERATING......................... 3/4 1-28 3.2-1 ALLOMABLE PEAK LINEAR HEAT RATE VS BURNUP............... 3/4 2-3 3~2 2 AXIAL SHAPE INDEX VS FRACTION OF MAXIMUM ALLOWABLE POWER LEVEL PER SPECIFICATION 4.2.).3................... 3/4 2-4 T T 3~2 3 ALLOWABLE COMBINATIONS OF THERMAL POWER AND F<e Fxy i ~ ~ ~ ~ 3/4 2 5 4.2-1 0 ELETED ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 2-6

~ e 3.2-4 AXIAL SHAPE INDEX OPERATING LIMITS WITH FOUR REACTOR COOLANT PUMPS OPERATING................................. 3/4 2-12 3.4-1 DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMITS VERSUS PERCENT OF RATED THERHAL POWER WITH THE PRIMARY COOLANT SPECIFIC ACTIVITY >I uC)/GRAM DOSE EQUIVALENT I-131........................................ 3/4 4 3.4-2 REACTOR COOLANT SYSTEH PRESSURE TEMPERATURE LIMITATIONS FOR 15 EFPY, HEATUP AND CORE CRITICAL................... 3/4 4-31a ST. LUG IE - UNIT 2 XXI Amendment No. m,

~

jiff~

INDEX LIST OF TABLES TABLE PAGE FREQUENCY NOTATION... 1-8 1.2 OPERATIONAL MODES....... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 1 9

2. 2=.1 REACTOR P ROTECTI V E INSTRUMENTATION TRIP SETPO INT L IMITS o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 2-4

3. 1-1 MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION FOR ST. LUCIE-2......................,.......... 3/4 1-17

3. 2-1 DELETED ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 2 ll 3~2 2 DNB MARGIN LIMITS....................................... 3/4 2-15 3.3-1 REA TECTIVE INSTRUMENTATION.. 3/4 3-2 ECEFEP 3.3-2 MEHVATK~KSPONSE-~

4.3-1 REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................................ 3/4 3-8 3~ 3 3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.............. .. . .....,............... 3/4 3-12 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUM 0 TRIP VALUES.......... ... 3/4 3-17

<<i~~ V'Ft E 'D 3.3-5 R~ESPONS~M 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS. 3/4 3-22 3.3-6 RADIATION iMONITORING INSTRUMENTATION. 3/4 3-25 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................. ~ ~ 3/4 3-28'.

3-7 SEISMIC MONITORING INSTRUMENTATION....................... 3/4 3-33 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................................. 3/4 3-34 3 '-8 METEOROLOGICAL MONITORING INSTRUMENTATION. 3/4 3-36 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-37 ST. LUCIE-UNIT 2 XXIII Amendment No.

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LIST OF TABLES (Continued) sssssssssssQssssQOQR%$ $ +~R~~~~~~~~~~~g~~~~~g+>+++

TAB~ ~PAG 3.3-9 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION.........,...,, 3/4 3 39 4.3-6 REMOTE SHUTDOWN SYSTEH INSTRUMENTATION SURVEILLANCE REQUIREMENTS................. - . ......... 3/4 3-40 3.3-10 ACC IDENT MONITORING INSTRUMENTATION.................. 3/4 3-42 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE R EQUI E o ~ ~ ~ ~ ~ ~ ~ ~ i ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ + ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3 43 PELE, AD

3. 3-11 M ~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

PSvSYG 3.3-12 SB3-EFFtUENMOtCTORTH~STRUHENTATÃ~~

QGLKTKP 4.3-8 UR"MME~fCN-TORkN~STRUMMt&'NN'UAVH ttANH~gtNKM aSi<E Ch 3 '-13 MONITORING INSTRUM TATION....................................... 3/4 3-54 8 LeSWa ~S 4.3-9 ~O~ITORI~G INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................. 3/4 3 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION........................... 3/4 4-16 4.4-2 STEAM GENERATOR TUBE INSPECTION....................... 3/4 4-17 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES...... 3/4 4-21 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY...................... 3/4 4-23 4 4-3.

~ REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS.......................................... 3/4 4-24 4.4-4 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS P ROGRAMo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 4-27 4.4-5 DELETED 3.4-3 LOW TEMPERATURE RCS OVERPRESSURE PROTECTION RANGE..... 3/4 4-37a.

3.4-4 HINIHUH COLD LEG TEMPERATURE FOR PORV USE FOR LTOP.... 3/4 4-37a 3.6-1 CONTAINMENT LEAKAGE PATHS......'....................... 3/4 6-5 3.6-2 CONTAINMENT ISOLATION VALVES.......................... 3/4 6-21 E

ST. LUCIE - UNIT 2 XXIV Amendment No. 8, 6l,

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~HEX LIST OF TABLES (Continued)

I I I I I 8 g S 0 8 S 0 5 5 S S 8 '5 8 8 5 5 8 S 8 S 5 8 5 S S S 8 5 8 8 5 S 8 5 S 8 5 S 8 8

%&RR&RR'RR It 8 8 5 5 8 g g g g g g g g g g g g g ~ g g g g g TAB ~PAG 3.7-1 MAXIMUM ALLOWABLE LINEAR POWER LEVEL-HIGH TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING OPERA-TION WITH BOTH STEAM GENERATORS........................ 3/4 7-2 4.7-0 STEAM LINE SAFETY VALVES PER LOOP...................... 3/4 7-3 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM...................................... 3/4 7-8

4. 7-2 SNUBBER VISUAL INSPECTION INTERVAL.................... 3/4 7-22 3.7-3a D ELETED ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ o ~ ~ ~ ~ ~ ~ 3/4 7-26 3.7-3b DELET 3/4 7-27

])B.S 8 3.7-4 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

3.7-5 sec ~veo liii-IPIHIIPI IPPHlll!IMIIHlttttt~

4.8-1 DIESEL GENERATOR TEST SCHEDULE........................ 3/4 8-8'ATTERY 4.8-2 SURVEILLANCE REQUIREMENT...................... 3/4 8-12 3.8-1 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPA EVICES........................................ 3/4 8-18 4.1'1-l s wnl

~PHPR NIIHIIIHItt

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P%.lET 0 4.12-1 AfOU5 0 ~ ~ ~ ~ ~ ~ ~ ~

B 3/4.2-1 D ELETED............................................... B 3/4 2-3 B 3/4..4-1 REACTOR VESSEL TOUGHNESS.............................. B 3/4 4-9 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS.................. 5-5 6.2-1 MINIMUM SHIFT CREW COMPOSITION-TWO UNITS WITH TWO SEPARATE CONTROL ROOMS................................ 6-5 ST. LUC IE - UNIT 2 XXV Amendment No. 8-,R-,

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TABLE 3. 3-1 Contfnued ACTION STATEMENTS ACTION 2 - a. fifth the nueber of channels OPERABLE one less than the Total Nusber of Channels, STARTUP and/or POMER OPERATION llay continue provided the fnoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . If the inoperable channel is bypassed, the desirability of maintaining this channel in the bypassed condition shall be reviewed in accordance with Specification 6.5. 1.6e.

The channel shall be returned to OPERABLE status no later than during the next COLD SHUTDONi.

b. fifth the nueber of channels OPERABLE one less than the Nnfam Channels OPERABLE, STARTUP and/or P(SER OPERATION say continue provided the following conditions are satf s fied:

l. Verffy that one of the inoperable channels has been bypassed and place the other inoperable channel fn the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2. All functional units affected by the bypassed/tripped channel shall also be placed fn the bypassed/trfppocL';,

condition.

Nth a channel process masu~nt circuit that affects eultfple functional units inoperable or fn test, bypass or, trip all associated functional units as listed below:

Process Neasu~nt Cfrcuit t Functional Unf Iypassed Safety Channel - Nuclear Instrusehtatfon Mfde Range Rate of Change of Power-Hfgh (RPS)

Linear Range Varfable Power Level-Hfgh (RPS)'.

Local Power Density-High (RPS)

Nargfn/Low Pressure (RPh)

'hersal

2. surfzer Pressure- Pressure -'igh (RPS) 'ressurizer Pressurizer Pressure-Low insert Thecal Nargfn/Low Pressure (RPS)

(ESF

3. Gontafneent Pressure- Contafnoont Pressure - High (RPS)

Contafneent Pressure - High (ESF)

4. Steam Generator Pressure - t aa rator P ssure - Low (RPS)

AFAS-1 and AFAS-2 (AFAS)! gc/gqs . 4404CH!enereto Steam Generator Pressure-Low (ESF) InScrt crea i Low Pressure RPS)

5. Steaa Generator Level teaa G nerator Level - Low (RPS)

Zf SG-2A, then AFAS-1 (AFAS)f Zf SG-2B, then,"-AFAS-2 (AFAS)I ST. LUCIE ' UNIT 2 3/4 3-4 Aeendsant N.~

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TABLE 3. 3-3 Continued TABLE NOTATION (a) Trip function may be bypassed in this MODE when pressurizer pressure is less than 1836 psia; bypass shall be automatically removed when pressurizer pressure is greater than or equal to 1836 psia.

(b) An SIAS signal is first necessary to enable CSAS logic.

(c) Trip function may be bypassed in this MODE below 700 psia; bypass shall be automatically removed at or above 700 psia.

The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 12- With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be ia at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 13- With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . If the inoperable channel is bypassed, the desirability of maintaining this channel in the bypassed condition shall be reviewed in accordance with Specification 6.5. 1.6m. The channel shall be returned to OPERABLE status no later than during the next COLD SHUTDOWN.

With a channel process measurement circuit that affects multiple functional units inoperable or in test, bypass or trip all associated functional units as listed below.

Process Measurement Circuit Functional Unit Bypassed

1. Containment Pressure Containment Pressure - High (SIAS, PGLGTE CIAS, CSAS)

Containment Pressure - High (RPS)

2. teaN Generator Pressure- Steam Generator Pressure - Low MSIS)

>AFAS-1 and AFAS-2 (AFAS

'inter'+ The Ma in/Low Pressure (RPS)

Steam Generator Pressure-Low (RP5)

"" 3. 'Steam Generator Level 44eaa-Gene~o WP5+

4. Pressurizer Pressure Pressurizer Pressure - Hsgh (RPS)

Pressurizer Pressure - Low (SIAS)

Steam Generator Level-Low (RPS) Thermal Margin/Low Pressure (RPS) i If If SG-2A, then AFAS-1 (AFAS)

SG-2B, then AFAS-2 (AFAS)

ST. LUCIE - UNIT 2 3/4 3-15 Amendment llo. P

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TABLE 3. 3-3 Continued TABLE NOTATION ACTION 14 - With the number of channels OPERABL'E one less than the Minimum Channels OPERABLE, STARTUP and/or POWER OPERATION may continue provided the following conditions are satisfied:

a. Verify that one of the inoperable channels has been bypassed and place the other inoperable channel in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b. All functional units affected by the bypassed/tripped channel shall also be placed in the bypassed/tripped condition as listed below.

Process Measurement Circuit Functional Unit Bypassed/Tripped

1. Containment Pressure Containment Pressure - High (SIAS, CIAS, CSAS)

Containment Pressure - High (RPS) pgI ~p 2. Steam Generator Pressure- Steam Generator sressure - Low

~w )

WSIS)

IAFAS-1 and AFAS-2 (AFAS ISteam Generator ressure-Low. (RPS insert al Mar in/Low Pressure (RPS)

Steam Generator Level DELE'.

Steam Generator Level-Low (RPS)

If

'If SG-2A, then AFAS-1 (AFAS)

SG-2B, then AFAS-2 AFAS)

4. Pressui izer Pressure Pressurizer Pressure - High (RPS)

Pressurizer Pressure - Low (SIAS)

Thermal Margin/Lcw Pressure (RPS)

ACTION 15 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channels to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 16 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoperable and take the ACTION required by Specification 3. 7. 1. 5.

ACTION 17- With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or place the inoperable channel in the tripped condition and verify that the Minimum Channels OPERABLE requirement .is demonstrated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4. 3. 2. 1.

ST. LUCIE - UNIT 2 3/4 3-16 Piaendment. NO

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TABLE 3. 3-6 Continued ACTION STATEMENTS ACTION 22 " With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 23- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6. l.

ACTION 24- With the number of channels OPERABLE less than re uired b the Minimum Channels OPERABLE requirement ~m N q m ACTION 25 " With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 26- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.

ACTION 27- With the number of OPERABLE Channels less than requi~ed by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel(s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or:

1) Initiate the preplanned alternate method of monitoring the appropriate parameter(s), and
2) Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of .the inoperability and the plans and schedule for restoring the system to OPERABLE status.
suspend all operations involving movement of fuel within the
'spent fuel storage pool and crane operations with loads over the.
spent fuel storage pool.
ST. LUCIE - UNIT 2 3/4 3-27
4 ~ ~ 4 ~ ~ ~
INSTRUMENTATION INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The incore detection system shall be OPERABLE with:
a. At least 75K of all incore detector locations, and
b. A minimum of two quadrant symmetric incore detector locations per core quadrant.
An OPERABLE incore detector location shall consist of a fuel assembly containing a fixed detector string with a minimum of three OPERABLE rhodium detectors.
APPLICABILITY: When the incore detection system is used for:
a~ Recalibration of the excore axial flux offset detection system,
b. Monitoring the AZIMUTHAL POWER TILT,.
C. Calibration of the power level neutron flux channels, or
d. Monitoring the linear heat rate.
ACTION:
With the incore detection system inoperable, do not use the system for the above applicable monitoring or calibration functions.
b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.3.3.2 The incore detection system shall be demonstrated OPERABLE:
V dc s
'RiS cAbQ4<< By performance of a CHANNEL CHECK within prior to its use WQfQloost 7 and eb-'~-once-p~~)aye-4hesea44ee when required for: .
C%qoeg60 t CA ue- 1. Recalibration of the excore axial flux offset detection system,
.gLI.Iq, (u/uI)u)
2. Monitoring the linear heat rate pursuant to Specification 4.2.1.
ST. LUCIE - UNIT 2 3/4 3"30 Amendment No.+4
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TABLE 4.3-7 I
ACCIDENT HONITORING INSTRUHENTATION SURVEILLANCE RE UIREHENTS n
M m
CHANNEL CHANNEL INSTRUHENT CHECK CALIBRAT ION C:
M
1. Containment Pressure H
2. Reactor Coolant Outlet Teeperature - TH (Narrow Range)
Hott H
3. Reactor Coolant Inlet Teaperature -TC ld (Wide Range)
Cold H
4. Reacto~ Coolant Pressure - Wide Range N
5. Pressurizer Water Level N
6. Steaa Generator Pr essure N R
7. Steaa Generator Water Level - Narrow Range H R
8. Steam Generator Water Level - Wide Range N R 4J
9. Refueling Water Storage Tank Water Level N iI I
D 4l
10. Auxiliary Feedwater Flow Rate (Each puap) N R Reactor Coolant Systea Subcooling Hargin Monitor H R PORV Position/Flow Indicator H R
13. PORV Block Valve Position Indicator N R ID
14. Safety Valve Position/FLow Indicator H R CL Containment Sump Water Level (Narrow Range) H R-9
16. Containment Water Level (Wide Range) H R t+
17. Incore Thereocouples H R O
18. Reactor Vessel Level Honitorinq System H R 15.
P<
w,L S t)
~Pages 3/4 3-45 through 3/4 3-46 (Amendment No. 55) have from the Technical Specifications. been'eleted ST. LUCIE - UNIT 2 3/4 3-44 Amendment No.P5
4 / e l"'
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IPages 3/4 3-49 through 3/4 3-52 {Amendment No. 61) have been
'deleted from the Technical Specifications.
ST. LUCIE - UNIT 2 3/4 3-48 AMENDMENT NO. 7g,
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TABLE 3.3-13 EXPLOSIVE GAS MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION
1. WASTE GAS DECAY TANKS EXPLOSIVE GAS HONITORING SYSTEH
a. Oxygen Monitors 35 TABLE NOTATION
During waste gas system operation.
ACTION 35 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of this system may continue for up to 30 days provided samples of Oa are analyzed by the lab gas partitioner at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
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TABLE 4.3-9 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVE LLA CE E UIREMENTS CHANNEL MODES IN WHICH I
n C
Pl ~ST LUMEN CHANNEL
~CECK SOURCE CHECK CHANNEL
~CIKEA IC FUNCTIONAL EEEE ~K SURVEILLANCE
1. WASTE GAS DECAY TANKS EXPLOSIVE GAS HONITORING SYSTEM
a. Oxygen Honitor PANES
b. Oxygen Monitor (alternate) D g(1) H Ae 4<s ul~y gal final 8/4 3-5$ (jbe< k) ABLE NOTATION
During waste gas holdup system operation.
(1) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
1. One volume percent oxygen, balance nitrogen, and
2. Four. volume percent oxygen, balance nitrogen.
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During waste gas sys oper ation.
ACTION 35 With th th mber of channels nimum Channels system may continue OPERABLE for up to req 'nt, P RABLE one 30 days p less than required by operation of this ed samples of Oz are analyzed by the lab gas partitioner at le ce per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
~~c~g ~g<~ ipfag,y,~<<oA To 8!6'K 5/Q 5 5f-Ace sA s-s+.
Pages 3/4 3-57 through 3/4 3-59 (Amendment No. 61) have been deleted from the Technical Specifications.
p,cp v6a ~656HZ ST. LUCIE - UNIT 2 3/4 3-56 Amendment No.
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TABLE 4.3-9 EXPLOSIVE GAS MONITORING INSTRUMENTATION SUR f LLA CE E UI RE TS CH N MODES IN MHICH
~ST ACUMEN CHANNEL CHECK SOURCE JC CCK CHANNEL i iiiiili ~iTCT IONAL SURVEILLANCE
1. MASTE GAS DECAY TANKS E P OSIVE GAS MONITORING SYST
a. Oxygen Mo or Q(1)
b. gen Monitor (alternate) Q(I)
~~sp~ ~~n igfo~waiiaN 'To PACK 5/+ 3-f5 gg sg m eS E'NAS<C ++< 3/+ 8-5<.
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TABLE NOTATION
Our> waste gas holdup system operation.
(I) The CHAN L CALIBRATION shall include the use f standard gas samples.
contain g a nominal:
1. ne volume percent oxygen, balance nitrogen, d Four volume percent oxygen, balance nitrogen.
i~SfCg. QiS tg&RNA'Tied Co P<E, 3/R g-g5's s~al oQ QoPbsco %4.s 5/p 3-55,
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Pages 3/4 11-2 through 3/4 11-13 (Amendment No. 61) have been deleted from the Technical Specifications.
ST. LUCIE - UNIT 2 3/4 11-1 AMENOMENT NO.
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CORE COOLING SYSTEMS
~ goDE
<e 5 ~Hh /CD NoÃ 6
~~~~<~ <<"~~3 'MERGENCY BASES ECCS SUBSYSTEMS Continued
, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling require-ments.
The trisodium phosphate dodecahydrate (TSP) stored in dissolving baskets located in the containment basement is provided to minimize the possibility of corrosion cracking of certain metal components during operation of the ECCS following a LOCA. The TSP provided this protection by dissolving in the sump water and causing its final pH to be raised to greater than or equal to 7.0.
The requirement for one high pressure safety injection pump to be rendered inoperable prior to entering MODE 5, although the analysis supports actuation of safety injection in a water solid RCS with pressurizer heaters energized.
provides additional administrative assurance that a mass addition pressure transient can be relieved by the operation of a single PORV or SDCRV.
The Surveillance Requirements provided to ensure OPERABILITY of each component ensure that at a minimum, the assumptions used in the accident analyses are met and that subsystem OPERABILITY is maintained. Surveillance Requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the'piping system to each injection point is necessary to: (1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration, (2) p~ovide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses. The requirement to dissolve a representative sample of TSP in a sample of RWT water provides ass@rance that the stored TSP will dissolve in borated water at the postulated post-LOOA temperatures.
3 4.5.4 REFUELING WATER TANK The OPERABILITY of the Refueling Water Tank (RWT) as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA. The limits on RWT minimum volume and boron concentration ensure that (1) sufficient water is available within contaizment to permit recirculation cooling flow to the core, and (2) the reactor will remain subcritical in the cold condition following mixing of the RWT and the RCS water volumes with all control rods inserted except for the most reactive control. assembly. These assumptions are consistent with the LOCA analyses.
ST. LUCIE - UNIT 2 B 3/4 5-2 Amendment No.
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3 4.11 RADIOACTIVE EFFLUENTS BASES Pages B 3/4 11-2 through B 3/4 11-3 (Amendment No. 61) have been deleted from the Technical Specifications.
ST. LUCIE UNIT 2 B 3/4 11-1 Amendment Ne+
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ML17228A891

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