St'. Lucie Unit 1 and Unit 2Docket Nos. 50-335 and 50-389Proposed License AmendmentsRelocation of LCO for Incore Detectorsto t e U date Fina Safet Anal sis Re ort

ATTACHMENT 3

ST. LUCIE UNIT 1 MARKED-UP TECHNICAL SPECIFICATION PAGES

Page IV

Page 3/4 2-2

Page 3/4 3-25

Page 3/4 3-26

Page 3/4,10-2

Page 3/4 10-5

Page B 3/4 2-1

Page B 3/4 3-2

950i3i0198 950i20PDR ADOCK 05000335P PDR

J

"i'».~

INDEX

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREHENTS

SECTION

3 4.2 POWER DISTRIBUTION LIMITS

3/4.2. 1 LINEAR HEAT RATE............................3/4.2.2 DELETED

PAGE

....... 3/4 2-13/4 2-6

3/4.2.3

3/4.2.4

3/4.2.5

TOTAL INTEGRATED RADIAL PEAKING FACTOR — FT.l

AZIMUTHAL POWER TILT - T ...................q

DNB PARAHETERS..................-..-. ~ ~ ~ ~ ~ ~ ~

....... 3/4 2-9

....... 3/4 2-113/4 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 SYSTEMINSTRUMENTATION.... ........ . . . ............... 3/4 3-9

3/4.3.3 MONITORING INSTRUMENTATION.......................... 3/4 3-21

Radiation Monitoring. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3 21

'THIS CRr,um I'KVIOOSI.VRGQQE'4tf.P By 'FPI

L+r. L-9II-IOI (S/Xllgy)

'Q IS CHA46t QCVu>V5LYR~6s~BP ey PPLLw. L 99-Jf8 (lo/x7I'B) Accident Monitoring Instrumentation .. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3 41

4 4m I~eIrsen4

Meteorological Instrumentation..;.................. 3/4 3-30

Remote Shutdown Instrumentation.................... 3/4 3-33

e4ec4on-kns4wmerkatkn.....................

Explosive Gas Monitoring Instrumentation........... 3/4 3-50

3 4.4 REACTOR COOLANT SYSTEM

3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION...... 3/4 4-1

3/4.4.2 SAFETY VALVES — SHUTDOWN. . . . ............... 3/4 4-23/4.4.3 SAFETY VALVES — OPERATING.......................... 3/4 4-3

ST. LUCIE — UNIT 1 IV

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POWER DISTRIBUTION LIMITS

SURVEILLANCE RE UIREMENTS (Continued

C. Verifying that the AXIAL SHAPE INDEX is maintained within theallowable limits of Figure 3.2-2, where 100 percent of maximumallowable power represents the maximum THERMAL POWER allowed bythe following expression:

MxN

where:

2.

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

N is the maximum allowable fraction of RATED THERMAL POWERas determined by the F curve of Figure 3.2-3.T

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 verifyingthat the incore detector Local Power Density alarms:

a ~

b.

Are adjusted to satis'fy the requirements of the core powerdistribution map which shall be updated at least once per31 days of accumulated operation in MODE 1.

C

Have their alarm setpoint adjusted to less than or equal tothe limits shown on Figure 3.2-l.ghee-4he-AA4ew+o

props-hH-:&y~ehtde~~>8 setting o f thes rms:

ent-ca c nal uncertainty factor of 1.07,

An en i ee ng uncertainty factor oERNL-PBWER-menu emend-unceN

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NSTRUMENTATI ON

IN RE DETECTORS

LIMIT G CONDITION FOR OPERATION

3.3.3.2 e incore detection system shall be OPERABLE with:

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

b. A mini m of two quadrant symmetric incore detector ocations percore qua rant.

An OPERABLE incore tector location shall consist of a uel assembly contain-ing a fixed detector tring with a minimum of three OP ABLE rhodium detectors.

APPLICABILITY: When the incore detection system is used for:

a. Recalibration of t excore axial flux ffset detection s'stem,b. Monitoring the AZIMUT L POWER TILT,

c. Calibration of the power evel n tron flux channels, or

d. Monitoring the linear heat

ACTION:

>th the incore detection system noperabl do not use the system for theabove applicable monitoring or alibration nctions. The provisions ofSpecifications 3.0.3 and 3.0. are not applica le.

SURVEILLANCE RE UIREMENTS

4.3.3.2 The incore d tection system shall be demonstr ted OPERABLE:7

ckv'.

By performance of a CHANNEL CHECK wit tf 6 prior to, itsse~ ee-pe~ er-ea44er when quired for:c tu e fketNNIi~~

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NSiRUMENTATION

SURV LANCE RE UIREMENTS Continued

b.

3. Monitoring the AZIMUTHAL POWER TILT, or

4. Calibration of the Power Level Neutron Flux annels.

At leas once per 18 months by performance of CHANNEL CALI-BRATION o eration which exempts the neutron d tectors but in-cludes all lectronic components. The neut n detectors shallbe calibrat d prior to installation in th reactor core.

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SP C A T T X [ONS

'GR UP H GHT N RT N AN POW R TR UT N M T

LIMITING CONDITION FOR OPERATIONa a a a a a a a a a a a a a a a a a a a a a a a a a a a 'a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a aaaaaaaaaaa

3.10.2 The group height, insertion.and power distribution limits ofSpecifications 3. l. 1.4, 3. 1.3. 1, 3.1.3-2, 3.1.3.5, 3.1.3.6, 3.2.3,and 3.2.4 may be suspended during the performance of PHYSICS TESTSprovided:

a. The THERMAL POWER is restricted to the test power plateauwhich shall not exceed 85X of RATED THERMAL POWER, and

— b. The limits of Specification 3.2.1 are maintained and deter-mined as specified in Specification 4.10.2.2 below.

~LCABI I: IIOOEB I C 2.ACTION:

With any of the limits of Specification 3.2.1 being exceeded while therequirements of Specifications 3. 1.1.4, 3.1.3.1, 3.1.3.2, 3.1.3.5,3.1.3.6, 3.2.3 and 3.2.4 are suspended, either:

a. Reduce THERMAL POWER sufficiently to satisfy the requirementsof Specification 3.2.1, or

b. Be in HOT STANDBY within 6 hours.

SURVEILLANCE REQUIREMENTSaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaa

4. 10.2. 1 The THERMAL POWER shall be determined at least once per hourduring PHYSICS TESTS in which the requirements of Specifications 3.1.1.4„3. 1.3. 1, 3. 1.3.5, 3. 1.3.6, 3.2.3 or 3.2.4 are suspended and shall beverified to be within the test power plateau. ~ >

4.10.2.2 The linear heat rate shall be determined to be within thelimits of Specification 3.2.1 by monitoring it continuously with theIncore Detect Mo itor S te ursuant to the requirements ofpec cat n during PHYSICS TESTS above 5X of

RATED THERMAL POWER n which the requirements of Specifications 3.1.1.4,3. 1.3.1, 3.1.3.5, 3.1.3.6, 3.2.3 or 3.2.4 are suspended.

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ST. LUCIE - UNIT 1 3/4 10-2 Amnndmnnt Nn. ~IO9+

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SPECIAL TEST EXCEPTIONS

CENTER CEA MISALIGNMENT

LIMITING CONDITION FOR OPERATION

3.10.5 The requirements of Specifications 3.1.3.1 and 3.1.3.6 may besuspended during the performance of PHYSICS TESTS to determine theisothermal temperature coefficient and power coefficient provided:

'a ~

b.

Only the center CEA (CEA 81) is misaligned, and

The limits of Specification 3.2.1 are maintained and determinedas specified in Specification 4.10.5.2 below.

APPLICABILITY: MOOES 1 and 2.

ACTION:

With any of the limits of Specification 3.2.1 being exceeded while therequirements of Specifications 3.1.3.1 and 3.1.3.6 are suspended, either:

a. Reduce THERMAL POWER sufficiently to satisfy the requirementsof Specification 3.2.1, or

b. Be in HOT STANOBY within 6 hours.

SURVEILLANCE RE UIREMENTS

4.10.5.1 The THERMAL POWER shall be determined at least once per hourduring PHYSICS TESTS in which the requirements of Specifications. 3.1.3.1and/or 3.1.3.6 are suspended and shall be verified to be within the testpower plateau.

4.10.5.:2 The linear heat rate shall be determined to be within thelimits of Specification 3.2.1 by monitoring it continuously with the,.

ete tor o i o in S stem pursuant to the requirements ofSpecification during PHYSICS TESTS above 5X, ofRATED THERMAL POWER in which t e requirements of Specifications 3.1.3.1and/or 3.1.3.6 are suspended.

CAcg

ST. LUCIE - UNIT 1 3/4 10-5

~~~~~~v~~ -. ~E=~g~~

3/4,2 POWER DISTRIBUTION LIMITS

BASES

3/4.2.1 LINEAR HEAT RATE

The limitation on linear heat rate ensures that in the event of a LOCA,the peak temperature of the fuel cladding will not exceed 2200'F..

Either of the two core power distribution monitoring systems, the ExcoreDetector Monitoring System and the Incore Detector Monitoring System, providesadequate monitoring of the core power distribution and is capable of verifyingthat the linear heat rate does not exceed its limits . The Excore DetectorMonitoring System performs this function by continuously monitoring the AXIALSHAPE INDEX with the OPERABLE quadrant symmetric excore neutron flux detectorsand verifying that the AXIAL SHAPE INDEX is maintained within the allowablelimits of Figure 3.2-2. In conjunction with the use of the excore monitoringsystem and in establishing the AXIAL SHAPE INDEX limits, the following assump-tions are made: 1) the CEA insertion limits of Specifications 3.1.3.5 and3.1.3.6 are satisfied, 2) the AZIMUTHAL POWER TILT restrictions of Specifica-tion 3.2.4 are satisfied, and 3) the TOTAL INTEGRATED RADIAL PEAKING FACTOR doesnot exceed the limits of Specification 3.2.3.

The Incore Detector Monitoring System continuously provides a directmeasure of the peaking factors and the alarms which have been established forthe individual incore detector segments ensure that the peak linear heat rateswill be maintained within the al lowable limits of Figure 3.2-1. The setpointsfor these alarms include allowances, set in the conse vative directions, for1) a measurement-calculational uncertainty facto 2) an engineeringuncertainty factor , 3) a THERMAL POWE measurement uncertainty facto~

M'EL.C-F3/4.2.3 and 3/4.2.4 TOTAL INTEGRATED RADIAL PEAKING FACTOR - F ANDrAZIMUTHAL POWER TILT - T

The limitations on F, and T are provided to ensure that the assump-r qtions used in the analysis for establishing the Linear Heat Rate andLocal Power Density-High LCOs and LSSS setpoints and

ST. LUCIE - UNIT 1 8 3/4 2-1 Amendment No. )7j,g,(r),ljf, 1d gl 9.

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INSTRUMENTATION

BASES

RADIATIONl t10NITORING INSTRUMENTATION (Continued)

by the individual channels; and (2) the alarm or automatic action is initiatedwhen the radiation level trip setpoint is exceeded; and (3) sufficient infor-mation is available on .selected plant parameters to monitor and assess thesevariables following an accident. This capability is consistent with themcommendations of Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During andFollowing an Accident," December 1980 and NUREG-0737, "Clarification of THIAction Plan Requirements," November 1980.

gqf~cs 'DfLEYEP

ERABILITY of thecomplement of equipment ensures that the me awned from use ofthis system accuratel e spatial neutron flux 'on of the3/4.3.3.3

OPERABIL TY of the seismi u lclentayabi ity is av ilable to promptly determine e magnit de of a eismic

event nd evalu e the re ponse of hose featu es impor nt to s ety. T iscapab lity is r quired t permit mparison o the mea red res nse to hat

sed inmls cAAOE Itsgu6~ 5v

3 4.3.3. 4 tlETEOROLOG ICAL INSTRUMENTATION fthm.m. t.-qq-ioi (g/zs(q~)

The OPCRABILITY of the meteorological instrumentation ensures thatsufficient meteorological data is available for estimating potential radiationdoses to the public as a result of routine or accidental release of radio-active materials.to the atmosphere. This capability is required to evaluatethe need for initiating protective measures to protect the health and safetyof the public and is consistent with the recommendations of Regulatory Guide1.23, "Onsite Meteorological Programs," February 1972.

3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION

The OPERABILITY of the remote shutdown instrumentation ensures that "sufficient capability is available to permit shutdown and maintenance of HOTSHUTDOWN of the facility from locations outside of the control room. Thiscapability is required in the event control room habitability is lost and isconsistent with General Design Criteria 19 of 10 CFP. 50.

ST. LUCIE - UNIT 1 B 3/4 3-2 Amendment No.

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St. Lucie Unit 1 and Unit 2Docket Nos. 50-335 and 50-389Proposed License AmendmentsRelocation of LCO for Incore Detectorsto t e U ated Final Safet Anal sis Re ort

ATTACHMENT 4

ST. LUCIE UNIT 2 MMRKED-UP TECHNICAL SPECIFICATION PAGES

Page V

Page 3/4 2-2

Page 3/4 3-30

Page 3/4 3-31

Page 3/4 10-2

Page 3/4 10-4

Page 3/4 10-5

Page B 3/4 2-1

Page B 3/4 3-2

INDEX

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS

SECTION

3 4.2 POWER DISTRIBUTION LIMITS

PAGE

3/4.2.13/4.2.23/4.2.33/4.2.43/4.2.5

LINEAR HEAT RATE.................................TOTAL PLANAR RADIAL PEAKING FACTOR — F„„..............TOTAL INTEGRATED RADIAL PEAKING FACTOR — F o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

AZIMUTHAL POWER TILT .......DNB PARAMETERS........................-..........-....

3/4 2-1

3/4 2-7

3/4 2-9

3/4 2-13

3/4 2-14

3 4. 3 INSTRUMENTATION

3/4.3.13/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM

INSTRUMENTATION................................. 3/4 3-1'1

REACTOR PROTECTIVE INSTRUMENTATION.................... 3/4 3-1

3/4.3. 3 MONITORING INSTRUMENTATIONRADIATION MONITORING INSTRUMENTATION.................. 3/4 3-24

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PGWER 'DISTRIBUTION LIMITS

SURVEILLANCE RE UIREMENTS Continued

C. Verifying that the AXIAL SHAPE INDEX is maintained within theallowable limits of Figure 3.2-2, where 100K of maximum allowablepower represents the maximum THERMAL POWER allowed by thefollowing expression:

MxN

where

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

'

2. N is the maximum allowable fraction of RATED THERMAL POWER asdetermined by the F„ curve of Figure 3.2-3.

4.2. 1.4 Incore Detector Monitorin S stem - The incore detector monitoringsystem may be used for monstorsng the core power distribution by verifyingthat the incore detector Local Power Density alarms:

~ a. Are adjusted to satisfy the requirements of the core power'distribution map which shall be updated at least once per 3l days ofaccumulated operation in MODE l.

b. Have their alarm setpoint adjusted to less than or equal to thelimits shown on Figure 3.2-l.ghee-@he-fo44e~g-4a

pe%;~y-iwcMded-H~Q setting of these alarms:

1-. A meas em nt-calculational uncertainty f r of 1.062,An engineering uncerta-' fa of 1.03,

A linear heat rat cer inty fa of 1.01 due to axial,u densif on a hermal expansio , d

RMAL POWER measurement uncertainty factor of 1.

If incore system becomes inoperable, reduce power to M x N within 4 hours andmonitor linear heat rate in accordance with Specification 4.2.1.3.

ST. LUCIE " UNIT 2 3/4 2"2 Amendment No. P7

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IASRUIMENTATION

SURVEILLANCE IREHENTS Continued)

3. Monitoring the THAL POMER .L-, or

4. Calibration of the Powe Le Neutron Flux Channels.

b. At least once p~e~18 months by performance a CHANNEL CALIBRATIONoperations i

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SPECIAL TEST EXCEPTIONS

3/4. 10. 2 MODERATOR TEMPERATURE COEFFICIENT GROUP HEIGHT INSERTION ANDPOWER DISTRIBUTION LIMITS

~ LIMITING CONDITION FOR OPERATION

3. 70.2 The moderator temperature coefficient, group height, insertion andpower distribution limits of Specifications 3. 1. 1.4, 3. 1. 3. 1, 3. 1. 3. 5,3. 1. 3. 6, 3. 2. 2, 3. 2. 3 and 3. 2. 4 may be suspended during the performance ofPHYSICS TESTS provided:

a.

b.

The THERMAL POWER is restricted to the test power plateauwhich shall not exceed 85K of RATED THERMAL POWER, andThe limits of Specification 3. 2. 1 are maintained and determined asspecified in Specification 4. 10.2.2 below.

APPLICABILITY: MODES 1 and 2.

ACTION:

With any of the limits of Specification 3.2.1 being exceeded while therequirements of Specifications 3.1.1.4, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3 ~ 2.2,3.2.3 and 3 '.4 are suspended, either:

a. Reduce THERMAL POWER sufficiently to satisfy the requirementsof Specification 3.2. 1, or

b. Be in HOT STANDBY within 6 hours.

SURVEILLANCE RE UIREMENTS

4. 10.2. 1 The THERMAL POWER shall be determined at least once per hour duringPHYSICS TESTS in which the requirements of Specifications 3. l. 1.4, 3. 1.3. 1,3. 1. 3. 5, 3. l. 3. 6, 3. 2. 2, 3. 2. 3, or 3. 2. 4 are suspended and shall be verifiedto be within the test power plateau.

4. 10.2.2 The linear heat rate shall be determined to be within the limits ofSpecification 3.2. 1 by monitoring it continuously with the Incore DetectorMonitoring System pursuant to the requirements of Specificatio 4.2. 1.4

during PHYSICS TESTS above 5X of RATED THERMAL POWER in w ic erequirements of Specifications 3. 1. 1. 4, 3. 1. 3. 1, 3. 1. 3. 5, 3. 1. 3. 6, 3. 2. 2,3. 2. 3, or 3. 2. 4 are suspended. Qg

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ST. LUCIE - UNIT 2 3/4 XO-2

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SPECIAL TEST EXCEPTIONS

3/4.10.4 CENTER CEA MISALIGNMENT

LIMITING CONDITION FOR OPERATION

3.10.4 The requirements of Specifications 3.1.3.1 and 3.1.3.6 may besuspended during the performance of PHYSICS TESTS to determine the isothermaltemperature coefficient, moderator temperature coefficient and powercoefficient provided:

a. Only the center CEA (CEA Pl) is misaligned, and

b. The limits of Specification 3.2. 1 are maintained and determinedas specified in Specification 4. 10.4.2 below.

APPLICABILITY: MODES 1 and 2.

ACTION:

With any of the limits of Specification 3.2.1 being exceeded while therequirements of Specifications 3.1.3.1 and 3.1.3.6 are suspended, either:

a. Reduce THERMAL POWER sufficiently to satisfy the requirementsof Specification 3. 2. 1, or

b. Be in HOT STANDBY within 6 hours.

SURVEILLANCE RE UIREMENTS

4. 10.4. 1 The THERMAL POWER shall be determined at least once per hour duringPHYSICS TESTS in which the requirements of Specifications 3. 1.3. 1 and/or'.

1.3.6 are suspended and shall be verified to be within the test powerplateau.

4. 10.4.2 The linear heat rate shall be determined to be within the limits ofSpecification 3.2. 1 by monitoring it continuously with the Incore DetectorMonitoring System pursuant to the requirements of Specificationduring PHYSICS TESTS above 5X of RATED THERMAL POWER in which the requirementsof Specifications 3. l. 3. 1 and/or 3.1.3. 6 are suspended.

ST. LUCIE - UNIT 2 3/4 10-4

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SPECIAL TEST EXCEPTIONS

3/4.10.5 CEA INSERTION DURING ITC MTC AND POWER COEFFICIENT MEASUREMENTS

LIMITING CONDITION FOR OPERATION

3. l.0.5 The requirements of Specifications 3. 1.3. 1 and 3. 1.3.6 may besuspended during the performance of PHYSICS TESTS to determine the isothermaltemperature coefficient, moderator temperature coefficient, and powercoefficient provided the limits of Specification 3.2. 1 are maintained anddetermined as specified in Specification 4. 10.5. 2 below.

APPLICABILITY: MODES 1 and 2.

ACTION:

With any of the limits of Specification 3.2.1 being exceeded while therequirements. of Specifications 3. 1.3. 1 and 3. 1.3.6 are suspended, either:

a. Reduce THERMAL POWER sufficiently to satisfy the requirements ofSpecification 3.2. 1, or

b. Be in HOT STANDBY within 6 hours.

SURVEILLANCE RE UIREMENTS

4. 10.5. 1 The THERMAL POWER shall be determined at least once per hour duringPHYSICS TESTS in which the requirements of Specifications 3. 1.3. 1 and 3. 1.3.6are suspended and shall be verified to be within the test power plateau.

4. 10.5.2 The linear heat rate shall be determined to be within the limits ofSpecification 3.2. 1 by monitoring it continuously with the Incore De ectorMonitoring System pursuant to the requirements of Specificatio . . . duringPHYSICS TESTS above SX of RATED THERMAL POWER in which the requirements oSpecifications 3. l. 3. 1 and 3. l. 3. 6 are suspended.

ST. LUCIE " UNIT 2 3/4 10-5

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BASES

3 4.2.1 LINEAR HEAT RATE

The limitation on linear heat rate ensures that in the event of a LOCA,the peak temperature of the fuel cladding will not exceed 2200'F.

Either of the two core power distribution monitoring systems, the ExcoreDetector Monitoring System and the Incore Detector Monitoring System, providesadequate monitoring of the core power distribution and are capable of verifyingthat the linear heat rate does not exceed its limits. The Excore DetectorMonitoring System performs this function by continuously monitoring the AXIALSHAPE INDEX with the OPERABLE quadrant syometric excore neutron flux detectorsand verifying that the-AXIAL SHAPE INDEX is maintained within the allowablelimits of Figure 3.2-2. In conjunction with the use of the excore monitoringsystem and in establishing the AXIAL SHAPE INDEX limits, the followingassumptions are made: (1) the CEA insertion limits of Specifications 3.'l.3.5and 3.1.3e6 are satisfied, (2) the AZIMUTHAL POWER TILT restrictions ofSoecification 3.2.4 are satisfied. and (3) the TOTAL PLANAR RADIAL PEAKINGFACTOR does not exceed the limits of Soecification 3.2.2.

The Incore Detector Monitoring System continuously provides a directmeasure of the peaking factors and the alarms which have been established forthe individual incore detector segments ensure that. the peak linear heat rateswill be maintained within the allowable limits of Figure 3.2-1. The setpointsfor these alarms include allowances, set in the conservative directions, for(1) a measurement-calculational'ncertainty factor , (2) an engineeringuncer'tainty'factor (3) an allowanc for axial fuel densificatioand thermai expansion, and (A) a THERMAL OW R measu ament uncertainty factor

5)ELF- CS3/4.2.2, 3 4.2.3 and 3 4.2.4 TOTAL PLANAR AND INTEGRATED RADIAL PEAKING

FACTORS - F„and Fr AND AZIMUTHAL POWER TILT - T

The limitations on F„ and T are provided to ensure that the assumptionsxyused in the analysis for establishing the Linear Heat Rate and Local PowerDensity - High LCOs and LSSS setpoints remain valid during operation at thevarious allowable CEA group insertion limits. The limitations o'n F and Tr qare provided to ensure that the assumptions used in the analysis establishingthe DNB Margin L'CO, the Thermal Margin/Low Pressure LSSS setpoints'remainvalid during operation at the various allowable CEA group insertion limits.If Fx , F„ or T exceed their basic limitations, operation may continue underthe additional restrictions imposed by the ACTION statements since theseadditional restrictions provide adequate provisions to assure that the

ST. LUCIE - UNIT 2 8 3/4 2-1 Amendment No.

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" rNS7RUMENTATION

BASES

individual channels; and (2) the alarm or automatic action is initiated whenthe radiation level trip setpoint is exceeded; and (3) sufficient informationis available on selected plant parameters to monitor and assess these variablesfollowing an accident.. This capability is consistent with the recommendationsof Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled NuclearPower Plants to Assess Plant and Fnvirons Conditions During and Following anAccident," December 1980 and NUREG-0737, "Clarification of TMI Action PlanRequirements," November 1980.

3/4. 3. 3. 2 QQRE ETEABILITY o

complement of equipment ensures thatthis system accuratel

casu rom use ofa sal neutron ribution of the

3/4. 3. 3. 3 ttMERABI ITY of th seisms nst

pabi ity is a ailable to promptly etermine the magnit Ue of a eismic evennd ev luate t e response of those eatures i portant to safety. Thisapab lity is equired t permit c mparison f the meas red res nse t tha

used- in the d sign basis for the f ci lity t determine if plant shutdg n isequ red pur uant to Ap endix A o 10 CFR P rt 100. T e instr mentation ion istent ith the re ommendat'

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3/4. 3. 3. 4. METEOROLOGICAL INSTRUMENTATIONThe OPERABILITY of the meteorological instrumentation ensures that

sufficient meteorological data are available for estimating potentialradiation doses to the public as a result of routine or accidental release ofradioactive materials to the atmosphere. This capability is required toevaluate the need for initiating protective measures to protect the health andsafety of the public.

3/4.3.3.5 REMOTE SHUTDOWN SYSTEM INSTRUMENTATIONThe OPERABILITY of the remote shutdown system instrumentation ensures

that sufficient capability is available to permit shutdown and maintenance ofHOT STANDBY of'the facility from locations outside of the control room. Thiscapability is required in the event control room habitability is lost and isconsistent with General Design Criterion 19 of 10 CFR Part 50.

The OPERABILITY of the remote shutdown system instrumentation ensuresthat a fire will not preclude achieving safe shutdown. The remote shutdown .system instrumentation, control circuits, and transfer switches are independentof areas where a fire could damage systems normally used to shut down thereactor. This capability is'consistent with General Design. Criterion 3 andAppendix R to 10 CFR Part 50.

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