ML17228B504: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(6 intermediate revisions by the same user not shown)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:St.LucieUnit1DocketNo.50-335ProposedExigentLicenseAmendmentThermalMarinandRCSFlowLimitsATTACHMENT4ST~LUCIEUNIT1MARKED-UPTECHNICALSPECIFICATIONPAGESPage2-1Page2-2RevisedFigure2.1-1Page2-4Page3/42-14Page5-5'606030192960601II'PDaADOCV05000SS5,'PDRii 2.0SAFETYLIMITSANDLIMITINGSAFETYSYSTEMSETTINGS2.1SAFETYLIMITSREACTORCORE'l])g,pre05+ZYl<~2.1.1ThecombinationofTHERMALPOWE,pressurizerpressure,andmaxi-mumcoldlegcoolanttemperatureshallnotexceedthelimitsshownonFigure2.1-1.APPLICABILITY:MODES1and2.ACTION:Wheneverthepointdefinedbythecombinationofmaximumcoldlegtemper-atureandTHERMALPOWERhasexceededtheappropriatepressurizerpressureline,beinHOTSTANDBYwithin1hour.I1REACTORCOOLANTSYSTEMPRESSURE2.1.2TheReactorCoolantSystempressureshallnotexceed2750psia.APPLICABILITY:MODES1,2,3,4and5.ACTION:MODES1and2WhenevertheReactorCoolantSystempressure'hasexceeded2750psia,beinHOTSTANDBYwiththeReactorCoolantSystempressurewithinitslimitwithin1hour.MODES3,4and5WhenevertheReactorCoolantSystempressurehasexceeded2750psia;reducetheReactorCoolantSystempressureto'ithinitslimitwithin5minutes."ForCycle14operationbeyond7000EFPH,THERMALPOWERshallnotexceed90%of,~2700Megawatts(thermal).ST.LUCIE-UNIT12-1 J~~laJfolI$a~>g}~W~p110~ClIv-<~F>JNJJ4gpJJ/o2%~g~l 0.K4J580560510520500UNACCEPTABLEOPERATIONREACTOROPERATIONLIMITTOLESSTHAN580'FBYACTUATION0HEMAINSTEAMLINESAFETYVALVEVESSELFLOWLESSMEASUREMENTUNCERTAINTIES-355.000GPLlLIMITSCONTAINNOALLOWANCEFORINSTRUMENTERRORORFLUCTUATIOBASEDONTHEAXIALSHAPEFIGUREB2.1-1UNACCEPTABOPERATIONIIIIIII480460PRESSUREIIA1750200022252400ACCEPTABLEOPERATIONId~gagsD~yg0.20.40.60.8$.2FRACTIONOFRATEDTHERMALPOWERL6FIGURE2.1-1REACTORCORETHERMALMARGINSAFETYLIMIT-,FOURREACTORCOOLINGPUMPSOPERATING
{{#Wiki_filter:St. Lucie Unit  1 Docket No. 50-335 Proposed Exigent License Amendment Thermal Mar in and RCS Flow Limits ATTACHMENT 4 ST ~ LUCIE UNIT 1 MARKED-UP TECHNICAL SPECIFICATION PAGES Page  2-1 Page  2-2 Revised Figure 2.1-1 Page  2-4 Page  3/4 2-14 Page  5-5
)//~I~/rl~'s1C~cq<~~~>L'Qhr>>g'taheMQ'A~JJ.yJ~~~J 600575550525UNACCEPTABLEOPERATIONREACTOROPERATIONLIMITEDTOLESSTHAN580DegFBYACI'UATIONOFTHEMAINSMAllLINESAFETYVALVESVESSELFLOWLESSifEASUREIKNTUNCERTAINTIES-046,000GPMILIMITSCONTAINNOALLOWANCEFORINSTRUMENTERRORORFLUCTUATIONSqrQUNACCEPFABLEOPERATIO'sg/~I'.I0Ia0O500BASEDONTHEAXIALSHAPEONFIGUREB2.1-1PRESSUREINPSIAgg,''~pf4754501750200022252400ACCEPTABLEOPERATION0.40.6O.Si.1.2FractionofRatedThermalPox'er1.6 TABLE2.2-1REACTORPROTECTIVEINSTRUMENTATIONTRIPSETPOINTLIMITSInmFUNCTIONALUNIT1.ManualReactorTrip2.PowerLevel-High(1)FourReactorCoolantPumpsOperatingTRIPSETPOINTNotApplicable<9.61K,aboveTHERMALPOWER,withaminimumsetpointof155ofRATEDTHERMALPOWER,andamaximumof<107.05ofRATEDTHERMALPOWER.ALLOWABLEVALUESNotApplicable<9.61KaboveTHERMALPOWER,~daminimumsetpointof15KofMiTEDTHERMALPOWERandamaximumof<107.0XofRATEDTHERMALPOWER.3.ReactorCoolantFlow-Low(1)FourReactorCoolantPumpsofdesignreactorcoolantOperatingflowwith4pumpsoperating*ofdesignreactorcoolantflowwith4pumpsoperating*4.PressurizerPressure-High5.ContainmentPressure-High<2400psia3.3psig<2400psia<33psig6.SteamGeneratorPressure-Low(2}>600psia7.SteamGeneratorWaterLevel-Low>20.5XHaterLevel-eachsteamgenerator>600psia>19.4MaterLevel-each~steamgeneratorOv~8.LocalPowerDensity-High(3)TripsetpointadjustedtonotexceedthelimitlinesofFigures2.2-1and2.2-2TripsetpointadjustedtonotexceedthelimitlinesofFigures2.2-1and2.2-2.*Designreactorcoolantflowwith4pumpsoperatingis,&gpm.
                                      '606030192 960601  I I'
0I~+0Q1<o.'ledQh
PDa  ADOCV 05000SS5,'
~yCfTABLE3.2-1DNBMARGINLIMITSParameterColdLegTemperaturePressurizerPressureReactorCoolantFlowRateAXIALSHAPEINDEXFourReactorCoolantPumps~0eratin(549'F>2225psia*>955-,888gpmFigure3.2-4,LimitnotapplicableduringeitheraTHERMALPOWERrampincreaseinexcessof5XofRATEDTHERMALPOWERoraTHERMALPOWERstepincreaseofgreaterthanlOXofRATEDTHERMALPOWER.ST.LUCIE-UNIT13/42-14AmendmentNo.~@7,  
PDRii
~QtJQ.)F1~
 
aOESIGNFEATURESCONTROLELEMENTASSEMBLIES5.3.2Thereactorcoreshallcontain73fulllengthandnopartlengthcontrolelementassemblies.ThecontrolelementassembliesshallbedesignedandmaintainedinaccordancewiththeoriginaldesignprovisionscontainedinSection4.2.3.2oftheFSARwithallowancefornormaldegradationpursuanttotheapplicableSurveillanceRequirements.5.4REACTORCOOLANTSYSTEMOESIGNPRESSUREANDTEMPERATURE5.4.1Thereactorcoolantsystemisdesignedandshallbemaintained:a.b.C.InaccordancewiththecoderequirementsspecifiedinSection5.2oftheFSARwithallowancefornormaldegradationpursuanttotheapplicableSurveillanceRequirements,Forapressureof2485psig,andForatemperatureof650'F,exceptforthepressurizerwhichis700'F.VOLUME5.4.2Thetotalwaterandsteamvolumeofthereactrclantsst'11,100+100cubicfeetatanominalTof067'menfloarcounjoiyAi'@am~werw6rAakplvyyl<g.5.5EMERGENCYCORECOOLINGSYSTEMS05.5.1Theemergencycorecoolingsystemsaredesignedandshallbemain-tainedinaccordancewiththeoriginaldesignprovisionscontainedinSection6.3oftheFSARwithallowancefornormaldegradationpursuanttotheapplicableSurveillanceRequirements.5.6FUELSTORAGECRITICALITY5.6.l.aThespentfuelstorageracksaredesignedandshallbemaintainedwith:l.Akffequivalenttolessthanorequalto0.95whenfloodedwitIIunboratedwater,whichincludesaconservativeallowanceof0.0065akforuncertainties.ST.LUCIE-UNIT15-5AmendmentNo.gg,27,7$,
2.0    SAFETY    LIMITS AND    LIMITING SAFETY  SYSTEM SETTINGS 2.1    SAFETY LIMITS                                                            '
We'.ag-~.r<s,;<v>se4'.QjSslbivo><~~0gf.viis~(i)',cmi>zwc>,-isn.o~err~."~:'I,'Ip, St.LucieUnit1DocketNo.50-335ProposedExigentLicenseAmendmentThermalMarinandRCSFlowLimitsENCLOSURESiemensPowerCorporation-NuclearDivision,St.LucieUnit1Chapter15EventReviewandAnalysisfor30%SteamGeneratorTubePlugging,EMF-96-135;May,1996  
l])g,pre 0 5+ZYl<~
}}
REACTOR CORE 2.1.1 The combination of THERMAL POWE, pressurizer pressure, and maxi-mum  cold leg coolant temperature shall not exceed the limits shown on Figure 2.1-1.
APPLICABILITY:       MODES  1  and 2.
ACTION:
Whenever the point defined by the combination of maximum cold leg temper-ature and THERMAL POWER has exceeded the appropriate pressurizer pressure line, be in HOT STANDBY within 1 hour.                                                   I 1
REACTOR COOLANT SYSTEM PRESSURE 2.1.2      The Reactor  Coolant System pressure shall not exceed 2750 psia.
APPLICABILITY:       MODES  1, 2, 3,   4 and  5.
ACTION:
MODES    1  and 2 Whenever the Reactor Coolant System pressure'has exceeded 2750 psia, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within    1  hour.
MODES    3, 4 and 5 Whenever the Reactor Coolant System pressure        has exceeded    2750  psia; reduce the Reactor Coolant System pressure        to'ithin its limit within  5 minutes.
  " For Cycle 14 operation beyond 7000 EFPH, THERMAL POWER shall not exceed 90% of,
~
2700 Megawatts (thermal).
ST. LUCIE     - UNIT 1                    2-1
 
J ~
  ~ la  J f    o  l    I $ a ~ >g}
                                          ~
W~
p 1          10
                  ~C l
                                            /              o I                                        2%
v - <~F>J NJJ4 gp  J J
                                                    ~ g   ~
l
 
UNACCEPTABLE OPERATION 580 UNACCEPTAB OPERATION I
0
.K  560 I
I I
I I
I REACTOR OPERATION LIMIT TO LESS 510 THAN 580 'F BY ACTUATION 0      HE 4J    MAIN STEAM LINE SAFETY VALVE VESSEL FLOW LESS MEASUREMENT UNCERTAINTIES 355.000 GPLl 520 LIMITS CONTAIN NO ALLOWANCE FOR I NSTRUMENT ERROR OR FLUCTUATIO BASED ON THE AXIAL SHAPE        FIGURE B 2.1-1 500 PRESSURE  I      IA I
480 ACCEPTABLE OPERATION          d~
D~gag 1750 2000                                    s y g 2225 2400 460 0.2            0.4        0.6        0.8           $ .2                  L6 FRACTION OF RATED THERMAL POWER FIGURE      2.1-1 REACTOR CORE THERMAL MARGIN SAFETY LIMIT
                          ,   FOUR REACTOR COOLING PUMPS OPERATING
 
                                    ~ I~
                                  )/
                                /
r/
l
                  ~
                      's 1 C  ~cq<
            ~~~>L'Q      hr>>g
    'tahe MQ'A~ J J. y J    ~ ~~J
 
600 UNACCEPTABLE OPERATION 575 qr Q    UNACCEPFABLE OPERATIO
                                                          's g          ~
                                                                  /
550 REACTOR OPERATION LIMITED TO LESS THAN 580 Deg F BY ACI'UATION OF THE                    I  '.
MAIN SMAll LINE SAFETY VALVES VESSEL FLOW LESS ifEASUREIKNT 525  UNCERTAINTIES  046,000 GPM                          I          0 I
LIMITS CONTAIN NO ALLOWANCE FOR                      I INSTRUMENT ERROR OR FLUCTUATIONS a                                                                              '
0 O 500    BASED ON THE AXIAL SHAPE ON FIGURE B    2.1-1 g g PRESSURE  IN PSIA ACCEPTABLE OPERATION 1750
~ pf 475 2000 2225 2400 450 0.4      0.6        O.S      i.             1.2                  1.6 Fraction of Rated Thermal Pox'er
 
TABLE  2.2-1 REACTOR PROTECTIVE INSTRUMENTATION        TRIP SETPOINT LIMITS I
n FUNCTIONAL UNIT                              TRIP SETPOINT                        ALLOWABLE VALUES m
: 1. Manual Reactor  Trip                      Not Applicable                        Not Applicable
: 2. Power Level - High (1)
Four Reactor Coolant Pumps                < 9.61K, above THERMAL POWER,       < 9.61K above THERMAL POWER,~d Operating                                with a minimum setpoint of 155        a minimum setpoint of 15K ofMiTED of RATED THERMAL POWER, and a        THERMAL POWER and a maximum of maximum of < 107.05 of RATED          < 107.0X of RATED THERMAL POWER.
THERMAL POWER.
: 3. Reactor Coolant Flow    - Low (1)
Four Reactor Coolant    Pumps                    of design reactor coolant            of design reactor coolant Operating                                flow with    4 pumps operating*       flow with 4 pumps operating*
: 4. Pressurizer Pressure    - High            <  2400 psia                          <  2400 psia
: 5. Containment Pressure      High             3.3 psig                          < 3 3  psig
: 6. Steam Generator  Pressure    - Low (2} > 600  psia                          >  600  psia
: 7. Steam Generator Water Level -Low         > 20.5X Hater Level steam generator
                                                                        - each        > 19.4 Mater Level - each steam generator
                                                                                                                    ~
: 8. Local Power Density  -   High (3)       Trip setpoint adjusted to not        Trip set point adjusted to not O                                              exceed the limit lines of            exceed the limit lines of v~
Figures 2.2-1 and 2.2-2              Figures 2.2-1 and 2.2-2.
  *Design reactor coolant flow with      4 pumps operating    is,       & gpm.
 
0 I~
      +0 Q1
  <o
      .'led Qh
 
Cf
~ y TABLE 3.2-1 DNB MARGIN LIMITS Four Reactor Coolant Pumps Parameter                          ~0eratin Cold Leg Temperature                    ( 549'F Pressurizer Pressure                    > 2225  psia*
Reactor Coolant Flow Rate                            > 955-,888 gpm AXIAL SHAPE INDEX                      Figure 3.2-4   ,
Limit not applicable during either a THERMAL POWER ramp incr ease in excess  of 5X of RATED THERMAL POWER or a THERMAL POWER step increase of greater than lOX of RATED THERMAL POWER.
ST. LUCIE - UNIT 1              3/4 2-14                Amendment No.~@7,
 
          ~ Qt JQ.) F 1~
 
a OESIGN FEATURES CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 73 full length and no part length control element assemblies.         The control element assemblies shall be designed and maintained in accordance wi th the original design provisions contained in Section 4.2.3.2 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.4    REACTOR COOLANT SYSTEM OESIGN PRESSURE      AND TEMPERATURE 5.4.1    The  reactor coolant system is designed    and  shall  be  maintained:
: a. In accordance with the code requirements specified in Section
: 5. 2 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements,
: b. For  a  pressure of 2485 psig, and C. For  a  temperature of 650'F, except  for the pressurizer      which is 700'F.
VOLUME 5.4.2    The total water and steam volume      of the react r  c    lant  s  st
  '11,100 + 100 cubic feet at a nominal T        of 067'     m  en flo    arcoun joiy
                                                                        ~werw6r Aakplvyyl<g.
Ai'@am 5.5    EMERGENCY CORE COOLING SYSTEMS 0
5.5.1 The emergency core cooling systems are designed and shall be main-tained in accordance with the original design provisions contained in Section 6.3 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
: 5. 6  FUEL STORAGE CRITICALITY 5.6.l.a      The spent    fuel storage racks are designed  and  shall  be maintained wi th:
: l.             equivalent to less than or equal to 0.95 when flooded witIIff A k unborated water, which includes a conservative allowance of 0.0065 ak for uncertainties.
ST. LUC IE    - UNIT  1                5-5              Amendment No. gg,27, 7$ ,
 
We
            '.ag- ~.r<s,;<v>se4 '.QjS slbivo> <~
              ~   0 g f'I, .viis~(i)',c mi>z wc>,-i sn.o~ err~."~:
                          'I p,
 
St. Lucie Unit  1 Docket No. 50-335 Proposed Exigent License Amendment Thermal Mar in and RCS Flow Limits ENCLOSURE Siemens Power Corporation-Nuclear  Division, St. Lucie Unit  1 Chapter 15 Event Review and Analysis  for 30% Steam Generator Tube Plugging, EMF-96-135; May, 1996}}

Latest revision as of 12:27, 4 February 2020

Proposed Tech Specs Re Thermal Margin & RCS Flow Limits
ML17228B504
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 06/01/1996
From:
FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17228B503 List:
References
NUDOCS 9606030192
Download: ML17228B504 (13)
v • d • e


Text

St. Lucie Unit 1 Docket No. 50-335 Proposed Exigent License Amendment Thermal Mar in and RCS Flow Limits ATTACHMENT 4 ST ~ LUCIE UNIT 1 MARKED-UP TECHNICAL SPECIFICATION PAGES Page 2-1 Page 2-2 Revised Figure 2.1-1 Page 2-4 Page 3/4 2-14 Page 5-5

'606030192 960601 I I'

PDa ADOCV 05000SS5,'

PDRii

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS '

l])g,pre 0 5+ZYl<~

REACTOR CORE 2.1.1 The combination of THERMAL POWE, pressurizer pressure, and maxi-mum cold leg coolant temperature shall not exceed the limits shown on Figure 2.1-1.

APPLICABILITY: MODES 1 and 2.

ACTION:

Whenever the point defined by the combination of maximum cold leg temper-ature and THERMAL POWER has exceeded the appropriate pressurizer pressure line, be in HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. I 1

REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2750 psia.

APPLICABILITY: MODES 1, 2, 3, 4 and 5.

ACTION:

MODES 1 and 2 Whenever the Reactor Coolant System pressure'has exceeded 2750 psia, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within 1 hour.

MODES 3, 4 and 5 Whenever the Reactor Coolant System pressure has exceeded 2750 psia; reduce the Reactor Coolant System pressure to'ithin its limit within 5 minutes.

" For Cycle 14 operation beyond 7000 EFPH, THERMAL POWER shall not exceed 90% of,

~

2700 Megawatts (thermal).

ST. LUCIE - UNIT 1 2-1

J ~

~ la J f o l I $ a ~ >g}

~

W~

p 1 10

~C l

/ o I 2%

v - <~F>J NJJ4 gp J J

~ g ~

l

UNACCEPTABLE OPERATION 580 UNACCEPTAB OPERATION I

0

.K 560 I

I I

I I

I REACTOR OPERATION LIMIT TO LESS 510 THAN 580 'F BY ACTUATION 0 HE 4J MAIN STEAM LINE SAFETY VALVE VESSEL FLOW LESS MEASUREMENT UNCERTAINTIES 355.000 GPLl 520 LIMITS CONTAIN NO ALLOWANCE FOR I NSTRUMENT ERROR OR FLUCTUATIO BASED ON THE AXIAL SHAPE FIGURE B 2.1-1 500 PRESSURE I IA I

480 ACCEPTABLE OPERATION d~

D~gag 1750 2000 s y g 2225 2400 460 0.2 0.4 0.6 0.8 $ .2 L6 FRACTION OF RATED THERMAL POWER FIGURE 2.1-1 REACTOR CORE THERMAL MARGIN SAFETY LIMIT

, FOUR REACTOR COOLING PUMPS OPERATING

~ I~

)/

/

r/

l

~

's 1 C ~cq<

~~~>L'Q hr>>g

'tahe MQ'A~ J J. y J ~ ~~J

600 UNACCEPTABLE OPERATION 575 qr Q UNACCEPFABLE OPERATIO

's g ~

/

550 REACTOR OPERATION LIMITED TO LESS THAN 580 Deg F BY ACI'UATION OF THE I '.

MAIN SMAll LINE SAFETY VALVES VESSEL FLOW LESS ifEASUREIKNT 525 UNCERTAINTIES 046,000 GPM I 0 I

LIMITS CONTAIN NO ALLOWANCE FOR I INSTRUMENT ERROR OR FLUCTUATIONS a '

0 O 500 BASED ON THE AXIAL SHAPE ON FIGURE B 2.1-1 g g PRESSURE IN PSIA ACCEPTABLE OPERATION 1750

~ pf 475 2000 2225 2400 450 0.4 0.6 O.S i. 1.2 1.6 Fraction of Rated Thermal Pox'er

TABLE 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS I

n FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES m

1. Manual Reactor Trip Not Applicable Not Applicable
2. Power Level - High (1)

Four Reactor Coolant Pumps < 9.61K, above THERMAL POWER, < 9.61K above THERMAL POWER,~d Operating with a minimum setpoint of 155 a minimum setpoint of 15K ofMiTED of RATED THERMAL POWER, and a THERMAL POWER and a maximum of maximum of < 107.05 of RATED < 107.0X of RATED THERMAL POWER.

THERMAL POWER.

3. Reactor Coolant Flow - Low (1)

Four Reactor Coolant Pumps of design reactor coolant of design reactor coolant Operating flow with 4 pumps operating* flow with 4 pumps operating*

4. Pressurizer Pressure - High < 2400 psia < 2400 psia
5. Containment Pressure High 3.3 psig < 3 3 psig
6. Steam Generator Pressure - Low (2} > 600 psia > 600 psia
7. Steam Generator Water Level -Low > 20.5X Hater Level steam generator

- each > 19.4 Mater Level - each steam generator

~

8. Local Power Density - High (3) Trip setpoint adjusted to not Trip set point adjusted to not O exceed the limit lines of exceed the limit lines of v~

Figures 2.2-1 and 2.2-2 Figures 2.2-1 and 2.2-2.

0 I~

+0 Q1

<o

.'led Qh

Cf

~ y TABLE 3.2-1 DNB MARGIN LIMITS Four Reactor Coolant Pumps Parameter ~0eratin Cold Leg Temperature ( 549'F Pressurizer Pressure > 2225 psia*

Reactor Coolant Flow Rate > 955-,888 gpm AXIAL SHAPE INDEX Figure 3.2-4 ,

Limit not applicable during either a THERMAL POWER ramp incr ease in excess of 5X of RATED THERMAL POWER or a THERMAL POWER step increase of greater than lOX of RATED THERMAL POWER.

ST. LUCIE - UNIT 1 3/4 2-14 Amendment No.~@7,

~ Qt JQ.) F 1~

a OESIGN FEATURES CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 73 full length and no part length control element assemblies. The control element assemblies shall be designed and maintained in accordance wi th the original design provisions contained in Section 4.2.3.2 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.

5.4 REACTOR COOLANT SYSTEM OESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:

a. In accordance with the code requirements specified in Section
5. 2 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements,
b. For a pressure of 2485 psig, and C. For a temperature of 650'F, except for the pressurizer which is 700'F.

VOLUME 5.4.2 The total water and steam volume of the react r c lant s st

'11,100 + 100 cubic feet at a nominal T of 067' m en flo arcoun joiy

~werw6r Aakplvyyl<g.

Ai'@am 5.5 EMERGENCY CORE COOLING SYSTEMS 0

5.5.1 The emergency core cooling systems are designed and shall be main-tained in accordance with the original design provisions contained in Section 6.3 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.

5. 6 FUEL STORAGE CRITICALITY 5.6.l.a The spent fuel storage racks are designed and shall be maintained wi th:
l. equivalent to less than or equal to 0.95 when flooded witIIff A k unborated water, which includes a conservative allowance of 0.0065 ak for uncertainties.

ST. LUC IE - UNIT 1 5-5 Amendment No. gg,27, 7$ ,

We

'.ag- ~.r<s,;<v>se4 '.QjS slbivo> <~

~ 0 g f'I, .viis~(i)',c mi>z wc>,-i sn.o~ err~."~:

'I p,

St. Lucie Unit 1 Docket No. 50-335 Proposed Exigent License Amendment Thermal Mar in and RCS Flow Limits ENCLOSURE Siemens Power Corporation-Nuclear Division, St. Lucie Unit 1 Chapter 15 Event Review and Analysis for 30% Steam Generator Tube Plugging, EMF-96-135; May, 1996

Retrieved from "https://kanterella.com/w/index.php?title=ML17228B504&oldid=2436099"