Text

Attachment 3, St. Lucie License Amendment Request Extended Power Uprate, Renewed Facility Operating License and Technical Specifications Markups and Clean Pages
	ML101160191
Person / Time
Site:	Saint Lucie
Issue date:	04/16/2010
From:	; Florida Power & Light Co
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML101160214	List: L-2010-078, ANP-2903(NP), Rev. 0, St. Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding.; L-2010-078, Attachment 1, St. Lucie License Amendment Request Extended Power Uprate, Description and Technical Justifications for the Renewed Facility Operating License, Technical Specifications, and Licensing Basis Changes; L-2010-078, Attachment 2, St. Lucie License Amendment Request Extended Power Uprate, Supplemental Environmental Report; L-2010-078, Attachment 3, St. Lucie License Amendment Request Extended Power Uprate, Renewed Facility Operating License and Technical Specifications Markups and Clean Pages; L-2010-078, Attachment 4, St. Lucie License Amendment Request Extended Power Uprate, Technical Specifications Bases Markups (for Information Only); L-2010-078, Attachment 5, St. Lucie Extended Power Uprate Licensing Report, Appendix D, List of Key Acronyms; L-2010-078, Attachment 5, St. Lucie Unit 1 Extended Power Uprate Licensing Report, Appendix B, Additional Codes and Methods; L-2010-078, Attachment 5, St. Lucie Unit 1 Extended Power Uprate Licensing Report, Appendix E, Supplement to Licensing Report Section 2.4.1, Reactor Protection, Engineered Safety Features Actuation, and Control Systems; L-2010-078, Attachment 5, St. Lucie Unit 1 Extended Power Uprate Licensing Report, Appendix a, Safety Evaluation Report Compliance; L-2010-078, Attachment 5, St. Lucie Unit 1, Extended Power Uprate Licensing Report, Appendix F, Caldon Ultrasonics Engineering Reports, No. 733, Rev 3, and No. 740, Rev 0; L-2010-078, Attachment 7, St. Lucie License Amendment Request Extended Power Uprate, Summary of Regulatory Commitments; L-2010-078, Attachment 8, St. Lucie License Amendment Request Extended Power Uprate, Criticality Summary Report Spent Fuel Pool and New Fuel Vault; L-2010-078, Attachment 9, St. Lucie License Amendment Request Extended Power Uprate, Core Operating Limits Report (COLR) Markups (for Information Only); L-2010-078, St. Lucie License Amendment Request Extended Power Uprate, Applications for Withholding Proprietary Information from Public Disclosure; L-2010-078, St. Lucie Unit 1 License Amendment Request for Extended Power Uprate; L-2010-078, WCAP-17197-NP, Rev. 0, St. Lucie Unit 1 RCS Pressure & Temperature Limits & Low-Temperature Overpressure Protection Report for 54 Effective Full Power Years.; ML101160182; ML101160186; ML101160189; ML101160191; ML101160192; ML101160195; ML101160196; ML101160197; ML101160198; ML101160201; ML101160202; ML101160204; ML101160205; ML101160207; ML101160208;
References
	L-2010-078
	Download: ML101160191 (135)
	v • d • e

St. Lucie Unit 1 L-2010-078 Docket No. 50-335 Attachment 3 ___________________________________________________________________________________ St. Lucie Unit 1 EPU LAR Att. 3-1 ATTACHMENT 3 LICENSE AMENDMENT REQUEST EXTENDED POWER UPRATE RENEWED FACILITY OPERATING LICENSE AND TECHNICAL SPECIFICATIONS MARKUPS AND CLEAN PAGES FLORIDA POWER & LIGHT ST. LUCIE NUCLEAR PLANT UNIT 1 This coversheet plus 134 pages Renewed Facility Operating License and Technical Specifications Markups and Clean Pages St.. Lucie Unit 1 L-2010-078 Docket No. 50-335 Attachment 3 LIST OF PAGES St. Lucie Unit 1 EPU LAR Att. 3-2 Renewed Facility Operating License and Technical Specifications Markups and Clean Pages Renewed Facility Operating License Technical Specifications I III VIII 1-3 INSERT 1 1-4 1-6 2-2 (replaced by INSERT 2) INSERT 2 2-4 INSERT 3 3/4 1-1 3/4 1-3 3-4 1-8 3/4 1-9a (deleted) 3/4 1-10 3/4 1-12 3/4 1-16 3/4 1-17 3/4 1-18 (renumbered to 3/4 1-17) 3/4 1-19 (renumbered to 3/4 1-18) INSERT 4 (new Page 3/4 1-19) 3/4 2-13 3/4 2-14 3/4 4-17 INSERT 5 3/4 4-19 3/4 4-20 3/4 4-21 3/4 4-22 3/4 4-23a (replaced by INSERT 6) INSERT 6 3/4 4-23b (replaced by INSERT 7) INSERT 7 3/4 4-23c (deleted) 3/4 4-59 3/4 4-60 3/4 5-1 3/4 5-3 3/4 5-5 3/4 5-8 3/4 6-12 3/4 7-3 3/4 7-6 3/4 8-1 Technical Specifications (continued) 3/4 8-6 INSERT 8 3/4 8-6a INSERT 9 3/4 8-7 3/4 9-1 3/4 9-11 3/4 9-16 (deleted) 3/4 10-1 3/4 11-15 5-4 INSERT 10 5-5 5-6 5-6b 5-6c 5-6d 5-6e 5-6f (INSERT 11 - new page) 6-15b 6-19 6-19a 6-19b "3020XXXXXXXXXXX,XXXX ST>?LUCIE?@?UNIT?AIBmendment?No>?DFG?HDG?JKG?JMGAKOINDEXDEFINITIONS SECTIPNQBREA>O???????VEWINITIPNSA>ABction>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@AA>DBxial?Shape?Index>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@AA>HBzimuthal?Qower?Tilt>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@AA>XChannel?Calibration>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@AA>KChannel?Check>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@AA>JChannel?Wunctional?Test>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@DA>FContainment?Yessel?Integrity>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@DA>ZControlled?Leakage>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@DA>MCore?Blteration>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@DA>MaCore?Pperating?Limits?[eport?\CPL[]>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@DA>AOVose?Equivalent?I@AHA>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@HA>AA????Bverage?Visintegration?Energy>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@HA>ADEngineered?Safety?Weatures?[esponse?Time>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@HA>AHWrequency?Notation>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@HA>AXRaseous?[adwaste?Treatment?System>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@HA>AKIdentified?Leakage>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@XA>AJLow?Temperature?[CS?Pverpressure?Qrotection?[ange>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@XA>AF^ember\s]?of?the?Qublic>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@XA>AZPffsite?Vose?Calculation?^anual?\PVC^]>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@XA>AMPperable?-?Pperability>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@KA>DOPperational?^ode?-?^ode>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@KA>DAQhysics?Tests>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@KA>DDQressure?_oundary?Leakage>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>>A@KEVose?Equivalent?`e@AHHVeleted

.-333(7:INDEXLIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS .1-3=/1-l~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~79~3}3-l/-2=1 .{9~7~7,=2-3=/=/-2=#~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~{977~-°$~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~{97~-°$~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~{9~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~{9(~',1 .~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~$~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~{9:$~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~{97)~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~{97'~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~{97,"~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~{9779,"~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~{9778,~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~{9;,~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~{9:2=#~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~1~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~"~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~.1~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~{9'(~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~':3/41-17

.-#6316/3-f}333fINDEXLIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS .1-3=/121$61#3/j="12-3=/.f,=2=/=/1/-2-3=/f3/.-26 1/-3=/<1l-3 1=/3/ 1/-"1/1-2-3=/.= 6/3-3=/./3"6#-=22/1="12,3#3-l2/1-2-$61#.-=2j1"==#,63#<3/j.'6-<=/==#3/==/=/3/ 1/-3.-3=/.l.-1 f'-12#1}1#~2-=2}1..1#f'ff."1/-$61#.-=2j1"==#fff$61#"==#}1/-3#-3=/.l.-1 ~$61#.-=2j1ff."1/-$62/1ff<1l-3 1~.-=2j1"==#ff'#-1.-1"1"-3=/.f'f.'6-<=/2j3/f'ff'j2=6"'13j'-3/.12-3=/"=12<3.-23,6-3=/#3 3-.f'f'<1#1-1<f'f'<1#1-1<f'f'1/-121 3.#3j/ 1/-f'DELETED DEFINITIONS DOSE EQUIVALENT I-131 - AVERAGE DISINTEGRATION ENERGY ENGINEERED SAFETY FEATURES RESPONSE TIME FREQUENCY NOTATION GASEOUS RADWASTE TREATMENT SYSTEM 11INSERT1 INSERT 1DOSE EQUIVALENT XE-133 DEFINITIONS IDENTIFED LEAKAGE LOW TEMPERATURE RCS OVERPRESSURE PROTECTION RANGE *':7 MEMBER(S) OF THE PUBLIC OFFSITE DOSE CALCULATION MANUAL (ODCM) Veleted

.-#6316/3-ffffDEFINITIONS RATED THERMAL POWERf1<-"=12 REACTOR TRIP SYSTEM RESPONSE TIMEf-2-23".l.-1 21."=/.1-3 1&43&/2REPORTABLE EVENTf21"=2-'f'$2'SHIELD BUILDING INTEGRITYf.'31#<,63#<3/j3/-1j23-l&œ-f-==SHUTDOWN MARGINf.'6-<=/3/&&&SITE BOUNDARYf'.3-1,=&SOURCE CHECKff.=621'1"4!HODO?

.-:FIGURE 2.1-1: REACTOR CORE THERMAL MARGIN SAFETY LIMIT - FOUR REACTOR COOLANT PUMPS OPERATING1"--3=/'9))8')))7(8)-=1"--3=/7~87~97~'7~)~:~;~9$~)~'---6-'11.6/12-3/.-2-3=/.9;)9:)8))8')89)8;)8:);))1"--3=/-Insert2-NewFigure 9;)9:)8))8')89)8;)8:);))))~')~9)~;)~:77~'7~97~;Fraction of Rated Thermal PowerMaximum Cold Leg Temperature, ºF--1<..-3=-1$1-l#}1.#3 3-##=/13/.-26 1/-=6--3=/./-'"3.'=/3j621'~77'9))8')))7(8)1"-,#12-3=/1"-"12-3=/1"-,#2-3=/"21..621-'12#=123 3-1<3 6$77$-1'1l-'11}1# INSERT2ST.LUCIE-UNIT12-2AmendmentNo.48,130,145,163FIGURE2.1-1:REACTORCORETHERMALMARGINSAFETYLIMIT-FOURREACTORCOOLANTPUMPSOPERATING .-88TABLE 2.2-1REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITSFUNCTIONAL UNITTRIP SETPOINTALLOWABLE VALUES7~'~7+;7-121<-'12)(~)--1<-'12#"=12~;7-121<-'12)(~)--1<-'12#"=12~7+9~8~*;~"'+(~8-8-:~&-~-~~HK>O?HX>FZG?refer?to?CPL[?Table?H>D@A>Wor?minimum¢¢G¢¢¢INSERT3 INSERT 3 ST>?LUCIE?@?UNIT?AH£X?A@ABmendment?No>?DFG?XKG?JHG?ZJG?AKDGAFA3/4.1 REACTIVITY CONTROL SYSTEMS3/4.1.1 BORATION CONTROLSHUTDOWN MARGIN - Tavg > 200 °°°°FLIMITING CONDITION FOR OPERATION H>A>A>AThe?SUTVP¥N?^B[RIN?shall?be?within?the?limits?specified?in?the?CPL[>APPLICABILITY:??^PVES?AG?D¢G?H?and?X>ACTION:¥ith?the?SUTVP¥N?^B[RIN?not?within?limits?immediately?initiate?and?continue?boration?at??XO?gpmof?greater?than?or?equal?to?AFDO?ppm?boron?or?equivalent?until?the?required?SUTVP¥N?^B[RIN?isrestored>SURVEILLANCE REQUIREMENTS X>A>A>A>AThe?SUTVP¥N?^B[RIN?shall?be?determined?to?be?within?the?CPL[?limits§a>¥ithin?one?hour?after?detection?of?an?inoperable?CEB\s]?and?at?least?once?perAD?hours?thereafter?while?the?CEB\s]?is?inoperable>??If?the?inoperable?CEB?is?notfully?insertedG?and?is?immovable?as?a?result?of?excessive?friction?or?mechanicalinterference?or?is?known?to?be?untrippableG?the?above?required?SUTVP¥N^B[RIN?shall?be?increased?by?an?amount?at?least?equal?to?the?withdrawn?worth?ofthe?immovable?or?untrippable?CEB\s]>b>¥hen?in?^PVES?A?or?D¨G?at?least?once?per?AD?hours?by?verifying?that?CEB?groupwithdrawal?is?within?the?Qower?Vependent?Insertion?Limits?of?Specification?H>A>H>J>c>¥hen?in?^PVE?D¨¨?at?least?once?during?CEB?withdrawal?and?at?least?once?per?hourthereafter?until?the?reactor?is?critical>d>Qrior?to?initial?operation?above?K?[BTEV?TE[^BL?QP¥E[?after?each?fuelloadingG?by?consideration?of?the?factors?of?e?belowG?with?the?CEB?groups?at?theQower?Vependent?Insertion?Limits?of?Specification?H>A>H>J>????????????????????????????????????¢See?Special?Test?Exception?H>AO>A>¨¥ith?©eff??A>O>¨¨¥ith?©eff??A>O>AMOO ST>?LUCIE?@?UNIT?AH£X?A@HBmendment?No>?XZG?ZJG?AFAREACTIVITY CONTROL SYSTEMSSHUTDOWN MARGIN - Tavg < 200 °°°°FLIMITING CONDITION FOR OPERATION H>A>A>DThe?SUTVP¥N?^B[RIN?shall?be§¥ithin?the?limits?specified?in?the?CPL[G?and?in?addition?with?the?[eactor?CoolantSystem?drained?below?the?hot?leg?centerlineG?one?charging?pump?shall?be?renderedinoperable>¢APPLICABILITY:??^PVE?K>ACTION:If?the?SUTVP¥N?^B[RIN?requirements?cannot?be?metG?immediately?initiate?andcontinue?boration?at??XO?gpm?of?greater?than?or?equal?to?AFDO?ppm?boron?or?equivalent?until?the?required?SUTVP¥N?^B[RIN?is?restored>SURVEILLANCE REQUIREMENTS X>A>A>DThe?SUTVP¥N?^B[RIN?requirements?of?Specification?H>A>A>D?shall?bedetermined§a>¥ithin?one?hour?after?detection?of?an?inoperable?CEB\s]?and?atleast?once?per?AD?hours?thereafter?while?the?CEB\s]?is?inoperable>If?the?inoperable?CEB?is??immovable?or?untrippableG?the?aboverequired?SUTVP¥N?^B[RIN?shall?be?increased?by?an?amount?at?leastequal?to?the?withdrawn?worth?of?the?immovable?or?untrippableCEB\s]>b>Bt?least?once?per?DX?hours?by?consideration?of?the?followingfactors§A>[eactor?coolant?system?boron?concentrationGD>CEB?positionGH>[eactor?coolant?system?average?temperatureGX>Wuel?burnup?based?on?gross?thermal?energy?generationGK>`enon?concentrationG?andJ>Samarium?concentration>c>Bt?least?once?per?DX?hoursG?when?the?[eactor?Coolant?System?isdrained?below?the?hot?leg?centerlineG?by?consideration?of?thefactors?in?X>A>A>D>b?and?by?verifying?at?least?one?chargingpump?is?rendered?inoperable>¢????????????????????????????????????¢_reaker?racked@out>AMOO ST>?LUCIE?@?UNIT?AH£X?A@ZBmendment?No>?JOG?ZAG?MOGMXG?AOHG?AOXG?AXAG?AKDG?AFMREACTIVITY CONTROL SYSTEMS3/4.1.2 BORATION SYSTEMSFLOW PATHS - SHUTDOWNLIMITING CONDITION FOR OPERATION H>A>D>ABs?a?minimumG?one?of?the?following?boron?in<<ection?flow?paths?shall?be?PQE[B_LE?andcapable?of?being?powered?from?an?PQE[B_LE?emergency?power?source>a>B?flow?path?from?the?boric?acid?makeup?tank?via?either?a?boric?acid?pump?or?agravity?feed?connection?and?any?charging?pump?to?the?[eactor?Coolant?System?ifonly?the?boric?acid?makeup?tank?in?Specification?H>A>D>Fa?is?PQE[B_LEG?orb>The?flow?path?from?the?refueling?water?tank?via?either?a?charging?pump?or?a?highpressure?safety?in<<ection?pump¢?to?the?[eactor?Coolant?System?if?only?the?refuelingwater?tank?in?Specification?H>A>D>Fb?is?PQE[B_LE>APPLICABILITY:??^PVES?K?and?J>ACTION:¥ith?none?of?the?above?flow?paths?PQE[B_LEG?suspend?all?operations?involving?CP[EBLTE[BTIPNS?or?positive?reactivity?changes¢¢?until?at?least?one?in<<ection?path?is?restored?toPQE[B_LE?status>SURVEILLANCE REQUIREMENTS X>A>D>ABt?least?one?of?the?above?required?flow?paths?shall?be?demonstrated?PQE[B_LE§a>Bt?least?once?per?HA?days?by?verifying?that?each?valve?\manualG?power?operated?orautomatic]?in?the?flow?path?that?is?not?lockedG?sealedG?or?otherwise?secured?inpositionG?is?in?its?correct?position>????????????????????????????????????¢The?flow?path?from?the?[¥T?to?the?[CS?via?a?single?QSI?pump?shall?only?be?established?if§\a]?the?[CS?pressure?boundary?does?not?existG?or?\b]?[CS?pressure?boundary?integrity?exists?andno?charging?pumps?are?operable>??In?the?latter?case§??A]?all?charging?pumps?shall?be?disabled¬D]?heatup?and?cooldown?rates?shall?be?limited?in?accordance?with?Wigure?H>A@Ab¬?and?H]?at?[CStemperatures?below?AAK°°°°WG?any?two?of?the?following?valves?in?the?operable?QSI?header?shall?beverified?closed?and?have?their?power?removed§High Pressure HeaderAuxiliary HeaderCY@HJAJCY@HJAFCY@HJDJCY@HJDFCY@HJHJCY@HJHFCY@HJXJCY@HJXF¢¢Qlant?temperature?changes?are?allowed?provided?the?temperature?change?is?accounted?forin?the?calculated?SUTVP¥N?^B[RIN>,. ST>?LUCIE?@?UNIT?AH£X?A@MaBmendment?No>?ZAG?AOXG?AXAG?AMJFIGURE 3.1-1bMAXIMUM ALLOWABLE HEATUP AND COOLDOWN RATES,SINGLE HPSI PUMP IN OPERATION(Applicable to 35 EFPY)7)):);)9)')):)7))7')79)7;)7:)')))--1 "$ DELETED ST>?LUCIE?@?UNIT?AH£X?A@AOBmendment?No>?XZG?ZJG?MOG?MXG?AFAREACTIVITY CONTROL SYSTEMSFLOW PATHS - OPERATINGLIMITING CONDITION FOR OPERATION H>A>D>DBt?least?two?of?the?following?three?boron?in<<ection?flow?pathsshall?be?PQE[B_LE§a>Pne?flow?path?from?the?boric?acid?makeup?tank\s]?with?thetank?meeting?Specification?H>A>D>Z?part?a]?or?b]G?via?aboric?acid?makeup?pump?through?a?charging?pump?to?the[eactor?Coolant?System>b>Pne?flow?path?from?the?boric?acid?makeup?tank\s]?with?thetank?meeting?Specification?H>A>D>Z?part?a]?or?b]G?via?agravity?feed?valve?through?a?charging?pump?to?the?[eactorCoolant?System>c>The?flow?path?from?the?refueling?water?storage?tank?via?acharging?pump?to?the?[eactor?Coolant?System>P[Bt?least?two?of?the?following?three?boron?in<<ection?flow?paths?shall?bePQE[B_LE§a>Pne?flow?path?from?each?boric?acid?makeup?tank?with?thecombined?tank?contents?meeting?Specification?H>A>D>Z?c]Gvia?both?boric?acid?makeup?pumps?through?a?charging?pumpto?the?[eactor?Coolant?System>b>Pne?flow?path?from?each?boric?acid?makeup?tank?with?thecombined?tank?contents?meeting?Specification?H>A>D>Z?c]Gvia?both?gravity?feed?valves?through?a?charging?pump?tothe?[eactor?Coolant?System>c>The?flow?path?from?the?refueling?water?storage?tankG?viaa?charging?pump?to?the?[eactor?Coolant?System>APPLICABILITY:??^PVES?AG?DG?H?and?X>ACTION:¥ith?only?one?of?the?above?required?boron?in<<ection?flow?paths?to?the[eactor?Coolant?System?PQE[B_LEG?restore?at?least?two?boron?in<<ectionflow?paths?to?the?[eactor?Coolant?System?to?PQE[B_LE?status?within?FDhours?or?make?the?reactor?subcritical?within?the?next?D?hours?andborate?to?a?SUTVP¥N?^B[RIN?equivalent?to?the?requirements?of?Specification?H>A>A>D?atDOO°°°°W¬?restore?at?least?two?flow?paths?to?PQE[B_LE?status?within?the?next?Fdays?or?be?in?CPLV?SUTVP¥N?within?the?next?HO?hours>MXG?d.e.f. ST>?LUCIE?@?UNIT?AH£X?A@ADBmendment?No>?JOG?ZAG?MOGAOXG?AAOG?AXAG?AKDG?AKHG?AFMREACTIVITY CONTROL SYSTEMSCHARGING PUMPS - SHUTDOWNLIMITING CONDITION FOR OPERATION H>A>D>HBt?least?one?charging?pump?or?high?pressure?safety?in<<ection?pump¢?in?the?boron?in<<ectionflow?path?required?PQE[B_LE?pursuant?to?Specification?H>A>D>A?shall?be?PQE[B_LE?andcapable?of?being?powered?from?an?PQE[B_LE?emergency?bus>APPLICABILITY:??^PVES?K?and?J>ACTION:¥ith?no?charging?pump?or?high?pressure?safety?in<<ection?pump¢?PQE[B_LEG?suspend?alloperations?involving?CP[E?BLTE[BTIPNS?or?positive?reactivity?changes¢¢?until?at?leastone?of?the?required?pumps?is?restored?to?PQE[B_LE?status>SURVEILLANCE REQUIREMENTS X>A>D>HBt?least?one?of?the?above?required?pumps?shall?be?demonstrated?PQE[B_LE?by?verifyingthe?charging?pump?develops?a?flow?rate?of?greater?than?or?equal?to?XO?gpm?or?the?highpressure?safety?in<<ection?pump?develops?a?total?head?of?greater?than?or?equal?to?DKFA?ft>when?tested?pursuant?to?the?Inservice?Testing?Qrogram>????????????????????????????????????¢The?flow?path?from?the?[¥T?to?the?[CS?via?a?single?QSI?pump?shall?be?established?only?if§\a]?the?[CS?pressure?boundary?does?not?existG?or?\b]?[CS?pressure?boundary?integrity?exists?andno?charging?pumps?are?operable>??In?the?latter?case§??A]?all?charging?pumps?shall?be?disabled¬D]?heatup?and?cooldown?rates?shall?be?limited?in?accordance?with?Wigure?H>A@Ab¬?and?H]?at?[CStemperatures?below?AAK°°°°WG?any?two?of?the?following?valves?in?the?operable?QSI?header?shall?beverified?closed?and?have?their?power?removed§High Pressure HeaderAuxiliary HeaderCY@HJAJCY@HJAFCY@HJDJCY@HJDFCY@HJHJCY@HJHFCY@HJXJCY@HJXF¢¢Qlant?temperature?changes?are?allowed?provided?the?temperature?change?is?accounted?for??in?the?calculated?SUTVP¥N?^B[RIN>?., ST>?LUCIE?@?UNIT?AH£X?A@AJBmendment?No>?DFG?MXG?AFMREACTIVITY CONTROL SYSTEMSBORATED WATER SOURCES - SHUTDOWNLIMITING CONDITION FOR OPERATION H>A>D>FBs?a?minimumG?one?of?the?following?borated?water?sources?shallbe?PQE[B_LE§a>Pne?boric?acid?makeup?tank?with?a?minimum?borated?watervolume?of?HJKO?gallons?of?D>K?to?H>K?weight?percent?boricacid?\XHFA?to?JAAM?ppm?boron]>b>The?refueling?water?tank?with§A>B?minimum?contained?volume?of?ADKGOOO?gallonsGD>B?minimum?boron?concentration?of?AFDO?ppmG?andH>B?minimum?solution?temperature?of?XO°°°°W>APPLICABILITY:??^PVES?K?and?J>ACTION:¥ith?no?borated?water?sources?PQE[B_LEG?suspend?all?operations?involvingpositive?reactivity?changes¢?until?at?least?one?borated?water?source?isrestored?to?PQE[B_LE?status>SURVEILLANCE REQUIREMENTS X>A>D>FThe?above?required?borated?water?source?shall?be?demonstratedPQE[B_LE§a>Bt?least?once?per?F?days?by§A>Yerifying?the?boron?concentration?of?the?waterGD>Yerifying?the?water?level?of?the?tankG?and>b>Bt?least?once?per?DX?hours?by?verifying?the?[¥T?temperaturewhen?it?is?the?source?of?borated?water?and?the?site?ambientair?temperature?is??XO°°°°W>c>Bt?least?once?per?DX?hours?when?the?[eactor?Buxiliary?_uildingair?temperature?is?less?than?KK°°°°W?by?verifying?that?the?_oricBcid?^akeup?Tank?solution?temperature?is?greater?than?KK°°°°W?whenthat?_oric?Bcid?^akeup?Tank?is?required?to?be?PQE[B_LE>????????????????????????????????????¢Qlant?temperature?changes?are?allowed?provided?the?temperature?change?is?accounted?for?in?the?calculated?SUTVP¥N?^B[RIN>?AMOOH>OKDXK .-7((9'0FIGURE 3.1-1 ST. LUCIE 1 MIN BAMT VOLUMEVS STORED BAMT CONCENTRATIONSTORED BAMT CONC (wt % boric acid)2.42.62.833.23.43.65,0001"--3=/*:())+*(8))+*;())+*808)+*89))+MIN BAMT VOLUME (gallons) 6,0007,0008,0009,0001"--3=/Insert4-NewFigureRelocatedtoTS3/4.1.2.8. REACTIVITYCONTROLSYSTEMSBORATEDWATERSOURCES-OPERATINGLIMITINGCONDITIONFOROPERATION3.1.2.8AtleasttwoofthefollowingfourboratedwatersourcesshallbeOPERABLE:a.BoricAcidMakeupTank1AinaccordancewithFigure3.1-1.b.BoricAcidMakeupTank1BinaccordancewithFigure3.1-1.c.BoricAcidMakeupTanks1Aand1BwithaminimumcombinedcontainedboratedwatervolumeinaccordancewithFigure3.1-1.d.Therefuelingwatertankwith:1.Aminimumcontainedvolumeof477,360gallonsofwater,2.Aminimumboronconcentrationof+H!;\:H)3.Amaximumsolutiontemperatureof100°F,4.Aminimumsolutiontemperatureof55°FwheninMODES1and2,and5.Aminimumsolutiontemperatureof40°FwheninMODES3and4.APPLICABILITY:MODES1,2,3and4.ACTION:WithonlyoneboratedwatersourceOPERABLE,restoreatleasttwoboratedwatersourcestoOPERABLEstatuswithin72hoursormakethereactorsubcriticalwithinthenext2hoursandboratetoaSHUTDOWNMARGINequivalenttotherequirementsofSpecification3.1.1.2at200°F;restoreatleasttwoboratedwatersourcestoOPERABLEstatuswithinthenext7daysorbeinCOLDSHUTDOWNwithinthenext30hours.SURVEILLANCEREQUIREMENTS4.1.2.8AtleasttwoboratedwatersourcesshallbedemonstratedOPERABLE:a.Atleastonceper7daysby:1.Verifyingtheboronconcentrationofthewatersource,ST.LUCIE-UNIT1Amendment-t2Q,m., .-709REACTIVITY CONTROL SYSTEMSSURVEILLANCE REQUIREMENTS * '~&~&-~&°&°$~H£X?A@AZ 631/}=#6 1=21< -=/1/-2-3=/9)))8)));)))())):)))0)))7))))))'88).-=21< -=/+ 3/-#6 1+1"-1="12-3=/6/1"-1="12-3=/*:())+*(8))+*;:))+*;77" +*8" +*8'9" + INSERT4(MODES1,2,3and4) .-7(8)POWER DISTRIBUTION LIMITSDNB PARAMETERSLIMITING CONDITION FOR OPERATION '~8-'7"%3/<1"APPLICABILITY1~ACTION121'12 12SURVEILLANCE REQUIREMENTS 9~'~8~71'~9~'~8~'-~/4-'11"=12~of?the?CPL[§*DNBrelated**¢????Limit?not?applicable?during?either?a?TE[^BL?QP¥E[?ramp?increase?in??????excess?of?K?per?minute?of?[BTEV?TE[^BL?QP¥E[?or?a?TE[^BL??????QP¥E[?step?increase?of?greater?than?AO?of?[BTEV?TE[^BL?QP¥E[>? .-79(:7988)TABLE 3.2-1DNB MARGINLIMITSParameterFour Reactor Coolant PumpsOperating°$3/<1"='9'121'12'121'12~[elocated?to?the?CPL[ .-7(0)7REACTOR COOLANT SYSTEMSPECIFIC ACTIVITYLIMITING CONDITION FOR OPERATION 9~:-&&µ.163-3µ~APPLICABILITY: =ACTION:MODES 1, 2 and 3&&7~)µ<=639°~&&7)){µ8))°~MODES 1, 2, 3, 4 and 5&&7~)µ<=63µ{-99&&SURVEILLANCE REQUIREMENTS 9~9~:-&&-9~°$~EE1?KAZ>M?Ci£gram?VPSE?andINSE[T?K? INSERT 5 ST>?LUCIE?@?UNIT?AH£X?X@AMTABLE 4.4-4PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLEAND ANALYSIS PROGRAMTYPE OF MEASUREMENTAND ANALYSIS MINIMUMFREQUENCYMODES IN WHICH SAMPLEAND ANALYSIS REQUIREDA>Rross?Bctivity?VeterminationH?times?per?F?days?with?amaximum?time?of?FD?hoursbetween?samplesAG?DG?H?and?XD>Isotopic?Bnalysis?for?VPSEUIYBLENT?I@AHA?ConcentrationA?per?AX?daysAH>[adiochemical?for????VeterminationA?per?J?monthsA¢X>Isotopic?Bnalysis?for?IodineIncluding?I@AHAG?I@AHHG?and?I@AHKa]Pnce?per?X?hoursGwhenever?the?VPSEUIYBLENT?I@AHAexceeds?A>O?µCi£gramGandA¨G?D¨G?H¨G?X¨?and?K¨b]Pne?sample?between?Dand?J?hours?followinga?TE[^BL?QP¥E[?changeexceeding?AK?percentof?the?[BTEV?TE[^BLQP¥E[?within?a?onehour?period>AG?DG?H?????????????????????????????????¨Until?the?specific?activity?of?the?primary?coolant?system?is?restored?within?its?limits>¢Bfter?at?least?D?EWQV?and?at?least?DO?days?since?the?last?shutdown?of?longer?than?XZ?hours>EBmendment?No>I@AHDGI@AHX`E@AHH?A?per?F?daysandH> .-')FIGURE 3.4-1DOSE EQUIVALENT I-131 Primary Coolant Specific Activity Limit VersusPercent of RATED THERMAL POWER with the Primary Coolant SpecificActivity > 1.0 µCi/gram Dose Equivalent I-13112')9)8);)():)0)7))'8)'))78)7))8))63}1"--3=/1"--3=/VELETEVAmendment No. .-'79REACTOR COOLANT SYSTEM3/4.4.9 PRESSURE/TEMPERATURE LIMITSREACTOR COOLANT SYSTEMLIMITING CONDITION FOR OPERATION 9~0~7-%+99&APPLICABILITY: -ACTION:.&'=-.-°99~-7~'~77~'~&&7-<°$~Wigure?H>X@Db>Wigures?H>X@Da?and?H>X@Db¢ .-7REACTOR COOLANT SYSTEMSURVEILLANCE REQUIREMENTS 9~9~0~7-~-&&~-4$2Wigures?H>X@DaG?H>X@Db?????????????????????????and?H>X@H>Wigures?H>X@Da?and?H>X@Db>? ST>?LUCIE?@?UNIT?AH£X?X@DHaBmendment?No>?AFG?DZG?ZAG?AOXGAXAG?AMJFIGURE 3.4-2aST. LUCIE UNIT 1 P/T LIMITS, 35 EFPYHEATUP AND CORE CRITICALLimiting?^aterial§??Lower?Shell?Bxial?¥elds?\t>?¨HOKXDX]Limiting?B[T?Yalues?at?HK?EWQ°§A£XTG?AMA°WH£XTG?AHF°W'8))')))78))7)))8))))7))'))9))8))-"2.3.=-=-1.8)-1 "~-621.3.= 3/~-1 "~#=1.-.12}31-621INSE[T?J?@?New?Wigure FIGURE3.4-2aST.LUCIEUNIT1PITLIMITS,54EFPYHEATUPANDCORECRITICAL1LOWESTSERVICETEMPERATURE165°F1----_1/-------------<<(j)0...illill0:::0...0:::illN0:::::J(j)(j)ill0:::0...oill<<<.,)oz--.1---=1550,0PSIA1-------1-----1----ISOTHERMAL-I..._.--._-._-----ALLOWABLEHEATUPRATE70°F/HRIooMIN_BOLTUPTEMP.BOoF100200300400TC-INDICATEDRGSTEMPERATURE,oF500LimitingMaterial:LowerShelJAxialWelds(Ht.#305424)LimitingARTValuesat54EFPY:1/4T,210°F3/4T,156°FST.LUCIE*UNIT13/44-23aAmendmentNo.tT,2&,&1,1-044,49& ST>?LUCIE?@?UNIT?AH£X?X@DHbBmendment?No>?AFG?DZG?ZAGAOXG?AXAG?AMJFIGURE 3.4-2bST. LUCIE UNIT 1 P/T LIMITS, 35 EFPYCOOLDOWN AND INSERVICE TESTLimiting?^aterial§??Lower?Shell?Bxial?¥elds?\t>?¨HOKXDX]?Limiting?B[T?Yalues?at?HK?EWQ°§A£XTG?AMA°W?H£XTG?AHF°W?-$)7))'))9))8))'8))')))78))7)))8)))"2.3/.12}31'l<2=.--3-1.-#=1.-.12}31-62170)$3.=7))-=3.= 3/~$')${'2${'2${'29)${'28)${'2${'27))INSE[T?F?@?New?Wigure FIGURE3A-2bST.LUCIEUNIT1PITLIMITS,54EFPYCOOLDOWNANDINSERVICETEST----------.------.J-{-----.--.--_..------------.-----.-----.....-..-....-....------1100*'F/HRTOISOTHERMALI'<::--"--------.-----.--.-.------._._.....---+-_.._--1----------h-..././o/...-/-.-1'".-/----1---.+-..-/-...---q.:------------------1--------_._--..-.----.-----ISOTHERMAL.__.---:::""'"'------------_._.-.__.._...._-----=1557.3PSIA---..-------..*****----I-----/--:----..-.'--.-.-----.-----**----------------1-:1...-..-.-------__----------.----.---------_-_.----t---t---------....--..--..-....-...----..-nLOWESTSERVICETEMPERATURE1lWF1--1-..INSERVICEHYDROSTATICTEST----<<(J)!l.W0::::J1500---._-----------r--*--f-*--*f--*---_.-.----------.--------.-.-.----..-..--..--.--.ill0::CL0::oc::J(J)(J)ill0::CLoilloozo100200300400TC-INDICATEDRCSTEMPERATURE,ofALLOWABLECOOLDOWNRATESt(/)CLo--20"F/HR==30'FIHR-==40*FIHR-50>F/HR=::::I100°F/HR.7"--/---------.--.MIN.BOLTUPTEMpERATURE80°FRATE.'F/HR20304050100TEMP.LIMIT,'F<125125-145145-160160-180>180500LimitingMaterial:LowerShellAxialWelds(Ht.#305424)LimitingARTValuesat54EFPY:1f4T,2100P3f4T,156°PST.LUCIE-UNIT13/44-23bAmendmentNo.84,+94,1-4'1,+9& ST>?LUCIE?@?UNIT?AH£X?X@DHcBmendment?No>?AFG?DZG?ZAGAOXG?AXAG?AMJFIGURE 3.4-3ST. LUCIE UNIT 1, 35 EFPYMAXIMUM ALLOWABLE COOLDOWN RATESNOTE:A MAXIMUM COOLDOWN RATE OF100°°°°F/HR IS ALLOWED AT ANYTEMPERATURE ABOVE 195°°°°F-:)7))7')79)7;)7:)'))'))7)):);)9)==#<=7))')9)-1 "~VELETEV .-80)7)9'REACTOR COOLANT SYSTEMPOWER OPERATED RELIEF VALVESLIMITING CONDITION FOR OPERATION -*"=2+"12,7~&'78°'~&2.°$~~7~&8°:7°$~'~&2.°)9°$~APPLICABILITY: =&)9°<<4~ACTION:"=<2}="12&2.~"=<1.*7+"=2}"1*'+2.7~(8~~"="=2}%.4~3=&&&&&+5&&&~"=+;~0~'&2}+&&~-SURVEILLANCE REQUIREMENTS 9~9~7"=",#&&"=2}//1#1.-&~3=~selected?during?heatupG?cooldown?and?isothermal?conditions?when?the?temperature?of?any?[CS?cold?leg?is?less?than?or?equal?to?DOOoW>selected?during?heatupG?cooldown?and?isothermal?conditions?when?the?temperature?of?any?[CS?cold?leg?is?greater?than?DOOoW?and?less?than?or?equal?to?HOOoW>HOOoW .-;))7)9REACTOR COOLANT SYSTEMREACTOR COOLANT PUMP - STARTINGLIMITING CONDITION FOR OPERATION 9~79&°$APPLICABILITY: =-ACTION:&°$40~7~SURVEILLANCE REQUIREMENTS 9~9~79&&°$~-2°$~300 .-78(3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)SAFETY INJECTION TANKS (SIT)LIMITING CONDITION FOR OPERATION 8~71&5-APPLICABILITY:ACTION:&&4'==-<=/~3=-<=/~SURVEILLANCE REQUIREMENTS 9~8~71&7~&5'~&&5DHO?and?DZOAMOO?ppm ST>?LUCIE?@?UNIT?AH£X?K@HBmendment?No>?DZG?AHMG?AJXG?AFFEMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION H>K>DTwo?independent?ECCS?subsystems?shall?be?PQE[B_LE?with?each?subsystemcomprised?of§a>Pne?PQE[B_LE?high@pressure?safety?in<<ection?\QSI]?pumpGb>Pne?PQE[B_LE?low@pressure?safety?in<<ection?pumpG?andc>Bn?independent?PQE[B_LE?flow?path?capable?of?taking?suction?from?therefueling?water?tank?on?a?Safety?In<<ection?Bctuation?Signal?and?automaticallytransferring?suction?to?the?containment?sump?on?a?[ecirculation?BctuationSignal>APPLICABILITY:??^PVES?AG?D?and?H¢>ACTION:a>A>¥ith?one?ECCS?subsystem?inoperable?only?because?its?associated?LQSItrain?is?inoperableG?restore?the?inoperable?subsystem?to?PQE[B_LEstatus?within?F?days?or?be?in?at?least?PT?STBNV_°?within?the?nextJ?hours?and?in?PT?SUTVP¥N?within?the?following?J?hours>D>¥ith?one?ECCS?subsystem?inoperable?for?reasons?other?than?conditiona>A>G?restore?the?inoperable?subsystem?to?PQE[B_LE?status?withinFD?hours?or?be?in?at?least?PT?STBNV_°?within?the?next?J?hours?and?inPT?SUTVP¥N?within?the?following?J?hours>b>In?the?event?the?ECCS?is?actuated?and?in<<ects?water?into?the?[eactor?CoolantSystemG?a?Special?[eport?shall?be?prepared?and?submitted?to?the?Commissionpursuant?to?Specification?J>M>D?within?MO?days?describing?the?circumstances?ofthe?actuation?and?the?total?accumulated?actuation?cycles?to?date>????????????????????????????????????¢¥ith?pressurizer?pressure??AFKO?psia>G?andd.OneOPERABLEchargingpump*.3**.*OneECCSsubsystemchargingpumpshallsatisfytheflowpathrequirementsofSpecification3.1.2.2.aor3.1.2.2.d.ThesecondECCSsubsystemchargingpumpshallsatisfytheflowpathrequirementsofSpecification3.1.2.2.bor3.1.2.2.e.** ST>?LUCIE?@?UNIT?AH£X?K@KBmendment?No>?DJG?MOG?AKHG?AJOG?AJXGAMXEMERGENCY CORE COOLING SYSTEMSSURVEILLANCE REQUIREMENTS \continued] e>Bt?least?once?per?AZ?monthsG?during?shutdownG?by§A>Yerifying?that?each?automatic?valve?in?the?flow?path?actuates?to?its?correctposition?on?a?Safety?In<<ection?Bctuation?Signal>D>Yerifying?that?each?of?the?following?pumps?start?automatically?upon?receiptof?a?Safety?In<<ection?Bctuation?Signal¬a>igh@Qressure?Safety?In<<ection?Qump>b>Low@Qressure?Safety?In<<ection?Qump>H>Yerifying?that?upon?receipt?of?an?actual?or?simulated?[ecirculation?BctuationSignal§??each?low@pressure?safety?in<<ection?pump?stopsG?each?containmentsump?isolation?valve?opensG?each?refueling?water?tank?outlet?valve?closesGand?each?safety?in<<ection?system?recirculation?valve?to?the?refueling?watertank?closes>f>_y?verifying?that?each?of?the?following?pumps?develops?the?specified?totaldeveloped?head?when?tested?pursuant?to?the?Inservice?Testing?Qrogram>A>igh@Qressure?Safety?In<<ection?pumps>D>Low@Qressure?Safety?In<<ection?pumps>Delete underline "_" pathsc>???Charging?Qumps>?Qumps> EMERGENCYCORECOOLINGSYSTEMSREFUELINGWATERTANKLIMITINGCONDITIONFOROPERATION3.5.4TherefuelingwatertankshallbeOPERABLEwith:a.Aminimumcontainedvolume477,360gallonsofboratedwater,b.Aminimumboronconcentrationofc.Amaximumwatertemperatureof100°F,d.Aminimumwatertemperatureof55°FwheninMODES1and2,ande.Aminimumwatertemperatureof40°FwheninMODES3and4APPLICABILITY:MODES1,2,3and4.ACTION:Withtherefuelingwatertankinoperable,restorethetanktoOPERABLEstatuswithin1hourorbeinatleastHOTSTANDBYwithin6hoursandinCOLDSHUTDOWNwithinthefollowing30hours.SURVEILLANCEREQUIREMENTS4.5.4TheRWTshallbedemonstratedOPERABLE:a.Atleastonceper7daysby:1.Verifyingthewaterlevelinthetank,and2.Verifyingtheboronconcentrationofthewater.b.Atleastonceper24hoursbyverifyingtheRWTtemperature.ST.LUCIE-UNIT13/45-8AmendmentNo.28, .-7'CONTAINMENT SYSTEMSINTERNAL PRESSURELIMITING CONDITION FOR OPERATION ;~7~9"&9".3j~APPLICABILITY:ACTION:'=-.-#<<=/~SURVEILLANCE REQUIREMENTS 9~;~7~9-&²?O>K?psig>Bmendment?No> ST>?LUCIE?@?UNIT?AH£X?F@HBmendment?No>?AJJTABLE 4.7-1STEAM LINE SAFETY VALVES PER LOOPVALVE NUMBERLIFT SETTING (+ 1% to - 3%) Header AHeader Ba>ZDOAZDOK?MKK>H?psig?and??MMK>H?psigb>ZDODZDOJ?MKK>H?psig?and??MMK>H?psigc>ZDOHZDOF?MKK>H?psig?and??MMK>H?psigd>ZDOXZDOZ?MKK>H?psig?and??MMK>H?psige>ZDOMZDAH?MMX>A?psig?and??AOHK>F?psigf>ZDAOZDAX?MMX>A?psig?and??AOHK>F?psigg>ZDAAZDAK?MMX>A?psig?and??AOHK>F?psigh>ZDADZDAJ?MMX>A?psig?and??AOHK>F?psigAOAK>H¢????²£@?H?for?valves?a?through?d?and?²D£@H?for?valves?e?through?hAOXJ>A* .-;PLANT SYSTEMSCONDENSATE STORAGE TANKLIMITING CONDITION FOR OPERATION (~7~-APPLICABILITY:ACTION:55=-.-;=.'6-<=/~SURVEILLANCE REQUIREMENTS 9~(~7~-&AKHGXOOBmendment?No> ST>?LUCIE?@?UNIT?AH£X?Z@ABmendment?No>?AOHG?AADG?AHZG?AFOGAZO3/4.8 ELECTRICAL POWER SYSTEMS3/4.8.1 A.C. SOURCESOPERATINGLIMITING CONDITION FOR OPERATION H>Z>A>ABs?a?minimumG?the?following?B>C>?electrical?power?sources?shall?be?PQE[B_LE§a>Two?physically?independent?circuits?between?the?offsite?transmission?networkand?the?onsite?Class?AE?distribution?systemG?andb>Two?separate?and?independent?diesel?generator?sets?each?with§A>Engine@mounted?fuel?tanks?containing?a?minimum?of?AKD?gallons?of?fuelGD>B?separate?fuel?storage?system?containing?a?minimum?of?AJGXKO?gallons?offuelG?andH>B?separate?fuel?transfer?pump>APPLICABILITY:??^PVES?AG?DG?H?and?X>ACTION:a>¥ith?one?offsite?circuit?of?H>Z>A>A>a?inoperableG?except?as?provided?in?Bction?f>belowG?demonstrate?the?PQE[B_ILIT°?of?the?remaining?B>C>?sources?byperforming?Surveillance?[equirement?X>Z>A>A>A>a?within?A?hour?and?at?leastonce?per?Z?hours?thereafter>??[estore?the?offsite?circuit?to?PQE[B_LE?statuswithin?FD?hours?or?be?in?at?least?PT?STBNV_°?within?the?next?J?hours?andCPLV?SUTVP¥N?within?the?following?HO?hours>b>¥ith?one?diesel?generator?of?H>Z>A>A>b?inoperableG?demonstrate?thePQE[B_ILIT°?of?the?B>C>?sources?by?performing?Surveillance?[equirementX>Z>A>A>A>a?within?A?hour?and?at?least?once?per?Z?hours?thereafter¬?and?if?theEVR?became?inoperable?due?to?any?cause?other?than?an?inoperable?supportsystemG?an?independently?testable?componentG?or?preplanned?preventativemaintenance?or?testingG?demonstrate?the?PQE[B_ILIT°?of?the?remainingPQE[B_LE?EVR?by?performing?Surveillance?[equirement?X>Z>A>A>D>a>X?withinZ?hoursG?unless?it?can?be?confirmed?that?the?cause?of?the?inoperable?EVR?doesnot?exist?on?the?remaining?EVR¢¬?restore?the?diesel?generator?to?PQE[B_LEstatus?within?AX?days?or?be?in?at?least?PT?STBNV_°?within?the?next?J?hoursand?in?CPLV?SUTVP¥N?within?the?following?HO?hours>??BdditionallyG?withinX?hours?from?the?discovery?of?concurrent?inoperability?of?required?redundantfeature\s]?\including?the?steam?driven?auxiliary?feed?pump?in?^PVE?AG?DG?and?H]Gdeclare?required?feature\s]?supported?by?the?inoperable?EVR?inoperable?if?itsredundant?required?feature\s]?is?inoperable>????????????????????????????????????¢If?the?absence?of?any?common@cause?failure?cannot?be?confirmedG?this?test?shall?becompleted?regardless?of?when?the?inoperable?EVR?is?restored?to?PQE[B_ILIT°>19,000 .-;ELECTRICAL POWER SYSTEMSSURVEILLANCE REQUIREMENTS&%4%49')³'~9~&4³'%4~8~1.$&%+}&&%+4%49')'}&&-~O>JO>JINSE[T?ZDAODAO INSERT 8 .-;ELECTRICAL POWER SYSTEMSSURVEILLANCE REQUIREMENTS;~&~--4³7~'4~(~&~:~&'&.&~-~0~&*&'%~7)~&77~&~&---~INSE[T?M INSERT 9 ST>?LUCIE?@?UNIT?AH£X?Z@FBmendment?No>?AOHG?AHZG?AFMELECTRICAL POWER SYSTEMSSHUTDOWNLIMITING CONDITION FOR OPERATION H>Z>A>DBs?a?minimumG?the?following?B>C>?electrical?power?sources?shall?be?PQE[B_LE§a>Pne?circuit?between?the?offsite?transmission?network?and?the?onsite?Class?AEdistribution?systemG?andb>Pne?diesel?generator?set?with§A>Engine@mounted?fuel?tanks?containing?a?minimum?of?AKD?gallons?of?fuelGD>B?fuel?storage?system?containing?a?minimum?of?AJGXKO?gallons?of?fuelG?andH>B?fuel?transfer?pump>APPLICABILITY:??^PVES?K?and?J>ACTION:¥ith?less?than?the?above?minimum?required?B>C>?electrical?power?sources?PQE[B_LEGimmediately?suspend?all?operations?involving?CP[E?BLTE[BTIPNSG?operations?involvingpositive?reactivity?additions?that?could?result?in?loss?of?required?SUTVP¥N?^B[RIN?or?boronconcentrationG?movement?of?irradiated?fuelG?or?crane?operation?with?loads?over?the?fuel?storagepool>??In?additionG?when?in?^PVE?K?with?the?reactor?coolant?loops?not?filledG?or?in?^PVE?J?withthe?water?level?less?than?DH?feet?above?the?top?of?irradiated?fuel?assemblies?seated?within?thereactor?vesselG?immediately?initiate?corrective?action?to?restore?the?required?sources?toPQE[B_LE?status?as?soon?as?possible>SURVEILLANCE REQUIREMENTS X>Z>A>D>AThe?above?required?B>C>?electrical?power?sources?shall?be?demonstratedPQE[B_LE?by?the?performance?of?each?of?the?Surveillance?[equirements?ofX>Z>A>A>A?and?X>Z>A>A>D?except?for?requirement?X>Z>A>A>Da>K>19,000 ST>?LUCIE?@?UNIT?AH£X?M@ABmendment?No>?AODG?AKOG?AFA3/4.9 REFUELING OPERATIONSBORON CONCENTRATIONLIMITING CONDITION FOR OPERATION H>M>A¥ith?the?reactor?vessel?head?unbolted?or?removedG?the?boron?concentration?of?allfilled?portions?of?the?[eactor?Coolant?System?and?the?refueling?cavity?shall?bemaintained?within?the?limit?specified?in?the?CPL[>APPLICABILITY:??^PVE?J¢>ACTION:¥ith?the?requirements?of?the?above?specification?not?satisfiedG?immediately?suspend?alloperations?involving?CP[E?BLTE[BTIPNS?or?positive?reactivity?changes?and?initiate?andcontinue?boration?at??XO?gpm?of?greater?than?or?equal?to?AFDO?ppm?boron?or?its?equivalent?torestore?boron?concentration?to?within?limits>?SURVEILLANCE REQUIREMENTS X>M>A>AThe?boron?concentration?limit?shall?be?determined?prior?to§a>[emoving?or?unbolting?the?reactor?vessel?headG?andb>¥ithdrawal?of?any?full?length?CEB?in?excess?of?H?feet?from?its?fully?insertedposition>X>M>A>DThe?boron?concentration?of?the?refueling?cavity?shall?be?determined?by?chemicalanalysis?at?least?H?times?per?F?days?with?a?maximum?time?interval?betweensamples?of?FD?hours>????????????????????????????????????¢The?reactor?shall?be?maintained?in?^PVE?J?when?the?reactor?vessel?head?is?unbolted?orremoved>AMOO .-¶*#631*¸*6/3-*¹º>>1/4*1/2¸¹¹1/2ºREFUELING OPERATIONSSPENT FUEL STORAGE POOLLIMITING CONDITION FOR OPERATION º¶1/2¶¹¹-*3/4-***¿º******5*-**4*¹¿Â*APPLICABILITY: *****ACTION:***********1/4*¶4********4*¶-**º¶Â¶º**SURVEILLANCE REQUIREMENTS 1/4¶1/2¶¹¹-*********4******1/4¶1/2¶¹¹¶¹&********AMOO .-7;9)REFUELING OPERATIONS3/4.9.14 DECAY TIME - STORAGE POOLLIMITING CONDITION FOR OPERATION 0~79-~APPLICABILITY:ACTION:)~SURVEILLANCE REQUIREMENTS 9~0~79-&55VELETEV .-)7((3/4.10 SPECIAL TEST EXCEPTIONSSHUTDOWN MARGINLIMITING CONDITION FOR OPERATION 7)~7-<=/3/47~7~71APPLICABILITY:1~ACTION:&<=/3/47~7~7&9)<=/3/47~7~7SURVEILLANCE REQUIREMENTS 9~7)~7~7-4~9~7)~7~'1<=/3/7~7~7~AMOO .-/3-77800RADIOACTIVE EFFLUENTSGAS STORAGE TANKSLIMITING CONDITION FOR OPERATION 77~'~;-&&5*APPLICABILITY:ACTION:&55~-)~SURVEILLANCE REQUIREMENTS 9~77~'~;-&55&17))KAZ>M?Ci£gram?VPSE?DODGKOO .-99;7798'DESIGN FEATURES 2.1.2 SHIELD BUILDING)))8&5~5~~DESIGN PRESSURE AND TEMPERATURE8~'~'-!°$~PENETRATIONS8~'~":~'~7~'~9~5.3 REACTOR COREFUEL ASSEMBLIES8~7-!9~7(&&~~8~7~71!/2~INSE[T?AO INSERT 10' .-¶*#631*¸*6/3-*¹¸¿*¿**1/2¹¹1/4*¹Åº*¹1/2ºDESIGN FEATURES CONTROL ELEMENT ASSEMBLIES¶º¶¿-*******-*****1/4¶¿¶º¶¿****¶5.4 REACTOR COOLANT SYSTEMDESIGN PRESSURE AND TEMPERATURE¶1/4¶¹-***3****¶¿*****¿1/4******ÅÂ°°°°$*!*%*ÂÂ°°°°$¶VOLUME¶1/4¶¿-*******¹¹¹ÂÂ*Ç*¹Â***Å°°°°$***5.5 EMERGENCY CORE COOLING SYSTEMS¶¶¹-*******Å¶º**¶5.6 FUEL STORAGECRITICALITY¶Å¶¹¶-**5*3/4¹¶5*¹¶Â******1/2¶¹*&*¶¿¶¹Â¶¹¿***¹******¹Â¶ºÂ*****¹*5***5¶Å****¿*****¶ .-¶*#631*¸*6/3-*¹¸Å*¿¿*¿1/4*º1/4*1/2¹*1/2¿*¹Â¿*¹1/2ºDESIGN FEATURES 23-3l*º¶**4*Â¶1/2***ÂÂ******1/2¶¹****&*¶1/4¶***4**¹**º****5**4**¶Å¶¹¶¶*}***1/2¶¹*&**&****Å¶*****4**¹**º¶-**¹*5**5**,***5**¶**¿º***¹*5*5¶¹¶-*!***6¸¿º*******5***4**1/4¶*¿¶¹*5******¶Å¸¹***4**¶Å¸¹*¶Å¸¿¶º¶¿*5*******¶Å¸¿***4*-*¶Å¸¹**¶Å¸¿¶**-*&**4**&*1/4¶*&¶Å¶¹¶¹****¹*5**5¶-*****&*****6¸¿º**4**1/4¶*******4*Â¶1/2**X>JX>Jin5.6.1.a.1and5.6.1.a.3.in5.6.1.c.2and5.6.1.c.3,,andTable5.6-3.maximum?planar?average .-¶*#631*¸*6/3-*¹¹*¹1/2º/=-1.3/4¹¶**&****4&¹*¿*º****¶Å¸¹*¶Å¸¿¶¿¶-*5*&***¶**5***&**º¶3***¹*5***5***¿*5¶1/4¶=*5*¶FIGURE 5.6-1Allowable Region 1 Storage Patterns and Fuel Alignments#=1<21j3=/*¹¸-=¸21j3=/*¹$6/*ºÉ¹¹¿ºº¿¹¹¹¹¿ºº¿¿ºº¿j,1-11/1/-* =<6#1.#=1<'112/.*.*/*¹**¿É¹¹¿ºº¿=2=2=2,?G?TableG?and?Table?K>J@H>? .-¶*#631*¸*6/3-*¹1/2º/=-1.3/4¹¶/**&**&**Å**-*¶Å¸¶Å¸¿¶¿¶-****Ž*Ž<*Ž1É**º¶*1***¿&***&**¶1/4¶******¶=*5*¶FIGURE 5.6-2Allowable Region 2 Storage Patterns and Arrangements=1<'1"12,=2<*.-j1--12/.*./*¹*¿É"*3/-121.-23-3=/.1/41/4/=/1=2=2ÅÅÅÅ##=1<*."13#/j1 1/-.3/4$**15$$$$$$$$""<"*1Ã**1 "-l*1##*.*/*1/4É$Ã**$21.'*$61#..1 ,#l5*ººººººººº**ºÉººººÇ*1Ç*1G?and?Table?K>J@H>J>?????This?arrangement?is?valid?only?for?fresh?assemblies?with?planar?average?enrichment??X>K?w£o>?(SeeNote6)?G?Table .-¶*#631*¸*6/3-*¹1/2ºTABLE 5.6-1Minimum Burnup as a Function of Enrichment for Non-Blanketed AssembliesCoefficientsMinimum Burnup (GWd/MTU) for Initial EnrichmentFuelTypeCoolingTimeABC1.9 w/o2.5 w/o3.0 w/o3.8 w/o1Â*&Â¶ÂÂ1/2¶º¹¸¿1/4¶º1/2Â¶ÂÂÂ¶ÂÂº¶1/4¹Â¶1/21/22Â*&Â¶ÂÂ¹Â¶¹¸¿¿¶ºÂ¶ÂÂº¶1/2º1/2¶¹¹¶1/23Â*&Â¶ÂÂ¹Â¶1/2¸¹1/4¶¹Å¶¹º¹¿¶¿¹¶¿Â¿Å¶1/2Â*&¸Â¶1/4¹¹¶ÂÂ¸¿¹¶º1/21/2¶1/4º¹¶¿¶1/2¿º¶¿1/2¹¿*&¸Â¶1/4¹Å¶¿¿¸¿Â¶Åº¶¿1/4¹Å¶¿º¶¹ºº¶¿¹¹*&¸Â¶º¹¶Å¸¿Â¶Â¶¹¹Å¶¿¿¿¶1/4º¿¶1/44¿Â*&¸Â¶1/4Å¹¶¹¹¸¹¶Â¶¿¹Å¶¹Â¿¿¶º1/2º¹¶1/2Â*&¸Â¶1/4¹¶1/41/2¸¹1/2¶¿¹Â¶1/4¹1/2¶º¿Å¶Â1/2ºÅ¶ÂÅ5*&¸Â¶Å¹¶Å1/4¸¹¶Å¹Â¶Â1/4¹¶1/2¿1/4¶¿ººº¶ÂÂ*&¸Â¶1/4¹¹¶Â¸¹¶1/2¹1/4¶¹¿º¶¿º¹¶1/41/41/4º¶º¹¿*&Â¶Â1/4¹º¶¹Â¸¹¿¶Å¹¿¶1/4¿Â¶1/41/4¿¶¹Âº¶Â¹*&Â¶¹º¹¿¶º¸¹¹¶º¹¿¶¹Å¹1/2¶1/2º¿Å¶1/4º¶Â1/26¿Â*&Â¶¿Å¹¹¶Å¸¹¹¶¹Å¹¹¶1/4¹1/2¶º¿¶ÅºÅ¶¿Â*&¸Â¶Å¿Â¶Â¸¹Å¶¿¹1/2¶¿1/2¿1/2¶Å¿º¶Â¶1/4Â¹¿*&¸Â¶Å¹¶Å¸¹¶¹¶¿¿1/4¶Åº¹¶1/4¿¶¿¹*&¸Â¶1/4º¹Å¶¿¸¹º¶1/4¹¶1/4¿1/4¶¹Âº¹¶Â1/41/4¹¶Â7¿Â*&Â¶¹¿¹¿¶1/2Â¸1/2¶Å¹¹¶ºº¿º¶º1/2ºÂ¶¹1/4¹¶¹1/4/=-1.3/4¹¶5****¿º***¿¶-*4&***&****Ž**Ž****¶****Ž*********Ž&Ž****,6*Ã*1¿*Ç*,1*Ç*,6*Ã***j<>> -6É1*Ã*3***¿ºÉ*,**Ã*º¶3***¶**Operatedat 2700MWt .-¶*#631*¸*6/3-*¹1/2ºTABLE 5.6-2Minimum Burnup as a Function of Enrichment for Blanketed AssembliesCoefficientsMinimum Burnup (GWd/MTU)for Initial EnrichmentFuelTypeCoolingTimeABC2.5 w/o3.0 w/o3.5 w/o4.0 w/o4.5 w/o1Â*&Â¶ÂÂ1/2¶º¹¸¿1/4¶º1/2Â¶ÂÂº¶1/4¶¿Â¹¿¶¹¶¹2Â*&Â¶ÂÂ¹Â¶¹¸¿¿¶ºº¶1/2º1/2¶¹¹1/4¶1/41/4¹1/2¶Å1/2¿1/4¶1/23Â*&Â¶ÂÂ¹Â¶1/2¸¹1/4¶¹¹¿¶¿¹¶¿Â¿º¶Å1/2¿1/2¶¹º1/4¶ÅÅÂ*&¸Â¶1/2¹¶1/2¸¿¿¶1/4¹¶Å¿¶º¹¶º¶ÅÅ1/4¿¶1/2*&¸Â¶1/4¹Å¶1/4¸¹1/2¶¹Â¹¶Åº¿º¶Å¿1/2¶ºº¶¿¿1/4Â¶º¹Â*&¸Â¶¹1/4¶º¸¹Å¶1/41/2¹Å¶¿¿¶¿¶Âºº¶º¹º¶¿¹*&¸Â¶1/4Å¹º¶1/4¸¹1/4¶Â¹Å¶¿¿¹¶¿¶ÂÅº¿¶¹ÂºÅ¶1/2¿4¿Â*&¸Â¶1/4¹¹¿¶1/2¸¹º¶1/4¹Å¶¹¿¹¶¹¿Å¶Åº¹¶Å¿ºÅ¶ºÂ*&¸Â¶1/4¹¶1/41/2¸¹1/2¶¿¹1/2¶º¿Å¶Â1/2º¿¶1/4ºº¶1/4Â1/41/4¶ÂÂ5*&¸Â¶Å¹¶Å1/4¸¹¶Å¹¶1/2¿1/4¶¿ººÂ¶¿ºº¶1/21/4¹¶º1/2Â*&¸Â¶¿1/4¹1/4¶¿º¸¹Â¶º¿º¶ÂºÂ¶¹ºÅ¶1/41/21/4¿¶Â1/4¶Â*&¸Â¶¿Â¹º¶¹Â¸1/2¶¿1/4¿¿¶¿Å¿¶¿Åº1/4¶¹Åº1/2¶1/2Å1/4¶ÅÅ¹Â*&¸Â¶¿º¹¿¶Â¸1/2¶¿¿¹¶Â1/4¿Å¶Åº¿¶ºÅº¶1/4º¶¿¿¹*&¸Â¶º¿¹º¶Â¿¸¹Â¶1/4¿Â¶Â¿¶Âº¹¶¹ºÅ¶1/41/4¹¶Åº6¿Â*&¸Â¶1/4¹1/4¶Â¸¹¿¶¹1/2¶1/4¹¿¶¹ÅºÂ¶Åº¶1/21/4Â¶1/21/2Â*&¸Â¶1/4¹1/2¶¿¸¹º¶1/4¿¿1/2¶1/4ÅºÅ¶1/4º¶ÅÂ¶¹1/4Å¶¿Â*&¸Â¶¿¹¶1/4Â¸¹¿¶Âº¿Å¶1/2ºº¶Å1/21/4Â¶Â1/4Å¶Â¹¶Å1/2¹Â*&¸Â¶ÅÅ¹Å¶º¿¸¹¹¶1/4Å¿¶¿¿º¹¶Åº¶1/4º¶¿Å1/4¶Å¿¹*&¸Â¶Å¹Å¶ÂÂ¸¹¹¶º¿1/4¶ÂºÂ¶¿1/4ºÅ¶ÂÅ1/4¹¶1/4Å¶Â7¿Â*&¸Â¶Å¹Å¶1/4¸¹¿¶¹¿º¶¿1/2¶Âº¶1/4Å1/4Â¶º1/4¶º/=-1.3/4¹¶*******!¸¿º********¶Å¸¹**%*****¿¶*>>¿¶-*4&***&****Ž**Ž****¶***Ž*********Ž&Ž****,6*Ã*1¿*Ç*,1*Ç*,6*Ã***j<>> -6É1*Ã*3***¿ºÉ*,**Ã*º¶3*****Operatedat?2700MWt TABLE 5.6-3 Minimum Burnup as a Function of Enrichment for Blanketed Assemblies (Operated atCoefficients Minimum Burnup (GWd/MTU) for Initial EnrichmentFuel TypeCooling TimeABC3.0 w/o3.8 w/o4.2 w/o4.6 w/o1234567 /=-1.'INSERT11 ST. LUCIE - UNIT 1 6-15b Amendment No. 69, 86, 123, 149, 187, 197, 206 ADMINISTRATIVE CONTROLS (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following: 1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM. 2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and 3) Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring. h. Containment Leakage Rate Testing Program A program to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50 Appendix J, Option B, as modified by approved exemptions. This program is in accordance with the guidelines contained in Regulatory Guide 1.163, Performance-Based Containment Leak-Test Program, as modified by the following exception(s): a) Bechtel Topical Report, BN-TOP-1 or ANS 56.8-1994 (as recommended by R.G. 1.163) will be used for type A testing. b) The first Type A test performed after the May 1993 Type A test shall be no later than May 2008. The peak calculated containment internal pressure for the design basis loss of coolant accident Pa, is 39.6 psig. The containment design pressure is 44 psig. The maximum allowed containment leakage rate, La, at Pa, shall be 0.50% of containment air weight per day. Leakage rate acceptance criteria are: a. Containment leakage rate acceptance criterion is < 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and C tests, < 0.75 La for Type A tests, and < 0.096 La for secondary containment bypass leakage paths. b. Air lock testing acceptance criteria are: 1) Overall air lock leakage rate is < 0.05 La when tested at > Pa. 2) For the personnel air lock door seal, leakage rate is < 0.01 La when pressurized to > 1.0 Pa. 3) For the emergency air lock door seal, leakage rate is < 0.01 La when pressurized to > 10 psig. XD>Z .-¶*#631*¸*6/3-*¹Å¸¹1/21/2*Å1/2*Å*¹¿º¹Â*¹Åº*¹¹*¹1/2¹ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ÉÅ¶1/2¶¹¶1/2**&**&****¹Â*******/2¶Å¶1/2¶¹¶¹Â**&*¹Â*&****Â*******/2¶6.9.1.11 CORE OPERATING LIMITS REPORT (COLR)************=#2*3/4º¶¹¶¹¶¹.~*-*j*-*¿ÂÂ°°°°$º¶¹¶¹¶¿.~*-**-*14*¿ÂÂ°°°°$º¶¹¶¹¶1/4*-*º¶¹¶º¶¹*~**¹*º¶¹¶º¶Å2*º¶¿¶¹#*º¶¿¶º-35*~º¶¿¶</,*º¶1/2¶¹2*=~**-***********/2*******=#2¶¹¶¹¹1/2Å¸"¸****"'=1/3"¸.&*"*¹1/2*&É¿¶/$¸-2¸1/2¸Â¹*/*&****-********¹1/21/2¶º¶"/¸¸¿*"/¸/$¸¸¿ÉÑ*1!!É***1/4¶1/4¸º"ÉÉ***&*%*3/4**¹*¶"/¸/$¸¿¸¿¹"ÉÉ**1!!**"2*-&**!-$VELETEV .-¶*#631*¸*6/3-*¹Â*¹Åº*¹1/2¹ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT*Å¶1 $¸1/4¸Â1/2º"ÉÉ**,5*&*"2*¶"/¸¸º¿"ÉÉ*****¶"/¸/$¸¿¸1/41/2"ÉÉ*1!!1 *"2*.*1/2¶"/¸/$¸¸1/41/4/"ÉÉ**1-"**¹Â¶"/¸/$¸Å¿¹"É**1!!*</,***"2****¹¹¶1 $¸¿Â"ÉÉ*.1 >>"2¸1/23/4***"2**¹¿¶"/¸/$¸¿¸ÂÅ"ÉÉ***1!!**1!*¹º¶¸¹ºº"ÉÉ*****"2&*****Å¿*j>> -6*¹1/4¶"/¸/$¸¸1/2¿*"É*1!!*6*j31!*-&**¹¶1/2¸¹¹"ÉÉ*&**3/4**¸#=**¹**¹Å¶<1#1-1<*¹¶1 $¸1/2¿¸¹¹Å"ÉÉ*j"2**¹¶1 $¸1/2¿¸¹º"É*'-"3/4******-**¹1/2¶1 $¸1/2Å¸Â¿1/2"ÉÉ**¹*¿**.&"***¹*~*&***¿*~**DELETED .-¶*#631*¸*6/3-*¹Åº*¹¹*¹1/2¹ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT*¿Â¶1 $¸¹1/2Å¹"ÉÉ*.&**-&*¿¹¶1 $¸¿º¹Â"ÉÉ*.2"*¹*#=&*"%*2*¿¿¶*1 $¸¿º¿"ÉÉ*"2*.5*#=*.¸*DH>???E^W@DAOH\Q]\B]?[evision?OG?[ealistic?Large?_reak?LPCB?^ethodology?????????for?Qressurized?¥ater?[eactorsG?Wramatone?BNQG?Inc>G?Bpril?DOOH? St. Lucie Unit 1 L-2010-078 Docket No. 50-335 Attachment 3 ___________________________________________________________________________________ St. Lucie Unit 1 EPU LAR ATTACHMENT 3 LICENSE AMENDMENT REQUEST EXTENDED POWER UPRATE RENEWED FACILITY OPERATING LICENSE AND TECHNICAL SPECIFICATIONS CLEAN PAGES FLORIDA POWER & LIGHT ST. LUCIE NUCLEAR PLANT UNIT 1 Renewed Facility Operating License and Technical Specifications Markups and Clean Pages Updated per Amendment 209 dated 06/30/09 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-335 ST. LUCIE PLANT UNIT NO. 1 RENEWED FACILITY OPERATING LICENSE NO. DPR-67 The U.S. Nuclear Regulatory Commission (the Commission) having previously made the findings set forth in License No. DPR-67 issued March 1, 1976, has now found that: a. The application to renew License No. DPR-67 filed by the Florida Power and Light Company (FPL or the licensee), complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter 1, and all required notifications to other agencies or bodies have been duly made; b. Actions have been identified and have been or will be taken with respect to (1) managing the effects of aging during the period of extended operation on the functionality of structures and components that have been identified to require review under 10 CFR 54.21(a)(1), and (2) time-limited aging analyses that have been identified to require review under 10 CFR 54.21(c), such that there is reasonable assurance that the activities authorized by this renewed license will continue to be conducted in accordance with the current licensing basis, as defined in 10 CFR 54.3, for St. Lucie Plant Unit No.1, and that any changes made to the plants current licensing basis in order to comply with 10 CFR 54.29(a) are in accord with the Act and the Commissions regulations; c. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; d. There is reasonable assurance: (i) that the activities authorized by this renewed operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission; e. FPL is technically and financially qualified to engage in the activities authorized by this renewed operating license in accordance with the rules and regulations of the Commission; f. FPL has satisfied the applicable provisions of 10 CFR Part 140, Financial Protection Requirements and Indemnity Agreements, of the Commissions regulations; g. The renewal of this operating license will not be inimical to the common defense and security or to the health and safety of the public; and h. After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the Renewed License No. DPR-67Revised by letter dated XXXXXX XX, XXXX issuance of Renewed Facility Operating License No. DPR-67, subject to the conditions for protection of the environment set forth herein, is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied. On the basis of the foregoing findings regarding this facility, Facility Operating License No. DPR-67, issued March 1, 1976, is superseded by Renewed Facility Operating License No. DPR-67, which is hereby issued to FPL to read as follows: 1. This renewed license applies to the St. Lucie Plant, Unit No. 1, a pressurized water nuclear reactor, and associated steam generators and electrical generating equipment (the facility). The facility is located on the licensees site on Hutchinson Island in St. Lucie County, Florida, and is described in the Updated Final Safety Analysis Report, as supplemented and amended, and the Environmental Report, as supplemented and amended. 2. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses FPL: A. Pursuant to Section 104b of the Act and 10 CFR Part 50, Licensing of Production and Utilization Facilities, to possess, use, and operate the facility as a utilization facility at the designated location on the St. Lucie site in accordance with the procedures and limitations set forth in this renewed license; B. Pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report as supplemented and amended; C. Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; D. Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material, without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and E. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. 3. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all Renewed License No. DPR-67Revised by letter dated XXXXXX XX, XXXX applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: A. Maximum Power Level FPL is authorized to operate the facility at steady state reactor core power levels not in excess of 3020 megawatts (thermal). B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. XXX are hereby incorporated in the renewed license. FPL shall operate the facility in accordance with the Technical Specifications. Appendix B, the Environmental Protection Plan (Non-Radiological), contains environmental conditions of the renewed license. If significant detrimental effects or evidence of irreversible damage are detected by the monitoring programs required by Appendix B of this license, FPL will provide the Commission with an analysis of the problem and plan of action to be taken subject to Commission approval to eliminate or significantly reduce the detrimental effects or damage. C. Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on March 28, 2003, describes certain future activities to be completed before the period of extended operation. FPL shall complete these activities no later than March 1, 2016, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection. The Updated Final Safety Analysis Report supplement as revised on March 28, 2003, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following issuance of this renewed license. Until that update is complete, FPL may make changes to the programs described in such supplement without prior Commission approval, provided that FPL evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section. D. Sustained Core Uncovery Actions Procedural guidance shall be in place to instruct operators to implement actions that are designed to mitigate a small-break loss-of-coolant accident prior to a calculated time of sustained core uncovery. Renewed License No. DPR-67Revised by letter dated XXXXXX XX, XXXX E. Fire Protection FPL shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility (The fire protection program and features were originally described in FPL submittals L-83-514 dated October 7, 1983, L-83-227 dated April 12, 1983, L-83-261 dated April 25, 1983, L-83-453 dated August 24, 1983, L-83-488 dated September 16, 1983, L-83-588 dated December 14, 1983, L-84-346 dated November 28, 1984, L-84-390 dated December 31, 1984, and L-85-71 dated February 21, 1985) and as approved by NRC letter dated July 17, 1984, and supplemented by NRC letters dated February 21, 1985, March 5, 1987, and October 4, 1988, subject to the following provision: FPL may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. F. Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provision of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: Florida Power and Light & FPL Energy Seabrook Physical Security Plan, Training and Qualification Plan and Safeguards Contingency Plan - Revision 3, submitted by letter dated May 18, 2006. G. Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas: (a) Fire fighting response strategy with the following elements: 1. Pre-defined coordinated fire response strategy and guidance 2. Assessment of mutual aid fire fighting assets 3. Designated staging areas for equipment and materials 4. Command and control 5. Training of response personnel (b) Operations to mitigate fuel damage considering the following: 1. Protection and use of personnel assets 2. Communications 3. Minimizing fire spread 4. Procedures for implementing integrated fire response strategy 5. Identification of readily-available pre-staged equipment 6. Training on integrated fire response strategy 7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of: 1. Water spray scrubbing 2. Dose to onsite responders Renewed License No. DPR-67Revised by letter dated XXXXXX XX, XXXX H. Control Room Habitability Upon implementation of Amendment No. 205, adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 4.7.7.1.e, in accordance with TS 6.8.4.m, the assessment of CRE habitability as required by Specification 6.8.4.m.c. (ii), and the measurement of CRE pressure as required by Specification 6.8.4.m.d, shall be considered met. Following implementation: (a) The first performance of SR 4.7.7.1.e, in accordance with Specification 6.8.4.m.c(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 4.0.2, as measured from September 2003, the date of the most recent successful tracer gas test, as stated in FPL letters to NRC dated December 9, 2003, and October 29, 2004, in response to Generic Letter 2003-01. (b) The first performance of the periodic assessment of CRE habitability, Specification 6.8.4.m.c(ii), shall be within 3 years, plus the 9-month allowance of SR 4.0.2, as measured from September 2003, the date of the most recent successful tracer gas test, as stated in FPL letters to NRC dated December 9, 2003, and October 29, 2004, in response to Generic Letter 2003-01, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years. (c) The first performance of the periodic measurement of CRE pressure, Specification 6.8.4.c.d, shall be within 36 months in a staggered test basis, plus the 138 days allowed by SR 4.0.2, as measured from June 30, 2006, which is the date of the most recent successful pressure measurement test, or within 138 days if not performed previously. 4. This renewed license is effective as of the date of issuance and shall expire at midnight on March 1, 2036. FOR THE NUCLEAR REGULATORY COMMISSION ORIGINAL SIGNED BY J. E. Dyer, Director Office of Nuclear Reactor Regulation Attachments: 1. Appendix A, Technical Specifications 2. Appendix B, Environmental Protection Plan Renewed License No. DPR-67Amendment No. 205Revised by letter dated XXXXXX XX, XXXX ST. LUCIE - UNIT 1 I Amendment No. 27, 32, 65, 69, 150, INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS 1.1 Action............................................................................................................................1-1 1.2 Axial Shape Index.........................................................................................................1-1 1.3 Azimuthal Power Tilt.....................................................................................................1-1 1.4 Channel Calibration......................................................................................................1-1 1.5 Channel Check.............................................................................................................1-1 1.6 Channel Functional Test...............................................................................................1-2 1.7 Containment Vessel Integrity........................................................................................1-2 1.8 Controlled Leakage.......................................................................................................1-2 1.9 Core Alteration..............................................................................................................1-2 1.9a Core Operating Limits Report (COLR)..........................................................................1-2 1.10 Dose Equivalent I-131...................................................................................................1-3 1.11 Dose Equivalent Xe-133...............................................................................................1-3 1.12 Engineered Safety Features Response Time...............................................................1-3 1.13 Frequency Notation......................................................................................................1-3 1.14 Gaseous Radwaste Treatment System........................................................................1-3 1.15 Identified Leakage........................................................................................................1-4 1.16 Deleted.........................................................................................................................1-4 1.17 Member(s) of the Public................................................................................................1-4 1.18 Offsite Dose Calculation Manual (ODCM)....................................................................1-4 1.19 Operable - Operability..................................................................................................1-5 1.20 Operational Mode - Mode............................................................................................1-5 1.21 Physics Tests................................................................................................................1-5 1.22 Pressure Boundary Leakage........................................................................................1-5 ST. LUCIE - UNIT 1 III Amendment No. 37, 118, 134, INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY..................................................................................................3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL.......................................................................................3/4 1-1 Shutdown Margin - Tavg > 200F........................................................................3/4 1-1 Shutdown Margin - Tavg < 200F........................................................................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 1-17 3/4.1.3 MOVABLE CONTROL ASSEMBLIES..............................................................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 - UNIT 1 VIII Amendment No. 4, 24, 25, 27, 56, 193, INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION..............................................................................3/4 9-1 3/4.9.2 INSTRUMENTATION.........................................................................................3/4 9-2 3/4.9.3 DECAY TIME......................................................................................................3/4 9-3 3/4.9.4 CONTAINMENT PENETRATIONS.....................................................................3/4 9-4 3/4.9.5 COMMUNICATIONS..........................................................................................3/4 9-5 3/4.9.6 MANIPULATOR CRANE OPERABILITY............................................................3/4 9-6 3/4.9.7 DELETED...........................................................................................................3/4 9-7 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION.................................3/4 9-8 3/4.9.9 CONTAINMENT ISOLATION SYSTEM..............................................................3/4 9-9 3/4.9.10 WATER LEVEL - REACTOR VESSEL............................................................3/4 9-10 3/4.9.11 SPENT FUEL STORAGE POOL......................................................................3/4 9-11 3/4.9.12 FUEL POOL VENTILATION SYSTEM - FUEL STORAGE..............................3/4 9-12 3/4.9.13 DELETED.........................................................................................................3/4 9-15 3/4.9.14 DELETED.........................................................................................................3/4 9-16 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN....................................................................................3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.........................................................................................................3/4 10-2 3/4.10.3 DELETED.........................................................................................................3/4 10-3 3/4.10.4 DELETED.........................................................................................................3/4 10-4 3/4.10.5 CENTER CEA MISALIGNMENT......................................................................3/4 10-5 ST. LUCIE - UNIT 1 1-3 Amendment No. 27, 69, 163, 195, 206, DEFINITIONS DOSE EQUIVALENT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (Ci/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Federal Guidance Report 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion." DOSE EQUIVALENT XE-133 1.11 DOSE EQUIVALENT XE-133 shall be that concentration of Xe-133 (Ci/gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity. The determination of DOSE EQUIVALENT XE-133 shall be performed using effective dose conversion factors for air submersion listed in Table III.1 of EPA Federal Guidance Report No. 12, 1993, External Exposure to Radionuclides in Air, Water, and Soil. ENGINEERED SAFETY FEATURES RESPONSE TIME 1.12 The ENGINEERED SAFETY FEATURES REPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC. FREQUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1. GASEOUS RADWASTE TREATMENT SYSTEM 1.14 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. ST. LUCIE - UNIT 1 1-4 Amendment No. 59, 60, 69, 81, 104, 123, 125, 200, DEFINITIONS IDENTIFED LEAKAGE 1.15 IDENTIFIED LEAKAGE shall be: a. Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured, and conducted to a sump or collecting tank, or b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or c. Reactor Coolant System leakage through a steam generator to the secondary system (Primary-to-secondary leakage). 1.16 Deleted MEMBER(S) OF THE PUBLIC 1.17 MEMBER OF THE PUBLIC means an individual in a controlled or unrestricted area. However, an individual is not a member of the public during any period in which the individual receives an occupational dose. OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.18 THE OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitor- ing Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9.1.7 and 6.9.1.8. ST. LUCIE - UNIT 1 1-6 Amendment No. 27, 32, 59, 65, 69, 125, 195, DEFINITIONS RATED THERMAL POWER 1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3020 MWt. REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power to the CEA drive mechanism is interrupted. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC. REPORTABLE EVENT 1.27 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50. SHIELD BUILDING INTEGRITY 1.28 SHIELD BUILDING INTEGRITY shall exist when: a. Each door is closed except when the access opening is being used for normal transit entry and exit; b. The shield building ventilation system is in compliance with Specification 3.6.6.1, and c. The sealing mechanism associated with each penetration (e.g., welds, bellows or O-rings) is OPERABLE. SHUTDOWN MARGIN 1.29 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full-length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fully withdrawn. SITE BOUNDARY 1.30 SITE BOUNDARY means that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee. SOURCE CHECK 1.31 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. 600r------------------------------------------,UNACCEPTABLEOPERATION200022252400PRESSUREINPSIA1750THERMALPOWERLIMITEDTOAMAXIMUMOF112%OFRATEDTHERMALPOWERBYTHEHIGHPOWERTRIPLEVELACCEPTABLEOPERATIONBASEDONTHEAXIALSHAPEONFIGUREB2.1-1REACTORCOOLANTSYSTEMTOTALFLOWRATESPECIFIEDINCOLRTABLE3.2-1REACTOROPERATIONLIMITEDTOLESSTHAN580°FBYACTUATIONOFTHEMAINSTEAMSAFETYVALVESLIMITSCONTAINNOALLOWANCESFORINSTRUMENTERRORORFLUCTUATIONS480580I---------------------""""i<<---Q,----<'r------.G--U-N-A-C--C-EP-T-A-B-LE-O...,..-PE-R-A-J--IO-N-Ju.oW560a:::>t;:a:u.Ia.540w....'"W....IC520....IoVi500Xc(:i:1.61.41.20.60.8FRACTIONOFRATEDTHERMALPOWEIR0.40.2460L-------1----JoFIGURE2.1-1:REACTORCORETHERMALMARGINSAFETYLIMITFOURREACTORCOOLANTPUMPSOPERATINGST.LUCIE-UNIT12-2AmendmentNo.48,+JQ,44a,49J, ST. LUCIE - UNIT 1 2-4 Amendment No. 3, 27, 32, 45, 105, 130, 145, 163, TABLE 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 1. Manual Reactor Trip Not Applicable Not Applicable 2. Power Level - High (1) Four Reactor Coolant Pumps Operating < 9.61% above THERMAL POWER, with a minimum setpoint of 15% of RATED THERMAL POWER, and a maximum of < 107.0% of RATED THERMAL POWER. < 9.61% above THERMAL POWER, and a minimum setpoint of 15% of RATED THERMAL POWER and a maximum of < 107.0% of RATED THERMAL POWER. 3. Reactor Coolant Flow - Low (1) Four Reactor Coolant Pumps Operating > 95% of design reactor coolant flow with 4 pumps operating * > 95% of design reactor coolant 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**,*** > 35.0% Water Level - each steam generator > 34.78% Water Level - each steam generator 8. Local Power Density - High (3) Trip setpoint adjusted to not exceed the limit lines of Figures 2.2-1 and 2.2-2. Trip set point adjusted to not exceed the limit lines of Figures 2.2-1 and 2.2-2.
For minimum reactor coolant flow with 4 pumps operating, refer to COLR Table 3.2-1. ** If the as-found channel setpoint is either outside its predefined as-found acceptance criteria band or is not conservative with respect to the Allowable Value, then the channel shall be declared inoperable and shall be evaluated to verify that it is functioning as required before returning the channel to service. *** The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the Trip Setpoint, or a value that is more conservative than the Trip Setpoint, otherwise that channel shall not be returned to OPERABLE status. The Trip Setpoint and the methodology used to determine the Trip Setpoint, the as-found acceptance criteria band, and the as-left acceptance criteria are specified in the UFSAR.

ST. LUCIE - UNIT 1 3/4 1-1 Amendment No. 27, 45, 63, 86, 152, 171, 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - Tavg > 200 F LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be within the limits specified in the COLR. APPLICABILITY: MODES 1, 2*, 3 and 4. ACTION: With the SHUTDOWN MARGIN not within limits immediately initiate and continue boration at > 40 gpm of greater than or equal to 1900 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored. SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be within the COLR limits: a. Within one hour after detection of an inoperable CEA(s) and at least once per 12 hours thereafter while the CEA(s) is inoperable. If the inoperable CEA is not fully inserted, and is immovable as a result of excessive friction or mechanical interference or is known to be untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable CEA(s). b. When in MODES 1 or 2#, at least once per 12 hours by verifying that CEA group withdrawal is within the Power Dependent Insertion Limits of Specification 3.1.3.6. c. When in MODE 2## at least once during CEA withdrawal and at least once per hour thereafter until the reactor is critical. d. Prior to initial operation above 5% RATED THERMAL POWER after each fuel loading, by consideration of the factors of e below, with the CEA groups at the Power Dependent Insertion Limits of Specification 3.1.3.6.

See Special Test Exception 3.10.1. # With Keff > 1.0. ## With Keff < 1.0.

ST. LUCIE - UNIT 1 3/4 1-3 Amendment No. 48, 86, 171, REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - Tavg < 200 F LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be: Within the limits specified in the COLR, and in addition with the Reactor Coolant System drained below the hot leg centerline, one charging pump shall be rendered inoperable.* APPLICABILITY: MODE 5. ACTION: If the SHUTDOWN MARGIN requirements cannot be met, immediately initiate and continue boration at > 40 gpm of greater than or equal to 1900 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored. SURVEILLANCE REQUIREMENTS 4.1.1.2 The SHUTDOWN MARGIN requirements of Specification 3.1.1.2 shall be determined: a. Within one hour after detection of an inoperable CEA(s) and at least once per 12 hours thereafter while the CEA(s) is inoperable. If the inoperable CEA is immovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable CEA(s). b. At least once per 24 hours by consideration of the following factors: 1. Reactor coolant system boron concentration, 2. CEA position, 3. Reactor coolant system average temperature, 4. Fuel burnup based on gross thermal energy generation, 5. Xenon concentration, and 6. Samarium concentration. c. At least once per 24 hours, when the Reactor Coolant System is drained below the hot leg centerline, by consideration of the factors in 4.1.1.2.b and by verifying at least one charging pump is rendered inoperable.*

Breaker racked-out.

ST. LUCIE - UNIT 1 3/4 1-8 Amendment No. 60, 81, 90, 94, 103, 104, 141, 152, 179, REACTIVITY CONTROL SYSTEMS 3/4.1.2 BORATION SYSTEMS FLOW PATHS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the following boron injection flow paths shall be OPERABLE and capable of being powered from an OPERABLE emergency power source. a. A flow path from the boric acid makeup tank via either a boric acid pump or a gravity feed connection and any charging pump to the Reactor Coolant System if only the boric acid makeup tank in Specification 3.1.2.7a is OPERABLE, or b. The flow path from the refueling water tank via either a charging pump or a high pressure safety injection pump* to the Reactor Coolant System if only the refueling water tank in Specification 3.1.2.7b is OPERABLE. APPLICABILITY: MODES 5 and 6. ACTION: With none of the above flow paths OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes** until at least one injection path is restored to OPERABLE status. SURVEILLANCE REQUIREMENTS 4.1.2.1 At least one of the above required flow paths shall be demonstrated OPERABLE: a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

The flow path from the RWT to the RCS via a single HPSI pump shall only be established if: (a) the RCS pressure boundary does not exist, or (b) RCS pressure boundary integrity exists and no charging pumps are operable. In the latter case, all charging pumps shall be disabled. ** Plant temperature changes are allowed provided the temperature change is accounted for in the calculated SHUTDOWN MARGIN.

ST. LUCIE - UNIT 1 3/4 1-9a Amendment No. 81, 104, 141, 196, DELETED ST. LUCIE - UNIT 1 3/4 1-10 Amendment No. 48, 86, 90, 94, 171, REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.2 At least two of the following three boron injection flow paths shall be OPERABLE: a. One flow path from the boric acid makeup tank(s) with the tank meeting Specification 3.1.2.8 part a) or b), via a boric acid makeup pump through a charging pump to the Reactor Coolant System. b. One flow path from the boric acid makeup tank(s) with the tank meeting Specification 3.1.2.8 part a) or b), via a gravity feed valve through a charging pump to the Reactor Coolant System. c. The flow path from the refueling water storage tank via a charging pump to the Reactor Coolant System. OR At least two of the following three boron injection flow paths shall be OPERABLE: d. One flow path from each boric acid makeup tank with the combined tank contents meeting Specification 3.1.2.8 c), via both boric acid makeup pumps through a charging pump to the Reactor Coolant System. e. One flow path from each boric acid makeup tank with the combined tank contents meeting Specification 3.1.2.8 c), via both gravity feed valves through a charging pump to the Reactor Coolant System. f. The flow path from the refueling water storage tank, via a charging pump to the Reactor Coolant System. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With only one of the above required boron injection flow paths to the Reactor Coolant System OPERABLE, restore at least two boron injection flow paths to the Reactor Coolant System to OPERABLE status within 72 hours or make the reactor subcritical within the next 2 hours and borate to a SHUTDOWN MARGIN equivalent to the requirements of Specification 3.1.1.2 at 200F; restore at least two flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours. ST. LUCIE - UNIT 1 3/4 1-12 Amendment No. 60, 81, 90, 104, 110, 141, 152, 153, 179, REACTIVITY CONTROL SYSTEMS CHARGING PUMPS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.3 At least one charging pump or high pressure safety injection pump* in the boron injection flow path required OPERABLE pursuant to Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus. APPLICABILITY: MODES 5 and 6. ACTION: With no charging pump or high pressure safety injection pump* OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes** until at least one of the required pumps is restored to OPERABLE status. SURVEILLANCE REQUIREMENTS 4.1.2.3 At least one of the above required pumps shall be demonstrated OPERABLE by verifying the charging pump develops a flow rate of greater than or equal to 40 gpm or the high pressure safety injection pump develops a total head of greater than or equal to 2571 ft. when tested pursuant to the Inservice Testing Program.

The flow path from the RWT to the RCS via a single HPSI pump shall be established only if: (a) the RCS pressure boundary does not exist, or (b) RCS pressure boundary integrity exists and no charging pumps are operable. In the latter case, all charging pumps shall be disabled. ** Plant temperature changes are allowed provided the temperature change is accounted for in the calculated SHUTDOWN MARGIN.

ST. LUCIE - UNIT 1 3/4 1-16 Amendment No. 27, 94, 179, REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.7 As a minimum, one of the following borated water sources shall be OPERABLE: a. One boric acid makeup tank with a minimum borated water volume of 3650 gallons of 3.0 to 3.5 weight percent boric acid (5245 to 6119 ppm boron). b. The refueling water tank with: 1. A minimum contained volume of 125,000 gallons, 2. A minimum boron concentration of 1900 ppm, and 3. A minimum solution temperature of 40F. APPLICABILITY: MODES 5 and 6. ACTION: With no borated water sources OPERABLE, suspend all operations involving positive reactivity changes* until at least one borated water source is restored to OPERABLE status. SURVEILLANCE REQUIREMENTS 4.1.2.7 The above required borated water source shall be demonstrated OPERABLE: a. At least once per 7 days by: 1. Verifying the boron concentration of the water, 2. Verifying the water level of the tank, and. b. At least once per 24 hours by verifying the RWT temperature when it is the source of borated water and the site ambient air temperature is < 40F. c. At least once per 24 hours when the Reactor Auxiliary Building air temperature is less than 55F by verifying that the Boric Acid Makeup Tank solution temperature is greater than 55F when that Boric Acid Makeup Tank is required to be OPERABLE.

Plant temperature changes are allowed provided the temperature change is accounted for in the calculated SHUTDOWN MARGIN.

ST. LUCIE - UNIT 1 3/4 1-17 Amendment No. 28, 48, 86, 94, 129, 171, 209, REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.8 At least two of the following four borated water sources shall be OPERABLE: a. Boric Acid Makeup Tank 1A in accordance with Figure 3.1-1. b. Boric Acid Makeup Tank 1B in accordance with Figure 3.1-1. c. Boric Acid Makeup Tanks 1A and 1B with a minimum combined contained borated water volume in accordance with Figure 3.1-1. d. The refueling water tank with: 1. A minimum contained volume of 477,360 gallons of water, 2. A minimum boron concentration of 1900 ppm, 3. A maximum solution temperature of 100F, 4. A minimum solution temperature of 55F when in MODES 1 and 2, and 5. A minimum solution temperature of 40F when in MODES 3 and 4. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With only one borated water source OPERABLE, restore at least two borated water sources to OPERABLE status within 72 hours or make the reactor subcritical within the next 2 hours and borate to a SHUTDOWN MARGIN equivalent to the requirements of Specification 3.1.1.2 at 200F; restore at least two borated water sources to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours. SURVEILLANCE REQUIREMENTS 4.1.2.8 At least two borated water sources shall be demonstrated OPERABLE: a. At least once per 7 days by: 1. Verifying the boron concentration of the water source, ST. LUCIE - UNIT 1 3/4 1-18 Amendment No. 94, REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2. Verifying the water level in each water source. b. At least once per 24 hours by verifying the RWT temperature. c. At least once per 24 hours by verifying that the Boric Acid Makeup Tank solution temperature is greater than 55F when the Reactor Auxiliary Building air temperature is below 55F. FIGURE3.1-1ST.LUCIE1MINBAMTVOLUMEVSSTOREDBAMTCONCENTRATION(MODES1,2,3and4)///.ACCEPTABLEOPERATION(8700)8000Ulc0roOl(7500)UJ7000:2:::J..JUNACCEPTABLE0>OPERATION(6800)I-:2:<tI1l6000z:2:5000+--------+--------+---------+---------j3.50(6119PPM)3.25(5682PPM)4000+-----------'------------+------------'----------j3.00(5245PPM)STOREDBAMTCONC(wt%boricacid)81.LUCIE-UNIT13/41-19AmendmentNo.2:+,94, ST. LUCIE - UNIT 1 3/4 2-13 Amendment No. 27, 150, POWER DISTRIBUTION LIMITS DNB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DNB related parameters shall be maintained within the limits shown on Table 3.2-1 of the COLR: a. Cold Leg Temperature b. Pressurizer Pressure* c. Reactor Coolant System Total Flow Rate d. AXIAL SHAPE INDEX APPLICABILITY: MODE 1. ACTION: With any of the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours or reduce THERMAL POWER to < 5% of RATED THERMAL POWER within the next 4 hours. SURVEILLANCE REQUIREMENTS 4.2.5.1 Each of the DNB related parameters shall be verified to be within their limits by instrument readout at least once per 12 hours. 4.2.5.2 The Reactor Coolant System total flow rate shall be determined to be within its limit by measurement** at least once per 18 months.

Limit not applicable during either a THERMAL POWER ramp increase in excess of 5% per minute of RATED THERMAL POWER or a THERMAL POWER step increase of greater than 10% of RATED THERMAL POWER. ** Not required to be performed until THERMAL POWER is > 90% of RATED THERMAL POWER.

ST. LUCIE - UNIT 1 3/4 2-14 Amendment No. 27, 48, 130, 145, 150, 163, Relocated to the COLR ST. LUCIE - UNIT 1 3/4 4-17 Amendment No. 69, 101, REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to: a. < 1.0 Ci/gram DOSE EQUIVALENT I-131, and b. < 518.9 Ci/gram DOSE EQUIVALENT XE-133. APPLICABILITY: MODES 1, 2, 3, and 4. ACTION: a. With the specific activity of the primary coolant >1.0 Ci/gram DOSE EQUIVALENT I-131, verify DOSE EQUIVALENT I-131 is < 60.0 Ci/gram once per four hours. b. With the specific activity of the primary coolant > 1.0 Ci/gram DOSE EQUIVALENT I-131, but < 60.0 Ci/gram DOSE EQUIVALENT I-131, operation may continue for up to 48 hours while efforts are made to restore DOSE EQUIVALENT I-131 to within the 1.0 Ci/gram limit. Specification 3.0.4 is not applicable. c. With the specific activity of the primary coolant > 1.0 Ci/gram DOSE EQUIVALENT I-131 for greater than 48 hours during one continuous time interval, or > 60.0 Ci/gram DOSE EQUIVALENT I-131, be in HOT STANDBY within 6 hours and COLD SHUTDOWN within the following 30 hours. d. With the specific activity of the primary coolant > 518.9 Ci/gram DOSE EQUIVALENT XE-133, operation may continue for up to 48 hours while efforts are made to restore DOSE EQUIVALENT XE-133 to within the 518.9 Ci/gram DOSE EQUIVALENT XE-133 limit. Specification 3.0.4 is not applicable. e. With the specific activity of the primary coolant > 518.9 Ci/gram DOSE EQUIVALENT XE-133 for greater than 48 hours during one continuous time interval, be in HOT STANDBY within 6 hours and COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis pro- gram of Table 4.4-4. ST. LUCIE - UNIT 1 3/4 4-19 Amendment No. TABLE 4.4-4 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM TYPE OF MEASUREMENT AND ANALYSIS MINIMUM FREQUENCY MODES IN WHICH SAMPLE AND ANALYSIS REQUIRED 1. DOSE EQUIVALENT XE-133 Determination 1 per 7 days 1, 2, 3 and 4 2. Isotopic Analysis for DOSE EQUIVALENT I-131 Concentration 1 per 14 days 1 3. Isotopic Analysis for Iodine Including I-131, I-132, I-133, I-134, and I-135 a) Once per 4 hours, whenever the DOSE EQUIVALENT I-131 exceeds 1.0 Ci/gram, and 1#, 2#, 3#, and 4# b) One sample between 2 and 6 hours following a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period. 1, 2, 3 # Until the specific activity of the primary coolant system is restored within its limits. ST. LUCIE - UNIT 1 3/4 4-20 Amendment No. DELETED ST. LUCIE - UNIT 1 3/4 4-21 Amendment No. 4, 81, 104, 152, REACTOR COOLANT SYSTEM 3/4.4.9 PRESSURE/TEMPERATURE LIMITS REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION 3.4.9.1 The Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 3.4-2a and 3.4-2b during heatup, cooldown, criticality, and inservice leak and hydrostatic testing. APPLICABILITY: At all times.* ACTION: With any of the above limits exceeded, restore the temperature and/or pressure to within the limits within 30 minutes; perform an analysis to determine the effects of the out-of-limit condition on the fracture toughness properties of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operations or be in at least HOT STANDBY within the next 6 hours and reduce the RCS Tavg to less than 200F within the following 30 hours in accordance with Figure 3.4-2b.

During hydrostatic testing operations above system design pressure, a maximum temperature change in any one hour period shall be limited to 5F.

ST. LUCIE - UNIT 1 3/4 4-22 Amendment No. 81, 113, REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.9.1 a. The Reactor Coolant System temperature and pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations. b. The Reactor Coolant System temperature and pressure conditions shall be determined to be to the right of the criticality limit line within 15 minutes prior to achieving reactor criticality. c. The reactor vessel material irradiation surveillance specimens shall be removed and examined, to determine changes in material properties as required by 10 CFR 50 Appendix H. The results of these examinations shall be used to update Figures 3.4-2a and 3.4-2b. FIGURE3.4-2aST.LUCIEUNIT1PITLIMITS,54EFPYHEATUPANDCORECRITICAL2000--2------------4----------------:t--***I-H--!,*-*-*-----1-------------.-.---------.-----/-------,.1-,'."'.'.,-."---l--',==_.--:1-*----1--.....---..--...I+--/--,...--.....--...--.+_.-.-.--+_.i"-It-*------1-------..:,.---f-'f-._----",-1*.-------.------j.-...-------..--.-.':.I*/.*\+.---f------\ICORECRITICAL-/-1000(f)fl0...<<CI)ll.uS:J(f)1500CI)llJ0...llJN0::::J(f)(f)llJ0:::ll.ollJ()ozi..._-+----MIN.BOLTUPTEMP.80°FIALLOWABLEHEATUPRATEI70'F/HRIo100200300400500Tc-INDICATEDRCSTEMPERATURE,oFLimitingMaterial:LowerShellAxialWelds(Ht.#305424)LimitingARTValuesat54EFPV:1/4T,210°F3/4T,156°FST.LUCIE..lJNIT13/44-23aAmendmentNo.++,;m,M,4Q4,44-t,.:t-96,. FIGURE3.4-2b5T.LUCIEUNIT1PITLIMITS,54EFPYCOOLDOWNANDIN5ERVICETEST1--'1---------_._---+--.---4.li._._..j-f--/--.I-=IMIN.BOLTl,JPTEMP!=RATURE80°Ft100"F/HRTOISOTHERMAL'.....1------..If-J--..>,---._fl'NSERVICEHYDROSTATICTEST+._,-_---,_":>.,,:1-+---IIf--1-----"IISOTHERMAL100°F/HR--..-fqLOWESTSERVICETEMPERATURE16S"F1.1==1.------.-.---:----1:=--------...-*1-1*!---so:II-I-.-jf.._.-'-I-+,=155703PSIA:m.*....500-.30°FIHR...._.....-t-:._.-::.::::::.400FIHR..-7L-..:--..-...._-_"..,,_*******...,*****_*T****..**,,***..***..--........**1;:**--+ALLOWABLECOOLDOWNRATES-_.-..50FIHRt-,RATE,oF/HRTEMP.LIMIT.4F.-20<12530125-14540145*16050160-180100>180f(f)oCk':0..<t:C/)0..u.f0:::::J1500ill0:::0..0:::illN0:::::J(j)(f)ill0:::0..ailloozo100200300400Te-INDICATEDReSTEMPERATURE,OF500LimitingMaterial:LowerShellAxialWelds(Ht.#305424)LimitingARTValuesat54EFPY:1/4T,210cF3/4T,156°FST.LUCIE-UNIT13/44-23bAmendmentNo.4+,28,8-t,4G4,444,4-ge, ST. LUCIE - UNIT 1 3/4 4-23c Amendment No. 17, 28, 81, 104, 141, 196, DELETED ST. LUCIE - UNIT 1 3/4 4-59 Amendment No. 60, 81, 104, 132, REACTOR COOLANT SYSTEM POWER OPERATED RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.13 Two power operated relief valves (PORVs) shall be OPERABLE, with their setpoints selected to the low temperature mode of operation as follows: a. A setpoint of less than or equal to 350 psia shall be selected during heatup, cooldown and isothermal conditions when the temperature of any RCS cold leg is less than or equal to 200F. b. A setpoint of less than or equal to 530 psia shall be selected during heatup, cooldown and isothermal conditions when the temperature of any RCS cold leg is greater than 200F and less than or equal to 300F. APPLICABILITY: MODE 4 when the temperature of any RCS cold leg is less than or equal to 300F, MODE 5, and MODE 6 when the head is on the reactor vessel; and the RCS is not vented through greater than a 1.75 square inch vent. ACTION: a. With one PORV inoperable in MODE 4, restore the inoperable PORV to OPERABLE status within 7 days; or depressurize and vent the RCS through greater than a 1.75 square inch vent within the next 8 hours. b. With one PORV inoperable in MODES 5 or 6, either (1) restore the inoperable PORV to OPERABLE status within 24 hours, or (2) complete depressurization and venting of the RCS through greater than a 1.75 square inch vent within a total of 32 hours. c. With both PORVs inoperable, restore at least one PORV to operable status or complete depressurization and venting of the RCS through greater than a 1.75 square inch vent within 24 hours. d. With the RCS vented per ACTIONS a, b, or c, verify the vent pathway at least once per 31 days when the pathway is provided by a valve(s) that is locked, sealed, or otherwise secured in the open position; otherwise, verify the vent pathway every 12 hours. e. In the event either the PORVs or the RCS vent(s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or RCS vent(s) on the transient, and any corrective action necessary to prevent recurrence. f. The provisions of Specification 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.4.13 Each PORV shall be demonstrated OPERABLE by: a. Verifying the PORV isolation valve is open at least once per 72 hours; and b. Performance of a CHANNEL FUNCTION TEST, but excluding valve operation, at least once per 31 days; and c. Performance of a CHANNEL CALIBRATION at least once per 18 months. ST. LUCIE - UNIT 1 3/4 4-60 Amendment No. 60, 81, 104, REACTOR COOLANT SYSTEM REACTOR COOLANT PUMP - STARTING LIMITING CONDITION FOR OPERATION 3.4.14 If the steam generator temperature exceeds the primary temperature by more than 30F, the first idle reactor coolant pump shall not be started. APPLICABILITY: MODES 4# and 5. ACTION: If a reactor coolant pump is started when the steam generator temperature exceeds primary temperature by more than 30F, evaluate the subsequent transient to determine compliance with Specification 3.4.9.1. SURVEILLANCE REQUIREMENTS 4.4.14 Prior to starting a reactor coolant pump, verify that the steam generator temperature does not exceed primary temperature by more than 30F. # Reactor Coolant System Cold Leg Temperature is less than 300F. ST. LUCIE - UNIT 1 3/4 5-1 Amendment No. 157, 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) SAFETY INJECTION TANKS (SIT) LIMITING CONDITION FOR OPERATION 3.5.1 Each reactor coolant system safety injection tank shall be OPERABLE with: a. The isolation valve open, b. Between 1090 and 1170 cubic feet of borated water, c. A minimum boron concentration of 1900 ppm, and d. A nitrogen cover-pressure of between 230 and 280 psig. APPLICABILITY: MODES 1, 2 and 3.* ACTION: a. With one SIT inoperable due to boron concentration not within limits, or due to an inability to verify the required water volume or nitrogen cover-pressure, restore the inoperable SIT to OPERABLE status with 72 hours; otherwise, be in at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours. b. With one SIT inoperable due to reasons other than those stated in ACTION-a, restore the inoperable SIT to OPERABLE status within 24 hours; otherwise, be in at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours. SURVEILLANCE REQUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE: a. At least once per 12 hours by: 1. Verifying that the borated water volume and nitrogen cover-pressure in the tanks are within their limits, and 2. Verifying that each safety injection tank isolation valve is open.

With pressurizer pressure > 1750 psia.

ST. LUCIE - UNIT 1 3/4 5-3 Amendment No. 28, 139, 164, 177, EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION 3.5.2 Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of: a. One OPERABLE high-pressure safety injection (HPSI) pump, b. One OPERABLE low-pressure safety injection pump, c. An independent OPERABLE flow path capable of taking suction from the refueling water tank on a Safety Injection Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal, and d. One OPERABLE charging pump*. APPLICABILITY: MODES 1, 2 and 3**. ACTION: a. 1. With one ECCS subsystem inoperable only because its associated LPSI train is inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours. 2. With one ECCS subsystem inoperable for reasons other than condition a.1., restore the inoperable subsystem to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours. b. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.

One ECCS subsystem charging pump shall satisfy the flow path requirements of Specification 3.1.2.2.a or 3.1.2.2.d. The second ECCS subsystem charging pump shall satisfy the flow path requirements of Specification 3.1.2.2.b or 3.1.2.2.e. ** With pressurizer pressure > 1750 psia.

ST. LUCIE - UNIT 1 3/4 5-5 Amendment No. 26, 90, 153, 160, 164, 194, EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (continued) e. At least once per 18 months, during shutdown, by: 1. Verifying that each automatic valve in the flow paths actuates to its correct position on a Safety Injection Actuation Signal. 2. Verifying that each of the following pumps start automatically upon receipt of a Safety Injection Actuation Signal; a. High-Pressure Safety Injection Pumps. b. Low-Pressure Safety Injection Pumps. c. Charging Pumps. 3. Verifying that upon receipt of an actual or simulated Recirculation Actuation Signal: each low-pressure safety injection pump stops, each containment sump isolation valve opens, each refueling water tank outlet valve closes, and each safety injection system recirculation valve to the refueling water tank closes. f. By verifying that each of the following pumps develops the specified total developed head when tested pursuant to the Inservice Testing Program. 1. High-Pressure Safety Injection pumps. 2. Low-Pressure Safety Injection pumps. ST. LUCIE - UNIT 1 3/4 5-8 Amendment No. 28, 209, EMERGENCY CORE COOLING SYSTEMS REFUELING WATER TANK LIMITING CONDITION FOR OPERATION 3.5.4 The refueling water tank shall be OPERABLE with: a. A minimum contained volume 477,360 gallons of borated water, b. A minimum boron concentration of 1900 ppm, c. A maximum water temperature of 100F, d. A minimum water temperature of 55F when in MODES 1 and 2, and e. A minimum water temperature of 40F when in MODES 3 and 4 APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With the refueling water tank inoperable, restore the tank to OPERABLE status within 1 hour or be in at least HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.5.4 The RWT shall be demonstrated OPERABLE: a. At least once per 7 days by: 1. Verifying the water level in the tank, and 2. Verifying the boron concentration of the water. b. At least once per 24 hours by verifying the RWT temperature. ST. LUCIE - UNIT 1 3/4 6-12 Amendment No. CONTAINMENT SYSTEMS INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION 3.6.1.4 Primary containment internal pressure shall be maintained between -0.7 and +0.5 psig. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With the containment internal pressure outside of the limits above, restore the internal pressure to within the limits within 1 hour or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.6.1.4 The primary containment internal pressure shall be determined to be within the limits at least once per 12 hours. ST. LUCIE - UNIT 1 3/4 7-3 Amendment No. 166, TABLE 4.7-1 STEAM LINE SAFETY VALVES PER LOOP VALVE NUMBER LIFT SETTING* Header A Header B a. 8201 8205 > 955.3 psig and < 1015.3 psig b. 8202 8206 > 955.3 psig and < 1015.3 psig c. 8203 8207 > 955.3 psig and < 1015.3 psig d. 8204 8208 > 955.3 psig and < 1015.3 psig e. 8209 8213 > 994.1 psig and < 1046.1 psig f. 8210 8214 > 994.1 psig and < 1046.1 psig g. 8211 8215 > 994.1 psig and < 1046.1 psig h. 8212 8216 > 994.1 psig and < 1046.1 psig _________________ * +/-3% for valves a through d and +2%/-3% for valves e through h ST. LUCIE - UNIT 1 3/4 7-6 Amendment No. PLANT SYSTEMS CONDENSATE STORAGE TANK LIMITING CONDITION FOR OPERATION 3.7.1.3 The condensate storage tank shall be OPERABLE with a minimum contained volume of 153,400 gallons. APPLICABILITY: MODES 1, 2 and 3. ACTION: With the condensate storage tank inoperable, restore the condensate storage tank to OPERABLE status within 4 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.7.1.3 The condensate storage tank shall be demonstrated OPERABLE at least once per 12 hours by verifying the water level. ST. LUCIE - UNIT 1 3/4 8-1 Amendment No. 103, 112, 138, 170, 180, 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE: a. Two physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system, and b. Two separate and independent diesel generator sets each with: 1. Engine-mounted fuel tanks containing a minimum of 152 gallons of fuel, 2. A separate fuel storage system containing a minimum of 19,000 gallons of fuel, and 3. A separate fuel transfer pump. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: a. With one offsite circuit of 3.8.1.1.a inoperable, except as provided in Action f. below, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1.a within 1 hour and at least once per 8 hours thereafter. Restore the offsite circuit to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and COLD SHUTDOWN within the following 30 hours. b. With one diesel generator of 3.8.1.1.b inoperable, demonstrate the OPERABILITY of the A.C. sources by performing Surveillance Requirement 4.8.1.1.1.a within 1 hour and at least once per 8 hours thereafter; and if the EDG became inoperable due to any cause other than an inoperable support system, an independently testable component, or preplanned preventative maintenance or testing, demonstrate the OPERABILITY of the remaining OPERABLE EDG by performing Surveillance Requirement 4.8.1.1.2.a.4 within 8 hours, unless it can be confirmed that the cause of the inoperable EDG does not exist on the remaining EDG*; restore the diesel generator to OPERABLE status within 14 days or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. Additionally, within 4 hours from the discovery of concurrent inoperability of required redundant feature(s) (including the steam driven auxiliary feed pump in MODE 1, 2, and 3), declare required feature(s) supported by the inoperable EDG inoperable if its redundant required feature(s) is inoperable.

If the absence of any common-cause failure cannot be confirmed, this test shall be completed regardless of when the inoperable EDG is restored to OPERABILITY.

ST. LUCIE - UNIT 1 3/4 8-6 Amendment No. 53, 103, ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b) Verifying the diesel starts on the auto-start signal****, energizes the emergency busses with permanently connected loads within 10 seconds, energizes the auto-connected shutdown loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads. After energization, the steady-state voltage and frequency of the emergency busses shall be maintained at 4160 + 210 volts and 60 + 0.6 Hz during this test. 4. Verifying that on an ESF actuation test signal (without loss-of-offsite power) the diesel generator starts**** on the auto-start signal, and: a) Within 10 seconds, generator voltage and frequency shall be 4160 + 420 volts and 60 + 1.2 Hz. b) Operates on standby for greater than or equal to 5 minutes. c) Steady-state generator voltage and frequency shall be 4160 + 210 volts and 60 + 0.6 Hz and shall be maintained throughout this test. 5. Simulating a loss-of-offsite power in conjunction with an ESF actuation test signal, and a) Verifying deenergization of the emergency busses and load shedding from the emergency busses. b) Verifying the diesel starts on the auto-start signal****, energizes the emergency busses with permanently connected loads within 10 seconds, energizes the auto-connected emergency (accident) loads through the auto-sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads. After energization, the steady-state voltage and frequency of the emergency busses shall be maintained at 4160 + 210 volts and 60 + 0.6 Hz during this test. c) Verifying that all automatic diesel generator trips, except engine overspeed and generator differential, are automatically bypassed upon loss of voltage on the emergency bus concurrent with a safety injection signal. **** This test may be conducted in accordance with the manufacturer's recommendations concerning engine prelube period. ST. LUCIE - UNIT 1 3/4 8-6a Amendment No. 103, 112, ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 6. Verifying that the diesel operates for at least 24 hours****. a) Within 10 seconds, generator voltage and frequency shall be 4160 + 420 volts and 60 + 1.2 Hz. b) Steady-state generator voltage and frequency shall be 4160 + 210 volts and 60 + 0.6 Hz and shall be maintained throughout this test. c) During the first 2 hours of this test, the diesel generator shall be loaded within a load band of 3800 to 3960 kW#, and d) During the remaining 22 hours of this test, the diesel generator shall be loaded within a load band of 3300 to 3500 kW#. 7. Verifying that the auto-connected loads do not exceed the 2000-hour rating of 3730 kW. 8. Verifying the diesel generator's capability to: a) Synchronize with the offsite power source while the generator is loaded with its emergency loads upon a simulated restoration of offsite power. b) Transfer its load to the offsite power source, and c) Be restored to its standby status. 9. Verifying that with the diesel generator operating in a test mode (connected to its bus), a simulated safety injection signal overrides the test mode by (1) returning the diesel generator to standby operation and (2) automatically energizes the emergency loads with offsite power. 10. Verifying that the fuel transfer pump transfers fuel from each fuel storage tank to the engine-mounted tanks to each diesel via the installed cross connection lines. 11. Verifying that the automatic load sequence timers are operable with the interval between each load block within + 1 second of its design interval. f. At least once per ten years or after any modification which could affect diesel generator independence by starting**** the diesel generators simultaneously, during shutdown, and verifying that the diesel generators accelerate to approximately 900 rpm in less than or equal to 10 seconds. # This band is meant as guidance to avoid routine overloading of the engine. Variations in load in excess of this band due to changing bus loads shall not invalidate this test. **** This test may be conducted in accordance with the manufacturer's recommendations concerning engine prelube period. ST. LUCIE - UNIT 1 3/4 8-7 Amendment No. 103, 138, 179, ELECTRICAL POWER SYSTEMS SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE: a. One circuit between the offsite transmission network and the onsite Class 1E distribution system, and b. One diesel generator set with: 1. Engine-mounted fuel tanks containing a minimum of 152 gallons of fuel, 2. A fuel storage system containing a minimum of 19,000 gallons of fuel, and 3. A fuel transfer pump. APPLICABILITY: MODES 5 and 6. ACTION: With less than the above minimum required A.C. electrical power sources OPERABLE, immediately suspend all operations involving CORE ALTERATIONS, operations involving positive reactivity additions that could result in loss of required SHUTDOWN MARGIN or boron concentration, movement of irradiated fuel, or crane operation with loads over the fuel storage pool. In addition, when in MODE 5 with the reactor coolant loops not filled, or in MODE 6 with the water level less than 23 feet above the top of irradiated fuel assemblies seated within the reactor vessel, immediately initiate corrective action to restore the required sources to OPERABLE status as soon as possible. SURVEILLANCE REQUIREMENTS 4.8.1.2.1 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1 and 4.8.1.1.2 except for requirement 4.8.1.1.2a.5. ST. LUCIE - UNIT 1 3/4 9-1 Amendment No. 102, 150, 171, 3/4.9 REFUELING OPERATIONS BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 With the reactor vessel head unbolted or removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling cavity shall be maintained within the limit specified in the COLR. APPLICABILITY: MODE 6*. ACTION: With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at > 40 gpm of greater than or equal to 1900 ppm boron or its equivalent to restore boron concentration to within limits. SURVEILLANCE REQUIREMENTS 4.9.1.1 The boron concentration limit shall be determined prior to: a. Removing or unbolting the reactor vessel head, and b. Withdrawal of any full length CEA in excess of 3 feet from its fully inserted position. 4.9.1.2 The boron concentration of the refueling cavity shall be determined by chemical analysis at least 3 times per 7 days with a maximum time interval between samples of 72 hours.

The reactor shall be maintained in MODE 6 when the reactor vessel head is unbolted or removed.

ST. LUCIE - UNIT 1 3/4 9-11 Amendment No. 193, REFUELING OPERATIONS SPENT FUEL STORAGE POOL LIMITING CONDITION FOR OPERATION 3.9.11 The Spent Fuel Pool shall be maintained with: a. The fuel storage pool water level greater than or equal to 23 ft over the top of irradiated fuel assemblies seated in the storage racks, and b. The fuel storage pool boron concentration greater than or equal to 1900 ppm. APPLICABILITY: Whenever irradiated fuel assemblies are in the spent fuel storage pool. ACTION: a. With the water level requirement not satisfied, immediately suspend all movement of fuel assemblies and crane operations with loads in the fuel storage areas and restore the water level to within its limit within 4 hours. b. With the boron concentration requirement not satisfied, immediately suspend all movement of fuel assemblies in the fuel storage pool and initiate action to restore the fuel storage pool boron concentration to within the required limit. c. The provisions of Specification 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS 4.9.11 The water level in the spent fuel storage pool shall be determined to be at least its minimum required depth at least once per 7 days when irradiated fuel assemblies are in the fuel storage pool. 4.9.11.1 Verify the fuel storage pool boron concentration is within limit at least once per 7 days. ST. LUCIE - UNIT 1 3/4 9-16 Amendment No. 24, 40, DELETED ST. LUCIE - UNIT 1 3/4 10-1 Amendment No. 27, 87, 3/4.10 SPECIAL TEST EXCEPTIONS SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of CEA worth and shutdown margin provided reactivity equivalent to at least the highest estimated CEA worth is available for trip insertion from OPERABLE CEA(s). APPLICABILITY: MODE 2. ACTION: a. With any full length CEA not fully inserted and with less than the above reactivity equivalent available for trip insertion, immediately initiate and continue boration at > 40 gpm of 1900 ppm boric acid solution or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored. b. With all full length CEAs inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at > 40 gpm of 1900 ppm boric acid solution or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored. SURVEILLANCE REQUIREMENTS 4.10.1.1 The position of each full length CEA required either partially or fully withdrawn shall be determined at least once per 2 hours. 4.10.1.2 Each CEA not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% withdrawn position within 7 days prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1. ST. LUCIE - UNIT 1 3/4 11-15 Amendment No. 59, 69, RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 202,500 curies noble gases (considered as Xe-133). APPLICABILITY: At all times. ACTION: a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 24 hours when radioactive materials are being added to the tank when reactor coolant system activity exceeds 518.9 Ci/gram DOSE EQUIVALENT XE-133. ST. LUCIE - UNIT 1 5-4 Amendment No. 34, 44, 76, 114, 152, DESIGN FEATURES 2.1.2 SHIELD BUILDING a. Minimum annular space = 4 feet b. Annulus nominal volume = 543,000 cubic feet c. Nominal outside height (measured from top of foundation base to the top of the dome) = 230.5 feet d. Nominal inside diameter = 148 feet e. Cylinder wall minimum thickness = 3 feet f. Dome minimum thickness = 2.5 feet g. Dome inside radius = 112 feet DESIGN PRESSURE AND TEMPERATURE 5.2.2 The containment vessel is designed and shall be maintained for a maximum internal pressure of 44 psig and a temperature of 264F. PENETRATIONS 5.2.3 Penetrations through the containment structure are designed and shall be maintained in accordance with the original design provisions contained in Sections 3.8.2.1.10 and 6.2.4 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements. 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 217 fuel assemblies. Each assembly shall consist of a matrix of Zircaloy clad fuel rods and/or poison rods, with fuel rods having an initial composition of natural or slightly enriched uranium dioxide (UO2) as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions. 5.3.1.1 Except for special test as authorized by the NRC, all fuel assemblies under control element assemblies shall be sleeved with a sleeve design previously approved by the NRC. ST. LUCIE - UNIT 1 5-5 Amendment No. 22, 27, 75, 91, 145, 163, 193, DESIGN 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 with 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 DESIGN 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 650F, except for the pressurizer which is 700F. 5.5 EMERGENCY CORE COOLING SYSTEMS 5.5.1 The emergency core cooling systems are designed and shall be maintained 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 5.6.1.a The spent fuel pool and spent fuel storage racks shall be maintained with: 1. keff less than 1.0 when fully flooded with unborated water, which includes an allowance for biases and uncertainties as described in Section 9.1 of the Updated Final Safety Analysis Report. 2. A nominal 10.12 inches center to center distance between fuel assemblies in Region 1 of the spent fuel pool storage racks, a nominal 10.30 inches center to center distance between fuel assemblies in the Region 1 cask pit storage rack, and a nominal 8.86 inches center to center distance between fuel assemblies in Region 2 of the spent fuel pool storage racks. ST. LUCIE - UNIT 1 5-6 Amendment No. 17, 22, 24, 34, 75, 91, 92, 102, 193, DESIGN FEATURES CRITICALITY (Continued) 3. A keff less than or equal to 0.95 when flooded with water containing 500 ppm boron, including an allowance for biases and uncertainties as described in Section 9.1 of the Updated Final Safety Analysis Report. 4. For storage of enriched fuel assemblies, requirements of Criteria in 5.6.1.a.1 and 5.6.1.a.3 shall be met by positioning fuel in the spent fuel storage racks consistent with the requirements of Specification 5.6.1.c. 5. Vessel Flux Reduction Assemblies (VFRAs), as defined in Section 9.1 of the Updated Final Safety Analysis Report, may be placed in any allowable fuel storage location. 6. Fissile material, not contained in a fuel assembly lattice, shall be stored in accordance with the requirements of Criteria in 5.6.1.a.1 and 5.6.1.a.3. b. The Region 1 cask pit storage rack shall contain neutron absorbing material (Boral) between stored fuel assemblies when installed in the spent fuel pool. c. Loading of spent fuel storage racks shall be controlled as described below. Criteria in 5.6.1.c.2 and 5.6.1.c.3 do not apply to the Region 1 cask pit storage rack. 1. The maximum initial planar average U-235 enrichment of any fuel assembly inserted in a spent fuel storage rack shall be less than or equal to 4.6 weight percent. 2. Fuel placed in Region 1 of the spent fuel pool storage racks shall comply with the storage patterns and alignment restrictions of Figure 5.6-1 and the minimum burnup requirements of Table 5.6-1, Table 5.6-2, and Table 5.6-3. 3. Fuel placed in Region 2 of the spent fuel pool storage racks shall comply with the storage patterns or allowed special arrangements of Figure 5.6-2 and the minimum burnup requirements of Table 5.6-1, Table 5.6-2, and Table 5.6-3. The allowed special arrangement for fresh fuel may be repeated, provided the applicable interface requirements specified by the safety analysis are met. 4. Any fuel satisfying criteria 5.6.1.c.1, including fresh fuel, may be placed in the Region 1 cask pit storage rack. d. The new fuel storage racks are designed for dry storage of unirradiated fuel assemblies having a maximum planar average U-235 enrichment less than or equal to 4.6 weight percent, while maintaining a keff of less than or equal to 0.98 under the most reactive condition. ST. LUCIE - UNIT 1 5-6b Amendment No. 91, 193, NOTES: 1. Numbering denotes fuel assembly type. Minimum burnup requirements for fuel assembly types 1, 2, 3, and 5 are defined in Table 5.6-1, Table 5.6-2, and Table 5.6-3. 2. The storage arrangement of fuel within a rack module may contain more than one pattern. Different fuel storage patterns within a rack module must be separated by an empty row of cells. 3. Interface restrictions on fuel placement apply between adjacent Region 1 rack modules. No interface restrictions apply between Region 1 racks and adjacent Region 2 racks. 4. Open cells within any checkerboard pattern are acceptable. FIGURE 5.6-1 Allowable Region 1 Storage Patterns and Fuel Alignments ALLOWEDREGION 1-TO-REGION 1FUEL ALIGNMENTS (see Note 3)155123321551155123322332GAP BETWEENADJACENT MODULESALLOWEDCHECKERBOARD STORAGEPATTERNS (See Notes 1 and 2)15512332ORORORPattern"A"Pattern"B" ST. LUCIE - UNIT 1 5-6c Amendment No. 193, NOTES: 1. Numbering denotes fuel assembly type. Minimum burnup requirements for fuel assembly types 3, 4, 6, and 7 are defined in Table 5.6-1, Table 5.6-2, and Table 5.6-3. 2. The storage arrangement within a rack module may contain more than one checkerboard pattern (patterns C, D, or E) provided an empty row of cells separates the patterns. 3. Fuel in peripheral cells need not contain CEAs. An empty row of cells separating these peripheral cells from the interior pattern is not required. Cells on the Region 2 periphery that form interior corners do not qualify for this arrangement. 4. Cells required to be empty as part of an allowed special arrangement may contain non-actinide material, such as an empty fuel assembly skeleton, as long as the material occupies no more than 75% of the cell volume. 5. Open cells within any checkerboard pattern are acceptable. 6. This arrangement is valid only for fresh assemblies with planar average enrichment 4.5 w/o. FIGURE 5.6-2 Allowable Region 2 Storage Patterns and Arrangements ALLOWEDCHECKERBOARD STORAGEPATTERNS (See Notes 1 and 2)RACK INTERFACERESTRICTIONS4774NONEOROR6666ALLOWED SPECIALARRANGEMENTS:Fresh Fuel Assemblies in Pattern "C" orPattern "E" racksFFFFFFFFPattern "C"Pattern "D"Pattern "E"= EMPTY CELL (See Note 4)F= FRESH FUEL ASSEMBLYInterior rack cellsmay be anyRegion 2 patternWall333333333(See Note 3)3333+ CEA+ CEA(See Note 6) ST. LUCIE - UNIT 1 5-6d Amendment No. 193, TABLE 5.6-1 Minimum Burnup as a Function of Enrichment for Non-Blanketed Assemblies* Coefficients Minimum Burnup (GWd/MTU) for Initial Enrichment Fuel Type Cooling Time A B C 1.9 w/o 2.5 w/o 3.0 w/o 3.8 w/o 1 0 years 0.00 9.31 -24.39 0.00 0.00 3.54 10.99 2 0 years 0.00 10.51 -22.35 0.00 3.93 9.18 17.59 3 0 years 0.00 10.97 -14.71 6.13 12.72 18.20 26.98 0 years -0.41 17.00 -21.39 9.43 18.55 25.92 37.29 12 years -0.54 16.22 -20.63 8.24 16.55 23.17 33.21 15 years -0.53 15.86 -20.07 8.15 16.27 22.74 32.54 4 20 years -0.46 15.11 -18.80 8.25 16.10 22.39 31.98 0 years -0.74 17.49 -19.72 10.84 19.38 26.09 36.06 5 5 years -0.56 15.64 -17.65 10.04 17.95 24.23 33.70 0 years -0.41 17.70 -17.97 14.18 23.72 31.44 43.37 12 years 0.04 13.10 -12.56 12.47 20.44 27.10 37.80 15 years 0.13 12.38 -11.83 12.16 19.93 26.48 37.09 6 20 years 0.26 11.56 -11.16 11.74 19.37 25.86 36.52 0 years -0.65 20.08 -16.52 19.29 29.62 37.87 50.40 12 years -0.65 17.76 -15.58 15.82 24.76 31.85 42.52 15 years -0.43 16.25 -13.84 15.48 24.10 31.04 41.70 7 20 years 0.12 12.90 -9.61 15.33 23.39 30.17 41.14 NOTES: 1. Enter this table for a non-blanketed assembly; defined as a fuel assembly without any designed axial variation in uranium-235 enrichment to control the axial burnup distribution. 2. To qualify in a fuel type, the calculated burnup of a fuel assembly must exceed the minimum burnup given in the table for the cooling time and initial enrichment of the fuel assembly. Alternatively, for fuel assembly characteristics between the increments depicted in the table, minimum burnup may be calculated by inserting the coefficients for the associated type and cooling time into the polynomial function: BU = A*E2 + B*E + C where: BU = Minimum Burnup (GWD/MTU) E = Initial Maximum Planar Average Enrichment (weight percent uranium-235) A, B, C = Coefficients 3. Interpolation between values of cooling time is not permitted. ___________________

Operated at 2700 MWt ST. LUCIE - UNIT 1 5-6e Amendment No. 193, TABLE 5.6-2 Minimum Burnup as a Function of Enrichment for Blanketed Assemblies* Coefficients Minimum Burnup (GWd/MTU) for Initial Enrichment Fuel Type Cooling Time A B C 2.5 w/o 3.0 w/o 3.5 w/o 4.0 w/o 4.5 w/o 1 0 years 0.00 9.31 -24.39 0.00 3.54 8.20 12.85 17.51 2 0 years 0.00 10.51 -22.35 3.93 9.18 14.44 19.69 24.95 3 0 years 0.00 10.97 -14.71 12.72 18.20 23.69 29.17 34.66 0 years -0.98 18.97 -22.54 18.76 25.55 31.85 37.66 42.98 5 years -0.74 16.54 -19.10 17.63 23.86 29.73 35.22 40.35 10 years -0.57 14.73 -16.49 16.77 22.57 28.08 33.31 38.25 15 years -0.46 13.54 -14.70 16.28 21.78 27.06 32.10 36.92 4 20 years -0.41 12.98 -13.74 16.15 21.51 26.67 31.62 36.37 0 years -0.74 17.49 -19.72 19.38 26.09 32.43 38.40 44.00 5 5 years -0.56 15.64 -17.65 17.95 24.23 30.23 35.95 41.39 0 years -0.24 14.23 -10.38 23.70 30.15 36.49 42.70 48.80 5 years -0.20 13.10 -9.24 22.26 28.26 34.16 39.96 45.66 10 years -0.23 12.70 -9.27 21.04 26.76 32.36 37.85 43.22 15 years -0.32 13.02 -10.48 20.07 25.70 31.17 36.48 41.63 6 20 years -0.47 14.08 -12.85 19.41 25.16 30.67 35.95 40.99 0 years -0.84 19.25 -13.42 29.46 36.77 43.67 50.14 56.20 5 years -0.72 17.40 -12.03 26.97 33.69 40.05 46.05 51.69 10 years -0.66 16.32 -11.46 25.22 31.56 37.58 43.26 48.62 15 years -0.67 16.00 -11.73 24.08 30.24 36.06 41.55 46.70 7 20 years -0.76 16.45 -12.81 23.57 29.70 35.46 40.83 45.83 NOTES: 1. Enter this table for a blanketed assembly; defined as a fuel assembly with designed axial variation in uranium-235 enrichment to control the axial burnup distribution. Use Table 5.6-1 to characterize blanketed assemblies having a central zone initial planar average enrichment of less than 2.5 w/o. 2. To qualify in a fuel type, the calculated burnup of a fuel assembly must exceed the minimum burnup given in the table for the cooling time and initial enrichment of the fuel assembly. Alternatively, for fuel assembly characteristics between the increments depicted in the table, minimum burnup may be calculated by inserting the coefficients for the associated type and cooling time into the polynomial function: BU = A*E2 + B*E + C where: BU = Minimum Burnup (GWD/MTU) E = Initial Maximum Planar Average Enrichment (weight percent uranium-235) A, B, C = Coefficients 3. Interpolation between values of cooling time is not permitted ___________________
Operated at 2700 MWt ST. LUCIE - UNIT 1 5-6f Amendment No. TABLE 5.6-3 Minimum Burnup as a Function of Enrichment for Blanketed Assemblies (Operated at 3020 MWt) Coefficients Minimum Burnup (GWd/MTU) for Initial Enrichment Fuel Type Cooling Time A B C 3.0 w/o 3.8 w/o 4.2 w/o 4.6 w/o 1 0 years 0.00 9.31 -19.39 8.54 15.99 19.71 23.44 2 0 years 0.00 10.51 -17.35 14.18 22.59 26.79 31.00 3 0 years 0.00 10.97 -9.71 23.20 31.98 36.36 40.75 0 years -0.98 18.97 -17.54 30.55 40.39 44.85 48.99 5 years -0.74 16.54 -14.10 28.86 38.07 42.31 46.33 10 years -0.57 14.73 -11.49 27.57 36.25 40.32 44.21 15 years -0.46 13.54 -9.70 26.78 35.11 39.05 42.85 4 20 years -0.41 12.98 -8.74 26.51 34.66 38.54 42.29 0 years -0.74 17.49 -14.72 31.09 41.06 45.68 50.08 5 5 years -0.56 15.64 -12.65 29.23 38.70 43.16 47.44 0 years -0.24 14.23 -5.38 35.15 45.23 50.15 55.00 5 years -0.20 13.10 -4.24 33.26 42.65 47.25 51.79 10 years -0.23 12.70 -4.27 31.76 40.67 45.01 49.28 15 years -0.32 13.02 -5.48 30.70 39.38 43.56 47.64 6 20 years -0.47 14.08 -7.85 30.16 38.87 43.00 46.97 0 years -0.84 19.25 -8.42 41.77 52.60 57.61 62.36 5 years -0.72 17.40 -7.03 38.69 48.69 53.35 57.77 10 years -0.66 16.32 -6.46 36.56 46.03 50.44 54.65 15 years -0.67 16.00 -6.73 35.24 44.40 48.65 52.69 7 20 years -0.76 16.45 -7.81 34.70 43.73 47.87 51.78 NOTES: 1. Enter this table for a blanketed assembly; defined as a fuel assembly with designed axial variation in uranium-235 enrichment to control the axial burnup distribution. 2. To qualify in a fuel type, the calculated burnup of a fuel assembly must exceed the minimum burnup given in the table for the cooling time and initial enrichment of the fuel assembly. Alternatively, for fuel assembly characteristics between the increments depicted in the table, minimum burnup may be calculated by inserting the coefficients for the associated type and cooling time into the polynomial function: BU = A*E2 + B*E + C where: BU = Minimum Burnup (GWD/MTU) E = Initial Maximum Planar Average Enrichment (weight percent uranium-235) A, B, C = Coefficients 3. Interpolation between values of cooling time is not permitted.

ST. LUCIE - UNIT 1 6-15b Amendment No. 69, 86, 123, 149, 187, 197, 206, ADMINISTRATIVE CONTROLS (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following: 1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM. 2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and 3) Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring. h. Containment Leakage Rate Testing Program A program to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50 Appendix J, Option B, as modified by approved exemptions. This program is in accordance with the guidelines contained in Regulatory Guide 1.163, Performance-Based Containment Leak-Test Program, as modified by the following exception(s): a) Bechtel Topical Report, BN-TOP-1 or ANS 56.8-1994 (as recommended by R.G. 1.163) will be used for type A testing. b) The first Type A test performed after the May 1993 Type A test shall be no later than May 2008. The peak calculated containment internal pressure for the design basis loss of coolant accident Pa, is 42.8 psig. The containment design pressure is 44 psig. The maximum allowed containment leakage rate, La, at Pa, shall be 0.50% of containment air weight per day. Leakage rate acceptance criteria are: a. Containment leakage rate acceptance criterion is < 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and C tests, < 0.75 La for Type A tests, and < 0.096 La for secondary containment bypass leakage paths. b. Air lock testing acceptance criteria are: 1) Overall air lock leakage rate is < 0.05 La when tested at > Pa. 2) For the personnel air lock door seal, leakage rate is < 0.01 La when pressurized to > 1.0 Pa. 3) For the emergency air lock door seal, leakage rate is < 0.01 La when pressurized to > 10 psig. ST. LUCIE - UNIT 1 6-19 Amendment No. 59, 69, 86, 123, 150, 163, 171, 191, ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (continued) 6.9.1.9 At least once every 5 years, an estimate of the actual population within 10 miles of the plant shall be prepared and submitted to the NRC. 6.9.1.10 At least once every 10 years, an estimate of the actual population within 50 miles of the plant shall be prepared and submitted to the NRC. 6.9.1.11 CORE OPERATING LIMITS REPORT (COLR) a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following: Specification 3.1.1.1 Shutdown Margin - Tavg Greater Than 200F Specification 3.1.1.2 Shutdown Margin - Tavg Less Than or Equal to 200F Specification 3.1.1.4 Moderator Temperature Coefficient Specification 3.1.3.1 Full Length CEA Position - Misalignment > 15 inches Specification 3.1.3.6 Regulating CEA Insertion Limits Specification 3.2.1 Linear Heat Rate Specification 3.2.3 Total Integrated Radial Peaking Factor - Specification 3.2.5 DNB Parameters Specification 3.9.1 Refueling Operations - Boron Concentration b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, as described in the following documents, approved Revisions and Supplements as specified in the COLR. 1. WCAP-11596-P-A, "Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988 (Westinghouse Proprietary) 2. NF-TR-95-01, "Nuclear Physics Methodology for Reload Design of Turkey Point & St. Lucie Nuclear Plants," Florida Power & Light Company, January 1995. 3. XN-75-27(A) [also issued as XN-NF-75-27(A)], "Exxon Nuclear Neutronic(s) Design Methods for Pressurized Water Reactors" 4. DELETED 5. XN-NF-82-21(P)(A), "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations" TrF ST. LUCIE - UNIT 1 6-19a Amendment No. 150, 163, 191, ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (continued) 6. DELETED 7. XN-75-32(P)(A), "Computational Procedure for Evaluating Fuel Rod Bowing" 8. DELETED 9. XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors" 10. XN-NF-621(P)(A), " Exxon Nuclear DNB Correlation for PWR Fuel Designs" 11. DELETED 12. XN-NF-82-06(P)(A), "Qualification of Exxon Nuclear Fuel for Extended Burnup" 13. ANF-88-133(P)(A), "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWd/MTU" 14. XN-NF-85-92 (P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results" 15. DELETED 16. DELETED 17. EMF-92-116(P)(A), "Generic Mechanical Design Criteria for PWR Fuel Design" 18. EMF-92-153(P)(A), "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel" 19. EMF-96-029(P)(A), Volumes 1 and 2, "Reactor Analysis System for PWRs Volume 1 - Methodology Description, Volume 2 - Benchmarking Results" ST. LUCIE - UNIT 1 6-19b Amendment No. 163, 171, 191, ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (continued) 20. EMF-1961(P)(A), "Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors" 21. EMF-2310(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurizer Water Reactors" 22. EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based" 23. EMF-2103(P)(A) Revision 0, "Realistic Large Break LOCA Methodology for Pressurized Water Reactors, Framatome ANP, Inc., April 2003}}

L-2010-078, Attachment 3, St. Lucie License Amendment Request Extended Power Uprate, Renewed Facility Operating License and Technical Specifications Markups and Clean Pages

Text

Navigation menu

Search