ML15301A253: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(5 intermediate revisions by the same user not shown)
Line 1: Line 1:
{{Adams
#REDIRECT [[L-2015-265, Cycle 22 Core Operating Limits Report]]
| number = ML15301A253
| issue date = 10/08/2015
| title = St. Lucie Unit 2 - Cycle 22 Core Operating Limits Report
| author name = Katzman E S
| author affiliation = Florida Power & Light Co
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000389
| license number =
| contact person =
| case reference number = L-2015-265
| document type = Fuel Cycle Reload Report, Letter
| page count = 19
}}
 
=Text=
{{#Wiki_filter:~L-2015-2650October 8, 2015 10 CFR 50.36iFPL.U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555Re: St. Lucie Unit 2Docket No. 50-3 89Cycle 22 Core Operating Limits ReportPursuant to St. Lucie Unit 2 Technical Specification (TS) 6.9.1.1 1..d, Florida Power & Light Company(FPL) is submitting the Core Operating Limits Report (COLR) for operating cycle 22.Technical Specification 6.9.1.11 .d requires that the COLR, including any mid-cycle revisions orsupplements, be provided to the NRC upon issuance for each reload cycle. Accordingly, attached is acopy of the St. Lucie Unit 2, Cycle 22 Core Operating Limits Report, Revision 1.Please contact us if there are any questions regarding this submittal.Very truly yours,Eric S. KatzmanLicensing ManagerSt. Lucie PlantESK/KWFAttachment -"St. Lucie Unit 1, Cycle 22 Core Operating Limits Report"cc: USNRC Regional Administrator, Region IIUSNRC Senior Resident Inspector, St. Lucie Nuclear PlantFlorida Power & Light Company6501 S. Ocean Drive, Jensen Beach, FL 34957 L-201 5-265AttachmentPage 1 of 18ST. LUCIE UNIT 2, CYCLE 22CORE OPERATING LIMITS REPORTRevision ISt. Lucie Unit 2 Cycle 22 COLR Rev. I Page 1 of ISSt, Lucie Unit 2 Cycle 22 COLRRev. 1Page I of 18 L-201 5-265AttachmentPage 2 of 18Table of ContentsDescription Pa~geg1.0 Introduction 32.0 Core Operating Limits 42.1 Moderator Temperature Coefficient 42.2 CEA Position -Misalignment > 15 inches 42.3 Regulating CEA Insertion Limits 42.4 Linear Heat Rate 42.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR 52.6 DNB Parameters 52.7 Refueling Operations -Boron Concentration 52.8 SHUTDOWN MARGIN -Tavg Greater Than 200 OF 52.9 SHUTDOWN MARGIN -Tavg Less Than or Equal To 200 OF 53.0 List of Approved Methods 14List of Tables and FiguresTitle PgTable 3.2-2 DNB Margin Limits 6Table 3.2-3 W(z) Factors as a Function of Core Height 7Fig 3.1-la Allowable Time To Realign CEA vs. Initial FT 8Fig 3.1-2 CEA Group Insertion Limits vs. THERMAL POWER 9Fig 3.2-1 Allowable Peak Linear Heat Rate vs. Burnup 10Fig 3.2-2 AXIAL SHAPE INDEX vs. Maximum Allowable Power Level 11Fig 3.2-3 Allowable Combinations of THERMAL POWER and FT 12Fig 3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER 13St. Lucie Unit 2 Cycle 22 COLRRe.IPg2of1Rev. 1Page 2 of 18 L-201 5-265AttachmentPage 3 of 1
 
==81.0 INTRODUCTION==
This CORE OPERATING LIMITS REPORT (COLR) describes the cycle-specific parameterlimits for operation of St. Lucie Unit 2. It contains the limits for the following as provided inSection 2.Moderator Temperature Coefficient,CEA Position -Misalignment > 15 Inches,Regulating CEA Insertion Limits,Linear Heat Rate,TOTAL INTEGRATED RADIAL PEAKING FACTOR -FTDNB Parameters,Refueling Operations -Boron Concentration,SHUTDOWN MARGIN -Tavg Greater Than 200 &deg;F,SHUTDOWN MARGIN -Tavg Less Than or Equal To 200 OF.This report also contains the necessary figures which give the limits for the above listedparameters.Terms appearing in capitalized type are DEFINED TERMS as defined in Section 1.0 of theTechnical Specifications.This report is prepared in accordance with the requirements of Technical Specification6.9.1.11.St_ Lucie Unit 2 Cycle 22 COLRRe.IPg3of1Rev. 1Page 3 of 18 L-201 5-265AttachmentPage 4 of 182.0 CORE OPERATING LIMITS2.1 Moderator Temperature Coefficient (TS 3.1.1.4)The moderator temperature coefficient (MTC) shall be less negative than -32 pcm/PFat RATED THERMAL POWER.2.2 CEA Position -Misaliqnment > 15 Inches (TS 3.1.3.1)The time constraints for full power operation with one full-length CEA misaligned fromany other CEA in its group by more than 15 inches are shown in Figure 3.1-1a.2.3 Regulatingq CEA Insertion Limits (TS 3.1.3.6)The regulating CEA groups shall be limited to the withdrawal sequence and to theinsertion limits shown on Figure 3.1-2, with CEA insertion between the Long TermSteady State Insertion Limits and the Power Dependent Insertion Limits restricted to:a. _< 4 hours per 24 hour interval,b. _< 5 Effective Full Power Days per 30 Effective Full Power Days, andc. _< 14 Effective Full Power Days per calendar year.2.4 Linear Heat Rate (TS 3.2.1)The linear heat rate shall not exceed the limits shown on Figure 3.2-1.The AXIAL SHAPE INDEX power dependent control limits are shown on Figure 3.2-2.Excore Detector Monitoringq SystemDuring operation, with the linear heat rate (LHR) being monitored by the ExcoreDetector Monitoring System, the AXIAL SHAPE INDEX shall be maintained within thelimits of Figure 3.2-2.Cycle specific W(z) curves to be used in the linear heat rate verification, to account forpower distribution transients, are shown in Table 3.2-3 as function of core height forvarious cycle burnups. For other cycle burnups, W(z) values may be interpolated orextrapolated as needed.If the margin to the linear heat rate has decreased as determined from the last twoflux maps, then the linear heat rate must be increased by an appropriate penalty. Avalue of 2% is chosen as the standard penalty. Linear heat rate margin decreasesthat are predicted to be greater than 2% per 31 Effective Full Power Days require thatpenalty factors of greater than 2%Y be used to increase the measured linear heat rateLHRM(z). The incremental penalty factors (in excess of margin decrease) areincluded in the W(z) function of Table 3.2-3.St. Lucie Unit 2 Cycle 22 COLRRe.IPe4of1Rev. 1Page 4 of 18 L-201 5-265AttachmentPage 5 of 18Incore Detector Monitoring SystemDuring operation, with the linear heat rate being monitored by the Incore DetectorMonitoring System, the Local Power Density alarm setpoints shall be adjusted to lessthan or equal to the limits shown on Figure 3.2-1.2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR -FT (TS 3.2.3)The calculated value of FrT shall be limited to _< 1.60.The power dependent FK limits are shown on Figure 3.2-3.2.6 DNB Parameters (TS 3.2.5)The following DNB-related parameters shall be maintained within the limits shown onTable 3.2-2:a. Cold Leg Temperatureb. Pressurizer Pressurec. AXIAL SHAPE INDEX2.7 Refuelingq Operations -Boron Concentration (TS 3.9.1)With the reactor vessel head closure bolts less than fully tensioned or with the headremoved, the boron concentration of all filled portions of the Reactor Coolant Systemand the refueling canal shall be maintained uniform and sufficient to ensure that themore restrictive of the following reactivity conditions is met:a. Either a Kefi of 0.95 or less, orb. A boron concentration of greater than or equal to 1900 ppm.2.8 SHUTDOWN MARGIN -T2.0 Greater Than 200 0F (TS 3.1.1.1)The SHUTDOWN MARGIN shall be greater than or equal to 3600 pcm.2.9 SHUTDOWN MARGIN Less Than or Eqiual To 200 &deg;F (TS 3.1.1.2)The SHUTDOWN MARGIN shall be greater than or equal to 3000 pcm.St. Lucie Unit 2 Cycle 22 COLRRe.IPg5of1Rev. 1Page 5 of 18 L-201 5-265AttachmentPage 6 of 18Table 3.2-2DNB MARGIN LIMITSPARAMETERFOUR REACTOR COOLANT.PUMPS OPERATINGCold Leg Temperature (narrow Range)Pressurizer Pressure*.AXIAL SHAPE INDEX5350F** < T < 551&deg;F2225 psia _< PPZR -< 2350 psia**Within the limits specified in Figure 3.2-4* Limit not applicable during either a THERMAL POWER ramp increase in excess of 5% perminute of RATED THERMAL POWER or a THERMAL POWER step increase of greater than10% of RATED THERMAL POWER.** Applicable only if power level _70% of RATED THERMAL POWER.St. Lucie Unit 2 Cycle 22 COLRRe.IPg6of1Rev. 1Page 6 of 18 L-201 5-265AttachmentPage 7 of 18COLR Table 3.2-3 -W(z) Factors as a Function of Core HeiglhtCore Height 100 EFPH 2000 EFPH 4000 EFPH 7000 EFPH 9000 (ft) (145 MTWD/MTU) (,2905 MWDIMTUI (5510 (10168 MWOIMTU) (13073 MWOIMTUI<1 &deg;59" 1,000 1,000 1.000 1.000 1.0001 .75 1,351 1.281 1.247 1,285 1.3851.91 1,337 1,269 1.240 1.257 1.2982.07 ~ 1.322 1.257 1,232 1.256 1 .2752.23 1,306 1,247 1.224 1.;244 1.2532.39 1.293 1.238 1.215 1.232 1.2342.55 1,279 1.229 1.207 1,218 1.2182.71 1:287 1.21 g 1.200 1,204 1,2042:88 1.267 1,211 1.1t93 1.190 1,1953.02 1....246 28118 .8 .83.18 t ,236 1.202 1.183 1.181 1.1843.34 1.227 1,198 1.1t79 1. 179 1,1793.50 1.218 1.193 1.175 1.175 1,1743:88 1,208 1.187 1,.171 1.172 1.1883.82 1,199 1.181. 1,187 1,168 1.1623.98 1.191 1.174 1,162 1.163 1,1574.14 1.182 1.187 1.188 1.158 1.1554,30 1.173 1 .1,9' l15,0 1,183 1 .1834,48 1.183 1.150 1.143 1,148- t,1494.62 1,153 1.141 1.138 1,139 1.1454.77 1,142 1 1.132 1.128 1,132 .1,1404,93 1,131 1.122 1.120 1.125 1.1355,9 1.121 .1.113 1.112 1.117 1.1298.25 1.it2 ~ 1 .105 1.103 1.108. 1.123"'5,41 ...... 1.103 1.097 ......1:095 1.102' 1,1225,57 1.095 1.092 1.092 1.102 1.127.73 1.094 1.092 1.093 1,110 1.1405,89 1 :095 1 095 1,099 1,.124. 1,1566:05 1.100 1.101 1.111 1.137 1.1726.21 1.105 1.107, 1.124 1.150 1.1876.37 1.109 1.I115 1.138 1.182 1.2016.52 1.-112 1 .126 1.151 1.174. 1.2146.68 1,115 .1.136 1.184 1.185 .1,2276.84 1; 121 1.1t47 1.1t77 1.197 1.2407.00 1.131 1.188 1.191 1.209 1.2517.16 1.142 1.170 1.205 1.221 1.2607.32 1,.153 1.i81 1.218 1.231 1.2867.48 1,183 .1.191 1:.230 1.241 1.2747.64 1.172. "1.200 1 241 1.2.49 1.2797.80 1.181 1.209 1.251 1.258 1.2827.968 1.189 1.217 1.260 1,282 1.2838.12. 1.197 1.223 1,268 1.288 1,2838.28 1.203 1.229 1.275- 1.289 1.2808.43 1.210 1.238 1.280 1.273 ~ 1.2778.89 1.218 1.246 1.256 1.280 1.2838.75 1.227 1 263 1.2.99 1.292 1.3078.9t 1.237 .1.289 1.323 1.309 ,1.3209.07 1,249 .1,318 I ;349 1,327 1,348923 1.2886 1.344 1.372 1.345 1.3679.39 1.299 1.370 1.392 1.366~ 1.3849.55 1.314 I1.398 1,41I3 1.389 1,4009).71 1.336 1.418 1.434 1.408 t.415>9.87 1.,o00 1.000 1:000 1,0o0 1.o000*Top and Bottom 15%V are excluded.**The above W(z) values are applicable to Full Power conditions. For Part Power application,divide these values by the power fraction or, alternately, divide the measured LHR by the power fraction.St. Lucie Unit 2 Cycle 22 COLRRev. 1Page 7 of 18 L-201 5-265AttachmentPage 8 of 181.621.60'In I IIp I I I Iliii Inl l il~ n qn l n l ql p~ ii l l ln l l 1 1 1 , ~ l i i i i l l l , l , , 1 1 1 l l 1 1 , , , , I I I ~ 1 1 1 1 , l ~ l l l m l ~ q 1 ! :,1 .5 8 1 I I I , IIIII II ' I II I rIIIII ' ''i'" 'I-.- ,ci)U,.'-.0rjII JI [ C C ''! [IIE I!'!! I : 111EIC IC '! C ::: :1:::III :' ClIr CI : CI': :1.56-J l l l l l l l l l l J l l l l l l J 1 1 1 1 1 I , , l l l l l ~ l l l r l l ll~IC C C Cl lIII ICCCCCC ICCIlIlI IIICCICCCCIC~C iCC::1.52-1.50-1.48IIII~~l~l~l[ ';I lC:r:ClC Cl:L[I~~ l l l l~~ :C:' l= l ;l l lL I I!I :1:1CC':: :CL :CIII:C :: CC C :C C:C:C:C,:'I]':EIIII L I :'r:'Ir i CC '::: C C i I1 I =IC CIICI===IIIC C ::I:CI C:C:IC: C=I ::, 'CC ::: CCII:IIIC:::C: :CIIC:I:I:C I:CICll=l~~l~llll~lll'CC:1.46-1.4I I I E l l l l ; I ; = = I l l l [ l = = ~ l = = l ; ; l~ l = = = l l = l;:11C C := ;1.42~o 5 1015202530354045 5055 606570 75Time at Full Power to Realign CEA, MinutesFIGURE 3.1-1aAllowable Time to Realign CEA vs. Initial FmSt. Lucie Unit 2 Cycle 22 COLRRe.IPe8of8Rev. 1Page 8 of 18 L-201 5-265AttachmentPage 9 of 180.$0 E" --- " o ,W) 0.300a. O , -.. ..I-0.10Gop No.ooIL I I O7T I I .Io 18 ) (16 5.)(7 )() {3)(0.) (16 5.)(72 0r # I I 7I I I I I(136) (100.0) (81.6) (54.4) (27.2) (0)4 2GroupNo. I I1I 1 1I1I I 1I 1! I(136) (100.0) (01.6) (54.4) (27.2) (0) (135) (100.0) (01.6) (54.4) (27.2) (0)CEA GROUP POSITION(INCHES WITHDRAWN)FIGURE 3.1-2CEA Group Insertion Limits vs. THERMAL POWERSt. Lucie Unit 2 Cycle 22 COLRRe.IPe of8Rev. 1Page 9 of 18 L-201 5-265AttachmentPage 10 of 1814.013.513.012.5wn 12.5U)11.0UNA ;CEP] ABLE OPER AC BLE &#xa2;PERATIrONBOLCycle LifeEOL(Fuel + Clad + Moderator)FIGURE 3.2-1Allowable Peak Linear Heat Rate vs. BurnupSt. Lucie Unit 2 Cycle 22 COLR Rv ae1 f1Rev. 1Page 10 of 18 L-201 5-265AttachmentPage 11 of 181.101.000.90a1_.-o 0.80-o 0.70SI-0.40 F-0.7-0.5 -0.3 -0.1 0.1 0.3Peripheral AXIAL SHAPE INDEX0.5 0.7(Not Applicable Below 40% Power)FIGURE 3.2-2AXIAL SHAPE INDEX vs. Maximum Allowable Power LevelNote: AXIAL SHAPE INDEX limits for Linear Heat Rate when using ExcoreDetector Monitoring SystemSt. Lucie Unit 2 Cycle 22 COLR Rv ae1 f1Rev. 1Page 11 of 18 L-201 5-265AttachmentPage 12 of 181.1.I"0-.14.)U(Uiii~ 11II:El0....., '', '',' ','' " -'' ,'', '', UN C E T B E-F': ---:. ..---'- -, '... ..~! ... .--" OPERATION" .:' i ' '' :" .... ' '. ' ' ' ' ".. .... ............... ........ ......... .......! ! ..... ! ! !"ACCEPTABLE""'..... : Y ; : ...... OP" RA[ ION; : ;' ;....I :::::i::i / ::: :::::::::::::::::::REG:::::O0:U.1.5 1. 1.6 1. 1.7Measured FrTFIGURE 3.2-3Allowable Combinations of THERMAL POWER and FrT(The expression specified in the Figure may be used for FJ at other power levels)1.St Lucie Unit 2 Cycle 22 COLR Rev. I ae11f1Page 12 of 18 L-201 5-265AttachmentPage 13 of 181.101.00L0.900.80-I-I-c 0.60U-c0.40UI IA ~E1AB T E_- -CEPfrABE-Ip O-----------------!,-0.7-0.5-0.3-0.10.1 0.30.50.7Peripheral AXIAL SHAPE INDEX (Y1)(Not Applicable Below 40% Power)FIGURE 3.2-4AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER(Four Reactor Coolant Pumps Operating)(AXIAL SHAPE INDEX limits for DNB)St. Lucie Unit 2 Cycle 22 COLR Rv ae1 f1Rev. 1Page t3 of 18 L-201 5-265AttachmentPage 14 of 183.0 LIST OF APPROVED METHODSThe analytical methods used to determine the core operating limits are those previouslyapproved by the NRC, and are listed below.1. WCAPR-1 1596-P-A, "Qualification of the PHOEN IX-P/ANC Nuclear Design System forPressurized 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 (NRC SERdated June 9, 1995), & Supplement 1, August 19973. Deleted.4. Deleted.5. CENPD-275-P, Revision 1-P-A, "C-E Methodology for Core Designs ContainingGadolinia-Urania Burnable Absorbers," May 1988, & Revision 1-P Supplement 1-P-A,April 19996. Deleted.7. Deleted.8. CEN-123(F)-P, "Statistical Combination of Uncertainties Methodology Part 1: CECalculated Local Power Density and Thermal Margin/Low Pressure LSSS for St.Lucie Unit 1," December 19799. Deleted.10. CEN-123(F)-P, "Statistical Combination of Uncertainties Methodology Part 3: CECalculated Departure from Nucleate Boiling and Linear Heat Rate Limiting Conditionsfor Operation for St. Lucie Unit 1," February 198011. CEN-191(B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert CliffsUnits 1 and 2," December 198112. Letter, J. W. Miller (NRC) to J. R. Williams, Jr. (FPL), Docket No. 50-389, RegardingUnit 2 Cycle 2 License Approval (Amendment No. 8 to NPF-1 6 and SER), November9, 1984 (Approval of CEN-123(F)-P (three parts) and CEN-191(B)-P)13. Deleted.14. Letter, J. A. Norris (NRC) to J. H. Goldberg (FPL), Docket No. 50-389, "St. Lucie Unit2 -Change to Technical Specification Bases Sections '2.1.1 Reactor Core' and'3/4.2.5 DNB Parameters' (TAC No. M87722)," March 14, 1994 (Approval of CEN-371 (F)-P)St. Lucie Unit 2 Cycle 22 COLR Rv ae1 f1Rev. 1Page 14 of 18 L-201 5-265AttachmentPage 15 of 1815. Deleted.16. Deleted.17. Deleted.18. Deleted.19. CENPD-225-P-A, "Fuel and Poison Rod Bowing," June 198320. CENPD-1 39-P-A, "C-E Fuel Evaluation Model Topical Report," July 197421. CEN-161(B)-P-A, "Improvements to Fuel Evaluation Model," August 198922. CEN-161(B)-P, Supplement 1-P-A, "Improvements to Fuel Evaluation Model,"January 199223. CENPD-1 32, Supplement 3-P-A, "Calculative Methods for the C-E Large Break LOCAEvaluation Model for the Analysis of C-E and _W Designed NSSS," June 198524. CENPD-133, Supplement 5-A, "CEFLASH-4A, A FORTRAN77 Digital ComputerProgram for Reactor Blowdown Analysis," June 198525. CENPD-134, Supplement 2-A, "COMPERC-II, a Program for Emergency Refill-Reflood of the Core," June 198526. CENPD-135-P, Supplement 5, "STRIKIN-II, A Cylindrical Geometry Fuel Rod HeatTransfer Program," April 197727. Letter, R. L. Baer (NRC) to A: E. Scherer (CE), "Evaluation of Topical Report CENPD-135, Supplement #5," September 6, 197828. CENPD-1 37, Supplement 1-P, "Calculative Methods for the C-E Small Break LOCAEvaluation Model," January 197729. CENPD-1 33, Supplement 3-P, "CEFLASH-4AS, A Computer Program for the ReactorBlowdown Analysis of the Small Break Loss of Coolant Accident," January 197730. Letter, K. Kniel (NRC) to A. E. Scherer (CE), "Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-1 37, Supplement 1-P," September 27, 197731. CENPD-1 38, Supplement 2-P, "PARCH, A FORTRAN-lV Digital Program to EvaluatePool Boiling, Axial Rod and Coolant Heatup," January 197732. Letter, C. Aniel (NRC) to A. E. Scherer (CE), "Evaluation of Topical Report CENPD-138, Supplement 2-P," April 10, 1978St. Lucie Unit 2 Cycle 22 COLR Rv ae1 f1Rev. 1Page 15 of 18 L-201 5-265AttachmentPage 16 of 1833. Letter, W. H. Bohike (FPL) to Document Control Desk (NRC), "St. Lucie Unit 2,Docket No. 50-389, Proposed License Amendment, MTC Changqe from -27 pcm to -30 pcrn," L-91-325, December 17, 199134. Letter, J. A. Norris (NRC) to J. H. Goldberg (FPL), "St. Lucie Unit 2 -Issuance ofAmendment Re: Moderator Temperature Coefficient (TAC No. M82517)," July 15,199235. Letter, J. W. Williams, Jr. (FPL) to D. G. Eisenhut (NRC), "St. Lucie Unit No. 2,Docket No. 50-389, Proposed License Amendment, Cycle 2 Reload," L-84-148, June4, 198436. Letter, J. R. Miller (NRC) to J. W. Williams, Jr. (FPL), Docket No. 50-389, RegardingUnit 2 Cycle 2 License Approval (Amendment No. 8 to NPF-1 6 and SER), November9, 1984 (Approval of Methodology contained in L-84-148)37. Deleted.38. Deleted.39. Deleted.40. Deleted.41. Deleted.42. CEN-348(B)-P-A, Supplement 1-P-A, "Extended Statistical Combination ofUncertainties," January 199743. CEN-372-P-A, "Fuel Rod Maximum Allowable Gas Pressure," May 199044. Deleted.45. Deleted.46. Deleted.47. Deleted.48. CEN-396(L)-P, "Verification of the Acceptability of a 1-Pin Burnup Limit of 60MWD/KG for St. Lucie Unit 2," November 1989 (NRC SER dated October 18, 1991,Letter J. A. Norris (NRC) to J. H. Goldberg (FPL), TAC No. 75947)49. CENPD-269-P, Rev. l-P, 'Extended Burnup Operation of Combustion EngineeringPWR Fuel," July 198450. CEN-289(A)-P, "Revised Rod Bow Penalties for Arkansas Nuclear One Unit 2,"December 1984 (NRC SER dated December 21, 1999, Letter K. N. Jabbour (NRC) toT. F. Plunkett (FPL), TAC No. MA4523)St. Lucie Unit 2 Cycle 22 COLR Rv ae1 f1Rev. 1Page 16 of 18 L-201 5-265AttachmentPage 17 of 1851. CENPD-1 37, Supplement 2-P-A, "Calculative Methods for the ABB CE Small BreakLOCA Evaluation Model," April 199852. CENPD-140-A, "Description of the CONTRANS Digital Computer Code forContainment Pressure and Temperature Transient Analysis," June 197653. Deleted.54. Deleted.55. CENPD-387-P-A, Revision 000, "ABB Critical Heat Flux Correlations for PWR Fuel,"May 200056. CENPD-132, Supplement 4-P-A, "Calculative Methods for the CE Nuclear PowerLarge Break LOCA Evaluation Model," March 200157. CENPD-1 37, Supplement 2-P-A, "Calculative Methods for the ABB CE Small BreakLOCA Evaluation Model," April 199858. CENPD-404-P-A, Rev. 0, "Implementation of ZIRLOTM Cladding Material in CENuclear Power Fuel Assembly Designs," November 200159. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology"' July 198560. WCAP-10216-P-A, Revision lA, "Relaxation of Constant Axial Offset Control; FQSurveillance Technical Specification," February 199461. WCAP-1 1397-P-A, (Proprietary), "Revised Thermal Design Procedure," April 198962. WCAP-14565-P-A, (Proprietary), "VIPRE-01 Modeling and Qualification forPressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis," October199963. WCAP-14565-P-A, Addendum 1-A, Revision 0, "Addendum 1Ito WCAP-14565-P-AQualification of ABB Critical Heat Flux Correlations with VIPRE-01 Code," August200464. Letter, W. Jefferson, Jr. (FPL) to Document Control Desk (USNRC), "St. Lucie Unit 2Docket No. 50-389: Proposed License Amendment WCAP-9272 Reload Methodologyand Implementing 30% Steam Generator Tube Plugging Limit," L-2003-276,December, 2003 (NRC SER dated January 31, 2005, Letter B. T. Moroney (NRC) toJ. A. Stall (FPL), TAC No. MC1566)65. WCAP-14882-P-A, Rev. 0, "RETRAN-02 Modeling and Qualification forWestinghouse Pressurized Water Reactor Non-LOCA Safety Analyses," April 1999.St. Lucie Unit 2 Cycle 22 COLR Rv ae1 f1Rev. 1Page 17 of 18 L-201 5-265AttachmentPage 18 of 1866. WCAP-7908-A, Rev. 0, "FACTRAN-A FORTRAN IV Code for Thermal Transients in aUO2 Fuel Rod," December 1989.67. WCAP-7979-P-A, Rev. 0, "TWINKLE -A Multi-Dimensional Neutron KineticsComputer Code," January 1975.68. WCAP-7588, Rev. 1-A, "An Evaluation of the Rod Ejection Accident in WestinghousePressurized Water Reactors Using Spatial Kinetics Methods," January 1975.69. WCAP-1261 0-P-A & CENPD-404-P-A, Addendum 2-A, "Westinghouse CladCorrosion Model for ZIRLO and Optimized ZIRLO," October 2013.St. Lucie Unit 2 Cycle 22 COLR Rv ae1 f1Rev. 1Page 18 of 18
~L-2015-2650October 8, 2015 10 CFR 50.36iFPL.U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555Re: St. Lucie Unit 2Docket No. 50-3 89Cycle 22 Core Operating Limits ReportPursuant to St. Lucie Unit 2 Technical Specification (TS) 6.9.1.1 1..d, Florida Power & Light Company(FPL) is submitting the Core Operating Limits Report (COLR) for operating cycle 22.Technical Specification 6.9.1.11 .d requires that the COLR, including any mid-cycle revisions orsupplements, be provided to the NRC upon issuance for each reload cycle. Accordingly, attached is acopy of the St. Lucie Unit 2, Cycle 22 Core Operating Limits Report, Revision 1.Please contact us if there are any questions regarding this submittal.Very truly yours,Eric S. KatzmanLicensing ManagerSt. Lucie PlantESK/KWFAttachment -"St. Lucie Unit 1, Cycle 22 Core Operating Limits Report"cc: USNRC Regional Administrator, Region IIUSNRC Senior Resident Inspector, St. Lucie Nuclear PlantFlorida Power & Light Company6501 S. Ocean Drive, Jensen Beach, FL 34957 L-201 5-265AttachmentPage 1 of 18ST. LUCIE UNIT 2, CYCLE 22CORE OPERATING LIMITS REPORTRevision ISt. Lucie Unit 2 Cycle 22 COLR Rev. I Page 1 of ISSt, Lucie Unit 2 Cycle 22 COLRRev. 1Page I of 18 L-201 5-265AttachmentPage 2 of 18Table of ContentsDescription Pa~geg1.0 Introduction 32.0 Core Operating Limits 42.1 Moderator Temperature Coefficient 42.2 CEA Position -Misalignment > 15 inches 42.3 Regulating CEA Insertion Limits 42.4 Linear Heat Rate 42.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR 52.6 DNB Parameters 52.7 Refueling Operations -Boron Concentration 52.8 SHUTDOWN MARGIN -Tavg Greater Than 200 OF 52.9 SHUTDOWN MARGIN -Tavg Less Than or Equal To 200 OF 53.0 List of Approved Methods 14List of Tables and FiguresTitle PgTable 3.2-2 DNB Margin Limits 6Table 3.2-3 W(z) Factors as a Function of Core Height 7Fig 3.1-la Allowable Time To Realign CEA vs. Initial FT 8Fig 3.1-2 CEA Group Insertion Limits vs. THERMAL POWER 9Fig 3.2-1 Allowable Peak Linear Heat Rate vs. Burnup 10Fig 3.2-2 AXIAL SHAPE INDEX vs. Maximum Allowable Power Level 11Fig 3.2-3 Allowable Combinations of THERMAL POWER and FT 12Fig 3.2-4 AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER 13St. Lucie Unit 2 Cycle 22 COLRRe.IPg2of1Rev. 1Page 2 of 18 L-201 5-265AttachmentPage 3 of 1
 
==81.0 INTRODUCTION==
This CORE OPERATING LIMITS REPORT (COLR) describes the cycle-specific parameterlimits for operation of St. Lucie Unit 2. It contains the limits for the following as provided inSection 2.Moderator Temperature Coefficient,CEA Position -Misalignment > 15 Inches,Regulating CEA Insertion Limits,Linear Heat Rate,TOTAL INTEGRATED RADIAL PEAKING FACTOR -FTDNB Parameters,Refueling Operations -Boron Concentration,SHUTDOWN MARGIN -Tavg Greater Than 200 &deg;F,SHUTDOWN MARGIN -Tavg Less Than or Equal To 200 OF.This report also contains the necessary figures which give the limits for the above listedparameters.Terms appearing in capitalized type are DEFINED TERMS as defined in Section 1.0 of theTechnical Specifications.This report is prepared in accordance with the requirements of Technical Specification6.9.1.11.St_ Lucie Unit 2 Cycle 22 COLRRe.IPg3of1Rev. 1Page 3 of 18 L-201 5-265AttachmentPage 4 of 182.0 CORE OPERATING LIMITS2.1 Moderator Temperature Coefficient (TS 3.1.1.4)The moderator temperature coefficient (MTC) shall be less negative than -32 pcm/PFat RATED THERMAL POWER.2.2 CEA Position -Misaliqnment > 15 Inches (TS 3.1.3.1)The time constraints for full power operation with one full-length CEA misaligned fromany other CEA in its group by more than 15 inches are shown in Figure 3.1-1a.2.3 Regulatingq CEA Insertion Limits (TS 3.1.3.6)The regulating CEA groups shall be limited to the withdrawal sequence and to theinsertion limits shown on Figure 3.1-2, with CEA insertion between the Long TermSteady State Insertion Limits and the Power Dependent Insertion Limits restricted to:a. _< 4 hours per 24 hour interval,b. _< 5 Effective Full Power Days per 30 Effective Full Power Days, andc. _< 14 Effective Full Power Days per calendar year.2.4 Linear Heat Rate (TS 3.2.1)The linear heat rate shall not exceed the limits shown on Figure 3.2-1.The AXIAL SHAPE INDEX power dependent control limits are shown on Figure 3.2-2.Excore Detector Monitoringq SystemDuring operation, with the linear heat rate (LHR) being monitored by the ExcoreDetector Monitoring System, the AXIAL SHAPE INDEX shall be maintained within thelimits of Figure 3.2-2.Cycle specific W(z) curves to be used in the linear heat rate verification, to account forpower distribution transients, are shown in Table 3.2-3 as function of core height forvarious cycle burnups. For other cycle burnups, W(z) values may be interpolated orextrapolated as needed.If the margin to the linear heat rate has decreased as determined from the last twoflux maps, then the linear heat rate must be increased by an appropriate penalty. Avalue of 2% is chosen as the standard penalty. Linear heat rate margin decreasesthat are predicted to be greater than 2% per 31 Effective Full Power Days require thatpenalty factors of greater than 2%Y be used to increase the measured linear heat rateLHRM(z). The incremental penalty factors (in excess of margin decrease) areincluded in the W(z) function of Table 3.2-3.St. Lucie Unit 2 Cycle 22 COLRRe.IPe4of1Rev. 1Page 4 of 18 L-201 5-265AttachmentPage 5 of 18Incore Detector Monitoring SystemDuring operation, with the linear heat rate being monitored by the Incore DetectorMonitoring System, the Local Power Density alarm setpoints shall be adjusted to lessthan or equal to the limits shown on Figure 3.2-1.2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR -FT (TS 3.2.3)The calculated value of FrT shall be limited to _< 1.60.The power dependent FK limits are shown on Figure 3.2-3.2.6 DNB Parameters (TS 3.2.5)The following DNB-related parameters shall be maintained within the limits shown onTable 3.2-2:a. Cold Leg Temperatureb. Pressurizer Pressurec. AXIAL SHAPE INDEX2.7 Refuelingq Operations -Boron Concentration (TS 3.9.1)With the reactor vessel head closure bolts less than fully tensioned or with the headremoved, the boron concentration of all filled portions of the Reactor Coolant Systemand the refueling canal shall be maintained uniform and sufficient to ensure that themore restrictive of the following reactivity conditions is met:a. Either a Kefi of 0.95 or less, orb. A boron concentration of greater than or equal to 1900 ppm.2.8 SHUTDOWN MARGIN -T2.0 Greater Than 200 0F (TS 3.1.1.1)The SHUTDOWN MARGIN shall be greater than or equal to 3600 pcm.2.9 SHUTDOWN MARGIN Less Than or Eqiual To 200 &deg;F (TS 3.1.1.2)The SHUTDOWN MARGIN shall be greater than or equal to 3000 pcm.St. Lucie Unit 2 Cycle 22 COLRRe.IPg5of1Rev. 1Page 5 of 18 L-201 5-265AttachmentPage 6 of 18Table 3.2-2DNB MARGIN LIMITSPARAMETERFOUR REACTOR COOLANT.PUMPS OPERATINGCold Leg Temperature (narrow Range)Pressurizer Pressure*.AXIAL SHAPE INDEX5350F** < T < 551&deg;F2225 psia _< PPZR -< 2350 psia**Within the limits specified in Figure 3.2-4* Limit not applicable during either a THERMAL POWER ramp increase in excess of 5% perminute of RATED THERMAL POWER or a THERMAL POWER step increase of greater than10% of RATED THERMAL POWER.** Applicable only if power level _70% of RATED THERMAL POWER.St. Lucie Unit 2 Cycle 22 COLRRe.IPg6of1Rev. 1Page 6 of 18 L-201 5-265AttachmentPage 7 of 18COLR Table 3.2-3 -W(z) Factors as a Function of Core HeiglhtCore Height 100 EFPH 2000 EFPH 4000 EFPH 7000 EFPH 9000 (ft) (145 MTWD/MTU) (,2905 MWDIMTUI (5510 (10168 MWOIMTU) (13073 MWOIMTUI<1 &deg;59" 1,000 1,000 1.000 1.000 1.0001 .75 1,351 1.281 1.247 1,285 1.3851.91 1,337 1,269 1.240 1.257 1.2982.07 ~ 1.322 1.257 1,232 1.256 1 .2752.23 1,306 1,247 1.224 1.;244 1.2532.39 1.293 1.238 1.215 1.232 1.2342.55 1,279 1.229 1.207 1,218 1.2182.71 1:287 1.21 g 1.200 1,204 1,2042:88 1.267 1,211 1.1t93 1.190 1,1953.02 1....246 28118 .8 .83.18 t ,236 1.202 1.183 1.181 1.1843.34 1.227 1,198 1.1t79 1. 179 1,1793.50 1.218 1.193 1.175 1.175 1,1743:88 1,208 1.187 1,.171 1.172 1.1883.82 1,199 1.181. 1,187 1,168 1.1623.98 1.191 1.174 1,162 1.163 1,1574.14 1.182 1.187 1.188 1.158 1.1554,30 1.173 1 .1,9' l15,0 1,183 1 .1834,48 1.183 1.150 1.143 1,148- t,1494.62 1,153 1.141 1.138 1,139 1.1454.77 1,142 1 1.132 1.128 1,132 .1,1404,93 1,131 1.122 1.120 1.125 1.1355,9 1.121 .1.113 1.112 1.117 1.1298.25 1.it2 ~ 1 .105 1.103 1.108. 1.123"'5,41 ...... 1.103 1.097 ......1:095 1.102' 1,1225,57 1.095 1.092 1.092 1.102 1.127.73 1.094 1.092 1.093 1,110 1.1405,89 1 :095 1 095 1,099 1,.124. 1,1566:05 1.100 1.101 1.111 1.137 1.1726.21 1.105 1.107, 1.124 1.150 1.1876.37 1.109 1.I115 1.138 1.182 1.2016.52 1.-112 1 .126 1.151 1.174. 1.2146.68 1,115 .1.136 1.184 1.185 .1,2276.84 1; 121 1.1t47 1.1t77 1.197 1.2407.00 1.131 1.188 1.191 1.209 1.2517.16 1.142 1.170 1.205 1.221 1.2607.32 1,.153 1.i81 1.218 1.231 1.2867.48 1,183 .1.191 1:.230 1.241 1.2747.64 1.172. "1.200 1 241 1.2.49 1.2797.80 1.181 1.209 1.251 1.258 1.2827.968 1.189 1.217 1.260 1,282 1.2838.12. 1.197 1.223 1,268 1.288 1,2838.28 1.203 1.229 1.275- 1.289 1.2808.43 1.210 1.238 1.280 1.273 ~ 1.2778.89 1.218 1.246 1.256 1.280 1.2838.75 1.227 1 263 1.2.99 1.292 1.3078.9t 1.237 .1.289 1.323 1.309 ,1.3209.07 1,249 .1,318 I ;349 1,327 1,348923 1.2886 1.344 1.372 1.345 1.3679.39 1.299 1.370 1.392 1.366~ 1.3849.55 1.314 I1.398 1,41I3 1.389 1,4009).71 1.336 1.418 1.434 1.408 t.415>9.87 1.,o00 1.000 1:000 1,0o0 1.o000*Top and Bottom 15%V are excluded.**The above W(z) values are applicable to Full Power conditions. For Part Power application,divide these values by the power fraction or, alternately, divide the measured LHR by the power fraction.St. Lucie Unit 2 Cycle 22 COLRRev. 1Page 7 of 18 L-201 5-265AttachmentPage 8 of 181.621.60'In I IIp I I I Iliii Inl l il~ n qn l n l ql p~ ii l l ln l l 1 1 1 , ~ l i i i i l l l , l , , 1 1 1 l l 1 1 , , , , I I I ~ 1 1 1 1 , l ~ l l l m l ~ q 1 ! :,1 .5 8 1 I I I , IIIII II ' I II I rIIIII ' ''i'" 'I-.- ,ci)U,.'-.0rjII JI [ C C ''! [IIE I!'!! I : 111EIC IC '! C ::: :1:::III :' ClIr CI : CI': :1.56-J l l l l l l l l l l J l l l l l l J 1 1 1 1 1 I , , l l l l l ~ l l l r l l ll~IC C C Cl lIII ICCCCCC ICCIlIlI IIICCICCCCIC~C iCC::1.52-1.50-1.48IIII~~l~l~l[ ';I lC:r:ClC Cl:L[I~~ l l l l~~ :C:' l= l ;l l lL I I!I :1:1CC':: :CL :CIII:C :: CC C :C C:C:C:C,:'I]':EIIII L I :'r:'Ir i CC '::: C C i I1 I =IC CIICI===IIIC C ::I:CI C:C:IC: C=I ::, 'CC ::: CCII:IIIC:::C: :CIIC:I:I:C I:CICll=l~~l~llll~lll'CC:1.46-1.4I I I E l l l l ; I ; = = I l l l [ l = = ~ l = = l ; ; l~ l = = = l l = l;:11C C := ;1.42~o 5 1015202530354045 5055 606570 75Time at Full Power to Realign CEA, MinutesFIGURE 3.1-1aAllowable Time to Realign CEA vs. Initial FmSt. Lucie Unit 2 Cycle 22 COLRRe.IPe8of8Rev. 1Page 8 of 18 L-201 5-265AttachmentPage 9 of 180.$0 E" --- " o ,W) 0.300a. O , -.. ..I-0.10Gop No.ooIL I I O7T I I .Io 18 ) (16 5.)(7 )() {3)(0.) (16 5.)(72 0r # I I 7I I I I I(136) (100.0) (81.6) (54.4) (27.2) (0)4 2GroupNo. I I1I 1 1I1I I 1I 1! I(136) (100.0) (01.6) (54.4) (27.2) (0) (135) (100.0) (01.6) (54.4) (27.2) (0)CEA GROUP POSITION(INCHES WITHDRAWN)FIGURE 3.1-2CEA Group Insertion Limits vs. THERMAL POWERSt. Lucie Unit 2 Cycle 22 COLRRe.IPe of8Rev. 1Page 9 of 18 L-201 5-265AttachmentPage 10 of 1814.013.513.012.5wn 12.5U)11.0UNA ;CEP] ABLE OPER AC BLE &#xa2;PERATIrONBOLCycle LifeEOL(Fuel + Clad + Moderator)FIGURE 3.2-1Allowable Peak Linear Heat Rate vs. BurnupSt. Lucie Unit 2 Cycle 22 COLR Rv ae1 f1Rev. 1Page 10 of 18 L-201 5-265AttachmentPage 11 of 181.101.000.90a1_.-o 0.80-o 0.70SI-0.40 F-0.7-0.5 -0.3 -0.1 0.1 0.3Peripheral AXIAL SHAPE INDEX0.5 0.7(Not Applicable Below 40% Power)FIGURE 3.2-2AXIAL SHAPE INDEX vs. Maximum Allowable Power LevelNote: AXIAL SHAPE INDEX limits for Linear Heat Rate when using ExcoreDetector Monitoring SystemSt. Lucie Unit 2 Cycle 22 COLR Rv ae1 f1Rev. 1Page 11 of 18 L-201 5-265AttachmentPage 12 of 181.1.I"0-.14.)U(Uiii~ 11II:El0....., '', '',' ','' " -'' ,'', '', UN C E T B E-F': ---:. ..---'- -, '... ..~! ... .--" OPERATION" .:' i ' '' :" .... ' '. ' ' ' ' ".. .... ............... ........ ......... .......! ! ..... ! ! !"ACCEPTABLE""'..... : Y ; : ...... OP" RA[ ION; : ;' ;....I :::::i::i / ::: :::::::::::::::::::REG:::::O0:U.1.5 1. 1.6 1. 1.7Measured FrTFIGURE 3.2-3Allowable Combinations of THERMAL POWER and FrT(The expression specified in the Figure may be used for FJ at other power levels)1.St Lucie Unit 2 Cycle 22 COLR Rev. I ae11f1Page 12 of 18 L-201 5-265AttachmentPage 13 of 181.101.00L0.900.80-I-I-c 0.60U-c0.40UI IA ~E1AB T E_- -CEPfrABE-Ip O-----------------!,-0.7-0.5-0.3-0.10.1 0.30.50.7Peripheral AXIAL SHAPE INDEX (Y1)(Not Applicable Below 40% Power)FIGURE 3.2-4AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER(Four Reactor Coolant Pumps Operating)(AXIAL SHAPE INDEX limits for DNB)St. Lucie Unit 2 Cycle 22 COLR Rv ae1 f1Rev. 1Page t3 of 18 L-201 5-265AttachmentPage 14 of 183.0 LIST OF APPROVED METHODSThe analytical methods used to determine the core operating limits are those previouslyapproved by the NRC, and are listed below.1. WCAPR-1 1596-P-A, "Qualification of the PHOEN IX-P/ANC Nuclear Design System forPressurized 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 (NRC SERdated June 9, 1995), & Supplement 1, August 19973. Deleted.4. Deleted.5. CENPD-275-P, Revision 1-P-A, "C-E Methodology for Core Designs ContainingGadolinia-Urania Burnable Absorbers," May 1988, & Revision 1-P Supplement 1-P-A,April 19996. Deleted.7. Deleted.8. CEN-123(F)-P, "Statistical Combination of Uncertainties Methodology Part 1: CECalculated Local Power Density and Thermal Margin/Low Pressure LSSS for St.Lucie Unit 1," December 19799. Deleted.10. CEN-123(F)-P, "Statistical Combination of Uncertainties Methodology Part 3: CECalculated Departure from Nucleate Boiling and Linear Heat Rate Limiting Conditionsfor Operation for St. Lucie Unit 1," February 198011. CEN-191(B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert CliffsUnits 1 and 2," December 198112. Letter, J. W. Miller (NRC) to J. R. Williams, Jr. (FPL), Docket No. 50-389, RegardingUnit 2 Cycle 2 License Approval (Amendment No. 8 to NPF-1 6 and SER), November9, 1984 (Approval of CEN-123(F)-P (three parts) and CEN-191(B)-P)13. Deleted.14. Letter, J. A. Norris (NRC) to J. H. Goldberg (FPL), Docket No. 50-389, "St. Lucie Unit2 -Change to Technical Specification Bases Sections '2.1.1 Reactor Core' and'3/4.2.5 DNB Parameters' (TAC No. M87722)," March 14, 1994 (Approval of CEN-371 (F)-P)St. Lucie Unit 2 Cycle 22 COLR Rv ae1 f1Rev. 1Page 14 of 18 L-201 5-265AttachmentPage 15 of 1815. Deleted.16. Deleted.17. Deleted.18. Deleted.19. CENPD-225-P-A, "Fuel and Poison Rod Bowing," June 198320. CENPD-1 39-P-A, "C-E Fuel Evaluation Model Topical Report," July 197421. CEN-161(B)-P-A, "Improvements to Fuel Evaluation Model," August 198922. CEN-161(B)-P, Supplement 1-P-A, "Improvements to Fuel Evaluation Model,"January 199223. CENPD-1 32, Supplement 3-P-A, "Calculative Methods for the C-E Large Break LOCAEvaluation Model for the Analysis of C-E and _W Designed NSSS," June 198524. CENPD-133, Supplement 5-A, "CEFLASH-4A, A FORTRAN77 Digital ComputerProgram for Reactor Blowdown Analysis," June 198525. CENPD-134, Supplement 2-A, "COMPERC-II, a Program for Emergency Refill-Reflood of the Core," June 198526. CENPD-135-P, Supplement 5, "STRIKIN-II, A Cylindrical Geometry Fuel Rod HeatTransfer Program," April 197727. Letter, R. L. Baer (NRC) to A: E. Scherer (CE), "Evaluation of Topical Report CENPD-135, Supplement #5," September 6, 197828. CENPD-1 37, Supplement 1-P, "Calculative Methods for the C-E Small Break LOCAEvaluation Model," January 197729. CENPD-1 33, Supplement 3-P, "CEFLASH-4AS, A Computer Program for the ReactorBlowdown Analysis of the Small Break Loss of Coolant Accident," January 197730. Letter, K. Kniel (NRC) to A. E. Scherer (CE), "Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-1 37, Supplement 1-P," September 27, 197731. CENPD-1 38, Supplement 2-P, "PARCH, A FORTRAN-lV Digital Program to EvaluatePool Boiling, Axial Rod and Coolant Heatup," January 197732. Letter, C. Aniel (NRC) to A. E. Scherer (CE), "Evaluation of Topical Report CENPD-138, Supplement 2-P," April 10, 1978St. Lucie Unit 2 Cycle 22 COLR Rv ae1 f1Rev. 1Page 15 of 18 L-201 5-265AttachmentPage 16 of 1833. Letter, W. H. Bohike (FPL) to Document Control Desk (NRC), "St. Lucie Unit 2,Docket No. 50-389, Proposed License Amendment, MTC Changqe from -27 pcm to -30 pcrn," L-91-325, December 17, 199134. Letter, J. A. Norris (NRC) to J. H. Goldberg (FPL), "St. Lucie Unit 2 -Issuance ofAmendment Re: Moderator Temperature Coefficient (TAC No. M82517)," July 15,199235. Letter, J. W. Williams, Jr. (FPL) to D. G. Eisenhut (NRC), "St. Lucie Unit No. 2,Docket No. 50-389, Proposed License Amendment, Cycle 2 Reload," L-84-148, June4, 198436. Letter, J. R. Miller (NRC) to J. W. Williams, Jr. (FPL), Docket No. 50-389, RegardingUnit 2 Cycle 2 License Approval (Amendment No. 8 to NPF-1 6 and SER), November9, 1984 (Approval of Methodology contained in L-84-148)37. Deleted.38. Deleted.39. Deleted.40. Deleted.41. Deleted.42. CEN-348(B)-P-A, Supplement 1-P-A, "Extended Statistical Combination ofUncertainties," January 199743. CEN-372-P-A, "Fuel Rod Maximum Allowable Gas Pressure," May 199044. Deleted.45. Deleted.46. Deleted.47. Deleted.48. CEN-396(L)-P, "Verification of the Acceptability of a 1-Pin Burnup Limit of 60MWD/KG for St. Lucie Unit 2," November 1989 (NRC SER dated October 18, 1991,Letter J. A. Norris (NRC) to J. H. Goldberg (FPL), TAC No. 75947)49. CENPD-269-P, Rev. l-P, 'Extended Burnup Operation of Combustion EngineeringPWR Fuel," July 198450. CEN-289(A)-P, "Revised Rod Bow Penalties for Arkansas Nuclear One Unit 2,"December 1984 (NRC SER dated December 21, 1999, Letter K. N. Jabbour (NRC) toT. F. Plunkett (FPL), TAC No. MA4523)St. Lucie Unit 2 Cycle 22 COLR Rv ae1 f1Rev. 1Page 16 of 18 L-201 5-265AttachmentPage 17 of 1851. CENPD-1 37, Supplement 2-P-A, "Calculative Methods for the ABB CE Small BreakLOCA Evaluation Model," April 199852. CENPD-140-A, "Description of the CONTRANS Digital Computer Code forContainment Pressure and Temperature Transient Analysis," June 197653. Deleted.54. Deleted.55. CENPD-387-P-A, Revision 000, "ABB Critical Heat Flux Correlations for PWR Fuel,"May 200056. CENPD-132, Supplement 4-P-A, "Calculative Methods for the CE Nuclear PowerLarge Break LOCA Evaluation Model," March 200157. CENPD-1 37, Supplement 2-P-A, "Calculative Methods for the ABB CE Small BreakLOCA Evaluation Model," April 199858. CENPD-404-P-A, Rev. 0, "Implementation of ZIRLOTM Cladding Material in CENuclear Power Fuel Assembly Designs," November 200159. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology"' July 198560. WCAP-10216-P-A, Revision lA, "Relaxation of Constant Axial Offset Control; FQSurveillance Technical Specification," February 199461. WCAP-1 1397-P-A, (Proprietary), "Revised Thermal Design Procedure," April 198962. WCAP-14565-P-A, (Proprietary), "VIPRE-01 Modeling and Qualification forPressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis," October199963. WCAP-14565-P-A, Addendum 1-A, Revision 0, "Addendum 1Ito WCAP-14565-P-AQualification of ABB Critical Heat Flux Correlations with VIPRE-01 Code," August200464. Letter, W. Jefferson, Jr. (FPL) to Document Control Desk (USNRC), "St. Lucie Unit 2Docket No. 50-389: Proposed License Amendment WCAP-9272 Reload Methodologyand Implementing 30% Steam Generator Tube Plugging Limit," L-2003-276,December, 2003 (NRC SER dated January 31, 2005, Letter B. T. Moroney (NRC) toJ. A. Stall (FPL), TAC No. MC1566)65. WCAP-14882-P-A, Rev. 0, "RETRAN-02 Modeling and Qualification forWestinghouse Pressurized Water Reactor Non-LOCA Safety Analyses," April 1999.St. Lucie Unit 2 Cycle 22 COLR Rv ae1 f1Rev. 1Page 17 of 18 L-201 5-265AttachmentPage 18 of 1866. WCAP-7908-A, Rev. 0, "FACTRAN-A FORTRAN IV Code for Thermal Transients in aUO2 Fuel Rod," December 1989.67. WCAP-7979-P-A, Rev. 0, "TWINKLE -A Multi-Dimensional Neutron KineticsComputer Code," January 1975.68. WCAP-7588, Rev. 1-A, "An Evaluation of the Rod Ejection Accident in WestinghousePressurized Water Reactors Using Spatial Kinetics Methods," January 1975.69. WCAP-1261 0-P-A & CENPD-404-P-A, Addendum 2-A, "Westinghouse CladCorrosion Model for ZIRLO and Optimized ZIRLO," October 2013.St. Lucie Unit 2 Cycle 22 COLR Rv ae1 f1Rev. 1Page 18 of 18}}

Latest revision as of 07:44, 7 April 2019

Redirect to:

Retrieved from "https://kanterella.com/w/index.php?title=ML15301A253&oldid=1417318"