L-2005-034, Cycle 15 Core Operating Limits Report
| ML050550086 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 02/11/2005 |
| From: | Jefferson W Florida Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-2005-034 | |
| Download: ML050550086 (19) | |
Text
FPL Florida Power& Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 February 11, 2005 L-2005-034 10 CFR 50.36 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re:
St. Lucie Unit 2 Docket No. 50-389 Cycle 15 Core Operating Limits Report Pursuant 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 15.
Technical Specification 6.9.1.11.d requires that the COLR, including any mid-cycle revisions or supplements, be provided to the NRC upon issuance for each reload cycle.
Accordingly, enclosed is a copy of the St. Lucie Unit 2, Cycle 15 Core Operating Limits Report, Revision 2.
Please contact us if there are any questions regarding this submittal.
William Xeffersc Vice President St. Lucie Plant WJ/spt Attachment fAcOI an FPL Group company
St. Lucie Unit 2 Docket No. 50-389 L-2005-034 Attachment ST. LUCIE UNIT 2, CYCLE 15 CORE OPERATING LIMITS REPORT Revision 2 lS ared By V1/ i/ 0 !;g er 1/f//ieB Verified By vsl/os-St. Lucle UnIt 2 Cycle 15 COLR Rev 2 Page 1 oilS St. Lucie Unit 2 Cycle 15 COLR Rev 2 Page 1 of 18
St. Lucie Unit 2 Docket No. 50-389 L-2005-034 Attachment Table of Contents Description 1.0 Introduction Page 3
2.0 Core Operating Umits 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 Moderator Temperature Coefficient CEA Position - Misalignment > 15 inches Regulating CEA Insertion Limits Linear Heat Rate TOTAL INTEGRATED RADIAL PEAKING FACTOR DNB Parameters - AXIAL SHAPE INDEX Refueling Operations - Boron Concentration SHUTDOWN MARGIN - Ta.,, Greater Than 200 0F SHUTDOWN MARGIN - T, Less Than or Equal To 200 cF 4
4 4
4 5
5 5
5 5
14 3.0 List of Approved Methods Table 3.2-2 Table 3.2-3 Fig 3.1-la Fig 3.1 -2 Fig 3.2-1 Fig 3.2-2 Fig 3.2-3 Fig 3.2-4 List of Tables and Figures Title DNB Margin Limits W(z) Factors as a Function of Core Height Allowable Time To Realign CEA vs. Initial FT CEA Insertion Umits vs. THERMAL POWER Allowable Peak Linear Heat Rate vs. Burnup AXIAL SHAPE INDEX vs. Maximum Allowable Power Level Allowable Combinations of THERMAL POWER and FrT AXIAL SHAPE INDEX Operating Limits vs. THERMAL POWER Page 6
7 8
9 10 11 12 13 St. Lucle Unit 2 Cycle 15 COLR Rev 2 Page 2 of 18 St. Lucie Unit 2 Cycle 15 COLR Rev 2 Page 2 of 18
St. Lucie Unit 2 Docket No. 50-389 L-2005-034 Attachment
1.0 INTRODUCTION
This Core Operating Limits Report (COLR) describes the cycle-specific parameter limits for operation of St. Lucie Unit 2. It contains the limits for the following as provided in Section 2.
Moderator Temperature Coefficient CEA Position - Misalignment > 15 Inches Regulating CEA Insertion Limits Linear Heat Rate TOTAL INTEGRATED RADIAL PEAKING FACTOR-FT DNB Parameter Refueling Operations - Boron Concentration SHUTDOWN MARGIN - Tavg Greater Than 200 OF SHUTDOWN MARGIN - T.v, Less Than or Equal To 200 OF This report also contains the necessary figures which give the limits for the above listed parameters.
Terms appearing in capitalized type are DEFINED TERMS as defined in Section 1.0 of the Technical Specifications.
This report is prepared in accordance with the requirements of Technical Specification 6.9.1.11.
SL Lucle UnIt 2 Cycle 15 COLR Rev 2 Page 3 of 18 St. Lucie Unit 2 Cycle 15 COLR Rev 2 Page 3 of 18
St. Lucie Unit 2 Docket No. 50-389 L-2005-034 Attachment 2.0 CORE OPERATING LIMITS 2.1 Moderator Temperature Coefficient (TS 3.1.1.4)
The moderator temperature coefficient (MTC) shall be less negative than -32 pcm/OF at RATED THERMAL POWER.
2.2 CEA Position - Misalignment > 15 Inches (TS 3.1.3.1)
The time constraints for full power operation with one full-length CEA misaligned from any other CEA in its group by more than 15 inches are shown in Figure 3.1 -la.
2.3 Regulating CEA Insertion Limits (TS 3.1.3.6)
The regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits shown on Figure 3.1-2, with CEA insertion between the Long Term Steady State Insertion Limits and the Power Dependent Insertion Limits restricted to:
- a.
Less than or equal to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval,
- b.
Less than or equal to 5 Effective Full Power Days per 30 Effective Full Power Days, and
- c.
Less than or equal to 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 Monitoring System During operation, with the linear heat rate (LHR) being monitored by the Excore Detector Monitoring System, the AXIAL SHAPE INDEX shall be maintained within the limits of Figure 3.2-2.
Cycle specific W(z) curves to be used in the linear heat rate verification, to account for power distribution transients, are shown in Table 3.2-3 as function of core height for various cycle bumups.
For other cycle burnups, W(z) values may be interpolated or extrapolated as needed.
If the margin to the linear heat rate has decreased as determined from the last two flux maps, then the linear heat rate must be increased by an appropriate penalty.
A value of 2% is chosen as the standard penalty.
Linear heat rate margin St._Lcle U 2 Cycle 15 CLR R_ 2 Pag_
St. Lucie Unit 2 Cycle 15 COLR Rev 2 Page 4of 18
St. Lucie Unit 2 Docket No. 50-389 L-2005-034 Attachment decreases that are predicted to be greater than 2% per 31 Effective Full Power Days require that penalty factors of greater than 2% be used to increase the measured linear heat rate LHRM(z). The Incremental penalty factors (in excess of 2% margin decrease) are included in the W(z) function of Table 3.2-3.
Incore Detector Monitorina System During operation, with the linear heat rate being monitored by the Incore Detector Monitoring System, the Local Power Density alarm setpoints shall be adjusted to less than or equal to the limits shown on Figure 3.2-1.
2.5 TOTAL INTEGRATED RADIAL PEAKING FACTOR - FrI (TS 3.2.3)
The calculated value of FT shall be limited to < 1.70.
The power dependent FT limits are shown on Figure 3.2-3.
The following DNB-related parameters shall be maintained within the limits shown on Table 3.2-2:
- a. Cold Leg Temperature
- b. Pressurizer Pressure
- c.
Reactor Coolant System Flow rate
- d.
AXIAL SHAPE INDEX 2.7 Refuelina Operations - Boron Concentration (TS 3.9.1)
With the reactor vessel head closure bolts less than fully tensioned or with the head removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met:
- a.
Either a Kef of 0.95 or less, or
- b.
A boron concentration of greater than or equal to 1720 ppm.
2.8 SHUTDOWN MARGIN - T Greater Than 200 OF (TS 3.1.1.1)
The SHUTDOWN MARGIN shall be greater than or equal to 3600 pcm.
2.9 SHUTDOWN MARGIN - T., Less Than or Equal To 200 OF (TS 3.1.1.2)
The SHUTDOWN MARGIN shall be greater than or equal to 3000 pcm.
St Lucle Unit 2 Cycle 15 COLR Rev 2 Pages5 of 18
St. Lucie Unit 2 Docket No. 50-389 L-2005-034 Attachment Table 3.2-2 DNB MARGIN LIMITS PARAMETER FOUR REACTOR COOLANT PUMPS OPERATING Cold Leg Temperature (narrow Range)
Pressurizer Pressure*
Reactor Coolant Flow Rate AXIAL SHAPE INDEX 5350F** 5 T
- 5490P 2225 psia 5 Ppzm
- 2350 psia**
2 335,000 gpm Within the limits specified in Figure 3.2-4 Limit not applicable during either a THERMAL POWER ramp increase in excess of 5% of RATED THERMAL POWER or a THERMAL POWER step increase of greater than 10%
of RATED THERMAL POWER.
Applicable only if power level 2 70% of RATED THERMAL POWER.
St
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2--a-6 18 St. Lucie Unit 2 Cycle 15 COLR Rev 2 Page 6 of IS
St. Lucie Unit 2 Docket No. 50-389 L-2005-034 Attachment COLR Table 3.2-3 W(z) Factors as a Function of Core Height Core Height 100 EFPH 2000 EFPH SOD0 EFPH 8000 EFPH 10000 EFPH
()
(130 MWD/MTU)
(2598 MWD/ TU)
(6494 MWDIMTU)
(10391 MWDlMTU) (12988 MWDIMTU) c1.59*
1.000 1.000 1.000 1.000 1.000 1.75 1.288 1.266 1.240 1.303 1.340 1.91 1279 1.255 1.231 1.292 1.321 2.07 1 270 1.246 1.221 1.280 1.302 2.23 1.262 1.236 1.211 1.268 1.280 2.39 1.253 1.226 1.204 1.255 1.259 2.55 1.243 1.217 1.197 1.241 1.245 2.70 1.234 1.209 1.189 1.227 1.231 2.86 1.226 1.206 1.184 1.217 1.215 3.02 1.219 1.203 1.181 1.211 1.210 3.18 1.213 1.199 1.180 1 206 1.207 3.34 1.206 1.194 1.177 1.201 1.202 3.50 1.199 1.188 1.175 1.197 1.197 3.66 1.193 1.182 1.171 1.192 1.191 3.82 1.188 1.175 1.167 1.187 1.186 3.98 1.182 1.167 1.163 1.181 1.183 4.14 1.176 1.160 1.157 1.175 1.181 4.30 1.169 1.154 1.152 1.167 1.177 4.45 1.162 1.148 1.145 1.160 1.173 4.61 1.153 1.142 1.139 1.152 1.168 4.77 1.145 1.135 1.132 1.144 1.163 4.93 1.136 1.128 1.124 1.135 1.157 5.09 1.127 1.121 1.117 1.126 1.150 5.25 1.118 1.113 1.109 1.117 1.144 5Al 1.108 1.106 1.103 1.110 1.142 5.57 1.101 1.102 1.102 1.109 1.148 5.73 1.100 1.102 1.102 1.115 1.161 5.89 1.103 1.104 1.108 1.130 1.177 6.05 1.105 1.108 1.122 1.146 1.190 6.20 1.111 1.120 1.137 1.162 1.203 6.36 1.122 1.137 1.150 1.177 1.215 6.52 1.136 1.152 1.163 1.191 1.226 6.68 1.150 1.167 1.176 1.205 1.237 6.84 1.163 1.182 1.190 1217 1.246 7.00 1.175 1.196 1.204 1.228 1.255 7.16 1.187 1.210 1.218 1.239 1.262 7.32 1.198 1.223 1.231 1.248 1.267 7.48 1.209 1.235 1.242 1.255 1.270 7.64 1.218 1.246 1.253 1.261 1.272 7.80 1.226 1.255 1.263 1.265 1.272 7.95 1.233 1.264 1.272 1.267 1.270 8.11 1.240 1.271 1.279 1.268 1.269 8.27 1.246 1.277 1.287 1.268 1.270 8.43 1.252 1.282 1.296 1.271 1.273 8.59 1.260 1.285 1.309 1.279 1.282 8.75 1.271 1.292 1.331 1.292 1.299 8.91 1.283 1.313 1.356 1.309 1.316 9.07 1.297 1.337 1.381 1.328 1.332 9.23 1.314 1.363 1.404 1.346 1.347 9.39 1.337 1.388 1.425 1.365 1.363 9.54 1.361 1.412 1
1.446 1.389 1.382 9.70 1.382 1.434 1.467 1.413 1.403
>9.86 1.000 1.000 1.000 1.000 1.000
'Top and Bottom 15% are excluded.
St. Lucie Unit 2 Cycle 15 COLR Rev 2 Page 7 of 18
St. Lucie Unit 2 Docket No. 50-389 L-2005-034 Attachment
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St. Lucie Unit 2 Cycle 1 5 COLR Rev 2 Page 9 of 18
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St. Lucle Unit 2 Cycle 15 COIR Rev 2 Page 11 of 18 St. Lucie Unit 2 Cycle 15 COLR Rev 2 Page 11 of 18
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(AXIAL SHAPE INDEX limits for DNB) 0.7 St Lucle Unit 2 Cycle 15 COLR Rev 2 Page 13 of 18
St. Lucie Unit 2 Docket No. 50-389 L-2005-034 Attachment 3.0 LIST OF APPROVED METHODS The analytical methods used to determine the core operating limits are those previously approved by the NRC, and are listed below.
- 1.
WCAP-1 1596-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 (NRC SER dated June 9, 1995), & Supplement 1, August 1997
- 3.
CENPD-1 99-P, Rev.1 -P-A, 'C-E Setpoint Methodology: CE Local Power Density and DNB LSSS and LCO Setpoint Methodology for Analog Protection Systems,' January 1986
- 4.
CENPD-266-P-A, NThe ROCS and DIT Computer Code for Nuclear Design,' April 1983
- 5.
CENPD-275-P, Revision 1-P-A, 'C-E Methodology for Core Designs Containing Gadolinia-Urania Burnable Absorbers," May 1988, & Revision 1-P Supplement 1 -P-A, April 1999
- 6.
CENPD-188-A, 'HERMITE: A Multi-Dimensional Space - Time Kinetics Code for PWR Transients,' July 1976
- 7.
CENPD-1 53-P, Rev. 1-P-A, 'Evaluation of Uncertainty in the Nuclear Power Peaking Measured by the Self-Powered, Fixed Incore Detector System," May 1980
- 8.
CEN-123(F)-P, 'Statistical Combination of Uncertainties Methodology Part 1: C-E Calculated Local Power Density and Thermal Margin/Low Pressure LSSS for St.
Lucie Unit 1,' December 1979
- 9.
CEN-123(F)-P, 'Statistical Combination of Uncertainties Methodology Part 2:
Combination of System Parameter Uncertainties In Thermal Margin Analyses for St.
Lucie Unit 1,' January 1980
- 10.
CEN-123(F)-P, 'Statistical Combination of Uncertainties Methodology Part 3: C-E Calculated Departure from Nucleate Boiling and Linear Heat Rate Limiting Conditions for Operation for St. Lucie Unit 1,' February 1980
- 11.
CEN-1 91 (B)-P, 'CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units 1 and 2,' December 1981 St. Lucle Unit 2 Cycle 15 COLR Rev 2 Page 14 of 18
St. Lucie Unit 2 Docket No. 50-389 L-2005-034 Attachment
- 12.
Letter, J. W. Miller (NRC) to J. R. Williams, Jr. (FPL), Docket No. 50-389, Regarding Unit 2 Cycle 2 Ucense Approval (Amendment No. 8 to NPF-16 and SER), November 9,1984 (Approval of CEN-123(F)-P (three parts) and CEN-191(B)-P)
- 13.
CEN-371(F)-P, "Extended Statistical Combination of Uncertainties,' July 1989
- 14.
Letter, J. A. Norris (NRC) to J. H. Goldberg (FPL), Docket No. 50-389, 'St. Lucie Unit 2 - 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)
- 15.
CENPD-161-P-A, 'TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core," April 1986
- 16.
CENPD-162-P-A, "Critical Heat Flux Correlation for C-E Fuel Assemblies with Standard Spacer Grids Part 1, Uniform Axial Power Distribution," April 1975
- 17.
CENPD-207-P-A, "Critical Heat Flux Correlation for C-E Fuel Assemblies with Standard Spacer Grids Part 2, Non-uniform Axial Power Distribution,* December 1984
- 18.
CENPD-206-P-A, STORC Code, Verification and Simplified Modeling Methods," June 1981
- 19.
CENPD-225-P-A, 'Fuel and Poison Rod Bowing," June 1983
- 20.
CENPD-1 39-P-A, OC-E Fuel Evaluation Model Topical Report," July 1974
- 21.
CEN-161 (B)-P-A, "Improvements to Fuel Evaluation Model," August 1989
- 22.
CEN-161(B)-P, Supplement 1-P-A, 'Improvements to Fuel Evaluation Model,"
January 1992
- 23.
CENPD-1 32, Supplement 3-P-A, 'Calculative Methods for the C-E Large Break LOCA Evaluation Model for the Analysis of C-E and W Designed NSSS," June 1985
- 24.
CENPD-133, Supplement 5-A, 'CEFLASH-4A, A FORTRAN77 Digital Computer Program for Reactor Blowdown Analysis," June 1985
- 25.
CENPD-134, Supplement 2-A, *COMPERC-11, a Program for Emergency Refill-Reflood of the Core," June 1985
- 26.
CENPD-135-P, Supplement 5, "STRIKIN-Il, A Cylindrical Geometry Fuel Rod Heat Transfer Program," April 1977 St_
e t 2 e 1_ CL Rv 2
_e 1 o St. Lucie Unit 2 Cycle 15 COLR Rev 2 Page 15 of 18
St. Lucie Unit 2 Docket No. 50-389 L-2005-034 Attachment
- 27.
Letter, R. L. Baer (NRC) to A. E. Scherer (CE), 'Evaluation of Topical Report CENPD-135, Supplement #5," September 6, 1978
- 28.
CENPD-137, Supplement 1-P, NCalculative Methods for the C-E Small Break LOCA Evaluation Model," January 1977
- 29.
CENPD-1 33, Supplement 3-P, NCEFLASH-4AS, A Computer Program for the Reactor Blowdown Analysis of the Small Break Loss of Coolant Accident," January 1977
- 30.
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,m September 27, 1977
- 31.
CENPD-1 38, Supplement 2-P, 'PARCH, A FORTRAN-IV Digital Program to Evaluate Pool Boiling, Axial Rod and Coolant Heatup," January 1977
- 32.
Letter, C. Aniel (NRC) to A. E. Scherer (CE), 'Evaluation of Topical Report CENPD-138, Supplement 2-P,m April 10, 1978
- 33.
Letter, W. H. Bohike (FPL) to Document Control Desk (NRC), "St. Lucie Unit 2, Docket No. 50-389, Proposed Ucense Amendment, MTC Chanae from -27 ycm to
-30 pcm," 1-91-325, December 17,1991
- 34.
Letter, J. A. Norris (NRC) to J. H. Goldberg (FPL), 'St. Lucie Unit 2 - Issuance of Amendment Re: Moderator Temperature Coefficient (TAC No. M82517)," July 15, 1992
- 35.
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, June 4,1984
- 36.
Letter, J. R. Miller (NRC) to J. W. Williams, Jr. (FPL), Docket No. 50-389, Regarding Unit 2 Cycle 2 License Approval (Amendment No. 8 to NPF-16 and SER), November 9, 1984 (Approval of Methodology contained in L-84-1 48)
- 37.
Letter, A. E. Scherer Enclosure 1-P to LD-82-001, "CESEC-Digital Simulation of a Combustion Engineering Nuclear Steam Supply System," December 1981
- 38.
Safety Evaluation Report, "CESEC Digital Simulation of a Combustion Engineering Steam Supply System (TAC No.: 01142)," October 27, 1983
- 39.
CENPD-282-P-A, Volumes 1, 2, and 3, and Supplement 1, "Technical Manual for the CENTS Code," February 1991, February 1991, October 1991, and June 1993, respectively S. _ul n~ 2 Cyl 15
_OL Re 2___
Pag._
16 o_ 18 St. Lucie Unit 2 Cycle 15 COLR Rev 2 Page 16 of 18
St. Lucie Unit 2 Docket No. 50-389 L-2005-034 Attachment
- 40.
CEN-121 (B)-P, rCEAW, Method of Analyzing Sequential Control Element Assembly Group Withdrawal Event for Analog Protected Systems," November 1979 (NRC SER dated December 21,1999, Letter K. N. Jabbour (NRC) to T. F. Plunkett (FPL), TAC No. MA4523)
- 41.
CEN-133(B), "FIESTA, A One Dimensional, Two Group Space-Time Kinetics Code for Calculating PWR Scram Reactivities," November 1979 (NRC SER dated December 21, 1999, Letter K. N. Jabbour (NRC) to T. F. Plunkett (FPL), TAC No.
MA4523)
- 42.
CEN-348(B)-P-A, Supplement 1-P-A, "Extended Statistical Combination of Uncertainties," January 1997
- 43.
CEN-372-P-A, "Fuel Rod Maximum Allowable Gas Pressure," May 1990
- 44.
CENPD-1 83-A, "C-E Methods for Loss of Flow Analysis," June 1984
- 45.
CENPD-1 90-A, "C-E Method for Control Element Assembly Ejection Analysis," July 1976
- 46.
CENPD-199-P, Rev. 1-P-A, Supplement 2-P-A, "CE Setpoint Methodology", June 1998
- 47.
CENPD-382-P-A, "Methodology for Core Designs Containing Erbium Burnable Absorbers," August 1993
- 48.
CEN-396(L)-P, "Verification of the Acceptability of a 1-Pin Bumup Limit of 60 MWD/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. 1-P, "Extended Burnup Operation of Combustion Engineering PWR Fuel," July 1984
- 50.
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) to T. F. Plunkett (FPL), TAC No. MA4523)
- 51.
CENPD-137, Supplement 2-P-A, "Calculative Methods for the ABB CE Small Break LOCA Evaluation Model," April 1998
- 52.
CENPD-140-A, 'Description of the CONTRANS Digital Computer Code. for Containment Pressure and Temperature Transient Analysis," June 1976
- 53.
CEN-365(L), "Boric Acid Concentration Reduction Effort, Technical Bases and Operational Analysis," June 1988 (NRC SER dated March 13, 1989, Letter J. A.
Norris (NRC) to W. F. Conway (FPL), TAC No. 69325)
StLc_ U~t2 yce 5 OL
-Rv 17 of 18-----
St. Lucie Unit 2 Cycle 1 5 COLR Rev 2 Page 17 of 18
St. Lucie Unit 2 Docket No. 50-389 L-2005-034 Attachment
- 54.
DP-456, F. M. Stem (CE) to E. Case (NRC), dated August 19,1974, Appendix 6B to CESSAR System 80 PSAR (NRC SER, NUREG-75/112, Docket No. STN 50-470, "NRC SER - Standard Reference System, CESSAR System 80," December 1975)
- 55.
CENPD-387-P-A, Revision 000, "ABB Critical Heat Flux Correlations for PWR Fuel,"
May 2000
- 56.
CENPD-1 32, Supplement 4-P-A, "Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model," March 2001
- 57.
CENPD-137, Supplement 2-P-A, "Calculative Methods for the ABB CE Small Break LOCA Evaluation Model," April 1998
- 58.
CENPD-404-P-A, Rev. 0, "Implementation of ZIRLOQm Cladding Material in CE Nuclear Power Fuel Assembly Designs," November 2001
- 59.
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology'" July 1985
- 60.
WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset Control; FQ Surveillance Technical Specification," February 1994
- 61.
WCAP-1 1397-P-A, (Proprietary), "Revised Thermal Design Procedure," April 1989
- 62.
WCAP-14565-P-A, (Proprietary),
"VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis," October 1999
- 63.
WCAP-14565-P-A, Addendum 1-A, Revision 0, "Addendum 1 to WCAP-14565-P-A Qualification of ABB Critical Heat Flux Correlations with VIPRE-01 Code," August 2004
- 64.
Letter, W. Jefferson, Jr. (FPL) to Document Control Desk (USNRC), "St. Lucie Unit 2 Docket No. 50-389: Proposed License Amendment WCAP-9272 Reload Methodology and Implementing 30% Steam Generator Tube Plugging Limit," L-2003-276, December, 2003 (NRC SER dated January 31, 2005, Letter B. T. Moroney (NRC) to J. A. Stall (FPL), TAC No. MCI1566)
St. _
Lu _
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_ 2 Cyl 15 CL Rev 2_._a__
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St. Lucie Unit 2 Cycle 15 COLR Rev 2 Page 18 of 18