ML14141A032

From kanterella
Revision as of 15:02, 1 July 2018 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
R.E. Ginna - Transmittal of Core Operating Limits Report (Colr) for Cycle 38
ML14141A032
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/13/2014
From: Mogren T G
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML14141A032 (21)
v • d • e


Text

AR.E. Ginna Nuclear Power Plant1503 Lake Rd.Exeonn Generation

Ontario, NY 14519-9364 Exe~o Gene ationwww.exeloncorp.-om May 13, 2014U.S. Nuclear Regulatory Commission ATTN: Document Control DeskWashington, DC 20555-0001 R.E. Ginna Nuclear Power PlantRenewed Facility Operating License No. DPR-18NRC Docket No. 50-244

Subject:

Transmittal of Core Operating Limits Report (COLR) for Cycle 38In accordance with the R.E. Ginna Nuclear Power Plant Improved Technical Specification 5.6.5.d, which requires the submittal of revisions to the COLR, the attachedreport is hereby submitted.

Should you have questions regarding this matter, pleasecontact Thomas Harding (585) 771-5219, or Thomas.HardingJr@cengllc.com.

Respectfully, Thomas G. MogrenManager -Engineering ServicesR.E. Ginna Nuclear Power PlantTGM/JPO

Attachment:

R.E. Ginna Nuclear Power Plant, Core Operating Limits Report, Cycle 38cc: NRC Regional Administrator, Region INRC Project Manager, GinnaNRC Senior Resident Inspector, Ginna ATTACHMENT R.E. GINNA NUCLEAR POWER PLANTCORE OPERATING LIMITS REPORTCYCLE 38R.E. Ginna Nuclear Power Plant, LLCMay 13, 2014 COLRCycle 38-m-" Exelon Generation R.E. Ginna Nuclear Power PlantCore Operating Limits ReportCOLRCycle 38Revision 0Responsible Manager:../ / Jo4ýazzaro-May 7, 2014Effective Date:Controlled Copy No.Record Cat.# 4.43.2R.E. Ginna Nuclear Power PlantCOL-R-1Revision 0

COLRCycle 381.0 CORE OPERATING LIMITS REPORTThis Core Operating Limits Report (COLR) for the R.E. Ginna Nuclear Power Plant has beenprepared in accordance with the requirements of Technical Specification 5.6.5.The Technical Specifications affected by this report are listed below:2.1 Safety Limits (SLs)3.1.1 SHUTDOWN MARGIN (SDM)3.1.3 MODERATOR TEMPERATURE COEFFICIENT (MTC)3.1.5 Shutdown Bank Insertion Limit3.1.6 Control Bank Insertion Limits3.2.1 Heat Flux Hot Channel Factor (FQ(Z))3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNAH)3.2.3 AXIAL FLUX DIFFERENCE (AFD)3.3.1 Reactor Trip System (RTS) Instrumentation 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)Limits3.9.1 Boron Concentration R.E. Ginna Nuclear Power PlantCOLR-2Revision 0

COLRCycle 382.0 OPERATING LIMITSThe cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in thefollowing subsections.

These limits have been developed using the NRC-approved methodologies specified in Technical Specification 5.6.5. All items thatappear in capitalized typeare defined in Technical Specification 1.1, Definitions.

2.1 SAFETY LIMITS (SLs)1(2.1)2.1.1 In MODES 1 and 2, the combination of THERMAL POWER, Reactor CoolantSystem (RCS) average temperature, and pressurizer pressure shall not exceedthe SLs specified in Figure COLR -1.2.2 SHUTDOWN MARGIN1(LCO 3.1.1)2.2.1 The SHUTDOWN MARGIN in MODE 2 with Keff < 1.0 and MODES 3 and 4shall be greater than or equal to the limits specified in Figure COLR -2 for thenumber of reactor coolant pumps in operation.

2.2.2 The SHUTDOWN MARGIN in MODE 4 when both reactor coolant pumps arenot in operation and in MODE 5 shall be greater than or equal to the one loopoperation curve of Figure COLR -2.2.2.3 The SHUTDOWN MARGIN required in LCO 3.1.4, LCO 3.1.5, LCO 3.1.6, LCO3.1.8, and LCO 3.4.5 shall be greater than the limits specified in Figure COLR -2 for the number of reactor coolant pumps in operation.

2.3 MODERATOR TEMPERATURE COEFFICIENT 1(LCO 3.1.3)2.3.1 The Moderator Temperature Coefficient (MTC) limits are:The BOL ARO/HZP -MTC shall be equal to or less positive than +5.0 pcm/OFfor power levels below 70% RTP and less than or equal to 0 pcm/°F for powerlevels at or above 70% RTP.The EOL ARO/RTP -MTC shall be less negative than -44.6 pcm/OF.where:ARO stands for All Rods OutBOL stands for Beginning of Cycle LifeR.E. Ginna Nuclear Power PlantCOLR-3Revision 0

COLRCycle 38EOL stands for End of Cycle LifeHZP stands for Hot Zero PowerRTP stands for RATED THERMAL POWER2.4 Shutdown Bank Insertion Limit1(LCO 3.1.5)2.4.1 The shutdown bank shall be fully withdrawn which is defined as _> 220 steps.2.5 Control Bank Insertion Limits1(LCO 3.1.6)2.5.1 The control banks shall be limited in physical insertion as shown in FigureCOLR -3. Control Bank A shall be at least 220 steps withdrawn.

2.5.2 The control rod banks shall be withdrawn maintaining a nominal 130 step tip-to-tip distance while moving in overlap through the active core region. Theminimum allowable tip-to-tip distance shall never be less than 121 stepsbetween two banks moving in the active core region.2.6 Heat Flux Hot Channel Factor (FQ(Z))2(LCO 3.2.1)2.6.1 FQ(Z)_<CFQ*K(Z)/PforP>0.5 FQ(Z) < CFQ

  • K(Z) / 0.5 for P < 0.5where:CFQ is the FQ(Z) limitP = THERMAL POWER / RATED THERMAL POWERZ is the height of the core2.6.2 CFQ = 2.602.6.3 K(Z) is provided in Figure COLR -42.6.4 W(Z) values are provided in Table COLR -1. For W(Z) data at a desiredburnup not listed in the table, but less than the maximum listed burnup, valuesat 3 or more burnup steps should be used to interpolate the W(Z) data to theR.E. Ginna Nuclear Power PlantCOLR-4Revision 0

COLRCycle 38desired burnup with a polynomial type fit that uses the W(Z) data for thenearest three burnup steps.For W(Z) data at a desired burnup outside of the listed burnup steps, a linearextrapolation of the W(Z) data for the nearest two burnup steps can be used. Ifdata are listed for only two burnup steps, a linear fit can be used for bothinterpolation and extrapolation.

2.6.5 The FQ(Z) penalty factors are provided in Table COLR -2.2.6.6 Table COLR -3 provides W(Z) values for the BOC startup flux map to be takenprior to exceeding 75% power. For part power surveillances during other timesin life or at powers other than 75%, the W(Z) values in Table COLR -1 shouldbe used. The W(Z) values in Table COLR -3 do not include the 1/P factor,where P is the surveillance power level. This factor will be applied by theINCORE-3D software.

2.7 Nuclear Enthalpy Rise Hot Channel Factor (FNAH)1(LCO 3.2.2)2.7.1 FNAH _< FRTPAH * (1 + PFAH * (1-P))where:FRTPAH= 1.72PFAH = 0.3, andP = THERMAL POWER / RATED THERMAL POWER2.8 AXIAL FLUX DIFFERENCE 3(LCO 3.2.3)2.8.1 The AFD acceptable operation limits are provided in Figure COLR -5.2.9 Reactor Trip System (RTS) Instrumentation 5(LCO 3.3.1)R.E. Ginna Nuclear Power PlantCOLR-5Revision 0

COLRCycle 382.9.1 Overtemperature AT Setpoint Parameter ValuesParameter Overtemperature AT reactor trip setpointValueK1, 1.19Overtemperature AT reactor trip K2 > 0.00093/psi depressurization setpoint penalty coefficient Overtemperature AT reactor trip heatup K3 >_ 0.0185/°F penaltysetpoint coefficient Measured lead time constant

-i1 >- 25 secondsMeasured lag time constant

'2 -< 5 secondsfl(AI) is a function of the indicated difference between top and bottom detectors of the power range nuclear ion chambers.

Selected gains are based onmeasured instrument response during plant startup tests, where qt and qb arepercent RATED THERMAL POWER in the upper and lower halves of the core,respectively, and qt + qb is the total percent RATED THERMAL POWER, suchthat:* For qt -qb between -14% and +6%, fl(AI) = 0.For each percent that the magnitude of qt -qb exceeds -14% the AT tripsetpoint shall be automatically reduced by an equivalent of 3.08% ofRATED THERMAL POWER.For each percent that the magnitude of qt -qb exceeds +6% the AT tripsetpoint shall be automatically reduced by an equivalent of 2.27% ofRATED THERMAL POWER.R.E. Ginna Nuclear Power PlantCOLR-6Revision 0

COLRCycle 382.9.2 Overpower AT Setpoint Parameter ValuesParameter ValueOverpower AT reactor trip setpointK4< 1.077Overpower AT reactor trip heatup setpoint K5 = 0/°F for T < T'penalty coefficient

_> 0.0014/°F for T _> T'Overpower AT reactor trip thermaltime delay setpoint penaltyMeasured impulse/lag time constantK6 > 0.00/°F for increasing T= 0.00/°F for decreasingT T3 = 0 secondsf2(AI) = 0.0% RTP for all Al2.10 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)Limits4(LCO 3.4.1)2.10.1 The pressurizer pressure shall be _> 2205 psig.2.10.2 The RCS average temperature shall be 577.5 'F.2.10.3 The RCS total flow rate shall be _> 177,300 gpm (includes 4% minimum flowuncertainty per Revised Thermal Design Methodology).

2.11 Boron Concentration 1(LCO 3.9.1)2.11.1 The boron concentrations of the hydraulically coupled Reactor Coolant Systemthe refueling canal, and the refueling cavity shall be _> 2750 ppm. Boronconcentration based on All Rods in less the highest worth rod with a K-effective of 0.95. A 100 ppm Factor of Safety has been included in this parameter.

3.0 REFERENCES

1. WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July 1985.2. WCAP-1 0054-P-A and WCAP-1 0081-A, "Westinghouse Small Break ECCSEvaluation Model Using the NOTRUMP Code," August 1985.R.E. Ginna Nuclear Power PlantCOLR-7Revision 0

COLRCycle 383. WCAP-1 0054-P-A, Addendum 2, Revision 1, "Addendum to the Westinghouse SmallBreak ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into theBroken Loop and COSI Condensation Model", Thompson, C.M., et. al., July 1997.4. WCAP-11145-P-A, "Westinghouse Small Break LOCA ECCS Evaluation ModelGeneric Study with the NOTRUMP Code", Rupprecht, S. D., et. al., October 1986.5. WCAP-1 0079-P-A, "NOTRUMP

-A Nodal Transient Small Break and General NetworkCode", Meyer, P. E., August 1985.6. WCAP-1 6009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using theAutomated Statistical Treatment of Uncertainty Method (ASTRUM)",

January 2005.7. WCAP-1 261 0-P-A, "VANTAGE

+ Fuel Assembly Reference Core Report,"

April 1995.8. WCAP-1 0216-P-A, Revision 1A (Proprietary),

Relaxation of Constant Axial OffsetControl FQ -Surveillance Technical Specification, February 1994.9. WCAP-11397-P-A, "Revised Thermal Design Procedure",

April 1989.10. WCAP-1471 0-P-A, "1-D Heat Conduction Model for Annular Fuel Pellets,"

Shimeck, D.J., May 1998.11. WCAP-8745, "Design Basis for the Thermal Overpower Delta T and ThermalOvertemperature Delta T Trip Functions",

March 1977.R.E. Ginna Nuclear Power PlantCOLR-8Revision 0

COLRCycle 38670650630610590570550530---- --,- n , ' , , , , , "1 "' ' , ,- .-......-1 -T r- r -".....~201 J .ia J I [ L L

  • I I 1 1 _Ji~~~~ T T, ...............,, , -T- : , : : : : --, i r ',,, ! ! " !T......00.2 0.4 0.6 0.8Power (fraction of 1775 MWt)Figure COLR -1Reactor Safety Limits1.2 1.4R.E. Ginna Nuclear Power PlantCOLR-9Revision 0

COLRCycle 3832.52L 2S1.5zI-ACCEPTABLE OPERATION

-t -_ -------(2500, 1.80) 1(0,t.80)

(2500,1.30)

(0, 1.30)UNCEPTABLE OPRAIONj02500O2000150010005000COOLANT BORON CONCENTRATION (ppm)--.-.--- One Loop Operation Two Loop Operation Figure COLR -2REQUIRED SHUTDOWN MARGINR.E. Ginna Nuclear Power PlantCOLR-10Revision 0

COLRCycle 38240220200180* 160140Z 120(00x 100zmo 8o6040(16,74, 225)(66.20, 225)(63.91, 219)(14.46, 219)B Bank(0,181)(100, 104)0 Bank(0. 51)20(30,0)00 10 2030 40 50 60CORE POWER (Percent of 1,775 MWT)70 80 90 100* The top of the active fuel corresponds to 219. The ARO parking position may be any position above thecorresponding top of active fuel for each respective bank. The control rod tip-to-tip distance is defined as 130steps while rods are moving in overlap.

The bank positions are given as follows:* Bank D: (184170)

  • (P-100) + 184 (for 30 < P < 100)o Bank C: (184/70)
  • (P-100) + 184 + 130 (for 0 < P < 66.20)o Bank B: (184170)
  • (P-100) + 184 + 130 + 130 (for 0 < P < 16.74)Where P is defined as the core power (in percent).

Figure COLR-3CONTROL BANK INSERTION LIMITSR.E. Ginna Nuclear Power PlantCOLR-1 1Revision 0

COLRCycle 381.2NS1.0L,.0UIL 0.8W 0.6< 0.4NE 0.2Total Fa = 2.600I-Elevation (ft)0.012.01.0z1.01.0L-0z0.0 2.0 4.0 6.0 8.0 10.0 12.0Elevation (ft)Figure COLR -4K(Z) -NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHTR.E. Ginna Nuclear Power PlantCOLR-12Revision 0

COLRCycle 38E1201101009080706050403020100-50 30 100 10 20 30 40 50Axial Rux Difference (percent Al)Figure COLR -5AXIAL FLUX DIFFERENCE ACCEPTABLE OPERATION LIMITS AS A FUNCTION OF RATEDTHERMAL POWERR.E. Ginna Nuclear Power PlantCOLR-13Revision 0

COLRCycle 38Table COLR -1RAOC Summary of W(Z) with HFP %AFD Band of -12/+6%(TOP 8% and BOTTOM 8% EXCLUDED) 150 3000 10000 16000Height (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU(Bottom) 0.00 1.0000 1.0000 1.0000 1.00000.17 1.0000 1.0000 1.0000 1.00000.33 1.0000 1.0000 1.0000 1.00000.50 1.0000 1.0000 1.0000 1.00000.67 1.0000 1.0000 1.0000 1.00000.83 1.0000 1.0000 1.0000 1.00001.00 1.4136 1.3502 1.2666 1.26051.17 1.4023 1.3394 1.2598 1.25311.33 1.3895 1.3273 1.2517 1.24451.50 1.3744 1.3130 1.2420 1.23441.67 1.3580 1.2973 1.2313 1.22341.83 1.3412 1.2815 1.2203 1.21222.00 1.3224 1.2637 1.2078 1.19982.17 1.3028 1.2455 1.1948 1.18672.33 1.2840 1.2280 1.1824 1.17442.50 1.2642 1.2092 1.1692 1.16342.67 1.2438 1.1939 1.1558 1.15462.83 1.2256 1.1844 1.1436 1.14793.00 1.2133 1.1756 1.1331 1.14223.17 1.2054 1.1686 1.1267 1.13833.33 1.1984 1.1640 1.1241 1.13603.50 1.1918 1.1592 1.1219 1.13363.67 1.1851 1.1538 1.1195 1.13083.83 1.1783 1.1484 1.1171 1.12764.00 1.1705 1.1421 1.1141 1.12334.17 1.1623 1.1352 1.1107 1.11934.33 1.1541 1.1290 1.1071 1.11724.50 1.1451 1.1241 1.1028 1.11704.67 1.1359 1.1201 1.0990 1.11734.83 1.1278 1.1156 1.0968 1.11685.00 1.1210 1.1105 1.0947 1.11605.17 1.1151 1.1051 1.0917 1.11455.33 1.1089 1.0998 1.0887 1.11275.50 1.1016 1.0941 1.0883 1.11175.67 1.0952 1.0875 1.0904 1.11115.83 1.0920 1.0816 1.0932 1.1104R.E. Ginna Nuclear Power PlantCOLR-14Revision 0

COLRCycle 38Table COLR -1 (Continued)

RAOC Summary of W(Z) with HFP %AFD Band of -12/+6%(TOP 8% and BOTTOM 8% EXCLUDED) 150 3000 10000 16000Height (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU6.00 1.0937 1.0826 1.0961 1.11056.17 1.0979 1.0889 1.1001 1.11306.33 1.1007 1.0945 1.1060 1.11816.50 1.1031 1.1000 1.1120 1.12326.67 1.1051 1.1051 1.1172 1.12726.83 1.1066 1.1095 1.1216 1.13057.00 1.1076 1.1137 1.1257 1.13347.17 1.1081 1.1173 1.1291 1.13557.33 1.1079 1.1201 1.1317 1.13677.50 1.1072 1.1224 1.1338 1.13727.67 1.1057 1.1241 1.1350 1.13697.83 1.1038 1.1250 1.1355 1.13588.00 1.1010 1.1253 1.1353 1.13378.17 1.0975 1.1248 1.1341 1.13088.33 1.0935 1.1236 1.1320 1.12828.50 1.0885 1.1214 1.1304 1.12718.67 1.0828 1.1185 1A1302 1.12688.83 1.0786 1.1182 1.1322 1.12819.00 1.0803 1.1218 1.1392 1.13239.17 1.0870 1.1323 1.1498 1.13909.33 1.0925 1.1411 1.1592 1.14569.50 1.0988 1.1498 1.1688 1.15249.67 1.1063 1.1580 1.1785 1.15889.83 1.1134 1.1645 1.1873 1.166110.00 1.1196 1.1730 1.1961 1.181910.17 1.1266 1.1832 1.2046 1.204610.33 1.1373 1.1914 1.2124 1.223910.50 1.1467 1.1981 1.2171 1.240210.67 1.1497 1.2017 1.2182 1.253110.83 1.1474 1.2006 1.2183 1.262411.00 1.1400 1.1953 1.2138 1.263811.17 1.0000 1.0000 1.0000 1.000011.33 1.0000 1.0000 1.0000 1.000011.50 1.0000 1.0000 1.0000 1.000011.67 1.0000 1.0000 1.0000 1.000011.83 1.0000 1.0000 1.0000 1.000012.00 (Top) 1.0000 1.0000 1.0000 1.0000R.E. Ginna Nuclear Power PlantCOLR-15Revision 0

COLRCycle 38Table COLR -2(a) A penalty multiplier is not required for part power surveillances during startup.The penalty factor should be applied beginning with the first full power surveillance.

R.E. Ginna Nuclear Power PlantCOLR-16Revision 0

COLRCycle 38Table COLR -3Part-Power W(Z) generated at 150 MWD/MTU, 75% Power(Top 8% and Bottom 8% Excluded)

Height (feet) HFP ARO 75% D at 180(Bottom)0.00 1.0000 1.00000.17 1.0000 1.00000.33 1.0000 1.00000.50 1.0000 1.00000.67 1.0000 1.00000.83 1.0000 1.00001.00 1.4136 1.47001.17 1.4023 1.45461.33 1.3895 1.43781.50 1.3744 1.41861.67 1.3580 1.39811.83 1.3412 1.37722.00 1.3224 1.35422.17 1.3028 1.33072.33 1.2840 1.30812.50 1.2642 1.28452.67 1.2438 1.26022.83 1.2256 1.23813.00 1.2133 1.22233.17 1.2054 1.21103.33 1.1984 1.20083.50 1.1918 1.19103.67 1.1851 1.18123.83 1.1783 1.17124.00 1.1705 1.16024.17 1.1623 1.14894.33 1.1541 1.13774.50 1.1451 1.12594.67 1.1359 1.11394.83 1.1278 1.10295.00 1.1210 1.09345.17 1.1151 1.08495.33 1.1089 1.07645.50 1.1016 1.06685.67 1.0952 1.05835.83 1.0920 1.05276.00 1.0937 1.0520R.E. Ginna Nuclear Power PlantCOLR-17Revision 0

COLRCycle 38Table COLR -3 (Continued)

Part-Power W(Z) generated at 150 MWD/MTU, 75% Power(Top 8% and Bottom 8% Excluded)

Height (feet) HFP ARO 75% D at 1806.17 1.0979 1.05406.33 1.1007 1.05456.50 1.1031 1.05496.67 1.1051 1.05526.83 1.1066 1.05557.00 1.1076 1.05597.17 1.1081 1.05577.33 1.1079 1.05467.50 1.1072 1.05257.67 1.1057 1.05007.83 1.1038 1.04758.00 1.1010 1.04498.17 1.0975 1.04178.33 1.0935 1.03848.50 1.0885 1.03478.67 1.0828 1.03048.83 1.0786 1.02719.00 1.0803 1.02859.17 1.0870 1.03469.33 1.0925 1.03999.50 1.0988 1.04659.67 1.1063 1.05449.83 1.1134 1.062210.00 1.1196 1.069310.17 1.1266 1.077510.33 1.1373 1.089410.50 1.1467 1.099510.67 1.1497 1.102810.83 1.1474 1.103511.00 1.1400 1.102511.17 1.0000 1.000011.33 1.0000 1.000011.50 1.0000 1.000011.67 1.0000 1.000011.83 1.0000 1.000012.00 (Top) 1.0000 1.0000R.E. Ginna Nuclear Power PlantCOLR-18Revision 0

COLRCycle 38END NOTES1.2.3.4.5.(Limits generated using(Limits generated using(Limits generated using(Limits generated using(Limits generated usingReference 1)References 1 tReferences 1Reference 9)Reference 11)through 8 and 10)and 8)R.E. Ginna Nuclear Power PlantCOLR-19Revision 0

Retrieved from "https://kanterella.com/w/index.php?title=ML14141A032&oldid=790658"