L-17-071, Cycle 20 Core Operating Limits Report

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Cycle 20 Core Operating Limits Report
ML17157B484
Person / Time
Site: Beaver Valley
Issue date: 06/06/2017
From: Richey M
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-17-071
Download: ML17157B484 (19)
v • d • e


Text

{{#Wiki_filter:FENOC ' Beaver Valley Power Station P.O. Box 4 FirstEnergy Nuclear Operating Company Shippingport, PA 15077 Marty L. Richey 724-682-5234 Site Vice President Fax: 724-643-8069 June 6, 2017 L-17-071 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Cycle 20 Core Operating Limits Report Pursuant to the requirements of Beaver Valley Power Station, Unit No. 2 Technical Specification 5.6.3, "CORE OPERATING LIMITS REPORT (COLR)," FirstEnergy Nuclear Operating Company hereby submits the COLR for Cycle 20. Technical Specification 5.6.3.d requires, in part, that the COLR be provided to the Nuclear Regulatory Commission upon issuance for each reload cycle. The Cycle 20 COLR was made effective on May 4, 2017. There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager- Fleet Licensing, at (330) 315-6810. Sincerely, 

                       -

1J1=- P M;ry L. Rict

Enclosure:

Beaver Valley Power Station, Unit No. 2, Core Operating Limits Report, Cycle 20

L-17-071 Page 2 of 2 cc: NRC Region I Administrator NRC Resident lnspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative

Enclosure L-17-071 Beaver Valley Power Station, Unit No. 2 Core Operating Limits Report, Cycle 20 (16 Pages Follow)

Licensing Requirements lvlanual Core Operating Limits Report 5.1 5.0 ADMI N ISTRATIVE CONTROLS 5.1 Core Operating Limits Report This Core Operating Limits Report provides the cycle specific parameter limits developed in accordance with the NHC approved methodologies specified in Technical Specification Adm inistrative Control 5.6.3. 5.1 .1 SL 2.1.1 Reactor Core Safety Limits See Figure 5.1-1 . 5.1 .2 H N IVIARGI

a. ln tvloDES 1, 2, 3, and 4, SHUTDOWN MARGIN shall be > 1 .77% 41nt6.{t)
b. Prior to manually blocking the Low Pressurizer Pressure Safety lnjection Signal, the Reactor Coolant System shall be borated to > the I\IODE 5 boron concentration and shall remain > this boron concentration at all times when this signal is blocked.
c. ln MODE 5, SHUTDOWN tvlARGlN shall be > 1.0% Atdk.

5.1.3 LCO 3.1.3 lt/oderator Temperature Coefficient (MTC)

a. Upper Limit - IUTC shall be maintained within the acceptable operation limit specified in Technical Specification Figure 3.1.3-1.
b. Lower Limit - IUTC shall be maintained less negative than - 4.29 x 10-a Atdtd'F at RATED THERMAL POWER.
c. 300 ppm Surveillance Limit: (- 35 pcm/"F)
d. The revised predicted near-EOL 300 ppm MTC shall be calculated using Figure 5.1-5 and the following algorithm from Heference 10 :

Revised Predicted tvlTC = Predicted MTC. + AFD Correction** + Predictive Correction*** where,

  • Predicted lvlTC is calculated from Figure 5.1-5 at the burnup corresponding to the measurement of 300 ppm at RTP conditions,
                        **

AFD Correction is the more negative value of  : 

                                                      -

{0 pcm/"F or (AAFD AFD Sensitivity)} where: AAFD is the measured AFD minus the predicted AFD from an incore flux map taken at or near the burnup corresponding to 300 ppm. and AFD Sensitivity = 0.10 pcmioF / AAFD 

                        ***Predictive Correction is -3 pcm/oF.

(1) The ttIODE 1 and TUODE 2 with ker ) 1 .0 SDM requirements are included to address SDIVI requirements (e.9., IUODE 1 Flequired Actions to verify SDh/) that are not within the applicability of LCO 3.1 .1, SHUTDOWN MARGIN (SD[U). COLR Cycle 20 Beaver Valley Unit 2 5.1 -1 LRIVI Revision 90

Licensing Requirements Jvlanual Core Operating Limits Report 5.1 5.1 Core Operating Limits Fleport lf the revised predicted [flTC is less negative than the SR 3.1.3.2 Iimit (COLR 5.1.3.c) and all of the benchmark data contained in the surveillance procedure are met, then an MTC measurement in accordance with SR 3.1 .3.2 is not required.

e. 60 ppm Surveillance Limit: (- a0.5 pcm/'F) 5.1 .4 LCO 3.1.5 Shutdown Bank lnsertion Limits The Shutdown Banks shall be withdrawn to at least 225 steps.tz) 5.1 .5 LCO 3.1.6 Control Bank lnsertion Limits
a. Control Banks A and B shalt be withdrawn to at least 225 steps.{z)
b. Control Banks C and D shall be limited in physical insertion as shown in Figure 5-1-2-{zt
c. Sequence Limits - The sequence of withdrawal shall be A, B, C and D bank, in that order.
d. Overlap Limits(z) - Overlap shall be such that step 129 on banks A, B, and C corresponds to step 1 on the following bank. When C bank is fully withdrawn, these limits are verified by confirming D bank is withdrawn at least to a position equal to the all-rods-out position minus 128 steps.

5.1.6 LCO 3.2.1 Heat Flux Hot Channel Factor (Fo(Z)) The Heat Flux Hot Channel Factor - l*(Z) limit is defined by: Fa(z) for P > 0.5 

                              = [T].*,r, Fa(z)                                     for P < 0.5
                              = [H].*,r, THERMAL POWER Where:      CFQ = 2.40                  I _ RATED      THERTUAL POWER K(Z) = the function obtained from Figure 5.1-3.

F3 (z) = FH (z) . 1 .oB1 s$ r$tzt = Ffi(z) 

                                              .w(z)

(2) As indicated by the group demand counter $ An additional uncertainty is to be applied if the number of measured thimbles for the moveable incore detector system is less than 75% of the total number of thimbles. lf there are less than 75% of the total number of thimbles and at least 50% of the total number of thimbles measured, and additional uncertainty of (0.01).(3-T/12.5) is added to the measurement uncertainty, 1 ,05, where T is the total number of measured thimbles. This adjusted measurement uncertainty is then multiplied by 1.03 to obtain the total uncertainty to be applied. At least three measured thimbles per core quadrant are also required. COLR Cycle 20 Beaver Valley Unit 2 5.1 -2 LRIU Revision 90

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Fleport The W(Z) values are provided in Tables 5.1-1 and 5.1-2. The W(Z) values in Table 5,1-1 were generated assuming that they will be used for a full power surveillance. The W(Z) values in Table 5.1-2 were generated assuming that they will be used for a part power surveillance during initial cycle startup following the refueling outage. When a part power surveillance is performed, the W(Z) values should be multiplied by the factor 1lP, when P > 0.5. When P is S 0.5, the W(Z) values should be rnultiplied by the factor 1/(0.5), or 2.0. This is consistent with the adjustment in the Fo(Z) limit at part power conditions. The Fo(Z) penalty function, applied when the analytic Fo(Z) function increases from one monthly measurement to the next, is provided in Table 5.1-3. 5.1 .7 LCO g.Z.lNuclear Enthalpy Rise Hot Channel Factor I flr1 {, acFo, . (1+ PFo* (1- e11s Where: cFo, = 1.59 up to 6,000 MWD/MTU And, CFo, = 1'62 from 6,000 tuWD/tuTU to EOL PF AH 

                                           = 0.3 ID -_ THERMAL POWER RATED THERMAL POWER 5.1 .8           LCO 3.2.3 Axial Flux Difference (AFD)

The AFD acceptable operation limits are provided in Figure 5.1-4. 5.1 .9 LCO 3.3.1 Reactor Trip Svstem lnstrumentation - Overtemperature and Overpower AT Parameter Values from Table Notations 3 and 4 a Overtempprature AT Setpoint Parameter Values: Parameter Value Overtemperature AT reactor trip setpoint K1 < 1.239 Overtemperature AT reactor trip setpoint Tavg K2> 0.0183/.F coefficient Overtemperature AT reactor trip setpoint pressure K3 > 0.001ipsia coefficient Tavg at RATED THERTUAL POWER T', < 574.20p(t) $ An additional uncertainty is to be applied if the number of measured thimbles for the moveable incore detector system is less than 75% of the total number of thimbles. If there are less than 75% of the total number of thimbles and at least 50% of the total number of thimbles measured, and additional uncertainty of (0.01)"(3-T/12.5) is added to the standard uncertainty on FNAH of 1 .04, where T is the total number of measured thimbles. At least three measured thimbles per core quadrant are also required. (1) T'represents the cycle-specific Full Power Tavg value used in core design. COLR Cycle 20 Beaver Valley Unit 2 5.1 -3 LRIU Revision 90

Licensing Requirements Manual Core Operating Limits Report 5-1 5.1 Core Operating Limits Fleport Nom inal pressurizer pressu re P' > 2250 psia Jvleasured reactor vessel AT lead/lag time constants Tr = 0 sec* (. The response time is toggled off to meet the analysis tz= 0 sgc* value of zero.) Measured reactor vessel AT lag time constant rs ( 6 secs ltleasured reactor vessel average temperature lead/lag t+ 2 30 secs time constants rs < 4 secs Measured reactor vessel average temperature lag time ra < 2 SecS constant f (Al) is a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers, with gains to be selected based on measured instrument response during plant startup tests such that: (i) Forqr - gu between -il7"/oand +157o, fr(AI) = 0, where gt and Quflre percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and Qt + Qn is total THERMAL POWER in percent of RATED THERh/AL POWER. (ii) For each percent that the magnitude of (qt - Qu) exceeds -37o/", the AT trip setpoint shall be automatically reduced by 2.52% of its value at RATED THERTUAL POWER. (iii) For each percent that the magnitude of (qt - Qo) exceeds +157o, the AT trip setpoint shall be automatically reduced by 1.47% of its value at RATED THERIVIAL POWER.

b. Overpower AT Setpoint Parameter Values:

Parameter Value Overpower AT reactor trip setpoint K4 < 1.094 Overpower AT reactor trip setpoint Tavg K5 > 0.02/"F for increasing rate/lag coefficient average temperature K5 = 0/"F for decreasing average temperature Overpower AT reactor trip setpoint Tavg K6>0.0021/oFforT>T" heatup coefficient K6=0/'FforT<T" Tavg at RATED THEHN/AL POWER T" < 574.201(t\ [\ileasured reactor vessel AT lead/lag Tr = 0 sec* time constants Tz = 0 sec* (. The response time is toggled off to meet the analysis value of zero.) (1) T" represenls the cycle-specific Full Power Tavg value used in core design COLR Cycle 20 Beaver Valley Unit 2 5.1 -4 LRIU Revision 90

Licensing Requirements Manual Core Operating Limits Report 5.1 5,1 Core Operating Limits Report Jvleasured reactor vessel AT lag time rs < 6 secs constant Ntleasured reactor vessel average tu t 2 SecS temperature lag time constant Measured reactor vessel average rz > 10 secs temperature rateilag time constant 5.1.10 LCO 3.4.1. RCS Pressure. Temperature. and Flow Departure from Nucleate Boilinq (DNB) Limits Pararneter lndicated Value Reactor Coolant System Tavg Tavg < 577.8'F(1) Pressurizer Pressure Pressure > 2214 psia(z) Reactor Coolant System Total FIow Flate Flow > 267,483 gpmts) 5.1 .'1 1 LCO 3.9.1 Boron Concentration (h/ODE 6) The boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained >2400 ppm. This value includes a 50 ppm conservative allowance for uncertainties. (1) The Reactor Coolant System (HCS) indicated Tavg value is determined by adding the appropriate allowances for rod control operation and verification via control board indication (3.6"F) to the cycle specific full power Tavg used in the core design. (2) The pressurizer pressure value includes allowances for pressurizer pressure control operation and verification via control board indication. (3) The RCS total flow rate includes allowances for normalization of the cold leg elbow taps with a beginning of cycle precision RCS flow calorimetric measurement and verification on a periodic basis via control board indication. COLR Cycle 20 Beaver Valley Unit 2 5.1 -5 LRNI Revision 90

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1 .12 References 1 WCAP.9272-P-A,'WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1 985 (Westinghouse Proprietary). 2 WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions," September 1986. J WCAP-12945-P-A, Volume 1 (Ftevision 2) and Volumes 2 through 5 (Hevision 1), "Code Qualification Document for Best Estimate LOCA Analysis," Nilarch 1 998 (Westinghouse Proprietary).

4. WCAP-10216-P-4, Revision 1A, "Relaxation of Constant Axial Offset Control-Fo Surueillance Technical Specification," February 1 994.
5. WCAP-1 4565-P-A, "VlPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis,"

October 1999. 6 WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Heport," April 1 gg5 (Westinghouse Proprietary). 7 WCAP-1 5025-P-A, "Modified WHB-2 Correlation, WFIB-zM, for Predicting Critical Heat Flux in 17x17 Rod Bundles with Modified LPD lrilixing Vane Grids," April 1999. I Caldon, lnc. Engineering Report-80P, "lmproving Thermal Power Accuracy and Plant Safety While lncreasing Operating Power Level Using the LEFTU{rM System," Revision 0, lvlarch 1997. q Caldon, Inc. Engineering Report-'160P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFIvlr/rM System," Revision 0, May 2000.

10. WCAP-13749-P-A, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient JVIeasurement," March 1 997 (Westinghouse Proprietary).

11 . WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PAFiAGON," August 2004.

12. WCAP-16045-P-4, Addendum 1-A, "Qualification of the NEXUS Nuclear Data tt/ethodology," August 2007.

COLR Cycle 20 Beaver Valley Unit 2 5.1 -6 LRIVI Revision 90

Licensing Requirements Manual Core Operating Limits Report 5.1 670 660 2435 PSIA UNACCEPTABLE OPERATION 650 640 630 

-

bo A h0 d F 620 

                                                                                 \

I92O PSIA 610 600 ACCEPTABLE OPERATION 590 580 0 o.2 0.4 0.6 0.8 1 7.2 1.4 FRACTION OF RATED THERMAL POWER Figure 5.1-1 (Page 1 of 1) HEACTOR CORE SAFETY LIIUIT THREE LOOP OPERATION (Technical Specif ication Safety Limit 2.1 .1) COLR Cycle 20 Beaver Valley Unit 2 5.1 -7 LRM Revision 90

Licensing Requirements Jvlanual Core Operating Limits Report 5.1 225 54.53, 

                                           /

E 200 BANK C 100, 1 E 175 (d 

     =                                                                     /

E 

    ?_

I 

                             /                                        /
                                                                    /

A 150 

    =U' o-o                 /

g 125 / z o E a 

                  ,114                         BANK D    /

o E 100 L 

    }c z                                            /
                                             /

T co 75 o / o 

                                                             !

E 

                                    /

50 f 25 

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(8, 0) 

                    ,l 0

0 10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 5.1-2 (Page 1 of 1) CONTROL ROD INSERTION LIMITS AS A FUNCTION OF RATED POWER LEVEL COLR Cycle 20 Beaver Valley Unit 2 5.1 -8 LRtvl Revision 90

Licensing Requirements Manual Core Operating Limits Fleport 5.1 1.2 o.o, 1.oo 6.0, 1.OO t 1.O 12.O, 0.92.5 o.8 s o.6 M o.4 o.2 o.o o 2 4 6 8 10 t2 Core Height (feet) Figure 5.1-3 (Page 1 of 1) FoT NORIVIALIZED OPERATING ENVELOPE, K(Z) COLR Cycle 20 Beaver Valley Unit 2 5.1 -9 LRM Revision 90

Licensing Requirements Manual Core Operating Limits Report 5-1 I20 110 

                                                                              .l f                          +     f J

100 I \ 

                                                               \

90 F I t t-NA CCE PT AB LE I UNAC CE PT AB LE U OP ERAT ION \ OPERATION CC EP TABL E L I OP ERAT IO N \ o BO 

                                         /                             \

o 

=

o- -o 70 I I F L I o 

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                                     /

F 60 t, o I I I E TE I I 50 o

  • o o\ (-25, 50) (+22, 5 0) 40 30 20 10 0
      -60   -50     -40    -30      -20      -10        0      10           20        30      40     50       60 Axial Flux Difference (Delta l)%

Figure 5.1-4 (Page 1 of 1) AXIAL FLUX DIFFERENCE LIhTITS AS A FUNCTION OF PERCENT OF HATED THERT\4AL POWER FOR RAOC COLR Cycle 20 Beaver Valley Unit 2 5.1 - 10 LR[/ Revision 90

Licensing Flequirements Manual Core Operating Limits Fleport 5.1 

          -30 . 00                                CYCI.E    BTIRI{T,P     uTc (rilr{D/HEU}       (pcm/orI t

o 1{000 18000 

                                                                        -30.08
                                                                        -31.34 IE Fl F

H H U H Er Fr ftl o U frl fr D E{ 

          -31 " 00
      #

H H fsl H fi o Fl 

      #

frl fI o E 

          -32.00 14000          15000          16000             17000           18000 cYcLE BIIRNLTP (MWD/!,rrU)

Figure 5.1-5 (Page 1 of 1) HOT FULL POWER PREDICTED MODERATOH TEMPEFIATU RE COEFFICI ENT AS A FUNCTION OF CYCLE BURNUP WHEN 3OO PPIVI IS ACHIEVED COLR Cycle 20 Beaver Valley Unit 2 5.1 - 11 LRM Revision 90

Licensing Requirements lvlanual Core Operating Limits Report 5.1 Table 5.1-1 (Page 1 of 2) Fo Surveillance W(Z) Function versus Burnup at 100% HTP Exclusion Axial Elevation 150 3000 8000 1 2000 1 6000 Zone Point (feet) (MWD/MTU) (MWD/MTU) (MWD/MTU) (MWD/MTU) (MWD/MTU)

  • 1 12,1 1.0000 1.0000 1.0000 1.0000 1.0000
  • 2 11.9 1.0000 1.0000 1.0000 1,0000 1,0000
  • 3 11.7 1.0000 1.0000 1.0000 1.0000 1,0000
  • 4 11.5 1.0000 1.0000 1.0000 1.0000 1.0000
  • 1.0000 1.0000 1.0000 5 11.3 1,0000 1.0000
  • 1.0000 1.0000 1.0000 1.0000 1.0000 6 11.1
  • 7 10.9 1.0000 1.0000 1.0000 1.0000 1.0000 8 10.7 1.1275 1.1787 1.2521 1.2179 1.2248 I 10.5 1.1226 1.1755 1.2449 1.21 19 1.2180 10 10.3 1.1166 1.1701 1.2362 1.2077 1.2112 11 10.1 1.1095 1.1630 1.2261 1.2056 1.2054 12 9.9 1.1025 1.1608 1.2156 1.2087 1 .1 990 13 9.7 1.0974 1.1611 1.2086 1.2095 1.1921 14 9.5 1.0979 1.1596 1.2109 1.2083 1.1850 15 9.3 1 .1035 1 .1543 1.2091 1.2057 1.1789 16 9.1 1.1 103 1 .1501 1.20s7 1.2029 1.1827 17 8.9 1.1155 1.1467 1.2091 1.2028 1 .1869 18 8.7 1.1232 1.1523 1.2145 1.2064 1 .1884 1g 8.5 1 .1306 1.1580 1.2188 1.2156 1 .1931 20 8.3 1 .1363 1.1618 1.2210 1.2218 1.2051 21 8.1 1.1409 1.1640 1.2207 1.2256 1.2143 22 7.9 1.1442 1.1650 1.2189 1.2275 1.2215 23 7.6 1.1452 1.1636 1.2145 1.2267 1.2261 24 7.4 1.1452 1 .1612 1.2088 1.2243 1.2292 25 7.2 1.1435 1.1567 1.2002 1.2187 1.2286 26 7.0 1.1409 1.1511 1.1899 1.2109 1.2256 27 6.8 1.1371 1.1443 1.1785 1.2025 1.2212 28 6.6 1.1316 1.1360 1.1656 1.1924 1.2154 29 6.4 1.1256 1.1269 1.1528 1.1808 1.2077 30 6.2 1.1 190 1.1 169 1.1435 1.1678 1"1981 31 6.0 1.1 158 1.1 104 1.1332 1.1538 1.1871 32 5.8 1.1122 1.1040 1.1222 '1.1391 1.1751 Note: Top and Bottom 10% Excluded COLR Cycle 20 Beaver Valley Unit 2 5.1 - 12 LR[/ Flevision 90

Licensing Requirements Manual Core Operating Limits Fleport 5.1 Table 5.1-1 (Page 2 ot 2) Fo Surueillance W(Z) Function versus Burnup at 100% RTP Exclusion Axial Elevation 150 3000 8000 1 2000 1 6000 Zone Point (feet) (MWD/MTU) (MWD/MTU) (MWD/MTU) (MWD/MTU) (MWD/MTU) 33 5.6 1"1083 1.1005 1.1107 1.1237 1.1616 34 5.4 1.1091 1.1001 1.1021 1.1144 1_1455 35 5.2 1.1150 1.1001 1.0975 1.1101 1.1357 36 5.0 1.1217 1.1019 1.0954 1.1066 1.1315 37 4.8 1.1281 1.1051 1.0926 1.1027 1.1259 38 4.6 1.1342 1.1086 1.0898 1.0984 1.1 199 39 4.4 1.1401 1.1 1 1g 1.0868 1.0938 1 .1 132 40 4.2 1.1455 1.1 149 1.0838 1.0893 1 .1064 41 4,0 1.1503 1.1 176 1.0809 1.0848 1.0996 42 3.8 1.1552 1.1207 1.0775 1.0794 1.0914 43 3.6 1.1596 1.1255 1.0740 1.0747 1.0830 44 3.4 1 .1660 1.1303 1.0704 1 .0715 1.0757 45 3.2 1.1740 1.1347 1.0697 1.0701 1.0748 46 3.0 1 .1796 1.1384 1.0704 1.0686 1.0808 47 2.8 1.1971 1.1540 1.0757 1.0726 1.0933 48 2.6 1.2239 1.1770 1.0888 1.0830 1.1069 49 2.4 1.2498 1.1988 1.1038 1.0946 1.1211 50 2.2 1.2762 1.2215 1.1 190 1.1077 1.1357 51 2.0 1.3026 1.2440 1.1338 1.1200 1.1492 52 1.8 1.3285 1.2663 1.1482 1.1318 1.1618 53 1.6 1.3523 1.2869 1.1619 1.1431 1.1741 54 1.4 1.3739 1.3057 1.1743 1 .1535 1.1855

  • 55 1.2 1.0000 1.0000 1.0000 1.0000 1.0000
  • 56 1.0 1.0000 1.0000 1.0000 1.0000 1.0000
  • 57 0.8 1.0000 1.0000 1.0000 1.0000 1.0000
  • 58 0.6 1.0000 1.0000 1.0000 1.0000 1.0000
  • 59 0.4 1.0000 1.0000 1.0000 1.0000 1.0000
  • 60 0.2 1.0000 1.0000 1.0000 1.0000 1.0000
  • 61 0.0 1.0000 1.0000 1.0000 1.0000 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 20 Beaver Valley Unit 2 5.1 - 13 LFtlVl Revision 90

Licensing Requ i rements lvlanual Core Operating Limits Fleport 5.1 Table 5.1-Z (Page 1 of 2) Fo Surveillance W(Z) Function at Initial Cycle Startup a175"/" RTP Exclusion Zone Axial Point Elevation (feet) 75% RTP

  • 1.0000 1 12.1
  • 2 11.9 1.0000
  • 11.7 1.0000 J
  • 4 11.5 1.0000
  • 5 11.3 1.0000
  • 6 11.1 1.0000
  • 7 10.9 1.0000 I 10.7 1.2169 I 10.5 1.1980 10 10.3 1.1775 11 10.1 1.1555 12 qq 1.1333 13 9.7 1.1 134 14 9.5 1 .1003 15 oa 1.0940 16 9.1 1.0895 17 8.9 1.0856 18 8.7 1.0863 19 8.5 1.0870 20 8.3 1.0856 21 8.1 1.0867 22 7.9 1.0860 23 7.6 1.0841 24 7.4 1.0828 25 7.2 1.0782 to 7.0 1.0765 27 6.8 1.0734 28 6.6 1.0678 29 6.4 1.0629 30 6.2 1.0587 31 6.0 1.0579 32 5.8 1.0559 Note: Top and Bottom 10% Excluded COLR Cycle 20 Beaver Valley Unit 2 5.1 - 14 LRIV Revision 90

Licensing Requirements Jvlanual Core Operating Limits Fleport 5.1 Table 5.1-2 (Page 2 of 2) Fo Surveillance W(Z) Function at lnitial Cycle Startup al75/o HTP Exclusion Zone Axial Point Elevation (feet) 75o/" RTP 33 5.6 1.0541 34 5.4 1.0579 35 5.2 1.0650 36 5.0 1.0731 37 4.8 1.0816 38 4.6 1.0901 39 4.4 1.0992 40 4.2 1.1080 41 4.0 1.1170 42 3.8 1.1253 43 3.6 1.1336 44 3.4 1.1438 45 3.2 1.1554 46 3.0 1.1647 47 2.8 1.1858 4B 2.6 1.2161 49 2.4 1.2458 50 2.2 1.2766 51 2.0 1.3076 52 1.8 1.3379 53 1.6 1.3662 54 1.4 1.3923

  • 55 1.2 1.0000
  • 1.0000 56 1.0
  • 57 0.8 1.0000
  • 5B 0.6 1.0000
  • 59 0.4 1.0000
  • 1.0000 60 0.2
  • 61 0.0 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 20 Beaver Valley Unit 2 5.1 - 15 LHM Revision 90

Licensing Requirements Manual Core Operating Limits Heport 5.1 Table 5.1-3 (Page 1 of 1) Fo(Z) Penalty Factor versus Burnup Cycle Burnup (lvlWD/MTU) Fo(Z) Penalty Factor 0-450 1 .0237 

                               > 450                        1.0200 Note: The Penalty Factor, to be applied to Fq(Z) in accordance with Technical Specification Surveillance Requirement (SR) 3.2.1.2, is the maximum factor by which Fo(Z) is expected to increase over a 39 Effective Full Power Day (EFPD) interval (surveillance interval of 31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance interval per Technical Specification SH 3.0.2) starting from the burnup at which the Fq(Z) was deterrnined.

COLH Cycle 20 Beaver Valley Unit 2 5.1 - 16 LRIU Revision 90}}

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