L-18-119, Cycle 26 Core Operating Limits Report

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Cycle 26 Core Operating Limits Report
ML18141A321
Person / Time
Site: Beaver Valley
Issue date: 05/21/2018
From: Bologna R
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-18-119
Download: ML18141A321 (18)
v • d • e


Text

FENOC^ Beaver Valley Power Station P.O. Box 4 FirstEnery Nudear Opnting Company pA 1il77 Shippingport, Richard D. Bologna 724-682-5234 Site Vice President Fax:724543-8069 May 21,2018 L-18-1 19 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DpR-66 Pursuant to the requirements of Beaver Valley Power Station, Unit No. 1 Technical specification 5.0.3, 'coRE opERATtNG LtMtrs REpoRr tior_i1,, iiistEnergy Nuclear Operating Company hereby submits the COLR for Cycle e'd. tetnnicat Specification 5.6.3.d requires, in part, that the COLR be provided to the Nuctear Regulatory Commission upon issuance for each reload cycle, includinj any midcycle revisions or supplements. The Cycle 26 COLR was made effective on"nprii 26,20tg.

There are no regulatory commitments contained in this submittal. lf there are any questions or if additional information is qequired, please contact Mr. Thomas A. Llntz, Manager - Nuclear Licensing & Regulatory Affaiis, at (330) 31s-6glo.

Sincerely, Richard D Enclosure Beaver Valley Power station, unit No. 1, core operating Limits Report, cycle 26 cc: NRG Region lAdministrator NRC Resident lnspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative

Enclosure L-18-119 Beaver Valley Power Station, Unit No. 1 Core Operating Limits Report, Cycle 26 (16 Pages Follow)

Licensing Requirements Manual Core Operating Limits Report 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Core Operating Limits Report This Core Operating Limits Report provides the cycle specific parameter limits developed in accordance with the NRC approved methodologies specified in Technical Specification Administrative Control 5.6.3.

5.1.1 SL 2.1.1 Reactor Core Safety Limits See Figure 5.1-1.

5.1.2 SHUTDOWN MARGIN (SDM)

a. In MODES 1, 2, 3, and 4, SHUTDOWN MARGIN shall be 1.77% k/k.(1)
b. Prior to manually blocking the Low Pressurizer Pressure Safety Injection Signal, the Reactor Coolant System shall be borated to the MODE 5 boron concentration and shall remain this boron concentration at all times when this signal is blocked.
c. In MODE 5, SHUTDOWN MARGIN shall be 1.0% k/k.

5.1.3 LCO 3.1.3 Moderator Temperature Coefficient (MTC)

a. Upper Limit - MTC shall be maintained within the acceptable operation limit specified in Technical Specification Figure 3.1.3-1.
b. Lower Limit - MTC shall be maintained less negative than - 4.4 x 10-4 k/k/F at RATED THERMAL POWER.
c. 300 ppm Surveillance Limit: (- 37 pcm/F)
d. The revised predicted near-EOL 300 ppm MTC shall be calculated using Figure 5.1-5 and the following algorithm from Reference 11 :

Revised Predicted MTC = Predicted MTC* + AFD Correction** + Predictive Correction***

where,

  • Predicted MTC 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 (AFD

  • AFD Sensitivity)}

where: AFD 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 pcm/F / AFD

      • Predictive Correction is -3 pcm/F.

(1) The MODE 1 and MODE 2 with keff 1.0 SDM requirements are included to address SDM requirements (e.g., MODE 1 Required Actions to verify SDM) that are not within the applicability of LCO 3.1.1, SHUTDOWN MARGIN (SDM).

COLR Cycle 26 Beaver Valley Unit 1 5.1 - 1 LRM Revision 101

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report If the revised predicted MTC is less negative than the SR 3.1.3.2 limit (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: (- 42.5 pcm/F) 5.1.4 LCO 3.1.5 Shutdown Bank Insertion Limits The Shutdown Banks shall be withdrawn to at least 225 steps.(2) 5.1.5 LCO 3.1.6 Control Bank Insertion Limits
a. Control Banks A and B shall be withdrawn to at least 225 steps.(2)
b. Control Banks C and D shall be limited in physical insertion as shown in Figure 5.1-2.(2)
c. Sequence Limits - The sequence of withdrawal shall be A, B, C and D bank, in that order.
d. Overlap Limits(2) - 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 (FQ(Z))

The Heat Flux Hot Channel Factor - FQ (Z) limit is defined by:

CFQ FQ (Z)

  • K(Z) for P > 0.5 P

CFQ FQ (Z)

  • K(Z) for P 0.5 0.5 THERMAL POWER Where: CFQ = 2.40 P = RATED THERMAL POWER K(Z) = the function obtained from Figure 5.1-3.

C M FQ (Z) = FQ (Z)

  • 1.0815$

FQW (Z) = FQC (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. If there are less than 75% of the total number of thimbles and at least 50% of the total number of thimbles measured, an 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 26 Beaver Valley Unit 1 5.1 - 2 LRM Revision 101

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report The W(Z) values are provided in Table 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 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 1/P, when P > 0.5. When P is 0.5, the W(Z) values should be multiplied by the factor 1/(0.5), or 2.0. This is consistent with the adjustment in the FQ(Z) limit at part power conditions.

The FQ(Z) penalty function, applied when the analytic FQ(Z) function increases from one monthly measurement to the next, is provided in Table 5.1-3.

5.1.7 LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( FNH )

FNH < CFH * (1 + PFH (1-P))$

Where: CFH = 1.62 PFH = 0.3 THERMAL POWER P = 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 System Instrumentation - Overtemperature and Overpower T Parameter Values from Table Notations 1 and 2

a. Overtemperature T Setpoint Parameter Values:

Parameter Value Overtemperature T reactor trip setpoint K1 1.242 Overtemperature T reactor trip setpoint Tavg K2 0.0183/F coefficient Overtemperature T reactor trip setpoint pressure K3 0.001/psia coefficient Tavg at RATED THERMAL POWER T' 577.9F(1)

$ 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, an additional uncertainty of (0.01)*(3-T/12.5) is added to the standard uncertainty on FNH 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 26 Beaver Valley Unit 1 5.1 - 3 LRM Revision 101

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report Nominal pressurizer pressure P' 2250 psia Measured reactor vessel average temperature lead/lag 1 30 secs time constants 2 4 secs Measured reactor vessel T lag time constant 4 6 secs Measured reactor vessel average temperature lag 5 2 secs time constant f (I) 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) For qt - qb between -37% and +15%, f(I) = 0 (where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POWER in percent of RATED THERMAL POWER).

(ii) For each percent that the magnitude of (qt - qb) exceeds -37%, the T trip setpoint shall be automatically reduced by 2.52% of its value at RATED THERMAL POWER.

(iii) For each percent that the magnitude of (qt - qb) exceeds +15%, the T trip setpoint shall be automatically reduced by 1.47% of its value at RATED THERMAL POWER.

b. Overpower T Setpoint Parameter Values:

Parameter Value Overpower T reactor trip setpoint K4 1.085 Overpower T reactor trip setpoint Tavg K5 0.02/F for increasing rate/lag coefficient average temperature K5 = 0/F for decreasing average temperature Overpower T reactor trip setpoint Tavg K6 0.0021/F for T > T" heatup coefficient K6 = 0/F for T T" Tavg at RATED THERMAL POWER T" 577.9F(2)

Measured reactor vessel average 3 10 secs temperature rate/lag time constant Measured reactor vessel T lag time 4 6 secs constant Measured reactor vessel average 5 2 secs temperature lag time constant (2) T represents the cycle-specific Full Power Tavg value used in core design.

COLR Cycle 26 Beaver Valley Unit 1 5.1 - 4 LRM Revision 101

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.10 LCO 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits Parameter Indicated Value Reactor Coolant System Tavg Tavg 581.5F(1)

Pressurizer Pressure Pressure 2218 psia(2)

Reactor Coolant System Total Flow Rate Flow 268,668 gpm(3) 5.1.11 LCO 3.9.1 Boron Concentration (MODE 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 (RCS) indicated Tavg value is determined by adding the appropriate allowances for rod control operation and verification via control board indication (3.6F) 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 26 Beaver Valley Unit 1 5.1 - 5 LRM Revision 101

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 1985 (Westinghouse Proprietary).
2. WCAP-8745-P-A, "Design Bases for the Thermal Overpower T and Thermal Overtemperature T Trip Functions," September 1986.
3. WCAP-12945-P-A, Volume 1 (Revision 2) and Volumes 2 through 5 (Revision 1), "Code Qualification Document for Best Estimate LOCA Analysis," March 1998 (Westinghouse Proprietary).
4. WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset Control-FQ Surveillance Technical Specification," February 1994.
5. WCAP-14565-P-A, "VIPRE-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 Report,"

April 1995 (Westinghouse Proprietary).

7. WCAP-15025-P-A, "Modified WRB-2 Correlation, WRB-2M, for Predicting Critical Heat Flux in 17x17 Rod Bundles with Modified LPD Mixing Vane Grids," April 1999.
8. Caldon, Inc. Engineering Report-80P, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFMTM System," Revision 0, March 1997.
9. Caldon, Inc. Engineering Report-160P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFMTM System," Revision 0, May 2000.
10. WCAP-16009-P-A, "Realistic Large Break LOCA Evaluation Methodology Using Automated Statistical Treatment of Uncertainty Method (ASTRUM),"

Revision 0, January 2005.

11. WCAP-13749-P-A, Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement, March 1997 (Westinghouse Proprietary).
12. WCAP-16045-P-A, Qualification of the Two-Dimensional Transport Code PARAGON, August 2004.
13. WCAP-16045-P-A, Addendum 1-A, Qualification of the NEXUS Nuclear Data Methodology, August 2007.

COLR Cycle 26 Beaver Valley Unit 1 5.1 - 6 LRM Revision 101

Licensing Requirements Manual Core Operating Limits Report 5.1 670 660 2435 PSIA UNACCEPTABLE OPERATION 650 2250 PSIA 640 630 Tavg (Deg F) 2000 PSIA 620 1920 PSIA 610 600 ACCEPTABLE OPERATION 590 580 0 0.2 0.4 0.6 0.8 1 1.2 1.4 FRACTION OF RATED THERMAL POWER Figure 5.1-1 (Page 1 of 1)

REACTOR CORE SAFETY LIMIT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1)

COLR Cycle 26 Beaver Valley Unit 1 5.1 - 7 LRM Revision 101

Licensing Requirements Manual Core Operating Limits Report 5.1 54.53, 225 200 100, 187 BANK C 150 Rod Bank (Steps Withdrawn) 0, 114 BANK D 100 50 8,0 0

0 20 40 60 80 100 Relative Power (Percent)

Figure 5.1-2 (Page 1 of 1)

CONTROL ROD INSERTION LIMITS COLR Cycle 26 Beaver Valley Unit 1 5.1 - 8 LRM Revision 101

Licensing Requirements Manual Core Operating Limits Report 5.1 1.2 0.0, 1.00 6.0, 1.00 1.0 12.0, 0.925 0.8 K(Z) 0.6 0.4 0.2 0.0 0 2 4 6 8 10 12 Core Height (feet)

Figure 5.1-3 (Page 1 of 1)

FQT NORMALIZED OPERATING ENVELOPE, K(Z)

COLR Cycle 26 Beaver Valley Unit 1 5.1 - 9 LRM Revision 101

Licensing Requirements Manual Core Operating Limits Report 5.1 1 20 1 10

( -8 , 10 0) ( +8 , 10 0) 1 00 90 UN AC CE PT AB LE U NA CCE PT AB LE OP ER AT IO N O PE RA TI ON

% of R at ed T her ma l Po we r A CC EP TA BL E OP ER AT IO N 80 70 60 50

(-2 5, 5 0) (+2 2, 50) 40 30 20 10 0

- 60 -50 -4 0 -3 0 - 20 - 10 0 10 20 30 40 50 60 Axi al F lu x Di ff eren ce (D el ta I )%

Figure 5.1-4 (Page 1 of 1)

AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RATED THERMAL POWER FOR RAOC COLR Cycle 26 Beaver Valley Unit 1 5.1 - 10 LRM Revision 101

Licensing Requirements Manual Core Operating Limits Report 5.1 Figure 5.1-5 (Page 1 of 1)

HOT FULL POWER PREDICTED MODERATOR TEMPERATURE COEFFICIENT AS A FUNCTION OF CYCLE BURNUP WHEN 300 PPM IS ACHIEVED COLR Cycle 26 Beaver Valley Unit 1 5.1 - 11 LRM Revision 101

Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-1 (Page 1 of 2)

FQ Surveillance W(Z) Function versus Burnup at 100% RTP Exclusion Axial Elevation 150 3000 8000 12000 16000 Zone Point (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU

  • 1 12.08 1.0000 1.0000 1.0000 1.0000 1.0000
  • 2 11.88 1.0000 1.0000 1.0000 1.0000 1.0000
  • 3 11.68 1.0000 1.0000 1.0000 1.0000 1.0000
  • 4 11.47 1.0000 1.0000 1.0000 1.0000 1.0000
  • 5 11.27 1.0000 1.0000 1.0000 1.0000 1.0000
  • 6 11.07 1.0000 1.0000 1.0000 1.0000 1.0000
  • 7 10.87 1.0000 1.0000 1.0000 1.0000 1.0000 8 10.67 1.1275 1.1799 1.2476 1.2393 1.2320 9 10.47 1.1232 1.1771 1.2408 1.2270 1.2192 10 10.27 1.1177 1.1754 1.2323 1.2097 1.2037 11 10.07 1.1111 1.1794 1.2225 1.2024 1.2003 12 9.86 1.1046 1.1741 1.2118 1.2048 1.1979 13 9.66 1.0981 1.1696 1.2109 1.2050 1.1946 14 9.46 1.0958 1.1633 1.2104 1.2032 1.1906 15 9.26 1.1019 1.1534 1.2059 1.2000 1.1864 16 9.06 1.1090 1.1497 1.2059 1.1966 1.1808 17 8.86 1.1145 1.1486 1.2044 1.1957 1.1771 18 8.66 1.1223 1.1569 1.2072 1.1975 1.1792 19 8.46 1.1300 1.1609 1.2114 1.2046 1.1837 20 8.25 1.1360 1.1640 1.2133 1.2102 1.1952 21 8.05 1.1408 1.1654 1.2130 1.2134 1.2041 22 7.85 1.1444 1.1657 1.2113 1.2150 1.2112 23 7.65 1.1457 1.1639 1.2073 1.2143 1.2159 24 7.45 1.1459 1.1610 1.2020 1.2122 1.2193 25 7.25 1.1446 1.1562 1.1940 1.2072 1.2194 26 7.05 1.1423 1.1508 1.1846 1.2003 1.2172 27 6.84 1.1387 1.1446 1.1741 1.1928 1.2136 28 6.64 1.1336 1.1369 1.1621 1.1840 1.2090 29 6.44 1.1279 1.1284 1.1489 1.1739 1.2026 30 6.24 1.1219 1.1195 1.1370 1.1624 1.1945 31 6.04 1.1146 1.1094 1.1275 1.1501 1.1851 32 5.84 1.1101 1.1026 1.1175 1.1371 1.1746 Note: Top and Bottom 10% Excluded COLR Cycle 26 Beaver Valley Unit 1 5.1 - 12 LRM Revision 101

Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-1 (Page 2 of 2)

FQ Surveillance W(Z) Function versus Burnup at 100% RTP Exclusion Axial Elevation 150 3000 8000 12000 16000 Zone Point (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 33 5.64 1.1081 1.1010 1.1095 1.1234 1.1627 34 5.44 1.1098 1.1007 1.1087 1.1154 1.1480 35 5.23 1.1169 1.1023 1.1068 1.1138 1.1382 36 5.03 1.1236 1.1042 1.1048 1.1109 1.1349 37 4.83 1.1300 1.1060 1.1024 1.1078 1.1303 38 4.63 1.1363 1.1087 1.0996 1.1042 1.1251 39 4.43 1.1422 1.1123 1.0965 1.1002 1.1192 40 4.23 1.1476 1.1153 1.0932 1.0960 1.1131 41 4.03 1.1524 1.1182 1.0898 1.0916 1.1067 42 3.83 1.1571 1.1208 1.0857 1.0864 1.0989 43 3.62 1.1617 1.1242 1.0813 1.0804 1.0905 44 3.42 1.1655 1.1285 1.0761 1.0766 1.0843 45 3.22 1.1708 1.1332 1.0771 1.0749 1.0768 46 3.02 1.1763 1.1357 1.0835 1.0724 1.0825 47 2.82 1.1910 1.1480 1.0934 1.0755 1.0963 48 2.62 1.2136 1.1681 1.1071 1.0854 1.1088 49 2.42 1.2361 1.1878 1.1223 1.0971 1.1226 50 2.21 1.2593 1.2080 1.1378 1.1092 1.1366 51 2.01 1.2834 1.2282 1.1530 1.1208 1.1495 52 1.81 1.3073 1.2482 1.1678 1.1320 1.1617 53 1.61 1.3292 1.2666 1.1818 1.1430 1.1735 54 1.41 1.3490 1.2833 1.1945 1.1532 1.1847

  • 55 1.21 1.0000 1.0000 1.0000 1.0000 1.0000
  • 56 1.01 1.0000 1.0000 1.0000 1.0000 1.0000
  • 57 0.81 1.0000 1.0000 1.0000 1.0000 1.0000
  • 58 0.60 1.0000 1.0000 1.0000 1.0000 1.0000
  • 59 0.40 1.0000 1.0000 1.0000 1.0000 1.0000
  • 60 0.20 1.0000 1.0000 1.0000 1.0000 1.0000
  • 61 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 26 Beaver Valley Unit 1 5.1 - 13 LRM Revision 101

Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-2 (Page 1 of 2)

FQ Surveillance W(Z) Function versus Burnup at 75% RTP Exclusion Axial Elevation Zone Point (feet) 75% RTP

  • 1 12.08 1.0000
  • 2 11.88 1.0000
  • 3 11.68 1.0000
  • 4 11.47 1.0000
  • 5 11.27 1.0000
  • 6 11.07 1.0000
  • 7 10.87 1.0000 8 10.67 1.2775 9 10.47 1.2581 10 10.27 1.2312 11 10.07 1.1967 12 9.86 1.1604 13 9.66 1.1274 14 9.46 1.1031 15 9.26 1.0924 16 9.06 1.0852 17 8.86 1.0799 18 8.66 1.0786 19 8.46 1.0792 20 8.25 1.0794 21 8.05 1.0794 22 7.85 1.0795 23 7.65 1.0783 24 7.45 1.0769 25 7.25 1.0750 26 7.05 1.0729 27 6.84 1.0699 28 6.64 1.0655 29 6.44 1.0616 30 6.24 1.0578 31 6.04 1.0527 32 5.84 1.0502 Note: Top and Bottom 10% Excluded COLR Cycle 26 Beaver Valley Unit 1 5.1 - 14 LRM Revision 101

Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-2 (Page 2 of 2)

FQ Surveillance W(Z) Function versus Burnup at 75% RTP Exclusion Axial Elevation 75% RTP Zone Point (feet) 33 5.64 1.0506 34 5.44 1.0554 35 5.23 1.0650 36 5.03 1.0745 37 4.83 1.0843 38 4.63 1.0940 39 4.43 1.1033 40 4.23 1.1119 41 4.03 1.1195 42 3.83 1.1289 43 3.62 1.1378 44 3.42 1.1451 45 3.22 1.1539 46 3.02 1.1633 47 2.82 1.1818 48 2.62 1.2087 49 2.42 1.2353 50 2.21 1.2627 51 2.01 1.2913 52 1.81 1.3198 53 1.61 1.3463 54 1.41 1.3698

  • 55 1.21 1.0000
  • 56 1.01 1.0000
  • 57 0.81 1.0000
  • 58 0.60 1.0000
  • 59 0.40 1.0000
  • 60 0.20 1.0000
  • 61 0.00 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 26 Beaver Valley Unit 1 5.1 - 15 LRM Revision 101

Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-3 (Page 1 of 1)

FQ(Z) Penalty Factor versus Burnup Cycle Burnup (MWD/MTU) FQ(Z) Penalty Factor

<751 1.0200 751 - 1651 1.0301

> 1651 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 FQ(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 SR 3.0.2) starting from the burnup at which the FQ(Z) was determined.

COLR Cycle 26 Beaver Valley Unit 1 5.1 - 16 LRM Revision 101

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