L-21-137, Cycle 28 Core Operating Limits Report

Cycle 28 Core Operating Limits Report

ML21153A077
Person / Time
Site:	Beaver Valley
Issue date:	05/21/2021
From:	Grabnar J Energy Harbor Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-21-137
Download: ML21153A077 (18)

Text

Energy Harbor Nuclear Corp.

Beaver Valley Power Station P. O. Box 4 Shippingport, PA 15077 May 21, 2020 L-21-137 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 Cycle 28 Core Operating Limits Report Pursuant to the requirements of Beaver Valley Power Station, Unit No. 1 Technical Specification 5.6.3, "CORE OPERATING LIMITS REPORT (COLR)," Energy Harbor Nuclear Corp. hereby submits the COLR for Cycle 28. 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, including any midcycle revisions or supplements.

The Cycle 28 COLR was made effective on April 23, 2021.

There are no regulatory commitments contained in this submittal. If there are any questions, or if additional information is required, please contact Mr. Phil H. Lashley, Manager - Fleet Licensing, at (330) 696-7208.

Sincerely, John J. Grabnar

Enclosure:

Beaver Valley Power Station, Unit No. 1, Core Operating Limits Report, Cycle 28 cc:

NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative John J. Grabnar Site Vice President, Beaver Valley Nuclear 724-682-5234

Enclosure L-21-137 Beaver Valley Power Station, Unit No. 1, Core Operating Limits Report, Cycle 28 (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 t 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 t the MODE 5 boron concentration and shall remain t this boron concentration at all times when this signal is blocked.

c.

In MODE 5, SHUTDOWN MARGIN shall be t 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/qF at RATED THERMAL POWER.

c.

300 ppm Surveillance Limit: (- 37 pcm/qF)

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/qF 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/qF / AFD

• • • Predictive Correction is -3 pcm/qF.

(1) The MODE 1 and MODE 2 with keff t 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 28 Beaver Valley Unit 1 5.1 - 1 LRM Revision 108

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/qF) 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 -

(Z)

FQ limit is defined by:

(Z)

FQ d

K(Z)

P CFQ

>>1/4

º

<<¬

for P > 0.5 (Z)

FQ d

K(Z) 0.5 CFQ

>>1/4

º

<<¬

for P d 0.5 Where:

CFQ = 2.40 P =

THERMAL POWER RATED THERMAL POWER K(Z) = the function obtained from Figure 5.1-3.

(Z)

FC Q

=

(Z)

FM Q

• 1.0815$

(Z)

FW Q

=

(Z)

FC Q

• 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 28 Beaver Valley Unit 1 5.1 - 2 LRM Revision 108

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 (

N H

F' )

N H

F' < CF'H * (1 + PF'H (1-P))$

Where:

CF'H = Value listed in Table 5.1-4 PF'H = 0.3 P =

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 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 d 1.242 Overtemperature 'T reactor trip setpoint Tavg coefficient K2 t 0.0183/qF Overtemperature 'T reactor trip setpoint pressure coefficient K3 t 0.001/psia Tavg at RATED THERMAL POWER T' d 577.9qF(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 28 Beaver Valley Unit 1 5.1 - 3 LRM Revision 108

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report Nominal pressurizer pressure P' t 2250 psia Measured reactor vessel average temperature lead/lag time constants W1 t 30 secs W2 d 4 secs Measured reactor vessel 'T lag time constant W4 d 6 secs Measured reactor vessel average temperature lag time constant W5 d 2 secs 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 d 1.085 Overpower 'T reactor trip setpoint Tavg rate/lag coefficient K5 t 0.02/qF for increasing average temperature K5 = 0/qF for decreasing average temperature Overpower 'T reactor trip setpoint Tavg heatup coefficient K6 t 0.0021/qF for T > T" K6 = 0/qF for T d T" Tavg at RATED THERMAL POWER T" d 577.9qF(2)

Measured reactor vessel average temperature rate/lag time constant W3 t 10 secs Measured reactor vessel 'T lag time constant W4 d 6 secs Measured reactor vessel average temperature lag time constant W5 d 2 secs (2)

T represents the cycle-specific Full Power Tavg value used in core design.

COLR Cycle 28 Beaver Valley Unit 1 5.1 - 4 LRM Revision 108

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 d 581.5qF(1)

Pressurizer Pressure Pressure t 2218 psia(2)

Reactor Coolant System Total Flow Rate Flow t Value listed in Table 5.1-4(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 t 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 (3.6qF) 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 28 Beaver Valley Unit 1 5.1 - 5 LRM Revision 108

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.

14.

WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLO', July 2006.

COLR Cycle 28 Beaver Valley Unit 1 5.1 - 6 LRM Revision 108

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

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

COLR Cycle 28 Beaver Valley Unit 1 5.1 - 7 LRM Revision 108 580 590 600 610 620 630 640 650 660 670 0

0.2 0.4 0.6 0.8 1

1.2 1.4 FRACTION OF RATED THERMAL POWER Tavg (Deg F)

UNACCEPTABLE OPERATION 2435 PSIA 2250 PSIA 2000 PSIA 1920 PSIA ACCEPTABLE OPERATION

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

CONTROL ROD INSERTION LIMITS COLR Cycle 28 Beaver Valley Unit 1 5.1 - 8 LRM Revision 108 0

50 100 150 200 0

20 40 60 80 100 Relative Power (Percent)

Rod Bank (Steps Withdrawn) 8,0 100, 187 54.53, 225 0, 114 BANK C BANK D

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

FQT NORMALIZED OPERATING ENVELOPE, K(Z)

COLR Cycle 28 Beaver Valley Unit 1 5.1 - 9 LRM Revision 108 0.0 0.2 0.4 0.6 0.8 1.0 1.2 0

2 4

6 8

10 12 Core Height (feet)

K(Z) 0.0, 1.00 6.0, 1.00 12.0, 0.925

Licensing Requirements Manual Core Operating Limits Report 5.1 Axial Flux Difference (Delta I)%

% of Rated Thermal Power

(-25, 50)

(-8, 100)

(+8, 100)

(+22, 50)

UNACCEPTABLE OPERATION ACCEPTABLE OPERATION UNACCEPTABLE OPERATION

-60

-50

-40

-30

-20

-10 0

10 20 30 40 50 60 0

10 20 30 40 50 60 70 80 90 100 110 120 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 28 Beaver Valley Unit 1 5.1 - 10 LRM Revision 108

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 28 Beaver Valley Unit 1 5.1 - 11 LRM Revision 108

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 Zone Axial Point Elevation (feet) 150 MWD/MTU 3000 MWD/MTU 8000 MWD/MTU 12000 MWD/MTU 16000 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 1.1076 1.1582 1.2370 1.2366 1.2096 9

10.47 1.1026 1.1559 1.2339 1.2303 1.2038 10 10.27 1.0971 1.1516 1.2283 1.2227 1.1974 11 10.07 1.1026 1.1496 1.2209 1.2142 1.1937 12 9.86 1.1079 1.1470 1.2125 1.2051 1.1953 13 9.66 1.1128 1.1446 1.2034 1.1956 1.2019 14 9.46 1.1142 1.1413 1.2009 1.1873 1.2078 15 9.26 1.1122 1.1355 1.2002 1.1829 1.2099 16 9.06 1.1141 1.1369 1.1988 1.1777 1.2171 17 8.86 1.1206 1.1373 1.1960 1.1742 1.2185 18 8.66 1.1306 1.1408 1.1973 1.1779 1.2238 19 8.46 1.1380 1.1466 1.2006 1.1855 1.2342 20 8.25 1.1440 1.1504 1.2017 1.1907 1.2423 21 8.05 1.1487 1.1529 1.2009 1.1939 1.2475 22 7.85 1.1523 1.1544 1.1988 1.1955 1.2508 23 7.65 1.1535 1.1536 1.1946 1.1950 1.2514 24 7.45 1.1536 1.1520 1.1892 1.1932 1.2505 25 7.25 1.1521 1.1484 1.1813 1.1887 1.2459 26 7.05 1.1500 1.1444 1.1723 1.1825 1.2389 27 6.84 1.1470 1.1395 1.1629 1.1758 1.2310 28 6.64 1.1423 1.1331 1.1521 1.1678 1.2216 29 6.44 1.1369 1.1260 1.1417 1.1586 1.2103 30 6.24 1.1312 1.1180 1.1345 1.1482 1.1971 31 6.04 1.1242 1.1131 1.1262 1.1370 1.1828 32 5.84 1.1196 1.1084 1.1173 1.1260 1.1677 Note: Top and Bottom 10% Excluded COLR Cycle 28 Beaver Valley Unit 1 5.1 - 12 LRM Revision 108

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 Zone Axial Point Elevation (feet) 150 MWD/MTU 3000 MWD/MTU 8000 MWD/MTU 12000 MWD/MTU 16000 MWD/MTU 33 5.64 1.1180 1.1033 1.1078 1.1187 1.1512 34 5.44 1.1173 1.1021 1.1005 1.1102 1.1373 35 5.23 1.1169 1.1025 1.0960 1.1049 1.1343 36 5.03 1.1170 1.1056 1.0930 1.1011 1.1292 37 4.83 1.1217 1.1101 1.0912 1.0970 1.1238 38 4.63 1.1273 1.1142 1.0889 1.0926 1.1176 39 4.43 1.1326 1.1180 1.0865 1.0881 1.1109 40 4.23 1.1373 1.1221 1.0840 1.0833 1.1040 41 4.03 1.1416 1.1274 1.0816 1.0804 1.0971 42 3.83 1.1458 1.1324 1.0788 1.0804 1.0885 43 3.62 1.1513 1.1371 1.0754 1.0802 1.0841 44 3.42 1.1570 1.1414 1.0748 1.0800 1.0819 45 3.22 1.1620 1.1452 1.0762 1.0799 1.0794 46 3.02 1.1672 1.1496 1.0767 1.0796 1.0763 47 2.82 1.1829 1.1605 1.0864 1.0828 1.0778 48 2.62 1.2045 1.1814 1.1033 1.0949 1.0883 49 2.42 1.2250 1.2055 1.1201 1.1101 1.1022 50 2.21 1.2460 1.2294 1.1378 1.1253 1.1159 51 2.01 1.2672 1.2535 1.1552 1.1397 1.1286 52 1.81 1.2881 1.2773 1.1722 1.1536 1.1405 53 1.61 1.3074 1.2993 1.1884 1.1667 1.1521 54 1.41 1.3249 1.3192 1.2031 1.1787 1.1628 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 28 Beaver Valley Unit 1 5.1 - 13 LRM Revision 108

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 Zone Axial Point Elevation (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 1.2103 9

10.47 1.1908 10 10.27 1.1698 11 10.07 1.1571 12 9.86 1.1447 13 9.66 1.1364 14 9.46 1.1210 15 9.26 1.1062 16 9.06 1.0929 17 8.86 1.0932 18 8.66 1.0935 19 8.46 1.0903 20 8.25 1.0908 21 8.05 1.0898 22 7.85 1.0897 23 7.65 1.0875 24 7.45 1.0857 25 7.25 1.0822 26 7.05 1.0806 27 6.84 1.0769 28 6.64 1.0736 29 6.44 1.0688 30 6.24 1.0655 31 6.04 1.0592 32 5.84 1.0572 Note: Top and Bottom 10% Excluded COLR Cycle 28 Beaver Valley Unit 1 5.1 - 14 LRM Revision 108

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 Zone Axial Point Elevation (feet) 75% RTP 33 5.64 1.0582 34 5.44 1.0596 35 5.23 1.0629 36 5.03 1.0640 37 4.83 1.0715 38 4.63 1.0793 39 4.43 1.0882 40 4.23 1.0944 41 4.03 1.1030 42 3.83 1.1113 43 3.62 1.1200 44 3.42 1.1298 45 3.22 1.1382 46 3.02 1.1484 47 2.82 1.1667 48 2.62 1.1926 49 2.42 1.2152 50 2.21 1.2390 51 2.01 1.2645 52 1.81 1.2899 53 1.61 1.3140 54 1.41 1.3357 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 28 Beaver Valley Unit 1 5.1 - 15 LRM Revision 108

Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-3 FQ(Z) Penalty Factor versus Burnup Cycle Burnup (MWD/MTU)

FQ(Z) Penalty Factor

> 0 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.

Table 5.1-4 F'H Limit versus Minimum Measured Flow Minimum Measured Flow (MMF)

(gpm)

F'H Limit MMF t 279,731 1.62 279,731 > MMF t 278,348 1.61 278,348 > MMF t 277,499 1.60 COLR Cycle 28 Beaver Valley Unit 1 5.1 - 16 LRM Revision 108