L-17-344, Cycle 25-1 Core Operating Limits Report

Cycle 25-1 Core Operating Limits Report

ML17332A160
Person / Time
Site:	Beaver Valley
Issue date:	11/28/2017
From:	Bologna R FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-17-344
Download: ML17332A160 (19)

Text

FENOC' FirstEnergy Nuclear Operating Company Richard D. Bologna Site Vice President November 28, 2017 L-17-344 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 25-1 Core Operating Limits Report Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 724-682-5234 Fax: 724-643-8069 Pursuant to the requirements of Beaver Valley Power Station, Unit No. 1 Technical Specification 5.6.3, "CORE OPERATING LIMITS REPORT (COLR)," FirstEnergy Nuclear Operating Company hereby submits the COLR for Cycle 25-1. 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 25-1 COLR was made effective on October 25, 2017.

The COLR revision increased the minimum reactor coolant system total flow rate required for the locked rotor accident evaluation.

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.

?;;~

Richard D. Bologna

Enclosure:

Beaver Valley Power Station, Unit No. 1, Core Operating Limits Report, Cycle 25-1

Beaver Valley Power Station, Unit No. 1 L-17-344 Page 2 cc:

NRC Region I Administrator NRC Resident Inspector N RC Project Manager Director BRP/DEP Site BRP/DEP Representative

Enclosure L-17-344 Beaver Valley Power Station, Unit No. 1 Core Operating Limits Report, Cycle 25-1 (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 (SOM) 5.1.3

a.

In MODES 1, 2, 3, and 4, SHUTDOWN MARGIN shall be~ 1.77% ~k/k.(1l

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.

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 :

{O 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= 0.05 pcm/°F / tiAFD

• • • Predictive Correction is -3 pcm/°F.

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

Beaver Valley Unit 1 5.1 - 1 COLR Cycle 25-1 LR M Revision 99

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: (- 43 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 5.1.6

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.

LCO 3.2.1 Heat Flux Hot Channel Factor (Fo(Z))

The Heat Flux Hot Channel Factor - F0 (Z) limit is defined by:

F0 (Z) e, [ C:Q ]* K(Z)

F (Z) ::; [CFQ]

• K(Z) a

0.5 Where

CFO = 2.40 for P > 0.5 for P::; 0.5 THERMAL POWER p = RATED THERMAL POWER K(Z) = the function obtained from Figure 5.1-3.

F5 (Z) = F~(Z)

• 1.0815$

F'g (Z) = F5 (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.

Beaver Valley Unit 1 5.1 - 2 COLR Cycle 25-1 LRM Revision 99

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 Pis :S 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 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 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( F~)

5.1.8 5.1.9 F~H ~ CFAH * (1 + PFAH (1-P))$

Where:

CFAH = 1.62 PFAH = 0.3 THERMAL POWER p = RATED THERMAL POWER LCO 3.2.3 Axial Flux Difference (AFD)

The AFD acceptable operation limits are provided in Figure 5.1-4.

LCO 3.3.1 Reactor Trip System Instrumentation - Overtemperature and Overpower L\\T Parameter Values from Table Notations 1 and 2

a.

Overtemperature L\\ T Setpoint Parameter Values:

Parameter Overtemperature L\\ T reactor trip setpoint Overtemperature L\\ T reactor trip setpoint Tavg coefficient Overtemperature L\\ T reactor trip setpoint pressure coefficient Tavg at RATED THERMAL POWER K1 ~ 1.242 K2 ~ 0.0183/°F K3 ~ 0.001 /psia T' ~ 577.9°F(1l 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 FN.1H 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.

Beaver Valley Unit 1 5.1 - 3 COLA Cycle 25-1 LRM Revision 99

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

-r1 ~ 30 secs time constants

-r2 ~ 4 secs Measured reactor vessel L\\ T lag time constant

't4 ~ 6 secs Measured reactor vessel average temperature lag

-r5 ~ 2 secs time constant f (L'.\\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(L'.\\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 L\\ 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 L\\ T trip setpoint shall be automatically reduced by 1.47% of its value at RATED THERMAL POWER.

b.

Overpower L\\ T Setpoint Parameter Values:

Beaver Valley Unit 1 Parameter Overpower L\\ T reactor trip setpoint Overpower L\\ T reactor trip setpoint Tavg rate/lag coefficient Overpower L\\ T reactor trip setpoint Tavg heatup coefficient Tavg at RATED THERMAL POWER Measured reactor vessel average temperature rate/lag time constant Measured reactor vessel L\\ T lag time constant Measured reactor vessel average temperature lag time constant Value K4 ~ 1.085 KS~ 0.02/°F for increasing average temperature KS= 0/°F for decreasing average temperature K6 ~ 0.0021 /°F for T > T" K6 = 0/°F for T ~ T" T" ~ 577.9°F(2l

't3 ~ 1 0 secs

't4 ~ 6 secs

-rs~ 2 secs (2)

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

5.1 - 4 COLR Cycle 25-1 LR M Revision 99

Licensing Requirements Manual 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 5.1.10 LCO 3.4.1, RCS Pressure, Temperature. and Flow Departure from Nucleate Boiling (DNB) Limits 5.1.11 Parameter Reactor Coolant System Tavg Pressurizer Pressure Reactor Coolant System Total Flow Rate LCO 3.9.1 Boron Concentration (MODE 6)

Indicated Value Tavg ~ 581.5°F(1l Pressure ~ 2218 psia(2l Flow~ 268,668 gpm(3l 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 T avg 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.

Beaver Valley Unit 1 5.1 - 5 COLR Cycle 25-1 LRM Revision 99

Licensing Requirements Manual 5.1 Core Operating Limits Report 5.1.12 References Core Operating Limits Report 5.1

1.

WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1985 (Westinghouse Proprietary).

2.

WCAP-87 45-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 1 A, "Relaxation of Constant Axial Offset Control-Fa 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-BOP, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFMv System," Revision 0, March 1997.

9.

Caldon, Inc. Engineering Report-160P, "Supplement to Topical Report ER-BOP: Basis for a Power Uprate With the LEFMv 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.

Beaver Valley Unit 1 5.1 - 6 COLA Cycle 25-1 LRM Revision 99

Licensing Requirements Manual Core Operating Limits Report 5.1 670------,------.-------.-----.----------------

UNACCEPTABLE OPERATION 600 ACCEPTABLE OPERATION 580+-----.-----+------.....-----+------,------,-------t 0

0.2 Beaver Valley Unit 1 0.4 0.6 0.8 1

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) 5.1 - 7 1.2 1.4 COLR Cycle 25-1 LR M Revision 99

Licensing Requirements Manual Core Operating Limits Report 5.1 200 150

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CONTROL ROD INSERTION LIMITS 5.1 - 8

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V 80 100 COLR Cycle 25-1 LRM Revision 99

Licensing Requirements Manual 1.2 1.0 l 0.0, 1.00 l 0.8

§ 0.6 0.4 0.2 0.0 0

2 4

, 6.0, 1.00 l - ----

6 8

Core Height (feet)

Figure 5.1-3 (Page 1 of 1)

Core Operating Limits Report 5.1

~ 1 12.0, 0.925 1 10 12 Fa T NORMALIZED OPERATING ENVELOPE, K(Z)

Beaver Valley Unit 1 5.1 - 9 COLR Cycle 25-1 LRM Revision 99

Licensing Requirements Manual Core Operating Limits Report 5.1 H

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0 P-i rl cu E:

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Figure 5.1-4 (Page 1 of 1)

AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RATED THERMAL POWER FOR RAOC I

so 60 Beaver Valley Unit 1 5.1 - 10 COLA Cycle 25-1 LAM Revision 99

Licensing Requirements Manual Core Operating Limits Report 5.1

-30.00 CYCLB BURNUP MTC' (MWD/MTU)

{PCM/0 P) 14000

-30.34 18000

-32.33

~ " " " " "

-33.00 14000 Beaver Valley Unit 1 15000 16000 17000 CYCLE BURNUP (MWD/MTU)

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 5.1 - 11 18000 COLA Cycle 25-1 LAM Revision 99

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

Fa Surveillance W(Z) Function versus Burnup at 100% RTP Exclusion Axial Elevation 150 Zone Point (feet)

MWD/MTU 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 1.1666 9

10.47 1.1601 10 10.27 1.1528 11 10.07 1.1450 12 9.86 1.1383 13 9.66 1.1360 14 9.46 1.1357 15 9.26 1.1331 16 9.06 1.1336 17 8.86 1.1415 18 8.66 1.1523 19 8.46 1.1598 20 8.25 1.1658 21 8.05 1.1699 22 7.85 1.1720 23 7.65 1.1723 24 7.45 1.1709 25 7.25 1.1683 26 7.05 1.1647 27 6.84 1.1601 28 6.64 1.1542 29 6.44 1.1473 30 6.24 1.1394 31 6.04 1.1303 32 5.84 1.1211 Note: Top and Bottom 10% Excluded Beaver Valley Unit 1 3000 8000 MWD/MTU MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2143 1.2454 1.2077 1.2372 1.2010 1.2278 1.1930 1.2173 1.1834 1.2093 1.1745 1.2037 1.1679 1.1981 1.1611 1.1908 1.1578 1.1816 1.1608 1.1801 1.1693 1.1832 1.1743 1.1845 1.1777 1.1881 1.1794 1.1906 1.1791 1.1910 1.1769 1.1893 1.1731 1.1858 1.1681 1.1805 1.1621 1.1744 1.1551 1.1674 1.1471 1.1591 1.1380 1.1497 1.1279 1.1391 1.1168 1.1278 1.1058 1.1151 5.1 - 12 12000 18000 MWD/MTU MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2073 1.2066 1.1998 1.1992 1.1940 1.1937 1.1920 1.1875 1.1932 1.1839 1.1965 1.1817 1.1976 1.1781 1.1969 1.1740 1.1965 1.1749 1.1969 1.1769 1.1996 1.1829 1.2041 1.1949 1.2076 1.2039 1.2089 1.2105 1.2081 1.2149 1.2050 1.2168 1.1999 1.2164 1.1930 1.2140 1.1846 1.2096 1.1749 1.2041 1.1639 1.1977 1.1518 1.1896 1.1400 1.1799 1.1306 1.1693 1.1218 1.1560 COLR Cycle 25-1 LRM Revision 99

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

Fo Surveillance W(Z) Function versus Burnup at 100% RTP Exclusion Axial Elevation 150 Zone Point (feet)

MWD/MTU 33 5.64 1.1125 34 5.44 1.1056 35 5.23 1.1071 36 5.03 1.1111 37 4.83 1.1137 38 4.63 1.1162 39 4.43 1.1183 40 4.23 1.1201 41 4.03 1.1212 42 3.83 1.1229 43 3.62 1.1272 44 3.42 1.1312 45 3.22 1.1345 46 3.02 1.1414 47 2.82 1.1567 48 2.62 1.1798 49 2.42 1.2034 50 2.21 1.2268 51 2.01 1.2500 52 1.81 1.2725 53 1.61 1.2940 54 1.41 1.3137 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 Beaver Valley Unit 1 3000 8000 MWD/MTU MWD/MTU 1.0981 1.1039 1.0966 1.1000 1.0956 1.0994 1.0960 1.0989 1.0975 1.0977 1.0985 1.0962 1.1011 1.0943 1.1035 1.0922 1.1054 1.0899 1.1070 1.0875 1.1082 1.0850 1.1091 1.0834 1.1109 1.0839 1.1189 1.0873 1.1365 1.0944 1.1599 1.1056 1.1840 1.1207 1.2081 1.1369 1.2321 1.1524 1.2556 1.1679 1.2780 1.1843 1.2986 1.2000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5.1 - 13 12000 18000 MWD/MTU MWD/MTU 1.1118 1.1436 1.1035 1.1403 1.0996 1.1380 1.0973 1.1346 1.0943 1.1304 1.0911 1.1253 1.0876 1.1195 1.0836 1.1130 1.0802 1.1060 1.0788 1.0987 1.0793 1.0911 1.0796 1.0840 1.0797 1.0788 1.0821 1.0799 1.0936 1.0897 1.1097 1.1044 1.1263 1.1196 1.1429 1.1346 1.1594 1.1495 1.1754 1.1639 1.1909 1.1780 1.2052 1.1912 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 COLR Cycle 25-1 LRM Revision 99

Licensing Requirements Manual Table 5.1-2 (Page 1 of 2)

Core Operating Limits Report 5.1 Fa Surveillance W(Z) Function versus Burnup at 75% RTP Exclusion Axial Zone Point 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 Note: Top and Bottom 10% Excluded Beaver Valley Unit 1 Elevation (feet) 12.08 11.88 11.68 11.47 11.27 11.07 10.87 10.67 10.47 10.27 10.07 9.86 9.66 9.46 9.26 9.06 8.86 8.66 8.46 8.25 8.05 7.85 7.65 7.45 7.25 7.05 6.84 6.64 6.44 6.24 6.04 5.84 5.1 - 14 75% RTP 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2873 1.2662 1.2440 1.2210 1.1942 1.1739 1.1592 1.1445 1.1317 1.1281 1.1290 1.1282 1.1274 1.1260 1.1238 1.1224 1.1195 1.1156 1.1107 1.1048 1.0979 1.0904 1.0818 1.0727 1.0640 COLR Cycle 25-1 LRM Revision 99

Licensing Requirements Manual Table 5.1-2 (Page 2 of 2)

Core Operating Limits Report 5.1 Fa Surveillance W(Z) Function versus Burnup at 75% RTP Exclusion Axial Zone Point 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 Note: Top and Bottom 10% Excluded Beaver Valley Unit 1 Elevation (feet) 5.64 5.44 5.23 5.03 4.83 4.63 4.43 4.23 4.03 3.83 3.62 3.42 3.22 3.02 2.82 2.62 2.42 2.21 2.01 1.81 1.61 1.41 1.21 1.01 0.81 0.60 0.40 0.20 0.00 5.1 - 15 75% RTP 1.0565 1.0514 1.0546 1.0602 1.0649 1.0700 1.0749 1.0796 1.0836 1.0882 1.0954 1.1026 1.1091 1.1191 1.1373 1.1631 1.1896 1.2159 1.2425 1.2688 1.2941 1.3175 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 COLA Cycle 25-1 LRM Revision 99

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

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

Fa(Z) Penalty Factor 0 - 1052 1.0265

> 1052 1.0200 Note: The Penalty Factor, to be applied to Fa(Z) in accordance with Technical Specification Surveillance Requirement (SR) 3.2.1.2, is the maximum factor by which Fa(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 Fa(Z) was determined.

Beaver Valley Unit 1 5.1 - 16 COLA Cycle 25-1 LAM Revision 99