L-20-078, Cycle 27-1 Core Operating Limits Report

Cycle 27-1 Core Operating Limits Report

ML20077H432
Person / Time
Site:	Beaver Valley
Issue date:	03/16/2020
From:	Penfield R Energy Harbor Nuclear Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-20-078
Download: ML20077H432 (18)

Text

March 16, 2020 energy harbor Rod L. Penfield Site Vice President, Beaver Valley Nuclear L-20-078 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 27-1 Core Operating Limits Report Energy Harbor Nuclear Corp.

Beaver Valley Power Station P. 0. Box 4 Shippingport, PA 15077 724-682-5234 Pursuant to the requirements of Beaver Valley Power Station, Unit No. 1 Technical Specification (TS) 5.6.3, "CORE OPERATING LIMITS REPORT (COLR)," Energy Harbor Nuclear Corp. hereby submits the COLR for Cycle 27-1. TS 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 27-1 COLR was made effective on February 26, 2020.

The COLR revision changes the F llH limit that is dependent on the measured reactor coolant system flow. The changes are based on a revised evaluation that demonstrates that no fuel rods would experience departure from nucleate boiling for the locked rotor accident.

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, Acting Manager, Nuclear Licensing and Regulatory Affairs, at (330) 315-6808.

Enclosure:

Beaver Valley Power Station, Unit No. 1, Core Operating Limits Report, Cycle 27-1 cc:

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

Enclosure L-20-078 Beaver Valley Power Station, Unit No. 1, Core Operating Limits Report, Cycle 27-1 (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 (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 27-1 Beaver Valley Unit 1 5.1 - 1 LRM Revision 105

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 -

(Z)

FQ limit is defined by:

(Z)

FQ K(Z)

P CFQ

for P > 0.5 (Z)

FQ K(Z) 0.5 CFQ

for P 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 27-1 Beaver Valley Unit 1 5.1 - 2 LRM Revision 105

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

Where:

CFH = Value listed in Table 5.1-4 PFH = 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 1.242 Overtemperature T reactor trip setpoint Tavg coefficient K2 0.0183/F Overtemperature T reactor trip setpoint pressure coefficient K3 0.001/psia 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 27-1 Beaver Valley Unit 1 5.1 - 3 LRM Revision 105

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 time constants 1 30 secs 2 4 secs Measured reactor vessel T lag time constant 4 6 secs Measured reactor vessel average temperature lag time constant 5 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 1.085 Overpower T reactor trip setpoint Tavg rate/lag coefficient K5 0.02/F for increasing average temperature K5 = 0/F for decreasing average temperature Overpower T reactor trip setpoint Tavg heatup coefficient K6 0.0021/F for T > T" K6 = 0/F for T T" Tavg at RATED THERMAL POWER T" 577.9F(2)

Measured reactor vessel average temperature rate/lag time constant 3 10 secs Measured reactor vessel T lag time constant 4 6 secs Measured reactor vessel average temperature lag time constant 5 2 secs (2)

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

COLR Cycle 27-1 Beaver Valley Unit 1 5.1 - 4 LRM Revision 105

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 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 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 27-1 Beaver Valley Unit 1 5.1 - 5 LRM Revision 105

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 27-1 Beaver Valley Unit 1 5.1 - 6 LRM Revision 105

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 27-1 Beaver Valley Unit 1 5.1 - 7 LRM Revision 105 580 590 600 610 620 630 640 650 660 670 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 27-1 Beaver Valley Unit 1 5.1 - 8 LRM Revision 105 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 27-1 Beaver Valley Unit 1 5.1 - 9 LRM Revision 105 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 27-1 Beaver Valley Unit 1 5.1 - 10 LRM Revision 105

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 27-1 Beaver Valley Unit 1 5.1 - 11 LRM Revision 105

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 1.1550 1.1976 1.2469 1.2126 1.1954 9

10.47 1.1500 1.1963 1.2385 1.2102 1.1908 10 10.27 1.1533 1.1930 1.2287 1.2060 1.1859 11 10.07 1.1437 1.1883 1.2200 1.2003 1.1807 12 9.86 1.1451 1.1842 1.2195 1.1982 1.1752 13 9.66 1.1500 1.1809 1.2185 1.1980 1.1694 14 9.46 1.1470 1.1715 1.2115 1.1957 1.1662 15 9.26 1.1412 1.1681 1.2106 1.1921 1.1721 16 9.06 1.1401 1.1635 1.2080 1.1884 1.1790 17 8.86 1.1415 1.1560 1.2030 1.1868 1.1832 18 8.66 1.1505 1.1558 1.2035 1.1877 1.1867 19 8.46 1.1574 1.1620 1.2062 1.1937 1.1894 20 8.25 1.1628 1.1655 1.2068 1.1986 1.1925 21 8.05 1.1668 1.1676 1.2053 1.2012 1.1947 22 7.85 1.1695 1.1685 1.2027 1.2023 1.1995 23 7.65 1.1698 1.1672 1.1979 1.2014 1.2031 24 7.45 1.1690 1.1648 1.1920 1.1992 1.2054 25 7.25 1.1664 1.1605 1.1837 1.1943 1.2045 26 7.05 1.1632 1.1556 1.1742 1.1877 1.2016 27 6.84 1.1590 1.1498 1.1644 1.1807 1.1976 28 6.64 1.1531 1.1424 1.1532 1.1724 1.1926 29 6.44 1.1466 1.1343 1.1443 1.1629 1.1861 30 6.24 1.1396 1.1256 1.1370 1.1522 1.1780 31 6.04 1.1315 1.1161 1.1286 1.1406 1.1688 32 5.84 1.1225 1.1053 1.1194 1.1294 1.1587 Note: Top and Bottom 10% Excluded COLR Cycle 27-1 Beaver Valley Unit 1 5.1 - 12 LRM Revision 105

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 1.1131 1.1002 1.1098 1.1217 1.1474 34 5.44 1.1109 1.0988 1.1021 1.1135 1.1364 35 5.23 1.1118 1.0996 1.0984 1.1098 1.1327 36 5.03 1.1114 1.1011 1.0974 1.1057 1.1292 37 4.83 1.1120 1.1023 1.0956 1.1029 1.1254 38 4.63 1.1157 1.1032 1.0938 1.0999 1.1208 39 4.43 1.1195 1.1039 1.0916 1.0965 1.1155 40 4.23 1.1227 1.1042 1.0894 1.0930 1.1101 41 4.03 1.1256 1.1042 1.0870 1.0895 1.1043 42 3.83 1.1295 1.1041 1.0842 1.0846 1.1008 43 3.62 1.1339 1.1037 1.0811 1.0838 1.0984 44 3.42 1.1376 1.1055 1.0781 1.0856 1.0958 45 3.22 1.1408 1.1104 1.0753 1.0873 1.0923 46 3.02 1.1442 1.1220 1.0749 1.0885 1.0945 47 2.82 1.1506 1.1417 1.0792 1.0938 1.1037 48 2.62 1.1665 1.1643 1.0918 1.1058 1.1172 49 2.42 1.1875 1.1873 1.1081 1.1201 1.1326 50 2.21 1.2079 1.2107 1.1251 1.1345 1.1481 51 2.01 1.2285 1.2342 1.1418 1.1482 1.1624 52 1.81 1.2488 1.2574 1.1581 1.1614 1.1759 53 1.61 1.2676 1.2790 1.1734 1.1739 1.1889 54 1.41 1.2844 1.2986 1.1874 1.1854 1.2009 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 27-1 Beaver Valley Unit 1 5.1 - 13 LRM Revision 105

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 1.2616 9

10.47 1.2465 10 10.27 1.2173 11 10.07 1.1881 12 9.86 1.1706 13 9.66 1.1635 14 9.46 1.1473 15 9.26 1.1237 16 9.06 1.1064 17 8.86 1.1019 18 8.66 1.1013 19 8.46 1.1016 20 8.25 1.1024 21 8.05 1.1014 22 7.85 1.1006 23 7.65 1.0982 24 7.45 1.0949 25 7.25 1.0925 26 7.05 1.0892 27 6.84 1.0860 28 6.64 1.0799 29 6.44 1.0758 30 6.24 1.0699 31 6.04 1.0640 32 5.84 1.0567 Note: Top and Bottom 10% Excluded COLR Cycle 27-1 Beaver Valley Unit 1 5.1 - 14 LRM Revision 105

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 1.0508 34 5.44 1.0510 35 5.23 1.0555 36 5.03 1.0569 37 4.83 1.0609 38 4.63 1.0673 39 4.43 1.0744 40 4.23 1.0798 41 4.03 1.0853 42 3.83 1.0943 43 3.62 1.1018 44 3.42 1.1093 45 3.22 1.1163 46 3.02 1.1236 47 2.82 1.1338 48 2.62 1.1529 49 2.42 1.1772 50 2.21 1.2008 51 2.01 1.2269 52 1.81 1.2504 53 1.61 1.2743 54 1.41 1.2940 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 27-1 Beaver Valley Unit 1 5.1 - 15 LRM Revision 105

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 FH Limit versus Minimum Measured Flow Minimum Measured Flow (MMF)

(gpm)

FH Limit MMF 279,731 1.62 279,731 > MMF 278,348 1.61 278,348 > MMF 277,499 1.60 COLR Cycle 27-1 Beaver Valley Unit 1 5.1 - 16 LRM Revision 105