L-20-143, Cycle 22 Core Operating Limits Report

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Cycle 22 Core Operating Limits Report
ML20129K046
Person / Time
Site: Beaver Valley
Issue date: 05/08/2020
From: Penfield R
Energy Harbor Nuclear Corp
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-20-143
Download: ML20129K046 (18)
v • d • e


Text

Energy Harbor Nuclear Corp.

Beaver Valley Power Station P. O. Box 4 Shippingport, PA 15077 Rod L. Penfield 724-682-5234 Site Vice President, Beaver Valley Nuclear May 8, 2020 L-20-143 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 22 Core Operating Limits Report Pursuant to the requirements of Beaver Valley Power Station, Unit No. 2 Technical Specification (TS) 5.6.3, CORE OPERATING LIMITS REPORT (COLR), Energy Harbor Nuclear Corp. hereby submits the COLR for Cycle 22. TS 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 22 COLR was made effective on April 21, 2020.

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, Nuclear Licensing and Regulatory Affairs, at (330) 315-6810.

Sincerely, Rod L. Penfield

Enclosure:

Beaver Valley Power Station, Unit No. 2, Core Operating Limits Report, Cycle 22 cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative

Enclosure L-20-143 Beaver Valley Power Station, Unit No. 2, Core Operating Limits Report, Cycle 22 (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 - 4.29 x 10-4

'k/k/qF at RATED THERMAL POWER.

c. 300 ppm Surveillance Limit: (- 35 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 10 :

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 22 Beaver Valley Unit 2 5.1 - 1 LRM Revision 95

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: (- 40.5 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 - FQ (Z) limit is defined by:

CFQ º FQ (Z) d <<

  • K(Z) for P > 0.5

¬ P >>1/4 CFQ º FQ (Z) d <<

  • K(Z) for P d 0.5

¬ 0.5 >>1/4 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) = FQ C (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, 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 22 Beaver Valley Unit 2 5.1 - 2 LRM Revision 95

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 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 1/P, when P > 0.5. When P is d 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.

N 5.1.7 LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( F'H )

N FH d CF * (1 PF (1 P)) $

H H Where: CF = 1.62 H

PF = 0.3 H

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 3 and 4

a. Overtemperature 'T Setpoint Parameter Values:

Parameter Value Overtemperature 'T reactor trip setpoint K1 d 1.239 Overtemperature 'T reactor trip setpoint Tavg K2 t 0.0183/qF coefficient Overtemperature 'T reactor trip setpoint pressure K3 t 0.001/psia coefficient Tavg at RATED THERMAL POWER T' d 574.2qF(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, and 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 22 Beaver Valley Unit 2 5.1 - 3 LRM Revision 95

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 'T lead/lag time constants W1 = 0 sec*

(* The response time is toggled off to meet the analysis W2 = 0 sec*

value of zero.)

Measured reactor vessel 'T lag time constant W3 d 6 secs Measured reactor vessel average temperature lead/lag W4 t 30 secs time constants W5 d 4 secs Measured reactor vessel average temperature lag time W6 d 2 secs 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%, f1('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 1.094 Overpower 'T reactor trip setpoint Tavg K5 t 0.02/qF for increasing rate/lag coefficient average temperature K5 = 0/qF for decreasing average temperature Overpower 'T reactor trip setpoint Tavg K6 t 0.0021/qF for T > T" heatup coefficient K6 = 0/qF for T d T" Tavg at RATED THERMAL POWER T" d 574.2qF(1)

Measured reactor vessel 'T lead/lag W1 = 0 sec*

time constants W2 = 0 sec*

(* The response time is toggled off to meet the analysis value of zero.)

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

COLR Cycle 22 Beaver Valley Unit 2 5.1 - 4 LRM Revision 95

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report Measured reactor vessel 'T lag time W3 d 6 secs constant Measured reactor vessel average W6 d 2 secs temperature lag time constant Measured reactor vessel average W7 t 10 secs temperature rate/lag time constant 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 577.8qF(1)

Pressurizer Pressure Pressure t 2214 psia(2)

Reactor Coolant System Total Flow Rate Flow t 267,483 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 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 22 Beaver Valley Unit 2 5.1 - 5 LRM Revision 95

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-13749-P-A, Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement, March 1997 (Westinghouse Proprietary).
11. WCAP-16045-P-A, Qualification of the Two-Dimensional Transport Code PARAGON, August 2004.
12. WCAP-16045-P-A, Addendum 1-A, Qualification of the NEXUS Nuclear Data Methodology, August 2007.
13. WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A Optimized ZIRLOTM, July 2006.

COLR Cycle 22 Beaver Valley Unit 2 5.1 - 6 LRM Revision 95

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 22 Beaver Valley Unit 2 5.1 - 7 LRM Revision 95

Licensing Requirements Manual Core Operating Limits Report 5.1 225 (54.53, 225) 200 BANK C (100, 187)

ROD BANK POSITION (Steps Withdrawn) 175 150 125 (0, 114) BANK D 100 75 50 25 (8, 0) 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 22 Beaver Valley Unit 2 5.1 - 8 LRM Revision 95

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 22 Beaver Valley Unit 2 5.1 - 9 LRM Revision 95

Licensing Requirements Manual Core Operating Limits Report 5.1 120 110

(-8, 100) (+8, 100) 100 90 UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION ACCEPTABLE OPERATION 80

% o f R ated T her mal Po wer 70 60 50

(-25, 50) (+22, 50) 40 30 20 10 0

-60 -50 -40 20 -10 0 10 20 30 40 50 60 Axial Flux Differ ence (Delta 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 22 Beaver Valley Unit 2 5.1 - 10 LRM Revision 95

Licensing Requirements Manual Core Operating Limits Report 5.1

-29.00 CYCLE BURNUP MTC (MWD/MTU) (pcm/°F) 14000 -29.956 18000 -31.234 MODERATOR TEMPERATURE COEFFICIENT (pcm/°F)

-30.00

-31.00

-32.00 14000 15000 16000 17000 18000 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 COLR Cycle 22 Beaver Valley Unit 2 5.1 - 11 LRM Revision 95

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 12.1 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
  • 5 11.3 1.0000 1.0000 1.0000 1.0000 1.0000
  • 6 11.1 1.0000 1.0000 1.0000 1.0000 1.0000
  • 7 10.9 1.0000 1.0000 1.0000 1.0000 1.0000 8 10.7 1.1331 1.1918 1.2494 1.2243 1.2208 9 10.5 1.1292 1.1876 1.2410 1.2217 1.2150 10 10.3 1.1285 1.1813 1.2311 1.2173 1.2087 11 10.1 1.1279 1.1731 1.2200 1.2114 1.2017 12 9.9 1.1281 1.1681 1.2110 1.2046 1.1942 13 9.7 1.1272 1.1682 1.2117 1.1972 1.1864 14 9.5 1.1243 1.1652 1.2107 1.1911 1.1783 15 9.3 1.1216 1.1580 1.2056 1.1935 1.1743 16 9.1 1.1281 1.1579 1.2037 1.1990 1.1794 17 8.9 1.1369 1.1564 1.2010 1.2004 1.1846 18 8.7 1.1456 1.1584 1.2030 1.2040 1.1903 19 8.5 1.1532 1.1634 1.2060 1.2102 1.1946 20 8.3 1.1590 1.1662 1.2072 1.2144 1.1981 21 8.1 1.1633 1.1677 1.2062 1.2163 1.2007 22 7.9 1.1665 1.1680 1.2040 1.2166 1.2066 23 7.6 1.1671 1.1661 1.1996 1.2147 1.2097 24 7.4 1.1666 1.1632 1.1941 1.2115 1.2118 25 7.2 1.1644 1.1584 1.1860 1.2053 1.2106 26 7.0 1.1611 1.1529 1.1767 1.1973 1.2072 27 6.8 1.1565 1.1467 1.1664 1.1889 1.2027 28 6.6 1.1503 1.1390 1.1547 1.1792 1.1972 29 6.4 1.1434 1.1305 1.1418 1.1681 1.1901 30 6.2 1.1360 1.1215 1.1305 1.1558 1.1813 31 6.0 1.1275 1.1117 1.1214 1.1427 1.1714 32 5.8 1.1182 1.1024 1.1119 1.1291 1.1606 Note: Top and Bottom 10% Excluded COLR Cycle 22 Beaver Valley Unit 2 5.1 - 12 LRM Revision 95

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 5.6 1.1093 1.1002 1.1019 1.1148 1.1486 34 5.4 1.1094 1.0996 1.0966 1.1100 1.1396 35 5.2 1.1099 1.1006 1.0959 1.1080 1.1379 36 5.0 1.1109 1.1022 1.0943 1.1053 1.1344 37 4.8 1.1156 1.1034 1.0925 1.1024 1.1304 38 4.6 1.1201 1.1044 1.0904 1.0990 1.1256 39 4.4 1.1245 1.1050 1.0880 1.0953 1.1202 40 4.2 1.1283 1.1055 1.0855 1.0913 1.1144 41 4.0 1.1316 1.1085 1.0829 1.0881 1.1084 42 3.8 1.1349 1.1138 1.0798 1.0873 1.1011 43 3.6 1.1382 1.1185 1.0762 1.0865 1.0928 44 3.4 1.1409 1.1226 1.0735 1.0853 1.0857 45 3.2 1.1436 1.1267 1.0739 1.0844 1.0850 46 3.0 1.1454 1.1290 1.0750 1.0825 1.0858 47 2.8 1.1584 1.1425 1.0787 1.0852 1.0920 48 2.6 1.1784 1.1639 1.0907 1.0957 1.1050 49 2.4 1.1971 1.1842 1.1064 1.1088 1.1191 50 2.2 1.2166 1.2053 1.1220 1.1220 1.1335 51 2.0 1.2361 1.2264 1.1374 1.1346 1.1469 52 1.8 1.2567 1.2473 1.1524 1.1467 1.1595 53 1.6 1.2759 1.2667 1.1666 1.1583 1.1717 54 1.4 1.2933 1.2843 1.1795 1.1690 1.1831

  • 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 22 Beaver Valley Unit 2 5.1 - 13 LRM Revision 95

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

FQ Surveillance W(Z) Function at Initial Cycle Startup at 75% RTP Exclusion Zone Axial Point Elevation (feet) 75% RTP

  • 1 12.1 1.0000
  • 2 11.9 1.0000
  • 3 11.7 1.0000
  • 4 11.5 1.0000
  • 5 11.3 1.0000
  • 6 11.1 1.0000
  • 7 10.9 1.0000 8 10.7 1.2492 9 10.5 1.2285 10 10.3 1.2099 11 10.1 1.1897 12 9.9 1.1711 13 9.7 1.1519 14 9.5 1.1328 15 9.3 1.1153 16 9.1 1.1071 17 8.9 1.1073 18 8.7 1.1086 19 8.5 1.1073 20 8.3 1.1081 21 8.1 1.1062 22 7.9 1.1063 23 7.6 1.1030 24 7.4 1.1014 25 7.2 1.0972 26 7.0 1.0945 27 6.8 1.0899 28 6.6 1.0851 29 6.4 1.0789 30 6.2 1.0727 31 6.0 1.0644 32 5.8 1.0573 Note: Top and Bottom 10% Excluded COLR Cycle 22 Beaver Valley Unit 2 5.1 - 14 LRM Revision 95

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

FQ Surveillance W(Z) Function at Initial Cycle Startup at 75% RTP Exclusion Zone Axial Point Elevation (feet) 75% RTP 33 5.6 1.0513 34 5.4 1.0535 35 5.2 1.0577 36 5.0 1.0613 37 4.8 1.0693 38 4.6 1.0766 39 4.4 1.0839 40 4.2 1.0900 41 4.0 1.0966 42 3.8 1.1033 43 3.6 1.1099 44 3.4 1.1160 45 3.2 1.1234 46 3.0 1.1281 47 2.8 1.1444 48 2.6 1.1686 49 2.4 1.1909 50 2.2 1.2133 51 2.0 1.2378 52 1.8 1.2627 53 1.6 1.2865 54 1.4 1.3071

  • 55 1.2 1.0000
  • 56 1.0 1.0000
  • 57 0.8 1.0000
  • 58 0.6 1.0000
  • 59 0.4 1.0000
  • 60 0.2 1.0000
  • 61 0.0 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 22 Beaver Valley Unit 2 5.1 - 15 LRM Revision 95

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 x>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.

COLR Cycle 22 Beaver Valley Unit 2 5.1 - 16 LRM Revision 95

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