L-19-239, Cycle 27 Core Operating Limits Report

Cycle 27 Core Operating Limits Report

ML19315A002
Person / Time
Site:	Beaver Valley
Issue date:	11/08/2019
From:	Penfield R FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-19-239
Download: ML19315A002 (18)

Text

Beaver Valley Power Station P.O. Box4 Shippingport, PA 15077 Rod L. Penfield 724-682-5234 Site Vice President Fax: 724-643-8069 November 8, 2019 L-19-239 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 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)," FirstEnergy Nuclear Operating Company hereby submits the COLR for Cycle 27. 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 27 COLR was made effective on October 22, 2019.

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

~~ly, #~~ !y )

~;;C7). ~ l~~Jl_ _ __/

Rod L. Penfield[ / '

Enclosure:

Beaver Valley Power Station, Unit No. 1, Core Operating Limits Report, Cycle 27 cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative

Enclosure L-19-239 Beaver Valley Power Station, Unit No. 1, Core Operating Limits Report, Cycle 27 (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)

a. In MODES 1, 2, 3, and 4, SHUTDOWN MARGIN shall be ~ 1.77% Llk/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% L'lk/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 L'lk/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 (MFD

• AFD Sensitivity)}

where: LlAFD 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 / LlAFD

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

(1) The MODE 1 and MODE 2 with keff ~ 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) .

COLR Cycle 27 Beaver Valley Unit 1 5.1 - 1 LRM Revision 104

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.(2l 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.(2l

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( 2l - 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 (Fa(Z))

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

Fa(Z) ::::; [ c;a]

• K(Z) for P > 0.5 F (Z) ::::: [CFQ]

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

Fg(Z) = F~(Z)

• 1.0815$

F'(j (Z) = Fg (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 27 Beaver Valley Unit 1 5.1 - 2 LRM Revision 104

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) v.:1lues in Table 5.1-1 were generated assuming that they will be used for full r, ower 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 Piss; 0.5, the W(Z) values should be multiplied by the factor 1/(0.5), or 2.0. This is consisrent with the adjustment in the Fa(Z) limit at part power conditions .

The Fa(Z) penalty function , applied when the analytic Fa(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~H)

F~H ~ CFt,H * (1 + PFt,H (1-P))$

Where: CF t,H = Value listed in Table 5.1-4 PFt,H = 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 11T Parameter Values from Table Notations 1 and 2

a. Overtemperature 11T Setpoint Parameter Values :

Parameter Overtemperature 11T reactor trip setpoint K1 ::; 1.242 Overtemperature 11T reactor trip setpoint Tavg K2 ~ 0.0183/°F coefficient Overtemperature 11T reactor trip setpoint pressure K3 ~ 0.001/psia coefficient Tavg at RATED THERMAL POWER T' ::; 577.9°F<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 FN11H 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 Beaver Valley Unit 1 5.1 - 3 LRM Revision 104

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report Nominal pressurizer pressure P' 2 2250 psia Measured reactor vessel average temperature lead/lag r 1 2 30 secs time constants r 2 :,::; 4 secs Measured reactor vessel ~ T lag time constant t4 s 6 secs Measured reactor vessel average temperature lag rs :,::; 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 RA TED THERMAL POWER in the top and bottom halves of the core respectively, and qt+ qb is total THERMAL POWER in percent of RA TED 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 RA TED 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 s 1.085 Overpower ~ T reactor trip setpoint Tavg K5 2 0.02/°F for increasing rate/lag coefficient average temperature K5 = 0/°F for decreasing average temperature Overpower ~ T reactor trip setpoint Tavg K6 2 0.0021/°F for T > T" heatup coefficient K6 = 0/°F for T s T" Tavg at RATED THERMAL POWER T" s 577.9°F(2l Measured reactor vessel average t32 10 secs temperature rate/lag time constant Measured reactor vessel ~T lag time t4 s 6 secs constant Measured reactor vessel average rs s 2 secs temperature lag time constant (2) T" represents the cycle-specific Full Power Tavg value used in core design .

COLR Cycle 27 Beaver Valley Unit 1 5.1 - 4 LRM Revision 104

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 .5°F(1l Pressurizer Pressure Pressure ~ 2218 psia( 2l Reactor Coolant System Total Flow Rate Flow ~ Value listed in Table 5.1-4(3l 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 (3.6°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 .

COLR Cycle 27 Beaver Valley Unit 1 5.1 - 5 LRM Revision 104

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-87 45-P-A, "Design Bases for the Thermal Overpower L1T and Thermal Overtemperature L1 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-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 LEFM ' System ," Revision 0, March 1997.

9. Caldon , Inc. Engineering Report-160P , "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFM ' 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-137 49-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 Beaver Valley Unit 1 5.1 - 6 LRM Revision 104

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

UN A C CE PT ABLE OPE RATION 600 ACCEPT ABLE OP E RATION 580 ,.___ _ _......,_ _ _ _.,...._ _ _......,_ ___ +-------------+-----"""'

0 0 .2 0.4 0.6 0 .8 1.2 1.4 FRACTION OF RA T E D THERMAL POW E R 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 Beaver Valley Unit 1 5.1 - 7 LRM Revision 104

Licensing Requirements Manual Core Operating Limits Report 5.1

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CONTROL ROD INSERTION LIMITS COLR Cycle 27 Beaver Valley Unit 1 5.1 - 8 LRM Revision 104

Licensing Requirements Manual Core Operating Limits Report 5.1 1.2 Io.o, 1.00 I 16.0, 1.00 I I

1.0 I 12.0, 0.925 1-0.8

§ 0.6 0.4 I

0.2 0.0 0 2 4 6 8 10 12 Core Height (feet)

Figure 5.1-3 (Page 1 of 1)

FoT NORMALIZED OPERATING ENVELOPE, K(Z)

COLR Cycle 27 Beaver Valley Unit 1 5.1 - 9 LRM Revision 104

Licensing Requirements Manual Core Operating Limits Report 5.1 120 110 100 I (-R 1m

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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 COLR Cycle 27 Beaver Valley Unit 1 5.1 - 10 LRM Revision 104

Licensing Requirements Manual Core Operating Limits Report 5.1

-3 0 . 00 CYCLE BURNUP MTC (M;ID/MTU) (pcm/ °F) 14000 -30.961 18000 -32 . 214 l

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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 Beaver Valley Unit 1 5.1 - 11 LRM Revision 104

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

Fa Surveillance W(Z) Function versus Burn up 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 1.1550 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 Beaver Valley Unit 1 5.1 - 12 LRM Revision 104

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

Fa 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 1.1131 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 Beaver Valley Unit 1 5.1 - 13 LRM Revision 104

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

Fa 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 1.2616 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 Beaver Valley Unit 1 5.1 - 14 LRM Revision 104

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

Fa Surveillance W(Z) Function versus Burnup at 75% RTP Exclusion Axial Elevation 75% RTP Zone Point (feet) 33  !:5.64 1.0508 34 ti.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.B3 1.0943 43 3.62 1.1018 44 3.4.2 1.1093 45 3.2:~ 1.1163 46 3.02 1.1236 47 2.8~* 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 Beaver Valley Unit 1 5.1 - 15 LRM Revision 104

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

>O 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.

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

(gpm) F~H Limit 2 283,583 1.62 283,583 > MMF 2 278,941 1.60 COLR Cycle 27 Beaver Valley Unit 1 5.1 - 16 LRM Revision 104