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

Rod L. Penfield Site Vice President 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 Beaver Valley Power Station P.O. Box4 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 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.

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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 5.1.2 5.1.3 SL 2.1.1 Reactor Core Safety Limits See Figure 5.1-1.

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.

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 RA TED 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).

Beaver Valley Unit 1 5.1 - 1 COLR Cycle 27 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)

F (Z) ::::: [CFQ]

• K(Z)

Q 0.5 for P > 0.5 forP ::::: 0.5 Where:

CFQ = 2.40 THERMAL POWER 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.

Beaver Valley Unit 1 5.1 - 2 COLR Cycle 27 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) 5.1.8 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 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 11 T Parameter Values from Table Notations 1 and 2

a.

Overtemperature 11 T Setpoint Parameter Values:

Parameter Overtemperature 11 T reactor trip setpoint Overtemperature 11 T reactor trip setpoint Tavg coefficient Overtemperature 11 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<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.

Beaver Valley Unit 1 5.1 - 3 COLR Cycle 27 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:

Beaver Valley Unit 1 Parameter Overpower ~ T reactor trip setpoint Overpower ~ T reactor trip setpoint Tavg rate/lag coefficient Overpower ~ T reactor trip setpoint Tavg heatup coefficient Tavg at RATED THERMAL POWER Measured reactor vessel average temperature rate/lag time constant Measured reactor vessel ~ T lag time constant Measured reactor vessel average temperature lag time constant Value K4 s 1.085 K5 2 0.02/°F for increasing average temperature K5 = 0/°F for decreasing average temperature K6 2 0.0021/°F for T > T" K6 = 0/°F for T s T" T" s 577.9°F(2l t 3 2 10 secs t4 s 6 secs rs s 2 secs (2)

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

5.1 - 4 COLR Cycle 27 LRM Revision 104

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 ~ Value listed in Table 5.1-4(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 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.

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

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 L1 T 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.

Beaver Valley Unit 1 5.1 - 6 COLR Cycle 27 LRM Revision 104

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

UN A CCEPT ABLE OPERATION 600 ACCEPT ABLE OPERATION 580,.__ ___

......, _ ___ +-------------+-----"""'

0 0.2 Beaver Valley Unit 1 0.4 0.6 0.8 FRACTION OF RA TED 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 27 LRM Revision 104

Licensing Requirements Manual Core Operating Limits Report 5.1

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V 80 100 COLR Cycle 27 LRM Revision 104

Licensing Requirements Manual 1.2 1.0 I o.o, 1.00 I 0.8

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Core Operating Limits Report 5.1 I

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

Licensing Requirements Manual Core Operating Limits Report 5.1

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AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RATED THERMAL POWER FOR RAOC 50 60 Beaver Valley Unit 1 5.1 - 10 COLR Cycle 27 LRM Revision 104

Licensing Requirements Manual Core Operating Limits Report 5.1

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(pcm/ °F) 14000

-30.961 18000

-32. 214 l

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 COLR Cycle 27 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 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 1.1550 9

10.47 1.1500 10 10.27 1.1533 11 10.07 1.1437 12 9.86 1.1451 13 9.66 1.1500 14 9.46 1.1470 15 9.26 1.1412 16 9.06 1.1401 17 8.86 1.1415 18 8.66 1.1505 19 8.46 1.1574 20 8.25 1.1628 21 8.05 1.1668 22 7.85 1.1695 23 7.65 1.1698 24 7.45 1.1690 25 7.25 1.1664 26 7.05 1.1632 27 6.84 1.1590 28 6.64 1.1531 29 6.44 1.1466 30 6.24 1.1396 31 6.04 1.1315 32 5.84 1.1225 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 1.1976 1.2469 1.1963 1.2385 1.1930 1.2287 1.1883 1.2200 1.1842 1.2195 1.1809 1.2185 1.1715 1.2115 1.1681 1.2106 1.1635 1.2080 1.1560 1.2030 1.1558 1.2035 1.1620 1.2062 1.1655 1.2068 1.1676 1.2053 1.1685 1.2027 1.1672 1.1979 1.1648 1.1920 1.1605 1.1837 1.1556 1.1742 1.1498 1.1644 1.1424 1.1532 1.1343 1.1443 1.1256 1.1370 1.1161 1.1286 1.1053 1.1194 5.1 - 12 12000 16000 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 1.2126 1.1954 1.2102 1.1908 1.2060 1.1859 1.2003 1.1807 1.1982 1.1752 1.1980 1.1694 1.1957 1.1662 1.1921 1.1721 1.1884 1.1790 1.1868 1.1832 1.1877 1.1867 1.1937 1.1894 1.1986 1.1925 1.2012 1.1947 1.2023 1.1995 1.2014 1.2031 1.1992 1.2054 1.1943 1.2045 1.1877 1.2016 1.1807 1.1976 1.1724 1.1926 1.1629 1.1861 1.1522 1.1780 1.1406 1.1688 1.1294 1.1587 COLR Cycle 27 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 Zone Point (feet)

MWD/MTU 33 5.64 1.1131 34 5.44 1.1109 35 5.23 1.1118 36 5.03 1.1114 37 4.83 1.1120 38 4.63 1.1157 39 4.43 1.1195 40 4.23 1.1227 41 4.03 1.1256 42 3.83 1.1295 43 3.62 1.1339 44 3.42 1.1376 45 3.22 1.1408 46 3.02 1.1442 47 2.82 1.1506 48 2.62 1.1665 49 2.42 1.1875 50 2.21 1.2079 51 2.01 1.2285 52 1.81 1.2488 53 1.61 1.2676 54 1.41 1.2844 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 1.1002 1.1098 1.0988 1.1021 1.0996 1.0984 1.1011 1.0974 1.1023 1.0956 1.1032 1.0938 1.1039 1.0916 1.1042 1.0894 1.1042 1.0870 1.1041 1.0842 1.1037 1.0811 1.1055 1.0781 1.1104 1.0753 1.1220 1.0749 1.1417 1.0792 1.1643 1.0918 1.1873 1.1081 1.2107 1.1251 1.2342 1.1418 1.2574 1.1581 1.2790 1.1734 1.2986 1.1874 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 16000 MWD/MTU MWD/MTU 1.1217 1.1474 1.1135 1.1364 1.1098 1.1327 1.1057 1.1292 1.1029 1.1254 1.0999 1.1208 1.0965 1.1155 1.0930 1.1101 1.0895 1.1043 1.0846 1.1008 1.0838 1.0984 1.0856 1.0958 1.0873 1.0923 1.0885 1.0945 1.0938 1.1037 1.1058 1.1172 1.1201 1.1326 1.1345 1.1481 1.1482 1.1624 1.1614 1.1759 1.1739 1.1889 1.1854 1.2009 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 27 LRM Revision 104

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 1.2616 1.2465 1.2173 1.1881 1.1706 1.1635 1.1473 1.1237 1.1064 1.1019 1.1013 1.1016 1.1024 1.1014 1.1006 1.0982 1.0949 1.0925 1.0892 1.0860 1.0799 1.0758 1.0699 1.0640 1.0567 COLR Cycle 27 LRM Revision 104

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 ti.44 5.23 5.03 4.83 4.63 4.43 4.. 23 4.03 3.B3 3.62 3.4.2 3.2:~

3.02 2.8~*

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 1.0508 1.0510 1.0555 1.0569 1.0609 1.0673 1.0744 1.0798 1.0853 1.0943 1.1018 1.1093 1.1163 1.1236 1.1338 1.1529 1.1772 1.2008 1.2269 1.2504 1.2743 1.2940 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 COLR Cycle 27 LRM Revision 104

Licensing Requirements Manual Table 5.1-3 Core Operating Limits Report 5.1 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)

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