Text

Core Operating Limits Reports Midcycle Revision
	ML16042A486
Person / Time
Site:	Beaver Valley
Issue date:	02/11/2016
From:	Richey M; FirstEnergy Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-16-048
	Download: ML16042A486 (36)
	v • d • e

FE NOC'

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RrstEnergy Nuclear Operating Company Marty L. Richey Site Vice President February 11, 2016 L-16-048 ATIN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Beaver Valley Power Station, Unit Nos. 1 and 2 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 Core Operating Limits Reports Midcycle Revision 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 Nos. 1 (BVPS-1) and 2 (BVPS-2) Technical Specification 5.6.3, "CORE OPERATING LIMITS REPORT (COLR)," FirstEnergy Nuclear Operating Company hereby submits the BVPS-1 COLR for mid cycle revision 24-2 and the BVPS-2 COLR for mid cycle revision 19-1. Technical Specification 5.6.3.d requires, in part, that the COLR be provided to the Nuclear Regulatory Commission upon issuance for any midcycle revisions or supplements.

These midcycle COLR revisions were made effective on January 28, 2016.

The COLRs were revised to apply plant specific uncertainty to the measured values of the nuclear enthalpy rise hot channel factor and heat flux hot channel factor if the number of measured incore detector thimbles is less than 75 percent and at least 50 percent of the total number of thimbles. When the number of measured thimbles is reduced to this range, the minimum required number of measured thimbles per core quadrant was changed to three. The changes are based on a plant-specific incore flux thimble deletion study.

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.

Sincerely, 1

~ie-~

Marty L. Ri~ey

\\

Beaver Valley Power Station, Unit Nos. 1 and 2 L-16-048 Page2

Enclosures:

A. Beaver Valley Power Station, Unit No. 1, Core Operating Limits Report, Midcycle Revision 24-2 B. Beaver Valley Power Station, Unit No. 2, Core Operating Limits Report, Midcycle Revision 19-1 cc:

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

Enclosure A L-16-048 Beaver Valley Power Station, Unit No. 1 Core Operating Limits Report, Midcycle Revision 24-2 (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 NRG 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% tik/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% tik/k.

5.1.3 LCO 3.1.3 Moderator Temperature Coefficient (MTC)

a.

Upper Limit - MTG shall be maintained within the acceptable operation limit specified in Technical Specification Figure 3.1.3-1.

b.

Lower Limit - MTG shall be maintained less negative than - 4.4 x 1Q-4 Lik/k/°F at RATED THERMAL POWER.

c.

300 ppm Surveillance Limit: (- 37 pcm/°F)

d.

The revised predicted near-EOL 300 ppm MTG shall be calculated using Figure 5.1-5 and the following algorithm from Reference 11 :

Revised Predicted MTG = Predicted MTG* + AFD Correction** + Predictive Correction***

where,

Predicted MTG 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 (LiAFD

AFD Sensitivity)}

where: LiAFD 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 I MFD

- - 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 24 LRM Revision 89

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

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 (Fa(Z))

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

Fa(Z) s [c:a]*K(Z)

F (Z) s [CFQ]

K(Z)

Q 0.5 for P > 0.5 for P s 0.5 Where:

CFQ = 2.40 THERMAL POWER p = RATED THERMAL POWER K(Z) =the function obtained from Figure 5.1-3.

F8 (Z) = F~(Z)

1.0815$

F~ (Z) = F8(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 24-2 LRM Revision 91

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::; 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 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 ~ CF~H * (1 + PF~H (1-P))$

Where:

CF~H = 1.62 PF~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~ T Parameter Values from Table Notations 1 and 2

a.

Overtemperature ~ T Setpoint Parameter Values:

Parameter Overtemperature ~ T reactor trip setpoint Overtemperature ~T reactor trip setpoint Tavg coefficient Overtemperature ~ T reactor trip setpoint pressure coefficient Tavg at RATED THERMAL POWER K1::; 1.242 K2 ~ 0.0183/°F K3 ~ 0.001/psia T's 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 FN~H 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 24-2 LRM Revision 91

Licensing Requirements Manual Core Operating Limits Report S.1 S.1 Core Operating Limits Report Nominal pressurizer pressure P' ~ 22SO psia Measured reactor vessel average temperature lead/lag t 1 ~ 30 secs time constants t 2 ::;; 4 secs Measured reactor vessel AT lag time constant t4 ::;; 6 secs Measured reactor vessel average temperature lag ts ::;; 2 secs time constant f (Al) 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 +1 So/o, f(AI) = O (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 (q1 - qb) exceeds -37%, the AT trip setpoint shall be automatically reduced by 2.S2% of its value at RATED THERMAL POWER.

(iii)

For each percent that the magnitude of (qt - qb) exceeds +1 So/o, the AT trip setpoint shall be automatically reduced by 1.4 7% of its value at RATED THERMAL POWER.

b.

Overpower AT Setpoint Parameter Values:

Beaver Valley Unit 1 Parameter Overpower AT reactor trip setpoint Overpower AT reactor trip setpoint Tavg rate/lag coefficient Overpower AT reactor trip setpoint Tavg heatup coefficient Tavg at RATED THERMAL POWER Measured reactor vessel average temperature rate/lag time constant Measured reactor vessel AT lag time constant Measured reactor vessel average temperature lag time constant Value K4::;; 1.08S 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"::;; S77.9°F<2>

t3 ~ 10 secs t4::;; 6 secs ts::;; 2 secs (2)

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

S.1 - 4 COLR Cycle 24-1 LRM Revision 90

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 CDNB) Limits 5.1.11 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~ 267,300 gpm<3l 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.

Beaver Valley Unit 1 5.1 - 5 COLR Cycle 24 LRM Revision 89

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 19S5 (Westinghouse Proprietary).

2.

WCAP-S7 45-P-A, "Design Bases for the Thermal Overpower ~ T and Thermal Overtemperature ~T Trip Functions," September 19S6.

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 199S (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.

S.

Caldon, Inc. Engineering Report-SOP, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM'1' System," Revision 0, March 1997.

9.

Caldon, Inc. Engineering Report-160P, "Supplement to Topical Report ER-SOP: Basis for a Power Uprate With the LEFM'1' 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.

Beaver Valley Unit 1 5.1 - 6 COLR Cycle 24 LRM Revision S9

Licensing Requirements Manual Core Operating Limits Report 5.1 UNACCEPTABLE OPERATION

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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 24 LRM Revision 89

Licensing Requirements Manual

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CONTROL ROD INSERTION LIMITS Beaver Valley Unit 1 5.1 - 8

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v 80 100 COLR Cycle 24 LRM Revision 89

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

§ 0.6 0.4 0.2 0.0 0

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Figure 5.1-3 (Page 1 of 1)

Core Operating Limits Report 5.1 I 12.0, 0.925 t 10 12 Fa T NORMALIZED OPERATING ENVELOPE, K(Z)

Beaver Valley Unit 1 5.1 - 9 COLR Cycle 24 LRM Revision 89

Licensing Requirements Manual Core Operating Limits Report 5.1 120 110 i( 8, 100) 1(+8, 10 0) I 100

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Figure 5.1-4 (Page 1 of 1)

AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RA TED THERMAL POWER FOR RAOC Beaver Valley Unit 1 5.1 - 10 COLR Cycle 24 LRM Revision 89

Licensing Requirements Manual Core Operating Limits Report 5.1 ii.

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14000 15000 16000 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

-........._ r-_

17000 COLR Cycle 24 LRM Revision 89

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

Core Operating Limits Report 5.1 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 1.1358 9

10.47 1.1294 10 10.27 1.1223 11 10.07 1.1151 12 9.86 1.1058 13 9.66 1.1023 14 9.46 1.1055 15 9.26 1.1061 16 9.06 1.1071 17 8.86 1.1154 18 8.66 1.1271 19 8.46 1.1356 20 8.25 1.1427 21 8.05 1.1481 22 7.85 1.1518 23 7.65 1.1538 24 7.45 1.1542 25 7.25 1.1534 26 7.05 1.1523 27 6.84 1.1505 28 6.64 1.1475 29 6.44 1.1436 30 6.24 1.1386 31 6.04 1.1324 32 5.84 1.1265 Note: Top and Bottom 10% Excluded Beaver Valley Unit 1 5.1 - 12 3000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1361 1.1320 1.1291 1.1248 1.1197 1.1138 1.1092 1.1084 1.1084 1.1157 1.1267 1.1347 1.1413 1.1462 1.1494 1.1508 1.1506 1.1493 1.1476 1.1453 1.1417 1.1372 1.1316 1.1251 1.1176 10000 18000 MWD/MTU MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2445 1.2372 1.2289 1.2199 1.2095 1.2008 1.1950 1.1897 1.1881 1.1930 1.2046 1.2137 1.2207 1.2253 1.2275 1.2273 1.2248 1.2201 1.2145 1.2080 1.2003 1.1910 1.1801 1.1681 1.1544 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2326 1.2152 1.1939 1.1758 1.1743 1.1775 1.1804 1.1817 1.1862 1.1898 1.1954 1.2067 1.2184 1.2276 1.2341 1.2379 1.2392 1.2382 1.2350 1.2306 1.2254 1.2187 1.2101 1.1998 1.1879 COLR Cycle 24 LRM Revision 89

Licensing Requirements Manual Table 5.1-1(Page2of2)

Core Operating Limits Report 5.1 Fa Surveillance W(Z) Function versus Burn up at 100% RTP Exclusion Axial Elevation 150 Zone Point (feet)

MWD/MTU 33 5.64 1.1230 34 5.44 1.1229 35 5.23 1.1255 36 5.03 1.1309 37 4.83 1.1370 38 4.63 1.1422 39 4.43 1.1469 40 4.23 1.1511 41 4.03 1.1547 42 3.83 1.1577 43 3.62 1.1604 44 3.42 1.1629 45 3.22 1.1633 46 3.02 1.1693 47 2.82 1.1856 48 2.62 1.2048 49 2.42 1.2240 50 2.21 1.2450 51 2.01 1.2672 52 1.81 1.2886 53 1.61 1.3090 54 1.41 1.3278 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 5.1 - 13 3000 MWD/MTU 1.1120 1.1122 1.1154 1.1192 1.1222 1.1247 1.1268 1.1285 1.1298 1.1309 1.1317 1.1327 1.1376 1.1532 1.1788 1.2044 1.2304 1.2568 1.2827 1.3080 1.3322 1.3543 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 10000 18000 MWD/MTU MWD/MTU 1.1402 1.1285 1.1185 1.1119 1.1073 1.1021 1.0978 1.0934 1.0878 1.0840 1.0840 1.0844 1.0843 1.0851 1.0900 1.0989 1.1137 1.1302 1.1459 1.1616 1.1767 1.1907 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1742 1.1599 1.1522 1.1473 1.1414 1.1345 1.1267 1.1180 1.1088 1.0989 1.0887 1.0810 1.0738 1.0750 1.0870 1.0977 1.1088 1.1205 1.1331 1.1470 1.1603 1.1730 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 COLR Cycle 24 LRM Revision 89

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 1.2023 1.1828 1.1630 1.1437 1.1213 1.1052 1.0972 1.0876 1.0792 1.0792 1.0834 1.0861 1.0885 1.0897 1.0899 1.0903 1.0904 1.0899 1.0895 1.0891 1.0877 1.0855 1.0826 1.0786 1.0750 COLR Cycle 24 LRM Revision 89

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

Core Operating Limits Report 5.1 F0 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 1.0736 1.0753 1.0799 1.0875 1.0963 1.1045 1.1123 1.1197 1.1268 1.1332 1.1399 1.1465 1.1509 1.1607 1.1806 1.2028 1.2251 1.2495 1.2754 1.3008 1.3253 1.3482 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 COLR Cycle 24 LRM Revision 89

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

F0 (Z) Penalty Factor versus Burnup Cycle Burnup (MWD/MTU)

Fo(Z) Penalty Factor

>O 1.0200 Note: The Penalty Factor, to be applied to F0 (Z) in accordance with Technical Specification Surveillance Requirement (SR) 3.2.1.2, is the maximum factor by which Fo(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 COLR Cycle 24 LRM Revision 89

Enclosure B L-16-048 Beaver Valley Power Station, Unit No. 2 Core Operating Limits Report, Midcycle Revision 19-1 (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)

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 - 4.29 x 10-4

~k/k/°F at RATED THERMAL POWER.

c.

300 ppm Surveillance Limit: (- 35 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 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 :

{O pcm/°F or (~AFD

AFD Sensitivity)}

where: AAFD 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 I AAFD

- - 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 SDM) that are not within the applicability of LCO 3.1.1, SHUTDOWN MARGIN (SOM).

Beaver Valley Unit 2 5.1 - 1 COLR Cycle 19 LRM Revision 85

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: (- 41 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 (Fa(Z))

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

F0 (Z) :,; [ c:a]*K(Z) for P > o.5 F (Z) :,; [CFQ]

K(Z)

Q 0.5 for P:,; 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~ (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 2 5.1 - 2 COLR Cycle 19-1 LRM Revision 86

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 Pis~ 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 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 ~CFl:IH *(1+PFl:IH(1-P))$

Where:

CF l:IH = 1.62 PFl:IH

= 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 Ii T Parameter Values from Table Notations 3 and 4

a.

Overtemperature Ii T Setpoint Parameter Values:

Parameter Overtemperature Ii T reactor trip setpoint Overtemperature Ii T reactor trip setpoint Tavg coefficient Overtemperature Ii T reactor trip setpoint pressure coefficient Tavg at RATED THERMAL POWER K1~1.239 K2::::: 0.0183/°F K3::::: 0.001/psia T' ~ 574.2°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!iH of 1.04, where Tis 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 2 5.1 - 3 COLR Cycle 19-1 LRM Revision 86

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report Nominal pressurizer pressure P' ~ 2250 psia Measured reactor vessel ""T lead/lag time constants

'!1 = O sec*

(*The response time is toggled off to meet the analysis

, 2 = O sec*

value of zero.)

Measured reactor vessel ""T lag time constant

'!3 s 6 secs Measured reactor vessel average temperature lead/lag

, 4 ~ 30 secs time constants

, 5 s 4 secs Measured reactor vessel average temperature lag time

, 6 s 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(""1) = 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 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 ""T lead/lag time constants Value K4 s 1.094 K5 ~ 0.02/°F for increasing average temperature K5 = 0/°F for decreasing average temperature K6 ~ 0.0021/°F for T > T" K6 = 0/°F for T s T" T" s 574.2°F<1>

'!1 = O sec*

'!2 = O 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.

Beaver Valley Unit 2 5.1 - 4 COLR Cycle 19-1 LRM Revision 86

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.10 5.1.11 Measured reactor vessel ~ T lag time constant Measured reactor vessel average temperature lag time constant Measured reactor vessel average temperature rate/lag time constant

-r3 ~ 6 secs

-rs~ 2 secs

1 ~ 10 secs LCO 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling CDNB) Limits Parameter Indicated Value Reactor Coolant System Tavg Tavg ~ 577.8°F<1>

Pressurizer Pressure Pressure~ 2214 psia<2>

Reactor Coolant System Total Flow Rate Flow~ 267,300 gpm<3>

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.

Beaver Valley Unit 2 5.1 - 5 COLR Cycle 19-1 LRM Revision 86

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 AT and Thermal Overtemperature AT 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.Y' 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.Y'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.

Beaver Valley Unit 2 5.1 - 6 COLR Cycle 19 LRM Revision 85

Licensing Requirements Manual Core Operating Limits Report 5.1 G:' 630

~

Q '-'

~

UNACCEPTABLE OPERATION

~ 620--~~~-+-~~~--1--"",.__~~-+-~~~--+-~~~---1----~~---'\\+-~~~--J 600 ACCEPT ABLE OPERATION 0

0.2 Beaver Valley Unit 2 0.4 0.6 0.8 FRACTION OF RA TED THERMAL POWER Figure5.1-1(Page1of1)

REACTOR CORE SAFETY LIMIT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1) 5.1 - 7 1.2 1.4 COLR Cycle 19 LRM Revision 85

Licensing Requirements Manual Core Operating Limits Report 5.1 c

175

<tJ

'U

.L:

+-' s 150 en a.

Q)

+-'

Cf) 125 225 v

~:53, ??5) 1J

/

~,

v1 BANKCI I <100. 187) I

/

v

,/ v V'

/

200 z

0 I-Cf) 100 0 a..

~

z

<(

75 ca 0

0 c::::

/

v I (o, 114>J

/BANK ol, v

/

/ v 50 25 I/

/

~ /I (8, o)

I 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 Beaver Valley Unit 2 5.1 - 8 COLR Cycle 19 LRM Revision 85

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

~ 0.6 0.4 0.2 0.0 0

2 4

16.0, 1.00 I 6

8 Core Height (feet)

Figure 5.1-3 (Page 1of1)

Core Operating Limits Report 5.1 I

12.0, 0.925 t I

10 12 Fo T NORMALIZED OPERATING ENVELOPE, K(Z)

Beaver Valley Unit 2 5.1 - 9 COLR Cycle 19 LRM Revision 85

Licensing Requirements Manual Core Operating Limits Report 5.1 0

ll..

ns E..

G>

.c 1-

'C G> -

ns a:: -

0

'<ft.

120 110 I (

8 1 10 0) 1(+8, 10 0) I 100 I

\\

J I UNACCEPTABLE I

/,

\\ I UNACCEPTABLE I OPERATION OPERATION 90 f 'ACCEPTABLE' \\

OPERATION

)

80 I

\\

I

\\

70 J

\\

I 60 I

\\

50

(-25, 50) 1(+22, 50) 40 30 20 10 0

-60

-50

-40

-30

-20

-10 0

10 20 30 40 50 60 Axial Flux Difference (Delta 1)%

Figure 5.1-4 (Page 1of1)

AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RATED THERMAL POWER FOR RAOC Beaver Valley Unit 2 5.1 - 10 COLR Cycle 19 LRM Revision 85

Licensing Requirements Manual Core Operating Limits Report 5.1

~

rz:i H u H

-29.00 1%1 -30.00 1%1 rz:i 0 u rz:i

~

t:>

~

rz:i Ill

s rz:i E-t

~

0

-31.00

~

rz:i c

~

-32.00 14000 Beaver Valley Unit 2 CYCLB BURNOP MTC (MWD/MTU)

(Pot/0 P) 14000

-29.41 18000

-31.39

~

15000 16000 17000 CYCLE BURNUP (MWD/MTU)

Figure 5.1-5 (Page 1of1)

HOT FULL POWER PREDICTED MODERATOR TEMPERATURE COEFFICIENT AS A FUNCTION OF CYCLE BURNUP WHEN 300 PPM IS ACHIEVED 5.1 - 11 18000 COLR Cycle 19 LRM Revision 85

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

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

(MWD/MTU) 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 1.1656 9

10.5 1.1666 10 10.3 1.1660 11

10. 1 1.1636 12 9.9 1.1601 13 9.7 1.1564 14 9.5 1.1530 15 9.3 1.1505 16 9.1 1.1496 17 8.9 1.1515 18 8.7 1.1564 19 8.5 1.1635 20 8.3 1.1700 21 8.1 1.1745 22 7.9 1.1773 23 7.6 1.1784 24 7.4 1.1779 25 7.2 1.1759 26 7.0 1.1723 27 6.8 1.1672 28 6.6 1.1608 29 6.4 1.1531 30 6.2 1.1442 31 6.0 1.1340 32 5.8 1.1235 Note: Top and Bottom 10% Excluded Beaver Valley Unit 2 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 1.2218 1.2278 1.2140 1.2255 1.2075 1.2236 1.1999 1.2208 1.1905 1.2171 1.1804 1.2130 1.1694 1.2075 1.1572 1.1998 1.1470 1.1929 1.1417 1.1897 1.1413 1.1892 1.1449 1.1905 1.1495 1.1933 1.1535 1.1964 1.1558 1.1980 1.1567 1.1979 1.1562 1.1961 1.1547 1.1928 1.1524 1.1881 1.1489 1.1821 1.1440 1.1748 1.1381 1.1659 1.1310 1.1558 1.1225 1.1447 1.1140 1.1320 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 1.2247 1.2293 1.2214 1.2208 1.2176 1.2084 1.2119 1.2024 1.2054 1.1976 1.2025 1.1907 1.2005 1.1850 1.2028 1.1868 1.2060 1.1901 1.2093 1.1904 1.2153 1.1912 1.2241 1.1939 1.2307 1.1957 1.2340 1.1972 1.2353 1.2007 1.2348 1.2046 1.2323 1.2062 1.2280 1.2056 1.2219 1.2032 1.2142 1.1995 1.2051 1.1944 1.1943 1.1878 1.1817 1.1795 1.1676 1.1698 1.1526 1.1586 COLR Cycle 19 LRM Revision 85

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

FQ Surveillance W(Z) Function versus Burn up at 100% RTP Exclusion Axial Elevation 150 Zone Point (feet)

(MWD/MTU) 33 5.6 1.1146 34 5.4 1.1115 35 5.2 1.1122 36 5.0 1.1150 37 4.8 1.1173 38 4.6 1.1192 39 4.4 1.1207 40 4.2 1.1216 41 4.0 1.1229 42 3.8 1.1251 43 3.6 1.1273 44 3.4 1.1290 45 3.2 1.1309 46 3.0 1.1358 47 2.8 1.1483 48 2.6 1.1670 49 2.4 1.1895 50 2.2 1.2131 51 2.0 1.2360 52 1.8 1.2581 53 1.6 1.2795 54 1.4 1.2995 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 Beaver Valley Unit 2 3000 8000 (MWD/MTU)

(MWD/MTU) 1.1069 1.1179 1.1015 1.1073 1.0984 1.1024 1.0979 1.0988 1.0991 1.0949 1.1000 1.0908 1.1005 1.0861 1.1013 1.0804 1.1030 1.0775 1.1059 1.0782 1.1091 1.0805 1.1116 1.0818 1.1134 1.0824 1.1196 1.0849 1.1393 1.0935 1.1663 1.1078 1.1920 1.1264 1.2172 1.1463 1.2427 1.1656 1.2676 1.1842 1.2914 1.2023 1.3138 1.2196 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) 1.1378 1.1461 1.1258 1.1371 1.1176 1.1329 1.1126 1.1283 1.1093 1.1218 1.1052 1.1149 1.1004 1.1071 1.0952 1.0979 1.0899 1.0912 1.0845 1.0895 1.0790 1.0889 1.0737 1.0871 1.0718 1.0857 1.0717 1.0854 1.0818 1.0955 1.0986 1.1127 1.1143 1.1283 1.1295 1.1433 1.1450 1.1585 1.1601 1.1734 1.1747 1.1878 1.1888 1.2019 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 19 LRM Revision 85

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

Core Operating Limits Report 5.1 Fa Surveillance W(Z) Function at Initial Cycle Startup at 75% RTP Exclusion Zone Axial Point Elevation (feet) 1 12.1 2

11.9 3

11.7 4

11.5 5

11.3 6

11.1 7

10.9 8

10.7 9

10.5 10 10.3 11 10.1 12 9.9 13 9.7 14 9.5 15 9.3 16 9.1 17 8.9 18 8.7 19 8.5 20 8.3 21 8.1 22 7.9 23 7.6 24 7.4 25 7.2 26 7.0 27 6.8 28 6.6 29 6.4 30 6.2 31 6.0 32 5.8 Note: Top and Bottom 10% Excluded Beaver Valley Unit 2 5.1 - 14 75% RTP 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2426 1.2289 1.2147 1.1998 1.1837 1.1683 1.1541 1.1417 1.1311 1.1244 1.1221 1.1234 1.1248 1.1249 1.1242 1.1230 1.1208 1.1175 1.1133 1.1080 1.1020 1.0950 1.0875 1.0791 1.0704 COLR Cycle 19 LRM Revision 85

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

Core Operating Limits Report 5.1 Fa Surveillance W(Z) Function at Initial Cycle Startup at 75% RTP Exclusion Zone Axial Point Elevation (feet) 33 5.6 34 5.4 35 5.2 36 5.0 37 4.8 38 4.6 39 4.4 40 4.2 41 4.0 42 3.8 43 3.6 44 3.4 45 3.2 46 3.0 47 2.8 48 2.6 49 2.4 50 2.2 51 2.0 52 1.8 53 1.6 54 1.4 55 1.2 56 1.0 57 0.8 58 0.6 59 0.4 60 0.2 61 0.0 Note: Top and Bottom 10% Excluded Beaver Valley Unit 2 5.1 - 15 75% RTP 1.0635 1.0623 1.0649 1.0696 1.0740 1.0781 1.0819 1.0852 1.0892 1.0941 1.0988 1.1025 1.1067 1.1147 1.1303 1.1518 1.1772 1.2037 1.2300 1.2555 1.2807 1.3045 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 COLR Cycle 19 LRM Revision 85

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

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

Fo(Z) Penalty Factor

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

Beaver Valley Unit 2 5.1 - 16 COLR Cycle 19 LRM Revision 85

FE NOC'

~

RrstEnergy Nuclear Operating Company Marty L. Richey Site Vice President February 11, 2016 L-16-048 ATIN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Beaver Valley Power Station, Unit Nos. 1 and 2 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 Core Operating Limits Reports Midcycle Revision 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 Nos. 1 (BVPS-1) and 2 (BVPS-2) Technical Specification 5.6.3, "CORE OPERATING LIMITS REPORT (COLR)," FirstEnergy Nuclear Operating Company hereby submits the BVPS-1 COLR for mid cycle revision 24-2 and the BVPS-2 COLR for mid cycle revision 19-1. Technical Specification 5.6.3.d requires, in part, that the COLR be provided to the Nuclear Regulatory Commission upon issuance for any midcycle revisions or supplements.

These midcycle COLR revisions were made effective on January 28, 2016.

The COLRs were revised to apply plant specific uncertainty to the measured values of the nuclear enthalpy rise hot channel factor and heat flux hot channel factor if the number of measured incore detector thimbles is less than 75 percent and at least 50 percent of the total number of thimbles. When the number of measured thimbles is reduced to this range, the minimum required number of measured thimbles per core quadrant was changed to three. The changes are based on a plant-specific incore flux thimble deletion study.

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.

Sincerely, 1

~ie-~

Marty L. Ri~ey

\\

Beaver Valley Power Station, Unit Nos. 1 and 2 L-16-048 Page2

Enclosures:

A. Beaver Valley Power Station, Unit No. 1, Core Operating Limits Report, Midcycle Revision 24-2 B. Beaver Valley Power Station, Unit No. 2, Core Operating Limits Report, Midcycle Revision 19-1 cc:

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

Enclosure A L-16-048 Beaver Valley Power Station, Unit No. 1 Core Operating Limits Report, Midcycle Revision 24-2 (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 NRG 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% tik/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% tik/k.

5.1.3 LCO 3.1.3 Moderator Temperature Coefficient (MTC)

a.

Upper Limit - MTG shall be maintained within the acceptable operation limit specified in Technical Specification Figure 3.1.3-1.

b.

Lower Limit - MTG shall be maintained less negative than - 4.4 x 1Q-4 Lik/k/°F at RATED THERMAL POWER.

c.

300 ppm Surveillance Limit: (- 37 pcm/°F)

d.

The revised predicted near-EOL 300 ppm MTG shall be calculated using Figure 5.1-5 and the following algorithm from Reference 11 :

Revised Predicted MTG = Predicted MTG* + AFD Correction** + Predictive Correction***

where,

Predicted MTG 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 (LiAFD

AFD Sensitivity)}

where: LiAFD 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 I MFD

- - 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 24 LRM Revision 89

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

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 (Fa(Z))

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

Fa(Z) s [c:a]*K(Z)

F (Z) s [CFQ]

K(Z)

Q 0.5 for P > 0.5 for P s 0.5 Where:

CFQ = 2.40 THERMAL POWER p = RATED THERMAL POWER K(Z) =the function obtained from Figure 5.1-3.

F8 (Z) = F~(Z)

1.0815$

F~ (Z) = F8(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 24-2 LRM Revision 91

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::; 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 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 ~ CF~H * (1 + PF~H (1-P))$

Where:

CF~H = 1.62 PF~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~ T Parameter Values from Table Notations 1 and 2

a.

Overtemperature ~ T Setpoint Parameter Values:

Parameter Overtemperature ~ T reactor trip setpoint Overtemperature ~T reactor trip setpoint Tavg coefficient Overtemperature ~ T reactor trip setpoint pressure coefficient Tavg at RATED THERMAL POWER K1::; 1.242 K2 ~ 0.0183/°F K3 ~ 0.001/psia T's 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 FN~H 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 24-2 LRM Revision 91

Licensing Requirements Manual Core Operating Limits Report S.1 S.1 Core Operating Limits Report Nominal pressurizer pressure P' ~ 22SO psia Measured reactor vessel average temperature lead/lag t 1 ~ 30 secs time constants t 2 ::;; 4 secs Measured reactor vessel AT lag time constant t4 ::;; 6 secs Measured reactor vessel average temperature lag ts ::;; 2 secs time constant f (Al) 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 +1 So/o, f(AI) = O (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 (q1 - qb) exceeds -37%, the AT trip setpoint shall be automatically reduced by 2.S2% of its value at RATED THERMAL POWER.

(iii)

For each percent that the magnitude of (qt - qb) exceeds +1 So/o, the AT trip setpoint shall be automatically reduced by 1.4 7% of its value at RATED THERMAL POWER.

b.

Overpower AT Setpoint Parameter Values:

Beaver Valley Unit 1 Parameter Overpower AT reactor trip setpoint Overpower AT reactor trip setpoint Tavg rate/lag coefficient Overpower AT reactor trip setpoint Tavg heatup coefficient Tavg at RATED THERMAL POWER Measured reactor vessel average temperature rate/lag time constant Measured reactor vessel AT lag time constant Measured reactor vessel average temperature lag time constant Value K4::;; 1.08S 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"::;; S77.9°F<2>

t3 ~ 10 secs t4::;; 6 secs ts::;; 2 secs (2)

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

S.1 - 4 COLR Cycle 24-1 LRM Revision 90

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 CDNB) Limits 5.1.11 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~ 267,300 gpm<3l 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.

Beaver Valley Unit 1 5.1 - 5 COLR Cycle 24 LRM Revision 89

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 19S5 (Westinghouse Proprietary).

2.

WCAP-S7 45-P-A, "Design Bases for the Thermal Overpower ~ T and Thermal Overtemperature ~T Trip Functions," September 19S6.

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 199S (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.

S.

Caldon, Inc. Engineering Report-SOP, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM'1' System," Revision 0, March 1997.

9.

Caldon, Inc. Engineering Report-160P, "Supplement to Topical Report ER-SOP: Basis for a Power Uprate With the LEFM'1' 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.

Beaver Valley Unit 1 5.1 - 6 COLR Cycle 24 LRM Revision S9

Licensing Requirements Manual Core Operating Limits Report 5.1 UNACCEPTABLE OPERATION

~ 630,.__~~----"'o,..-+~~~~-t--~~~-t-~--~~f--~~~-t---~~--t-~~~-----J OI)

(1)

Cl OI)

~

~ 620ol-~~~-+~~~~+---°'4-~~-1-~~~~f--~~~,-J-~~~4+~~~----1 600 ACCEPT ABLE OPERATION 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 24 LRM Revision 89

Licensing Requirements Manual

/

Core Operating Limits Report 5.1

/ v 54.53, 225 I

/

200

/

/ v I

I

/

I BANKC I

/

/ /

150 c::

~

v

/ v

/

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v

/

0 i::z:::

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/ /

/ v

/

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50

/ v

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/ / I 0

0 20 40 60 Relative Power (Percent)

Figure 5.1-2 (Page 1 of 1)

CONTROL ROD INSERTION LIMITS Beaver Valley Unit 1 5.1 - 8

/

loo, 187 1/

/

II'

/

II'

/

v 80 100 COLR Cycle 24 LRM Revision 89

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

§ 0.6 0.4 0.2 0.0 0

2 16.0, 1.00 I 4

6 8

Core Height (feet)

Figure 5.1-3 (Page 1 of 1)

Core Operating Limits Report 5.1 I 12.0, 0.925 t 10 12 Fa T NORMALIZED OPERATING ENVELOPE, K(Z)

Beaver Valley Unit 1 5.1 - 9 COLR Cycle 24 LRM Revision 89

Licensing Requirements Manual Core Operating Limits Report 5.1 120 110 i( 8, 100) 1(+8, 10 0) I 100

\\

90 J

I UN AC CE PT ABLE I

/,

\\

I UNACCEPTABLE I OPERATION OPERATION QJ

s:

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r-1 f rccEPTABLEI \\

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-60

-50

-40

-30

-20

-10 0

10 20 30 40 50 60 Axial Flux Difference (Delta I)%

Figure 5.1-4 (Page 1 of 1)

AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RA TED THERMAL POWER FOR RAOC Beaver Valley Unit 1 5.1 - 10 COLR Cycle 24 LRM Revision 89

Licensing Requirements Manual Core Operating Limits Report 5.1 ii.

0 8 u

-28.00

.34 -29.00 E-< z i:Ll H u H µ,. -30.00

µ,.

i:Ll 0 u i:Ll p::;

p E-<

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~

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-31.00

-32.00

-33.00

-34.00 13000 Beaver Valley Unit 1

~

14000 15000 16000 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

-........._ r-_

17000 COLR Cycle 24 LRM Revision 89

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

Core Operating Limits Report 5.1 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 1.1358 9

10.47 1.1294 10 10.27 1.1223 11 10.07 1.1151 12 9.86 1.1058 13 9.66 1.1023 14 9.46 1.1055 15 9.26 1.1061 16 9.06 1.1071 17 8.86 1.1154 18 8.66 1.1271 19 8.46 1.1356 20 8.25 1.1427 21 8.05 1.1481 22 7.85 1.1518 23 7.65 1.1538 24 7.45 1.1542 25 7.25 1.1534 26 7.05 1.1523 27 6.84 1.1505 28 6.64 1.1475 29 6.44 1.1436 30 6.24 1.1386 31 6.04 1.1324 32 5.84 1.1265 Note: Top and Bottom 10% Excluded Beaver Valley Unit 1 5.1 - 12 3000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1361 1.1320 1.1291 1.1248 1.1197 1.1138 1.1092 1.1084 1.1084 1.1157 1.1267 1.1347 1.1413 1.1462 1.1494 1.1508 1.1506 1.1493 1.1476 1.1453 1.1417 1.1372 1.1316 1.1251 1.1176 10000 18000 MWD/MTU MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2445 1.2372 1.2289 1.2199 1.2095 1.2008 1.1950 1.1897 1.1881 1.1930 1.2046 1.2137 1.2207 1.2253 1.2275 1.2273 1.2248 1.2201 1.2145 1.2080 1.2003 1.1910 1.1801 1.1681 1.1544 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2326 1.2152 1.1939 1.1758 1.1743 1.1775 1.1804 1.1817 1.1862 1.1898 1.1954 1.2067 1.2184 1.2276 1.2341 1.2379 1.2392 1.2382 1.2350 1.2306 1.2254 1.2187 1.2101 1.1998 1.1879 COLR Cycle 24 LRM Revision 89

Licensing Requirements Manual Table 5.1-1(Page2of2)

Core Operating Limits Report 5.1 Fa Surveillance W(Z) Function versus Burn up at 100% RTP Exclusion Axial Elevation 150 Zone Point (feet)

MWD/MTU 33 5.64 1.1230 34 5.44 1.1229 35 5.23 1.1255 36 5.03 1.1309 37 4.83 1.1370 38 4.63 1.1422 39 4.43 1.1469 40 4.23 1.1511 41 4.03 1.1547 42 3.83 1.1577 43 3.62 1.1604 44 3.42 1.1629 45 3.22 1.1633 46 3.02 1.1693 47 2.82 1.1856 48 2.62 1.2048 49 2.42 1.2240 50 2.21 1.2450 51 2.01 1.2672 52 1.81 1.2886 53 1.61 1.3090 54 1.41 1.3278 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 5.1 - 13 3000 MWD/MTU 1.1120 1.1122 1.1154 1.1192 1.1222 1.1247 1.1268 1.1285 1.1298 1.1309 1.1317 1.1327 1.1376 1.1532 1.1788 1.2044 1.2304 1.2568 1.2827 1.3080 1.3322 1.3543 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 10000 18000 MWD/MTU MWD/MTU 1.1402 1.1285 1.1185 1.1119 1.1073 1.1021 1.0978 1.0934 1.0878 1.0840 1.0840 1.0844 1.0843 1.0851 1.0900 1.0989 1.1137 1.1302 1.1459 1.1616 1.1767 1.1907 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1742 1.1599 1.1522 1.1473 1.1414 1.1345 1.1267 1.1180 1.1088 1.0989 1.0887 1.0810 1.0738 1.0750 1.0870 1.0977 1.1088 1.1205 1.1331 1.1470 1.1603 1.1730 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 COLR Cycle 24 LRM Revision 89

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 1.2023 1.1828 1.1630 1.1437 1.1213 1.1052 1.0972 1.0876 1.0792 1.0792 1.0834 1.0861 1.0885 1.0897 1.0899 1.0903 1.0904 1.0899 1.0895 1.0891 1.0877 1.0855 1.0826 1.0786 1.0750 COLR Cycle 24 LRM Revision 89

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

Core Operating Limits Report 5.1 F0 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 1.0736 1.0753 1.0799 1.0875 1.0963 1.1045 1.1123 1.1197 1.1268 1.1332 1.1399 1.1465 1.1509 1.1607 1.1806 1.2028 1.2251 1.2495 1.2754 1.3008 1.3253 1.3482 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 COLR Cycle 24 LRM Revision 89

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

F0 (Z) Penalty Factor versus Burnup Cycle Burnup (MWD/MTU)

Fo(Z) Penalty Factor

>O 1.0200 Note: The Penalty Factor, to be applied to F0 (Z) in accordance with Technical Specification Surveillance Requirement (SR) 3.2.1.2, is the maximum factor by which Fo(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 COLR Cycle 24 LRM Revision 89

Enclosure B L-16-048 Beaver Valley Power Station, Unit No. 2 Core Operating Limits Report, Midcycle Revision 19-1 (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)

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 - 4.29 x 10-4

~k/k/°F at RATED THERMAL POWER.

c.

300 ppm Surveillance Limit: (- 35 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 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 :

{O pcm/°F or (~AFD

AFD Sensitivity)}

where: AAFD 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 I AAFD

- - 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 SDM) that are not within the applicability of LCO 3.1.1, SHUTDOWN MARGIN (SOM).

Beaver Valley Unit 2 5.1 - 1 COLR Cycle 19 LRM Revision 85

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: (- 41 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 (Fa(Z))

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

F0 (Z) :,; [ c:a]*K(Z) for P > o.5 F (Z) :,; [CFQ]

K(Z)

Q 0.5 for P:,; 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~ (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 2 5.1 - 2 COLR Cycle 19-1 LRM Revision 86

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 Pis~ 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 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 ~CFl:IH *(1+PFl:IH(1-P))$

Where:

CF l:IH = 1.62 PFl:IH

= 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 Ii T Parameter Values from Table Notations 3 and 4

a.

Overtemperature Ii T Setpoint Parameter Values:

Parameter Overtemperature Ii T reactor trip setpoint Overtemperature Ii T reactor trip setpoint Tavg coefficient Overtemperature Ii T reactor trip setpoint pressure coefficient Tavg at RATED THERMAL POWER K1~1.239 K2::::: 0.0183/°F K3::::: 0.001/psia T' ~ 574.2°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!iH of 1.04, where Tis 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 2 5.1 - 3 COLR Cycle 19-1 LRM Revision 86

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report Nominal pressurizer pressure P' ~ 2250 psia Measured reactor vessel ""T lead/lag time constants

'!1 = O sec*

(*The response time is toggled off to meet the analysis

, 2 = O sec*

value of zero.)

Measured reactor vessel ""T lag time constant

'!3 s 6 secs Measured reactor vessel average temperature lead/lag

, 4 ~ 30 secs time constants

, 5 s 4 secs Measured reactor vessel average temperature lag time

, 6 s 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(""1) = 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 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 ""T lead/lag time constants Value K4 s 1.094 K5 ~ 0.02/°F for increasing average temperature K5 = 0/°F for decreasing average temperature K6 ~ 0.0021/°F for T > T" K6 = 0/°F for T s T" T" s 574.2°F<1>

'!1 = O sec*

'!2 = O 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.

Beaver Valley Unit 2 5.1 - 4 COLR Cycle 19-1 LRM Revision 86

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.10 5.1.11 Measured reactor vessel ~ T lag time constant Measured reactor vessel average temperature lag time constant Measured reactor vessel average temperature rate/lag time constant

-r3 ~ 6 secs

-rs~ 2 secs

1 ~ 10 secs LCO 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling CDNB) Limits Parameter Indicated Value Reactor Coolant System Tavg Tavg ~ 577.8°F<1>