L-16-048, Core Operating Limits Reports Midcycle Revision

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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


Text

FENOC' ~

Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 RrstEnergy Nuclear Operating Company Marty L. Richey 724-682-5234 Site Vice President Fax: 724-643-8069 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 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).

COLR Cycle 24 Beaver Valley Unit 1 5.1 - 1 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) for P > 0.5 F (Z) s [CFQ]

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

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.

COLR Cycle 24-2 Beaver Valley Unit 1 5.1 - 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 K1::; 1.242 Overtemperature ~T reactor trip setpoint Tavg K2 ~ 0.0183/°F coefficient Overtemperature ~ T reactor trip setpoint pressure K3 ~ 0.001/psia coefficient Tavg at RATED THERMAL POWER 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.

COLR Cycle 24-2 Beaver Valley Unit 1 5.1 - 3 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 1.47% of its value at RATED THERMAL POWER.

b. Overpower AT Setpoint Parameter Values:

Parameter Value Overpower AT reactor trip setpoint K4::;; 1.08S Overpower AT reactor trip setpoint Tavg KS ~ 0.02/°F for increasing rate/lag coefficient average temperature KS = 0/°F for decreasing average temperature Overpower AT reactor trip setpoint Tavg K6 ~ 0.0021/°F for T > T" heatup coefficient K6 = 0/°F for T ::;; T" Tavg at RATED THERMAL POWER T"::;; S77.9°F<2 >

Measured reactor vessel average t3 ~ 10 secs temperature rate/lag time constant Measured reactor vessel AT lag time t4::;; 6 secs constant Measured reactor vessel average ts::;; 2 secs temperature lag time constant (2) T" represents the cycle-specific Full Power Tavg value used in core design.

COLR Cycle 24-1 Beaver Valley Unit 1 S.1 - 4 LRM Revision 90

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.10 LCO 3.4.1. RCS Pressure. Temperature. and Flow Departure from Nucleate Boiling CDNB) Limits Parameter Indicated Value Reactor Coolant System Tavg Tavg::;: 581.5°F< 1l Pressurizer Pressure Pressure ~ 2218 psia< 2l Reactor Coolant System Total Flow Rate Flow~ 267,300 gpm< 3l 5.1.11 LCO 3.9.1 Boron Concentration (MODE 6)

The boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained ~ 2400 ppm. This value includes a 50 ppm conservative allowance for uncertainties.

(1) The Reactor Coolant System (RCS) indicated Tavg value is determined by adding the appropriate allowances for rod control operation and verification via control board indication (3.6°F) to the cycle specific full power Tavg used in the core design.

(2) The pressurizer pressure value includes allowances for pressurizer pressure control operation and verification via control board indication.

(3) The RCS total flow rate includes allowances for normalization of the cold leg elbow taps with a beginning of cycle precision RCS flow calorimetric measurement and verification on a periodic basis via control board indication.

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

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.12 References

1. WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 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 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.

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.

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

Licensing Requirements Manual Core Operating Limits Report 5.1 UNACCEPTABLE OPERATION

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REACTOR CORE SAFETY LIMIT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1)

COLR Cycle 24 Beaver Valley Unit 1 5.1 - 7 LRM Revision 89

Licensing Requirements Manual Core Operating Limits Report 5.1

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CONTROL ROD INSERTION LIMITS COLR Cycle 24 Beaver Valley Unit 1 5.1 - 8 LRM Revision 89

Licensing Requirements Manual Core Operating Limits Report 5.1 1.2 Io.o, 1.00 I 16.0, 1.00 I 1.0 I 12.0, 0.925 t 0.8

§ 0.6 0.4 0.2 0.0 0 2 4 6 8 10 12 Core Height (feet)

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FaT NORMALIZED OPERATING ENVELOPE, K(Z)

COLR Cycle 24 Beaver Valley Unit 1 5.1 - 9 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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AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RA TED THERMAL POWER FOR RAOC COLR Cycle 24 Beaver Valley Unit 1 5.1 - 10 LRM Revision 89

Licensing Requirements Manual Core Operating Limits Report 5.1

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HOT FULL POWER PREDICTED MODERATOR TEMPERATURE COEFFICIENT AS A FUNCTION OF CYCLE BURNUP WHEN 300 PPM IS ACHIEVED COLR Cycle 24 Beaver Valley Unit 1 5.1 - 11 LRM Revision 89

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

Fa Surveillance W(Z) Function versus Burnup at 100% RTP Exclusion Axial Elevation 150 3000 10000 18000 Zone Point (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU

  • 1 12.08 1.0000 1.0000 1.0000 1.0000
  • 2 11.88 1.0000 1.0000 1.0000 1.0000
  • 3 11.68 1.0000 1.0000 1.0000 1.0000
  • 4 11.47 1.0000 1.0000 1.0000 1.0000
  • 5 11.27 1.0000 1.0000 1.0000 1.0000
  • 6 11.07 1.0000 1.0000 1.0000 1.0000
  • 7 10.87 1.0000 1.0000 1.0000 1.0000 8 10.67 1.1358 1.1361 1.2445 1.2326 9 10.47 1.1294 1.1320 1.2372 1.2152 10 10.27 1.1223 1.1291 1.2289 1.1939 11 10.07 1.1151 1.1248 1.2199 1.1758 12 9.86 1.1058 1.1197 1.2095 1.1743 13 9.66 1.1023 1.1138 1.2008 1.1775 14 9.46 1.1055 1.1092 1.1950 1.1804 15 9.26 1.1061 1.1084 1.1897 1.1817 16 9.06 1.1071 1.1084 1.1881 1.1862 17 8.86 1.1154 1.1157 1.1930 1.1898 18 8.66 1.1271 1.1267 1.2046 1.1954 19 8.46 1.1356 1.1347 1.2137 1.2067 20 8.25 1.1427 1.1413 1.2207 1.2184 21 8.05 1.1481 1.1462 1.2253 1.2276 22 7.85 1.1518 1.1494 1.2275 1.2341 23 7.65 1.1538 1.1508 1.2273 1.2379 24 7.45 1.1542 1.1506 1.2248 1.2392 25 7.25 1.1534 1.1493 1.2201 1.2382 26 7.05 1.1523 1.1476 1.2145 1.2350 27 6.84 1.1505 1.1453 1.2080 1.2306 28 6.64 1.1475 1.1417 1.2003 1.2254 29 6.44 1.1436 1.1372 1.1910 1.2187 30 6.24 1.1386 1.1316 1.1801 1.2101 31 6.04 1.1324 1.1251 1.1681 1.1998 32 5.84 1.1265 1.1176 1.1544 1.1879 Note: Top and Bottom 10% Excluded COLR Cycle 24 Beaver Valley Unit 1 5.1 - 12 LRM Revision 89

Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-1(Page2of2)

Fa Surveillance W(Z) Function versus Burn up at 100% RTP Exclusion Axial Elevation 150 3000 10000 18000 Zone Point (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 33 5.64 1.1230 1.1120 1.1402 1.1742 34 5.44 1.1229 1.1122 1.1285 1.1599 35 5.23 1.1255 1.1154 1.1185 1.1522 36 5.03 1.1309 1.1192 1.1119 1.1473 37 4.83 1.1370 1.1222 1.1073 1.1414 38 4.63 1.1422 1.1247 1.1021 1.1345 39 4.43 1.1469 1.1268 1.0978 1.1267 40 4.23 1.1511 1.1285 1.0934 1.1180 41 4.03 1.1547 1.1298 1.0878 1.1088 42 3.83 1.1577 1.1309 1.0840 1.0989 43 3.62 1.1604 1.1317 1.0840 1.0887 44 3.42 1.1629 1.1327 1.0844 1.0810 45 3.22 1.1633 1.1376 1.0843 1.0738 46 3.02 1.1693 1.1532 1.0851 1.0750 47 2.82 1.1856 1.1788 1.0900 1.0870 48 2.62 1.2048 1.2044 1.0989 1.0977 49 2.42 1.2240 1.2304 1.1137 1.1088 50 2.21 1.2450 1.2568 1.1302 1.1205 51 2.01 1.2672 1.2827 1.1459 1.1331 52 1.81 1.2886 1.3080 1.1616 1.1470 53 1.61 1.3090 1.3322 1.1767 1.1603 54 1.41 1.3278 1.3543 1.1907 1.1730

  • 55 1.21 1.0000 1.0000 1.0000 1.0000
  • 56 1.01 1.0000 1.0000 1.0000 1.0000
  • 57 0.81 1.0000 1.0000 1.0000 1.0000
  • 58 0.60 1.0000 1.0000 1.0000 1.0000
  • 59 0.40 1.0000 1.0000 1.0000 1.0000
  • 60 0.20 1.0000 1.0000 1.0000 1.0000
  • 61 0.00 1.0000 1.0000 1.0000 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 24 Beaver Valley Unit 1 5.1 - 13 LRM Revision 89

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

Fa Surveillance W(Z) Function versus Burnup at 75% RTP Exclusion Axial Elevation 75% RTP Zone Point (feet)

  • 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 1.2023 9 10.47 1.1828 10 10.27 1.1630 11 10.07 1.1437 12 9.86 1.1213 13 9.66 1.1052 14 9.46 1.0972 15 9.26 1.0876 16 9.06 1.0792 17 8.86 1.0792 18 8.66 1.0834 19 8.46 1.0861 20 8.25 1.0885 21 8.05 1.0897 22 7.85 1.0899 23 7.65 1.0903 24 7.45 1.0904 25 7.25 1.0899 26 7.05 1.0895 27 6.84 1.0891 28 6.64 1.0877 29 6.44 1.0855 30 6.24 1.0826 31 6.04 1.0786 32 5.84 1.0750 Note: Top and Bottom 10% Excluded COLR Cycle 24 Beaver Valley Unit 1 5.1 - 14 LRM Revision 89

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

F0 Surveillance W(Z) Function versus Burnup at 75% RTP Exclusion Axial Elevation 75% RTP Zone Point (feet) 33 5.64 1.0736 34 5.44 1.0753 35 5.23 1.0799 36 5.03 1.0875 37 4.83 1.0963 38 4.63 1.1045 39 4.43 1.1123 40 4.23 1.1197 41 4.03 1.1268 42 3.83 1.1332 43 3.62 1.1399 44 3.42 1.1465 45 3.22 1.1509 46 3.02 1.1607 47 2.82 1.1806 48 2.62 1.2028 49 2.42 1.2251 50 2.21 1.2495 51 2.01 1.2754 52 1.81 1.3008 53 1.61 1.3253 54 1.41 1.3482

  • 55 1.21 1.0000
  • 56 1.01 1.0000
  • 57 0.81 1.0000
  • 58 0.60 1.0000
  • 59 0.40 1.0000
  • 60 0.20 1.0000
  • 61 0.00 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 24 Beaver Valley Unit 1 5.1 - 15 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.

COLR Cycle 24 Beaver Valley Unit 1 5.1 - 16 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).

COLR Cycle 19 Beaver Valley Unit 2 5.1 - 1 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) for P:,; 0.5 Q 0.5 THERMAL POWER Where: CFQ = 2.40 p = RATED THERMAL POWER K(Z) =the function obtained from Figure 5.1-3.

Fg(Z) = F~(Z) *1.0815$

F~ (Z) = Fg(Z)

  • W(Z)

(2) As indicated by the group demand counter

$ An additional uncertainty is to be applied if the number of measured thimbles for the moveable incore detector system is less than 75% of the total number of thimbles. If there are less than 75% of the total number of thimbles and at least 50% of the total number of thimbles measured, an additional uncertainty of (0.01)*(3-T/12.5) is added to the measurement uncertainty, 1.05, where T is the total number of measured thimbles. This adjusted measurement uncertainty is then multiplied by 1.03 to obtain the total uncertainty to be applied. At least three measured thimbles per core quadrant are also required.

COLR Cycle 19-1 Beaver Valley Unit 2 5.1 - 2 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: CFl: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 IiT reactor trip setpoint K1~1.239 Overtemperature Ii T reactor trip setpoint Tavg K2::::: 0.0183/°F coefficient Overtemperature Ii T reactor trip setpoint pressure K3::::: 0.001/psia coefficient Tavg at RATED THERMAL POWER 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.

COLR Cycle 19-1 Beaver Valley Unit 2 5.1 - 3 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 Value Overpower~ T reactor trip setpoint K4 s 1.094 Overpower""T reactor trip setpoint Tavg K5 ~ 0.02/°F for increasing rate/lag coefficient average temperature K5 = 0/°F for decreasing average temperature Overpower""T reactor trip setpoint Tavg K6 ~ 0.0021/°F for T > T" heatup coefficient K6 = 0/°F for T s T" Tavg at RATED THERMAL POWER T" s 574.2°F< 1>

Measured reactor vessel ""T lead/lag '!1 = O sec*

time constants '!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.

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

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report Measured reactor vessel ~T lag time -r3 ~ 6 secs constant Measured reactor vessel average -rs~ 2 secs temperature lag time constant Measured reactor vessel average *1 ~ 10 secs temperature rate/lag time constant 5.1.10 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>

5.1.11 LCO 3.9.1 Boron Concentration (MODE 6)

The boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained ~ 2400 ppm. This value includes a 50 ppm conservative allowance for uncertainties.

(1) The Reactor Coolant System (RCS) indicated Tavg value is determined by adding the appropriate allowances for rod control operation and verification via control board indication (3.6°F) to the cycle specific full power Tavg used in the core design.

(2) The pressurizer pressure value includes allowances for pressurizer pressure control operation and verification via control board indication.

(3) The RCS total flow rate includes allowances for normalization of the cold leg elbow taps with a beginning of cycle precision RCS flow calorimetric measurement and verification on a periodic basis via control board indication.

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

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.12 References

1. WCAP-9272-P-A, 'WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1985 (Westinghouse Proprietary).
2. WCAP-87 45-P-A, "Design Bases for the Thermal Overpower 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.

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

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

~

Q

~

~ 620--~~~-+-~~~--1--"",.__~~-+-~~~--+-~~~---1----~~---'\+-~~~--J 600 ACCEPTABLE OPERATION 0 0.2 0.4 0.6 0.8 1.2 1.4 FRACTION OF RA TED THERMAL POWER Figure5.1-1(Page1of1)

REACTOR CORE SAFETY LIMIT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1)

COLR Cycle 19 Beaver Valley Unit 2 5.1 - 7 LRM Revision 85

Licensing Requirements Manual Core Operating Limits Report 5.1 225 v~:53, ??5) J 1

/

c 200 175 v1 ~,

BANKCI I <100. 187) I

/

v

<tJ

'U

.L:

sen

+-' / /

v

,/

150 a.

Q)

--z

+-'

Cf)

/ V' v

125 0 /

I- I (o, 114>J /BANK ol, v

Cf) 0 100 a..

~

z

<(

ca 75 /

0 0 v

,/

c::::

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

Licensing Requirements Manual Core Operating Limits Report 5.1 1.2 Io.o, 1.00 I 16.0, 1.00 I I 1.0 I 12.0, 0.925 t 0.8

~ 0.6 0.4 0.2 0.0 0 2 4 6 8 10 12 Core Height (feet)

Figure 5.1-3 (Page 1of1)

FoT NORMALIZED OPERATING ENVELOPE, K(Z)

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

Licensing Requirements Manual Core Operating Limits Report 5.1 120 110 I ( 81 10 0) 1(+8, 10 0) I 100 I \

J 90 I UNACCEPTABLE OPERATION I /, \ I UNACCEPTABLE OPERATION I

80 f 'ACCEPTABLE' OPERATION \

0 ll..

70 I

)

' \

ns E I \

G>

.c 1- 60 J \,

'C G>

ns a::

0 50 I

I

\

'<ft. (-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 COLR Cycle 19 Beaver Valley Unit 2 5.1 - 10 LRM Revision 85

Licensing Requirements Manual Core Operating Limits Report 5.1

-29.00 CYCLB BURNOP MTC (MWD/MTU) (Pot/0 P) 14000 -29.41 18000 -31.39

~

rz:i H

u " "'

H 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 15000 16000 17000 18000 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 COLR Cycle 19 Beaver Valley Unit 2 5.1 - 11 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 3000 8000 12000 16000 Zone Point (feet) (MWD/MTU) (MWD/MTU) (MWD/MTU) (MWD/MTU) (MWD/MTU)

  • 1 12.1 1.0000 1.0000 1.0000 1.0000 1.0000
  • 2 11.9 1.0000 1.0000 1.0000 1.0000 1.0000
  • 3 11.7 1.0000 1.0000 1.0000 1.0000 1.0000
  • 4 11.5 1.0000 1.0000 1.0000 1.0000 1.0000
  • 5 11.3 1.0000 1.0000 1.0000 1.0000 1.0000
  • 6 11.1 1.0000 1.0000 1.0000 1.0000 1.0000
  • 7 10.9 1.0000 1.0000 1.0000 1.0000 1.0000 8 10.7 1.1656 1.2218 1.2278 1.2247 1.2293 9 10.5 1.1666 1.2140 1.2255 1.2214 1.2208 10 10.3 1.1660 1.2075 1.2236 1.2176 1.2084 11 10. 1 1.1636 1.1999 1.2208 1.2119 1.2024 12 9.9 1.1601 1.1905 1.2171 1.2054 1.1976 13 9.7 1.1564 1.1804 1.2130 1.2025 1.1907 14 9.5 1.1530 1.1694 1.2075 1.2005 1.1850 15 9.3 1.1505 1.1572 1.1998 1.2028 1.1868 16 9.1 1.1496 1.1470 1.1929 1.2060 1.1901 17 8.9 1.1515 1.1417 1.1897 1.2093 1.1904 18 8.7 1.1564 1.1413 1.1892 1.2153 1.1912 19 8.5 1.1635 1.1449 1.1905 1.2241 1.1939 20 8.3 1.1700 1.1495 1.1933 1.2307 1.1957 21 8.1 1.1745 1.1535 1.1964 1.2340 1.1972 22 7.9 1.1773 1.1558 1.1980 1.2353 1.2007 23 7.6 1.1784 1.1567 1.1979 1.2348 1.2046 24 7.4 1.1779 1.1562 1.1961 1.2323 1.2062 25 7.2 1.1759 1.1547 1.1928 1.2280 1.2056 26 7.0 1.1723 1.1524 1.1881 1.2219 1.2032 27 6.8 1.1672 1.1489 1.1821 1.2142 1.1995 28 6.6 1.1608 1.1440 1.1748 1.2051 1.1944 29 6.4 1.1531 1.1381 1.1659 1.1943 1.1878 30 6.2 1.1442 1.1310 1.1558 1.1817 1.1795 31 6.0 1.1340 1.1225 1.1447 1.1676 1.1698 32 5.8 1.1235 1.1140 1.1320 1.1526 1.1586 Note: Top and Bottom 10% Excluded COLR Cycle 19 Beaver Valley Unit 2 5.1 - 12 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 3000 8000 12000 16000 Zone Point (feet) (MWD/MTU) (MWD/MTU) (MWD/MTU) (MWD/MTU) (MWD/MTU) 33 5.6 1.1146 1.1069 1.1179 1.1378 1.1461 34 5.4 1.1115 1.1015 1.1073 1.1258 1.1371 35 5.2 1.1122 1.0984 1.1024 1.1176 1.1329 36 5.0 1.1150 1.0979 1.0988 1.1126 1.1283 37 4.8 1.1173 1.0991 1.0949 1.1093 1.1218 38 4.6 1.1192 1.1000 1.0908 1.1052 1.1149 39 4.4 1.1207 1.1005 1.0861 1.1004 1.1071 40 4.2 1.1216 1.1013 1.0804 1.0952 1.0979 41 4.0 1.1229 1.1030 1.0775 1.0899 1.0912 42 3.8 1.1251 1.1059 1.0782 1.0845 1.0895 43 3.6 1.1273 1.1091 1.0805 1.0790 1.0889 44 3.4 1.1290 1.1116 1.0818 1.0737 1.0871 45 3.2 1.1309 1.1134 1.0824 1.0718 1.0857 46 3.0 1.1358 1.1196 1.0849 1.0717 1.0854 47 2.8 1.1483 1.1393 1.0935 1.0818 1.0955 48 2.6 1.1670 1.1663 1.1078 1.0986 1.1127 49 2.4 1.1895 1.1920 1.1264 1.1143 1.1283 50 2.2 1.2131 1.2172 1.1463 1.1295 1.1433 51 2.0 1.2360 1.2427 1.1656 1.1450 1.1585 52 1.8 1.2581 1.2676 1.1842 1.1601 1.1734 53 1.6 1.2795 1.2914 1.2023 1.1747 1.1878 54 1.4 1.2995 1.3138 1.2196 1.1888 1.2019

  • 55 1.2 1.0000 1.0000 1.0000 1.0000 1.0000
  • 56 1.0 1.0000 1.0000 1.0000 1.0000 1.0000
  • 57 0.8 1.0000 1.0000 1.0000 1.0000 1.0000
  • 58 0.6 1.0000 1.0000 1.0000 1.0000 1.0000
  • 59 0.4 1.0000 1.0000 1.0000 1.0000 1.0000
  • 60 0.2 1.0000 1.0000 1.0000 1.0000 1.0000
  • 61 0.0 1.0000 1.0000 1.0000 1.0000 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 19 Beaver Valley Unit 2 5.1 - 13 LRM Revision 85

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

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

  • 1 12.1 1.0000
  • 2 11.9 1.0000
  • 3 11.7 1.0000
  • 4 11.5 1.0000
  • 5 11.3 1.0000
  • 6 11.1 1.0000
  • 7 10.9 1.0000 8 10.7 1.2426 9 10.5 1.2289 10 10.3 1.2147 11 10.1 1.1998 12 9.9 1.1837 13 9.7 1.1683 14 9.5 1.1541 15 9.3 1.1417 16 9.1 1.1311 17 8.9 1.1244 18 8.7 1.1221 19 8.5 1.1234 20 8.3 1.1248 21 8.1 1.1249 22 7.9 1.1242 23 7.6 1.1230 24 7.4 1.1208 25 7.2 1.1175 26 7.0 1.1133 27 6.8 1.1080 28 6.6 1.1020 29 6.4 1.0950 30 6.2 1.0875 31 6.0 1.0791 32 5.8 1.0704 Note: Top and Bottom 10% Excluded COLR Cycle 19 Beaver Valley Unit 2 5.1 - 14 LRM Revision 85

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

Fa Surveillance W(Z) Function at Initial Cycle Startup at 75% RTP Exclusion Zone Axial Point Elevation (feet) 75% RTP 33 5.6 1.0635 34 5.4 1.0623 35 5.2 1.0649 36 5.0 1.0696 37 4.8 1.0740 38 4.6 1.0781 39 4.4 1.0819 40 4.2 1.0852 41 4.0 1.0892 42 3.8 1.0941 43 3.6 1.0988 44 3.4 1.1025 45 3.2 1.1067 46 3.0 1.1147 47 2.8 1.1303 48 2.6 1.1518 49 2.4 1.1772 50 2.2 1.2037 51 2.0 1.2300 52 1.8 1.2555 53 1.6 1.2807 54 1.4 1.3045

  • 55 1.2 1.0000
  • 56 1.0 1.0000
  • 57 0.8 1.0000
  • 58 0.6 1.0000
  • 59 0.4 1.0000
  • 60 0.2 1.0000
  • 61 0.0 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 19 Beaver Valley Unit 2 5.1 - 15 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.

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

FENOC' ~

Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 RrstEnergy Nuclear Operating Company Marty L. Richey 724-682-5234 Site Vice President Fax: 724-643-8069 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 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).

COLR Cycle 24 Beaver Valley Unit 1 5.1 - 1 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) for P > 0.5 F (Z) s [CFQ]

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

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.

COLR Cycle 24-2 Beaver Valley Unit 1 5.1 - 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 K1::; 1.242 Overtemperature ~T reactor trip setpoint Tavg K2 ~ 0.0183/°F coefficient Overtemperature ~ T reactor trip setpoint pressure K3 ~ 0.001/psia coefficient Tavg at RATED THERMAL POWER 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.

COLR Cycle 24-2 Beaver Valley Unit 1 5.1 - 3 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 1.47% of its value at RATED THERMAL POWER.

b. Overpower AT Setpoint Parameter Values:

Parameter Value Overpower AT reactor trip setpoint K4::;; 1.08S Overpower AT reactor trip setpoint Tavg KS ~ 0.02/°F for increasing rate/lag coefficient average temperature KS = 0/°F for decreasing average temperature Overpower AT reactor trip setpoint Tavg K6 ~ 0.0021/°F for T > T" heatup coefficient K6 = 0/°F for T ::;; T" Tavg at RATED THERMAL POWER T"::;; S77.9°F<2 >

Measured reactor vessel average t3 ~ 10 secs temperature rate/lag time constant Measured reactor vessel AT lag time t4::;; 6 secs constant Measured reactor vessel average ts::;; 2 secs temperature lag time constant (2) T" represents the cycle-specific Full Power Tavg value used in core design.

COLR Cycle 24-1 Beaver Valley Unit 1 S.1 - 4 LRM Revision 90

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.10 LCO 3.4.1. RCS Pressure. Temperature. and Flow Departure from Nucleate Boiling CDNB) Limits Parameter Indicated Value Reactor Coolant System Tavg Tavg::;: 581.5°F< 1l Pressurizer Pressure Pressure ~ 2218 psia< 2l Reactor Coolant System Total Flow Rate Flow~ 267,300 gpm< 3l 5.1.11 LCO 3.9.1 Boron Concentration (MODE 6)

The boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained ~ 2400 ppm. This value includes a 50 ppm conservative allowance for uncertainties.

(1) The Reactor Coolant System (RCS) indicated Tavg value is determined by adding the appropriate allowances for rod control operation and verification via control board indication (3.6°F) to the cycle specific full power Tavg used in the core design.

(2) The pressurizer pressure value includes allowances for pressurizer pressure control operation and verification via control board indication.

(3) The RCS total flow rate includes allowances for normalization of the cold leg elbow taps with a beginning of cycle precision RCS flow calorimetric measurement and verification on a periodic basis via control board indication.

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

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.12 References

1. WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 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 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.

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.

COLR Cycle 24 Beaver Valley Unit 1 5.1 - 6 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 ACCEPTABLE OPERATION 0 0.2 0.4 0.6 0.8 1.2 1.4 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)

COLR Cycle 24 Beaver Valley Unit 1 5.1 - 7 LRM Revision 89

Licensing Requirements Manual Core Operating Limits Report 5.1

/

v 54.53, 225 I

/

/

200 /

/

/

v

/

/ I I BANKC I

I loo, 187

,,1/

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/ I 0 20 40 60 80 100 Relative Power (Percent)

Figure 5.1-2 (Page 1 of 1)

CONTROL ROD INSERTION LIMITS COLR Cycle 24 Beaver Valley Unit 1 5.1 - 8 LRM Revision 89

Licensing Requirements Manual Core Operating Limits Report 5.1 1.2 Io.o, 1.00 I 16.0, 1.00 I 1.0 I 12.0, 0.925 t 0.8

§ 0.6 0.4 0.2 0.0 0 2 4 6 8 10 12 Core Height (feet)

Figure 5.1-3 (Page 1 of 1)

FaT NORMALIZED OPERATING ENVELOPE, K(Z)

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

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

\

J 90 I

UN AC CE PT ABLE I /, I UNACCEPTABLE I QJ OPERATION f rccEPTABLEI

\ OPERATION

s:

0 p_, 80 OPERATION \

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I J

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

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 COLR Cycle 24 Beaver Valley Unit 1 5.1 - 10 LRM Revision 89

Licensing Requirements Manual Core Operating Limits Report 5.1

-28.00 ii.

0 8

u

.34 -29.00 E-<

z i:Ll H

u H

µ,.

µ,. -30.00 i:Ll 0

u --............_

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-33.00

-34.00 13000 14000 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 COLR Cycle 24 Beaver Valley Unit 1 5.1 - 11 LRM Revision 89

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

Fa Surveillance W(Z) Function versus Burnup at 100% RTP Exclusion Axial Elevation 150 3000 10000 18000 Zone Point (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU

  • 1 12.08 1.0000 1.0000 1.0000 1.0000
  • 2 11.88 1.0000 1.0000 1.0000 1.0000
  • 3 11.68 1.0000 1.0000 1.0000 1.0000
  • 4 11.47 1.0000 1.0000 1.0000 1.0000
  • 5 11.27 1.0000 1.0000 1.0000 1.0000
  • 6 11.07 1.0000 1.0000 1.0000 1.0000
  • 7 10.87 1.0000 1.0000 1.0000 1.0000 8 10.67 1.1358 1.1361 1.2445 1.2326 9 10.47 1.1294 1.1320 1.2372 1.2152 10 10.27 1.1223 1.1291 1.2289 1.1939 11 10.07 1.1151 1.1248 1.2199 1.1758 12 9.86 1.1058 1.1197 1.2095 1.1743 13 9.66 1.1023 1.1138 1.2008 1.1775 14 9.46 1.1055 1.1092 1.1950 1.1804 15 9.26 1.1061 1.1084 1.1897 1.1817 16 9.06 1.1071 1.1084 1.1881 1.1862 17 8.86 1.1154 1.1157 1.1930 1.1898 18 8.66 1.1271 1.1267 1.2046 1.1954 19 8.46 1.1356 1.1347 1.2137 1.2067 20 8.25 1.1427 1.1413 1.2207 1.2184 21 8.05 1.1481 1.1462 1.2253 1.2276 22 7.85 1.1518 1.1494 1.2275 1.2341 23 7.65 1.1538 1.1508 1.2273 1.2379 24 7.45 1.1542 1.1506 1.2248 1.2392 25 7.25 1.1534 1.1493 1.2201 1.2382 26 7.05 1.1523 1.1476 1.2145 1.2350 27 6.84 1.1505 1.1453 1.2080 1.2306 28 6.64 1.1475 1.1417 1.2003 1.2254 29 6.44 1.1436 1.1372 1.1910 1.2187 30 6.24 1.1386 1.1316 1.1801 1.2101 31 6.04 1.1324 1.1251 1.1681 1.1998 32 5.84 1.1265 1.1176 1.1544 1.1879 Note: Top and Bottom 10% Excluded COLR Cycle 24 Beaver Valley Unit 1 5.1 - 12 LRM Revision 89

Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-1(Page2of2)

Fa Surveillance W(Z) Function versus Burn up at 100% RTP Exclusion Axial Elevation 150 3000 10000 18000 Zone Point (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 33 5.64 1.1230 1.1120 1.1402 1.1742 34 5.44 1.1229 1.1122 1.1285 1.1599 35 5.23 1.1255 1.1154 1.1185 1.1522 36 5.03 1.1309 1.1192 1.1119 1.1473 37 4.83 1.1370 1.1222 1.1073 1.1414 38 4.63 1.1422 1.1247 1.1021 1.1345 39 4.43 1.1469 1.1268 1.0978 1.1267 40 4.23 1.1511 1.1285 1.0934 1.1180 41 4.03 1.1547 1.1298 1.0878 1.1088 42 3.83 1.1577 1.1309 1.0840 1.0989 43 3.62 1.1604 1.1317 1.0840 1.0887 44 3.42 1.1629 1.1327 1.0844 1.0810 45 3.22 1.1633 1.1376 1.0843 1.0738 46 3.02 1.1693 1.1532 1.0851 1.0750 47 2.82 1.1856 1.1788 1.0900 1.0870 48 2.62 1.2048 1.2044 1.0989 1.0977 49 2.42 1.2240 1.2304 1.1137 1.1088 50 2.21 1.2450 1.2568 1.1302 1.1205 51 2.01 1.2672 1.2827 1.1459 1.1331 52 1.81 1.2886 1.3080 1.1616 1.1470 53 1.61 1.3090 1.3322 1.1767 1.1603 54 1.41 1.3278 1.3543 1.1907 1.1730

  • 55 1.21 1.0000 1.0000 1.0000 1.0000
  • 56 1.01 1.0000 1.0000 1.0000 1.0000
  • 57 0.81 1.0000 1.0000 1.0000 1.0000
  • 58 0.60 1.0000 1.0000 1.0000 1.0000
  • 59 0.40 1.0000 1.0000 1.0000 1.0000
  • 60 0.20 1.0000 1.0000 1.0000 1.0000
  • 61 0.00 1.0000 1.0000 1.0000 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 24 Beaver Valley Unit 1 5.1 - 13 LRM Revision 89

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

Fa Surveillance W(Z) Function versus Burnup at 75% RTP Exclusion Axial Elevation 75% RTP Zone Point (feet)

  • 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 1.2023 9 10.47 1.1828 10 10.27 1.1630 11 10.07 1.1437 12 9.86 1.1213 13 9.66 1.1052 14 9.46 1.0972 15 9.26 1.0876 16 9.06 1.0792 17 8.86 1.0792 18 8.66 1.0834 19 8.46 1.0861 20 8.25 1.0885 21 8.05 1.0897 22 7.85 1.0899 23 7.65 1.0903 24 7.45 1.0904 25 7.25 1.0899 26 7.05 1.0895 27 6.84 1.0891 28 6.64 1.0877 29 6.44 1.0855 30 6.24 1.0826 31 6.04 1.0786 32 5.84 1.0750 Note: Top and Bottom 10% Excluded COLR Cycle 24 Beaver Valley Unit 1 5.1 - 14 LRM Revision 89

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

F0 Surveillance W(Z) Function versus Burnup at 75% RTP Exclusion Axial Elevation 75% RTP Zone Point (feet) 33 5.64 1.0736 34 5.44 1.0753 35 5.23 1.0799 36 5.03 1.0875 37 4.83 1.0963 38 4.63 1.1045 39 4.43 1.1123 40 4.23 1.1197 41 4.03 1.1268 42 3.83 1.1332 43 3.62 1.1399 44 3.42 1.1465 45 3.22 1.1509 46 3.02 1.1607 47 2.82 1.1806 48 2.62 1.2028 49 2.42 1.2251 50 2.21 1.2495 51 2.01 1.2754 52 1.81 1.3008 53 1.61 1.3253 54 1.41 1.3482

  • 55 1.21 1.0000
  • 56 1.01 1.0000
  • 57 0.81 1.0000
  • 58 0.60 1.0000
  • 59 0.40 1.0000
  • 60 0.20 1.0000
  • 61 0.00 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 24 Beaver Valley Unit 1 5.1 - 15 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.

COLR Cycle 24 Beaver Valley Unit 1 5.1 - 16 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).

COLR Cycle 19 Beaver Valley Unit 2 5.1 - 1 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) for P:,; 0.5 Q 0.5 THERMAL POWER Where: CFQ = 2.40 p = RATED THERMAL POWER K(Z) =the function obtained from Figure 5.1-3.

Fg(Z) = F~(Z) *1.0815$

F~ (Z) = Fg(Z)

  • W(Z)

(2) As indicated by the group demand counter

$ An additional uncertainty is to be applied if the number of measured thimbles for the moveable incore detector system is less than 75% of the total number of thimbles. If there are less than 75% of the total number of thimbles and at least 50% of the total number of thimbles measured, an additional uncertainty of (0.01)*(3-T/12.5) is added to the measurement uncertainty, 1.05, where T is the total number of measured thimbles. This adjusted measurement uncertainty is then multiplied by 1.03 to obtain the total uncertainty to be applied. At least three measured thimbles per core quadrant are also required.

COLR Cycle 19-1 Beaver Valley Unit 2 5.1 - 2 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: CFl: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 IiT reactor trip setpoint K1~1.239 Overtemperature Ii T reactor trip setpoint Tavg K2::::: 0.0183/°F coefficient Overtemperature Ii T reactor trip setpoint pressure K3::::: 0.001/psia coefficient Tavg at RATED THERMAL POWER 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.

COLR Cycle 19-1 Beaver Valley Unit 2 5.1 - 3 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 Value Overpower~ T reactor trip setpoint K4 s 1.094 Overpower""T reactor trip setpoint Tavg K5 ~ 0.02/°F for increasing rate/lag coefficient average temperature K5 = 0/°F for decreasing average temperature Overpower""T reactor trip setpoint Tavg K6 ~ 0.0021/°F for T > T" heatup coefficient K6 = 0/°F for T s T" Tavg at RATED THERMAL POWER T" s 574.2°F< 1>

Measured reactor vessel ""T lead/lag '!1 = O sec*

time constants '!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.

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

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report Measured reactor vessel ~T lag time -r3 ~ 6 secs constant Measured reactor vessel average -rs~ 2 secs temperature lag time constant Measured reactor vessel average *1 ~ 10 secs temperature rate/lag time constant 5.1.10 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>

5.1.11 LCO 3.9.1 Boron Concentration (MODE 6)

The boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained ~ 2400 ppm. This value includes a 50 ppm conservative allowance for uncertainties.

(1) The Reactor Coolant System (RCS) indicated Tavg value is determined by adding the appropriate allowances for rod control operation and verification via control board indication (3.6°F) to the cycle specific full power Tavg used in the core design.

(2) The pressurizer pressure value includes allowances for pressurizer pressure control operation and verification via control board indication.

(3) The RCS total flow rate includes allowances for normalization of the cold leg elbow taps with a beginning of cycle precision RCS flow calorimetric measurement and verification on a periodic basis via control board indication.

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

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.12 References

1. WCAP-9272-P-A, 'WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1985 (Westinghouse Proprietary).
2. WCAP-87 45-P-A, "Design Bases for the Thermal Overpower 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.

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

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

~

Q

~

~ 620--~~~-+-~~~--1--"",.__~~-+-~~~--+-~~~---1----~~---'\+-~~~--J 600 ACCEPTABLE OPERATION 0 0.2 0.4 0.6 0.8 1.2 1.4 FRACTION OF RA TED THERMAL POWER Figure5.1-1(Page1of1)

REACTOR CORE SAFETY LIMIT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1)

COLR Cycle 19 Beaver Valley Unit 2 5.1 - 7 LRM Revision 85

Licensing Requirements Manual Core Operating Limits Report 5.1 225 v~:53, ??5) J 1

/

c 200 175 v1 ~,

BANKCI I <100. 187) I

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0 0 10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 5.1-2 (Page 1 of 1)

CONTROL ROD INSERTION LIMITS AS A FUNCTION OF RATED POWER LEVEL COLR Cycle 19 Beaver Valley Unit 2 5.1 - 8 LRM Revision 85

Licensing Requirements Manual Core Operating Limits Report 5.1 1.2 Io.o, 1.00 I 16.0, 1.00 I I 1.0 I 12.0, 0.925 t 0.8

~ 0.6 0.4 0.2 0.0 0 2 4 6 8 10 12 Core Height (feet)

Figure 5.1-3 (Page 1of1)

FoT NORMALIZED OPERATING ENVELOPE, K(Z)

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

Licensing Requirements Manual Core Operating Limits Report 5.1 120 110 I ( 81 10 0) 1(+8, 10 0) I 100 I \

J 90 I UNACCEPTABLE OPERATION I /, \ I UNACCEPTABLE OPERATION I

80 f 'ACCEPTABLE' OPERATION \

0 ll..

70 I

)

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ns E I \

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-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 COLR Cycle 19 Beaver Valley Unit 2 5.1 - 10 LRM Revision 85

Licensing Requirements Manual Core Operating Limits Report 5.1

-29.00 CYCLB BURNOP MTC (MWD/MTU) (Pot/0 P) 14000 -29.41 18000 -31.39

~

rz:i H

u " "'

H 1%1 -30.00 1%1 rz:i 0

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~

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-32.00 14000 15000 16000 17000 18000 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 COLR Cycle 19 Beaver Valley Unit 2 5.1 - 11 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 3000 8000 12000 16000 Zone Point (feet) (MWD/MTU) (MWD/MTU) (MWD/MTU) (MWD/MTU) (MWD/MTU)

  • 1 12.1 1.0000 1.0000 1.0000 1.0000 1.0000
  • 2 11.9 1.0000 1.0000 1.0000 1.0000 1.0000
  • 3 11.7 1.0000 1.0000 1.0000 1.0000 1.0000
  • 4 11.5 1.0000 1.0000 1.0000 1.0000 1.0000
  • 5 11.3 1.0000 1.0000 1.0000 1.0000 1.0000
  • 6 11.1 1.0000 1.0000 1.0000 1.0000 1.0000
  • 7 10.9 1.0000 1.0000 1.0000 1.0000 1.0000 8 10.7 1.1656 1.2218 1.2278 1.2247 1.2293 9 10.5 1.1666 1.2140 1.2255 1.2214 1.2208 10 10.3 1.1660 1.2075 1.2236 1.2176 1.2084 11 10. 1 1.1636 1.1999 1.2208 1.2119 1.2024 12 9.9 1.1601 1.1905 1.2171 1.2054 1.1976 13 9.7 1.1564 1.1804 1.2130 1.2025 1.1907 14 9.5 1.1530 1.1694 1.2075 1.2005 1.1850 15 9.3 1.1505 1.1572 1.1998 1.2028 1.1868 16 9.1 1.1496 1.1470 1.1929 1.2060 1.1901 17 8.9 1.1515 1.1417 1.1897 1.2093 1.1904 18 8.7 1.1564 1.1413 1.1892 1.2153 1.1912 19 8.5 1.1635 1.1449 1.1905 1.2241 1.1939 20 8.3 1.1700 1.1495 1.1933 1.2307 1.1957 21 8.1 1.1745 1.1535 1.1964 1.2340 1.1972 22 7.9 1.1773 1.1558 1.1980 1.2353 1.2007 23 7.6 1.1784 1.1567 1.1979 1.2348 1.2046 24 7.4 1.1779 1.1562 1.1961 1.2323 1.2062 25 7.2 1.1759 1.1547 1.1928 1.2280 1.2056 26 7.0 1.1723 1.1524 1.1881 1.2219 1.2032 27 6.8 1.1672 1.1489 1.1821 1.2142 1.1995 28 6.6 1.1608 1.1440 1.1748 1.2051 1.1944 29 6.4 1.1531 1.1381 1.1659 1.1943 1.1878 30 6.2 1.1442 1.1310 1.1558 1.1817 1.1795 31 6.0 1.1340 1.1225 1.1447 1.1676 1.1698 32 5.8 1.1235 1.1140 1.1320 1.1526 1.1586 Note: Top and Bottom 10% Excluded COLR Cycle 19 Beaver Valley Unit 2 5.1 - 12 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 3000 8000 12000 16000 Zone Point (feet) (MWD/MTU) (MWD/MTU) (MWD/MTU) (MWD/MTU) (MWD/MTU) 33 5.6 1.1146 1.1069 1.1179 1.1378 1.1461 34 5.4 1.1115 1.1015 1.1073 1.1258 1.1371 35 5.2 1.1122 1.0984 1.1024 1.1176 1.1329 36 5.0 1.1150 1.0979 1.0988 1.1126 1.1283 37 4.8 1.1173 1.0991 1.0949 1.1093 1.1218 38 4.6 1.1192 1.1000 1.0908 1.1052 1.1149 39 4.4 1.1207 1.1005 1.0861 1.1004 1.1071 40 4.2 1.1216 1.1013 1.0804 1.0952 1.0979 41 4.0 1.1229 1.1030 1.0775 1.0899 1.0912 42 3.8 1.1251 1.1059 1.0782 1.0845 1.0895 43 3.6 1.1273 1.1091 1.0805 1.0790 1.0889 44 3.4 1.1290 1.1116 1.0818 1.0737 1.0871 45 3.2 1.1309 1.1134 1.0824 1.0718 1.0857 46 3.0 1.1358 1.1196 1.0849 1.0717 1.0854 47 2.8 1.1483 1.1393 1.0935 1.0818 1.0955 48 2.6 1.1670 1.1663 1.1078 1.0986 1.1127 49 2.4 1.1895 1.1920 1.1264 1.1143 1.1283 50 2.2 1.2131 1.2172 1.1463 1.1295 1.1433 51 2.0 1.2360 1.2427 1.1656 1.1450 1.1585 52 1.8 1.2581 1.2676 1.1842 1.1601 1.1734 53 1.6 1.2795 1.2914 1.2023 1.1747 1.1878 54 1.4 1.2995 1.3138 1.2196 1.1888 1.2019

  • 55 1.2 1.0000 1.0000 1.0000 1.0000 1.0000
  • 56 1.0 1.0000 1.0000 1.0000 1.0000 1.0000
  • 57 0.8 1.0000 1.0000 1.0000 1.0000 1.0000
  • 58 0.6 1.0000 1.0000 1.0000 1.0000 1.0000
  • 59 0.4 1.0000 1.0000 1.0000 1.0000 1.0000
  • 60 0.2 1.0000 1.0000 1.0000 1.0000 1.0000
  • 61 0.0 1.0000 1.0000 1.0000 1.0000 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 19 Beaver Valley Unit 2 5.1 - 13 LRM Revision 85

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

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

  • 1 12.1 1.0000
  • 2 11.9 1.0000
  • 3 11.7 1.0000
  • 4 11.5 1.0000
  • 5 11.3 1.0000
  • 6 11.1 1.0000
  • 7 10.9 1.0000 8 10.7 1.2426 9 10.5 1.2289 10 10.3 1.2147 11 10.1 1.1998 12 9.9 1.1837 13 9.7 1.1683 14 9.5 1.1541 15 9.3 1.1417 16 9.1 1.1311 17 8.9 1.1244 18 8.7 1.1221 19 8.5 1.1234 20 8.3 1.1248 21 8.1 1.1249 22 7.9 1.1242 23 7.6 1.1230 24 7.4 1.1208 25 7.2 1.1175 26 7.0 1.1133 27 6.8 1.1080 28 6.6 1.1020 29 6.4 1.0950 30 6.2 1.0875 31 6.0 1.0791 32 5.8 1.0704 Note: Top and Bottom 10% Excluded COLR Cycle 19 Beaver Valley Unit 2 5.1 - 14 LRM Revision 85

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

Fa Surveillance W(Z) Function at Initial Cycle Startup at 75% RTP Exclusion Zone Axial Point Elevation (feet) 75% RTP 33 5.6 1.0635 34 5.4 1.0623 35 5.2 1.0649 36 5.0 1.0696 37 4.8 1.0740 38 4.6 1.0781 39 4.4 1.0819 40 4.2 1.0852 41 4.0 1.0892 42 3.8 1.0941 43 3.6 1.0988 44 3.4 1.1025 45 3.2 1.1067 46 3.0 1.1147 47 2.8 1.1303 48 2.6 1.1518 49 2.4 1.1772 50 2.2 1.2037 51 2.0 1.2300 52 1.8 1.2555 53 1.6 1.2807 54 1.4 1.3045

  • 55 1.2 1.0000
  • 56 1.0 1.0000
  • 57 0.8 1.0000
  • 58 0.6 1.0000
  • 59 0.4 1.0000
  • 60 0.2 1.0000
  • 61 0.0 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 19 Beaver Valley Unit 2 5.1 - 15 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.

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

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