L-14-389, Submittal of Core Operating Limits Report

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Submittal of Core Operating Limits Report
ML14345A674
Person / Time
Site: Beaver Valley
Issue date: 12/11/2014
From: Emily Larson
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-14-389
Download: ML14345A674 (31)
v • d • e


Text

FENOC' Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 FirstEnergy Nuclear Operating Company Eric A. Larson 724-682-5234 Site Vice President Fax: 724-643-8069 December 11, 2014 L-14-389 ATTN: 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 Unit Nos. 1 and 2 Core Operating Limits Report 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 (FENOC) hereby submits the BVPS-1 COLR for Cycle 23 and the BVPS-2 COLR for Cycle 18. The COLRs have been revised to implement license amendments 291 (BVPS-1) and 178 (BVPS-2) that allow the normally required near end-of-life moderator temperature coefficient measurement to not be performed under certain conditions. Technical Specification 5.6.3.d requires, in part, that the COLR be provided to the Nuclear Regulatory Commission (NRC) upon issuance for any midcycle revisions or supplements. The COLRs were effective November 14, 2014.

There are no regulatory commitments established 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, r0t~

Eric A Larson

Enclosures:

A Beaver Valley Power Station, Unit No. 1, Core Operating Limits Report, Cycle 23 B. Beaver Valley Power Station, Unit No. 2, Core Operating Limits Report, Cycle 18 cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative

Enclosure A L-14-389 Beaver Valley Power Station, Unit No. 1 Core Operating Limits Report, Cycle 23 (14 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 2 1. 77% L\k/k. <1>
b. Prior to manually blocking the Low Pressurizer Pressure Safety Injection Signal, the Reactor Coolant System shall be borated to 2 the MODE 5 boron concentration and shall remain 2 this boron concentration at all times when this signal is blocked.
c. In MODE 5, SHUTDOWN MARGIN shall be 2 1.0% L\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 - 4.4 x 10-4 -1k/k/°F at RATED THERMAL POWER.
c. 300 ppm Surveillance Limit: (- 37 pcm/°F)
d. The revised predicted near-EOL 300 ppm MTC shall be calculated using Figure 5.1-5 and the following algorithm from Reference 11 :

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

where,

  • Predicted MTC is calculated from Figure 5.1-5 at the burnup corresponding to the measurement of 300 ppm at RTP conditions,
    • AFD Correction is the more negative value of :

{O pcm/°F or (MFD

  • AFD Sensitivity)}

where: MFD 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 2 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 23-1 Beaver Valley Unit 1 5.1 - 1 LRM Revision 86

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 (Fo(Z))

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

Fo(Z) ~. [ c:oJ

  • K(Z) for P > 0.5 F (Z)

Q

~ [CFQ]*K(Z) 0.5 for P ~ 0.5 THERMAL POWER Where: CFQ =2.40 p = RATED THERMAL POWER K(Z) =the function obtained from Figure 5.1-3.

F;f (Z) = F5 (Z)

  • W(Z)

(2) As indicated by the group demand counter COLR Cycle 23-1 Beaver Valley Unit 1 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 Table 5.1-1. The W(Z) values are generated assuming that they will be used for a full power surveillance. 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 :s; 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 Fo(Z) penalty function, applied when the analytic Fo(Z) function increases from one monthly measurement to the next, is provided in Table 5.1-2.

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

F~H .::: CFAH * (1 + PFAH (1-P))

Where: CFAH = 1.62 PFAH = 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 /1 T Parameter Values from Table Notations 1 and 2

a. Overtemperature /1 T Setpoint Parameter Values:

Parameter Value Overtemperature /1 T reactor trip setpoint K1 ~ 1.242 Overtemperature /1 T reactor trip setpoint Tavg K2 ~ 0.0183/°F coefficient Overtemperature 11T reactor trip setpoint pressure K3 ~ 0.001/psia coefficient Tavg at RATED THERMAL POWER T' ~ 577.9°F( 1l Nominal pressurizer pressure P' ~ 2250 psia Measured reactor vessel average temperature lead/lag 11 ~ 30 secs time constants 12 ~ 4 secs Measured reactor vessel /1 T lag time constant 14 ~ 6 secs (1) T' represents the cycle-specific Full Power Tavg value used in core design.

COLR Cycle 23-1 Beaver Valley Unit 1 5.1 - 3 LRM Revision 86

Licensing Requirements Manual Core Operating Limits Report S.1 S.1 Core Operating Limits Report Measured reactor vessel average temperature lag -rs:::;; 2 secs time constant f (~I) is a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:

(i) For qt - qb between -37% and +1 S%, f(~I) = 0 (where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qi+ 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.S2% of its value at RATED THERMAL POWER.

(iii) For each percent that the magnitude of (qt - qb) exceeds +1S%, the ~T trip setpoint shall be automatically reduced by 1.47% of its value at RA TED THERMAL POWER.

b. Overpower~T Setpoint Parameter Values:

Parameter Overpower ~ T reactor trip setpoint K4:::;; 1.08S Overpower~T reactor trip setpoint Tavg KS~ 0.02/°F for increasing rate/lag coefficient average temperature

=

KS 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 :::;; T" Tavg at RATED THERMAL POWER T":::;; S77.9°F<2l Measured reactor vessel average -rs~ 10 secs temperature rate/lag time constant Measured reactor vessel ~T lag time 't4:::;; 6 secs constant Measured reactor vessel average -rs:::;; 2 secs temperature lag time constant (2) T" represents the cycle-specific Full Power Tavg value used in core design.

COLR Cycle 23-1 Beaver Valley Unit 1 S.1 - 4 LRM Revision 86

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.10 LCO 3.4.1, RCS Pressure. Temperature. and Flow Departure from Nucleate Boiling (DNB) Limits Parameter Indicated Value Reactor Coolant System Tavg Tavg:;:; 581.5°F<1l Pressurizer Pressure Pressure~ 2218 psia<2>

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 23-1 Beaver Valley Unit 1 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 19S5 (Westinghouse Proprietary).
2. WCAP-S745-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, "Qualification of the NEXUS Nuclear Data Methodology," November 2005.

COLR Cycle 23-1 Beaver Valley Unit 1 5.1 - 6 LRM Revision S6

Licensing Requirements Manual Core Operating Limits Report 5.1 UNACCEPTABLE OPERATION 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(Page1of1)

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

COLR Cycle 23-1 Beaver Valley Unit 1 5.1 - 7 LRM Revision 86

Licensing Requirements Manual Core Operating Limits Report 5.1 7 I I I v 54.53, 225 1

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v 200

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CONTROL ROD INSERTION LIMITS COLR Cycle 23-1 Beaver Valley Unit 1 5.1 - 8 LRM Revision 86

Licensing Requirements Manual Core Operating Limits Report 5.1 1.2 Io.o, 1.00 I 16.0, 1.00 I 1.0 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)

Fo T NORMALIZED OPERA Tl NG ENVELOPE, K(Z)

COLR Cycle 23-1 Beaver Valley Unit 1 5.1 - 9 LRM Revision 86

Licensing Requirements Manual Core Operating Limits Report 5.1 120 110 8 10 0) +8 10 0)

I ( - I I ( I I 100

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J 90 I UNACCEPTABLE I I UNACCEPTABLE H

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o\O I (-2 5, 5 0) I( +2 2, 5 0) 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 RATED THERMAL POWER FOR RAOC COLR Cycle 23-1 Beaver Valley Unit 1 5.1 - 10 LRM Revision 86

Licensing Requirements Manual Core Operating Limits Report 5.1

-28.00 i:z...

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HOT FULL POWER PREDICTED MODERATOR TEMPERATURE COEFFICIENT AS A FUNCTION OF CYCLE BURNUP WHEN 300 PPM IS ACHIEVED COLR Cycle 23-1 Beaver Valley Unit 1 5.1 - 11 LRM Revision 86

Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-1(Page1of2)

F0 Surveillance W(Z) Function versus Burnup 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 1.1709 1.1930 1.2357 1.2060 9 10.47 1.1645 1.1882 1.2302 1.2013 10 10.27 1.1572 1.1825 1.2248 1.1960 11 10.06 1.1490 1.1756 1.2179 1.1903 12 9.86 1.1428 1.1687 1.2096 1.1841 13 9.66 1.1388 1.1670 1.2005 1.1768 14 9.46 1.1353 1.1675 1.1903 1.1708 15 9.26 1.1304 1.1633 1.1797 1.1696 16 9.06 1.1234 1.1614 1.1771 1.1743 17 8.86 1.1240 1.1660 1.1816 1.1772 18 8.66 1.1298 1.1763 1.1919 1.1822 19 8.45 1.1348 1.1828 1.1986 1.1942 20 8.25 1.1420 1.1875 1.2035 1.2038 21 8.05 1.1476 1.1901 1.2063 1.2109 22 7.85 1.1511 1.1906 1.2069 1.2158 23 7.65 1.1531 1.1890 1.2053 1.2182 24 7.45 1.1534 1.1855 1.2018 1.2182 25 7.25 1.1525 1.1803 1.1964 1.2162 26 7.05 1.1512 1.1737 1.1902 1.2122 27 6.84 1.1492 1.1658 1.1833 1.2072 28 6.64 1.1460 1.1568 1.1754 1.2016 29 6.44 1.1417 1.1467 1.1662 1.1946 30 6.24 1.1364 1.1356 1.1557 1.1859 31 6.04 1.1303 1.1232 1.1443 1.1758 32 5.84 1.1229 1.1110 1.1315 1.1640 Note: Top and Bottom 10% Excluded COLR Cycle 23 Beaver Valley Unit 1 5.1 - 12 LRM Revision 82

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

Fa Surveillance W(Z) Function versus Burnup Exclusion Axial Elevation 150 3000 10000 18000 Zone Point (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 33 5.64 1.1153 1.1026 1.1190 1.1515 34 5.44 1.1107 1.1012 1.1106 1.1418 35 5.23 1.1085 1.1008 1.1027 1.1367 36 5.03 1.1095 1.1006 1.0980 1.1330 37 4.83 1.1122 1.1007 1.0961 1.1283 38 4.63 1.1145 1.1012 1.0935 1.1227 39 4.43 1.1187 1.1024 1.0906 1.1165 40 4.23 1.1229 1.1034 1.0873 1.1094 41 4.03 1.1265 1.1039 1.0839 1.1022 42 3.83 1.1298 1.1047 1.0819 1.0956 43 3.62 1.1327 1.1066 1.0816 1.0901 44 3.42 1.1354 1.1091 1.0813 1.0853 45 3.22 1.1372 1.1127 1.0812 1.0799 46 3.02 1.1410 1.1210 1.0826 1.0812 47 2.82 1.1529 1.1354 1.0906 1.0920 48 2.62 1.1753 1.1527 1.1050 1.1045 49 2.42 1.1985 1.1747 1.1200 1.1191 50 2.21 1.2213 1.1982 1.1350 1.1344 51 2.01 1.2441 1.2211 1.1500 1.1491 52 1.81 1.2662 1.2436 1.1646 1.1636 53 1.61 1.2872 1.2652 1.1788 1.1776 54 1.41 1.3065 1.2850 1.1918 1.1909

  • 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 23 Beaver Valley Unit 1 5.1 - 13 LRM Revision 82

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

F0 (Z) Penalty Factor versus Burnup Cycle Burnup (MWD/MTU) F0 (Z) Penalty Factor Oto 1600 1.0425

> 1600 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 F0 (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 F0 (Z) was determined.

COLR Cycle 23 Beaver Valley Unit 1 5.1 - 14 LRM Revision 82

Enclosure 8 L-14-389 Beaver Valley Power Station, Unit No. 2 Core Operating Limits Report, Cycle 18 (14 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 l
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 1o*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 1O :

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

where,

  • Predicted MTC is calculated from Figure 5.1-5 at the burnup corresponding to the measurement of 300 ppm at RTP conditions,
    • AFD Correction is the more negative value of :

{O pcm/°F or (MFD

  • AFD Sensitivity)}

where: MFD 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 keff:::: 1.0 SOM requirements are included to address SOM requirements (e.g., MODE 1 Required Actions to verify SOM) that are not within the applicability of LCO 3.1.1, SHUTDOWN MARGIN (SOM).

COLR Cycle 18-1 Beaver Valley Unit 2 5.1 - 1 LRM Revision 82

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:

Fa(Z)::; [c:o}K(Z) for P > 0.5 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'g (Z) = Fg (Z)
  • W(Z)

(2) As indicated by the group demand counter COLR Cycle 18-1 Beaver Valley Unit 2 5.1 - 2 LRM Revision 82

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report W(Z) values are provided in Table 5.1-1. The W(Z) values are generated assuming that they will be used for a full power surveillance. When a part power surveillance is performed, the W(Z) values should be multiplied by the factor 1/P, when P > 0.5. When P is s 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 Fo(Z) limit at part power conditions.

The Fo(Z) penalty function, applied when the analytic Fo(Z) function increases from one monthly measurement to the next, is provided in Table 5.1-2.

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

F~H s;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 11T Parameter Values from Table Notations 3 and 4

a. Overtemperature 11T Setpoint Parameter Values:

Parameter Overtemperature 11 T reactor trip setpoint K1s1.239 Overtemperature 11T reactor trip setpoint Tavg K2 2:: 0.0183/°F coefficient Overtemperature 11T reactor trip setpoint pressure K3 2:: 0.001/psia coefficient Tavg at RATED THERMAL POWER T's 574.2°F(1)

Nominal pressurizer pressure P' 2:: 2250 psia Measured reactor vessel 11T lead/lag time constants *1 = O sec*

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

12 O sec*

value of zero.)

Measured reactor vessel 11T lag time constant 13 s 6 secs (1) T' represents the cycle-specific Full Power Tavg value used in core design.

COLR Cycle 18-1 Beaver Valley Unit 2 5.1 - 3 LRM Revision 82

Licensing Requirements Manual Core Operating Limits Report 5.1 S.1 Core Operating Limits Report 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 +1S%, 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 RA TED THERMAL POWER.

(ii) For each percent that the magnitude of (qt - qb) exceeds -37%, the ~T trip setpoint shall be automatically reduced by 2.S2% 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 K4s1.094 Overpower~ T reactor trip setpoint Tavg KS~ 0.02/°F for increasing rate/lag coefficient average temperature KS = 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 S74.2°F<1>

Measured reactor vessel ~T lead/lag t1 =O sec*

time constants t2 =O sec*

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

Measured reactor vessel ~T lag time 't3 s 6 secs constant Measured reactor vessel average *es 2 secs temperature lag time constant Measured reactor vessel average *? ~ 10 secs temperature rate/lag time constant (1) T" represents the cycle-specific Full Power Tavg value used in core design.

COLR Cycle 18-1 Beaver Valley Unit 2 S.1 - 4 LRM Revision 82

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.10 LCO 3.4.1. RCS Pressure. Temperature. and Flow Departure from Nucleate Boiling (DNB) Limits Parameter Indicated Value Reactor Coolant System Tavg Tavg ::;; 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 18-1 Beaver Valley Unit 2 5.1 - 5 LRM Revision 82

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 LiT and Thermal Overtemperature LiT 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-SOP, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM.../' System," Revision 0, March 1997.
9. Caldon, Inc. Engineering Report-160P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFM.../' System," Revision 0, May 2000.
10. WCAP-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, "Qualification of the NEXUS Nuclear Data Methodology," November 2005.

COLR Cycle 18-1 Beaver Valley Unit 2 5.1 - 6 LRM Revision 82

Licensing Requirements Manual Core Operating Limits Report 5.1 UNACCEPTABLE OPERATION 600 ACCEPTABLE OPERATION 0 0.2 0.4 0.6 0.8 1.2 1.4 FRACTION OF RATED THERMAL POWER Figure 5.1-1(Page1of1)

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

COLR Cycle 18-1 Beaver Valley Unit 2 5.1 - 7 LRM Revision 82

Licensing Requirements Manual Core Operating Limits Report 5.1 225 Vr (54.~3, 225) I 200 ,/

c y1 ~

BANKC I I (100, 187) I

/

175

/

"O

.c

~

+-'

~ 150 ~

/ /

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a.

Q)

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v 100 /

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0 0 /

,/

0:::

50 25 /

/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 RA TED POWER LEVEL COLR Cycle 18-1 Beaver Valley Unit 2 5.1 - 8 LRM Revision 82

Licensing Requirements Manual Core Operating Limits Report 5.1 1.2 Io.o, 1.00 I 16.0, 1.00 I 1.0 12.0. 0.925 I 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 18-1 Beaver Valley Unit 2 5.1 - 9 LRM Revision 82

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

\,

j 90 I UNACCEPTABLE I I UNACCEPTABLE OPERATION I f rccEPTABLEI

\ OPERATION I

... 80 OPERATION \

~

0 a.

cu 70 I

j

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E (J,)

.c:

1- 60 J ' \

\,

"C

.....cu(J,) ,I

....0:::0 50

~ (-2 5, 50) I( +2 2 I 5 0) 40 30 20 10 0

50 -40 -30 -20 -10 0 10 20 30 40 50 60 Axial Flux Difference (Delta 1)%

Figure 5.1-4 (Page 1 of 1)

AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RATED THERMAL POWER FOR RAOC COLR Cycle 18-1 Beaver Valley Unit 2 5.1 - 10 LRM Revision 82

Licensing Requirements Manual Core Operating Limits Report 5.1

-28.00

~

Ii-I 0

"S {)

P..

.._... -29.00 E-t i:i::I H

0 H

~ -30.00 i:i::I ,....__

0 0 -----...... r-....

i:i::I ~

i:i:: I'"--.....

J ----..__

E-t ............

-31.00 --........,

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i:i::I P.l -.............. i--.......

~

i:i::I E-t i:i::

0 -32.00

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

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~

i:i::I i:::i 0

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-33.00

-34.00 14000 15000 16000 17000 18000 CYCLE BURNUP (MWD/MTU)

Figure 5.1-5 (Page 1 of 1)

HOT FULL POWER PREDICTED MODERATOR TEMPERATURE COEFFICIENT AS A FUNCTION OF CYCLE BURNUP WHEN 300 PPM IS ACHIEVED COLR Cycle 18-1 Beaver Valley Unit 2 5.1 - 11 LRM Revision 82

Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-1(Page1of2)

Fa Surveillance W(Z) Function versus Burnup 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 1.1506 1.1928 1.2322 1.2296 1.2203 9 10.5 1.1446 1.1860 1.2247 1.2235 1.2105 10 10.3 1.1390 1.1783 1.2162 1.2162 1.2053 11 10.1 1.1347 1.1700 1.2084 1.2084 1.1995 12 9.9 1.1345 1.1618 1.2027 1.2000 1.1931 13 9.7 1.1378 1.1570 1.1971 1.1909 1.1852 14 9.5 1.1418 1.1561 1.1907 1.1815 1.1798 15 9.3 1.1440 1.1542 1.1857 1.1719 1.1813 16 9.1 1.1472 1.1518 1.1850 1.1607 1.1864 17 8.9 1.1593 1.1556 1.1905 1.1597 1.1883 18 8.7 1.1758 1.1664 1.2013 1.1647 1.1929 19 8.5 1.1884 1.1745 1.2082 1.1750 1.2045 20 8.3 1.1987 1.1807 1.2130 1.1825 1.2133 21 8.1 1.2066 1.1849 1.2157 1.1880 1.2196 22 7.9 1.2121 1.1872 1.2162 1.1917 1.2239 23 7.6 1.2155 1.1878 1.2148 1.1936 1.2260 24 7.4 1.2168 1.1868 1.2115 1.1937 1.2260 25 7.2 1.2161 1.1843 1.2063 1.1922 1.2239 26 7.0 1.2133 1.1813 1.2002 1.1889 1.2197 27 6.8 1.2086 1.1771 1.1931 1.1849 1.2142 28 6.6 1.2021 1.1712 1.1845 1.1803 1.2080 29 6.4 1.1940 1.1639 1.1745 1.1740 1.2000 30 6.2 1.1842 1.1553 1.1630 1.1662 1.1901 31 6.0 1.1732 1.1456 1.1504 1.1571 1.1790 32 5.8 1.1605 1.1345 1.1365 1.1468 1.1657 Note: Top and Bottom 10% Excluded COLR Cycle 18 Beaver Valley Unit 2 5.1 - 12 LRM Revision 80

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

F0 Surveillance W(Z) Function versus Burnup Exclusion Axial Elevation 150 3000 8000 12000 16000 Zone Point (feet) (MWD/MTU) (MWD/MTU) (MWD/MTU) (MWD/MTU) (MWD/MTU) 33 5.6 1.1477 1.1229 1.1233 1.1354 1.1523 34 5.4 1.1386 1.1141 1.1138 1.1243 1.1447 35 5.2 1.1308 1.1104 1.1036 1.1163 1.1414 36 5.0 1.1258 1.1092 1.0963 1.1112 1.1382 37 4.8 1.1233 1.1089 1.0924 1.1078 1.1336 38 4.6 1.1206 1.1098 1.0885 1.1047 1.1283 39 4.4 1.1172 1.1106 1.0849 1.1011 1.1222 40 4.2 1.1167 1.1112 1.0810 1.0970 1.1155 41 4.0 1.1194 1.1114 1.0773 1.0927 1.1084 42 3.8 1.1234 1.1119 1.0749 1.0881 1.1009 43 3.6 1.1266 1.1141 1.0746 1.0834 1.0933 44 3.4 1.1294 1.1168 1.0743 1.0799 1.0860 45 3.2 1.1329 1.1196 1.0747 1.0775 1.0773 46 3.0 1.1377 1.1266 1.0776 1.0790 1.0747 47 2.8 1.1466 1.1426 1.0893 1.0912 1.0839 48 2.6 1.1642 1.1673 1.1068 1.1050 1.0990 49 2.4 1.1855 1.1927 1.1251 1.1192 1.1143 50 2.2 1.2075 1.2180 1.1434 1.1337 1.1296 51 2.0 1.2290 1.2433 1.1619 1.1481 1.1447 52 1.8 1.2500 1.2680 1.1800 1.1622 1.1595 53 1.6 1.2701 1.2917 1.1976 1.1760 1.1739 54 1.4 1.2887 1.3135 1.2139 1.1888 1.1876

  • 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 18 Beaver Valley Unit 2 5.1 - 13 LRM Revision 80

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

Fa(Z) Penalty Factor versus Burnup C cle Burnup (MWD/MTU) F0 (Z) Penalt 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 F0 (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 F0 (Z) was determined.

COLR Cycle 18 Beaver Valley Unit 2 5.1 - 14 LRM Revision 80

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