L-15-376, Cycle 24-1 Core Operating Limits Report
| ML15362A539 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/28/2015 |
| From: | Emily Larson FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-15-376 | |
| Download: ML15362A539 (19) | |
Text
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FirstEnergy Nuclear Operating Company Eric A. Larson Site Vice President December 28, 2015 L-15-376 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Cycle 24-1 Core Operating Limits Report Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 724-682-5234 Fax: 724-643-8069 Pursuant to the requirements of Beaver Valley Power Station, Unit No. 1 Technical Specification 5.6.3, "CORE OPERATING LIMITS REPORT (COLR)," FirstEnergy Nuclear Operating Company hereby submits the COLR for Cycle 24-1. Technical Specification 5.6.3.d requires, in part, that the COLR be provided to the Nuclear Regulatory Commission upon issuance for any midcycle revision. The Cycle 24-1 COLR was made effective on December 3, 2015.
The COLR was revised for Cycle 24 to require that additional specified uncertainty be applied 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 between 50 and 75 percent of the total number of thimbles. When the number of measured thimbles is between 50 and 75 percent, at least 4 measured thimbles per core quadrant are also required.
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.
Eric A. Larson
Enclosure:
Beaver Valley Power Station, Unit No. 1, Core Operating Limits Report, Cycle 24-1
Beaver Valley Power Station, Unit No. 1 L-15-376 Page 2 cc:
NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative
Enclosure L-15-376 Beaver Valley Power Station, Unit No. 1 Core Operating Limits Report, Cycle 24-1 (16 Pages Follow)
Licensing Requirements Manual 5.0 ADMINISTRATIVE CONTROLS 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 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% L'lk/k. <1l
- b.
Prior to manually blocking the Low Pressurizer Pressure Safety Injection Signal, the Reactor Coolant System shall be borated to;;:: the MODE 5 boron concentration and shall remain ;;:: this boron concentration at all times when this signal is blocked.
- c.
In MODE 5, SHUTDOWN MARGIN shall be;;:: 1.0% L'lk/k.
5.1.3 LCO 3.1.3 Moderator Temperature Coefficient (MTC)
- a.
Upper Limit - MTC shall be maintained within the acceptable operation limit specified in Technical Specification Figure 3.1.3-1.
- b.
Lower Limit - MTC shall be maintained less negative than - 4.4 x 10-4 L'lk/k/°F at RATED THERMAL POWER.
- c.
300 ppm Surveillance Limit: (- 37 pcm/°F)
- d.
The revised predicted near-EOL 300 ppm MTC shall be calculated using Figure 5.1-5 and the following algorithm from Reference 11 :
Revised Predicted MTC = Predicted MTC* + AFD Correction** + Predictive Correction***
- where,
- Predicted MTC is calculated from Figure 5.1-5 at the burnup corresponding to the measurement of 300 ppm at RTP conditions,
- AFD Correction is the more negative value of :
{O pcm/°F or (~AFD
- AFD Sensitivity)}
where: ~AFD 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).
Beaver Valley Unit 1 5.1 - 1 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report If the revised predicted MTG 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 MTG 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.<2J
- c.
Sequence Limits - The sequence of withdrawal shall be A, B, C and D bank, in that order.
- d.
Overlap Limits<2J - 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:
Fa(Z) s [ c:o]*K(Z)
F (Z) s [CFQ]*K(Z)
Q 0.5 for P > 0.5 for P s 0.5 Where:
CFQ = 2.40 THERMAL POWER p = RATED THERMAL POWER K(Z) = the function obtained from Figure 5.1-3.
F8(Z) = F~(Z)
- 1.0815$
F;f' (Z) = F8(Z)
- W(Z)
(2) As indicated by the group demand counter For Cycle 24 of Unit 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 ((75-T)/(75-50))*0.12 is added to the measurement uncertainty, 1.05, where T is the percentage of measured thimbles. This adjusted measurement uncertainty is then multiplied by 1.03 to obtain the total uncertainty to be applied. At least four measured thimbles per core quadrant are also required.
Beaver Valley Unit 1 5.1 - 2 COLR Cycle 24-1 LRM Revision 90
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 Piss 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 5.1-3.
5.1. 7 LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( F~H)
F~H ~ CFt.H * (1 + PFt.H (1-P))$
Where:
CFt.H = 1.62 PFt.H = 0.3 THERMAL POWER p = RATED THERMAL POWER 5.1.8 LCO 3.2.3 Axial Flux Difference (AFD)
The AFD acceptable operation limits are provided in Figure 5.1-4.
5.1.9 LCO 3.3.1 Reactor Trip System Instrumentation - Overtemperature and Overpower AT Parameter Values from Table Notations 1 and 2
- a.
Overtemperature AT Setpoint Parameter Values:
Parameter Overtemperature AT reactor trip setpoint Overtemperature AT reactor trip setpoint Tavg coefficient Overtemperature AT reactor trip setpoint pressure coefficient Tavg at RATED THERMAL POWER K1s1.242 K2 ~ 0.01831°F K3 ~ 0.001/psia T'S 577.9°F(1)
For Cycle 24 of Unit 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 ((75-T)/(75-50))*0.06 is added to the standard uncertainty on F~H of 1.04., where Tis the percentage of measured thimbles. At least four measured thimbles per core quadrant are also required.
(1)
T' represents the cycle-specific Full Power Tavg value used in core design.
Beaver Valley Unit 1 5.1 - 3 COLR Cycle 24-1 LRM Revision 90
Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report Nominal pressurizer pressure P' ;:::: 2250 psia Measured reactor vessel average temperature lead/lag
-r1 ;:::: 30 secs time constants
-r2 ~ 4 secs Measured reactor vessel AT lag time constant
't4 ~ 6 secs Measured reactor vessel average temperature lag
-rs ~ 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 + 15%, f(AI) = O (where qt and qb are percent RA TED THERMAL POWER in the top and bottom halves of the core respectively, and qt+ qb is total THERMAL POWER in percent of RATED THERMAL POWER).
(ii)
For each percent that the magnitude of (qt - qb) exceeds -37%, the AT trip setpoint shall be automatically reduced by 2.52% of its value at RATED THERMAL POWER.
(iii)
For each percent that the magnitude of (q1 - qb) exceeds +15%, the AT trip setpoint shall be automatically reduced by 1.47% of its value at RATED THERMAL POWER.
- b.
Overpower AT Setpoint Parameter Values:
Beaver Valley Unit 1 Parameter Overpower AT reactor trip setpoint Overpower AT reactor trip setpoint Tavg rate/lag coefficient Overpower AT reactor trip setpoint Tavg heatup coefficient Tavg at RATED THERMAL POWER Measured reactor vessel average temperature rate/lag time constant Measured reactor vessel AT lag time constant Measured reactor vessel average temperature lag time constant Value K4 ~ 1.085 K5 ;:::: 0.02/°F for increasing average temperature K5 = 0/°F for decreasing average temperature K6;:::: 0.0021/°F for T > T" K6 = 0/°F for T ~ T" T" ~ 577.9°F<2>
't3::::: 10 secs
- 4 ~ 6 secs
-rs~ 2 secs (2)
T" represents the cycle-specific Full Power Tavg value used in core design.
5.1 - 4 COLR Cycle 24-1 LRM Revision 90
Licensing Requirements Manual 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 5.1.1 O LCO 3.4.1. RCS Pressure. Temperature. and Flow Departure from Nucleate Boiling (DNB) Limits 5.1.11 Parameter Indicated Value Reactor Coolant System Tavg Tavg::; 581.5°F<1>
Pressurizer Pressure Pressure~ 2218 psia<2>
Reactor Coolant System Total Flow Rate Flow~ 267,300 gpm<3>
LCO 3.9.1 Boron Concentration (MODE 6)
The boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained ~ 2400 ppm. This value includes a 50 ppm conservative allowance for uncertainties.
(1)
The Reactor Coolant System (RCS) indicated Tavg value is determined by adding the appropriate allowances for rod control operation and verification via control board indication (3.6°F) to the cycle specific full power Tavg used in the core design.
(2)
The pressurizer pressure value includes allowances for pressurizer pressure control operation and verification via control board indication.
(3)
The RCS total flow rate includes allowances for normalization of the cold leg elbow taps with a beginning of cycle precision RCS flow calorimetric measurement and verification on a periodic basis via control board indication.
Beaver Valley Unit 1 5.1 - 5 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual 5.1 Core Operating Limits Report 5.1. 12 References Core Operating Limits Report 5.1
- 1.
WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 19B5 (Westinghouse Proprietary).
- 2.
WCAP-B745-P-A, "Design Bases for the Thermal Overpower Li T and Thermal Overtemperature Li T Trip Functions," September 19B6.
- 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 199B (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.
B.
Caldon, Inc. Engineering Report-BOP, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM-V' System," Revision 0, March 1997.
- 9.
Caldon, Inc. Engineering Report-160P, "Supplement to Topical Report ER-BOP: Basis for a Power Uprate With the LEFM-V' System," Revision 0, May 2000.
- 10.
WCAP-16009-P-A, "Realistic Large Break LOCA Evaluation Methodology Using Automated Statistical Treatment of Uncertainty Method (ASTRUM),"
Revision 0, January 2005.
- 11.
WCAP-137 49-P-A, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement," March 1997 (Westinghouse Proprietary).
- 12.
WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON," August 2004.
- 13.
WCAP-16045-P-A, Addendum 1-A, "Qualification of the NEXUS Nuclear Data Methodology," August 2007.
Beaver Valley Unit 1 5.1 - 6 COLR Cycle 24 LRM Revision B9
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REACTOR CORE SAFETY LIMIT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1) 5.1 - 7 1.2 1.4 COLR Cycle 24 LRM Revision 89
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CONTROL ROD INSERTION LIMITS 5.1 - 8 80 100 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual 1.2 1.0 I o.o, 1.00 I 0.8
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Beaver Valley Unit 1 5.1 - 9 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual Core Operating Limits Report 5.1 120 110 1(-8, 10 0)
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AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RATED THERMAL POWER FOR RAOC Beaver Valley Unit 1 5.1 - 10 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual Core Operating Limits Report 5.1
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-34.00 13000 Beaver Valley Unit 1 14000 15000 16000 CYCLE BURNUP (MWD/MTU)
Figure 5.1-5(Page1of1)
HOT FULL POWER PREDICTED MODERATOR TEMPERATURE COEFFICIENT AS A FUNCTION OF CYCLE BURNUP WHEN 300 PPM IS ACHIEVED 5.1 - 11 17000 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual Table 5.1-1(Page1of2)
Core Operating Limits Report 5.1 Fa Surveillance W(Z) Function versus Burn up at 100% RTP Exclusion Axial Elevation 150 Zone Point (feet)
MWD/MTU 1
12.08 1.0000 2
11.88 1.0000 3
11.68 1.0000 4
11.47 1.0000 5
11.27 1.0000 6
11.07 1.0000 7
10.87 1.0000 8
10.67 1.1358 9
10.47 1.1294 10 10.27 1.1223 11 10.07 1.1151 12 9.86 1.1058 13 9.66 1.1023 14 9.46 1.1055 15 9.26 1.1061 16 9.06 1.1071 17 8.86 1.1154 18 8.66 1.1271 19 8.46 1.1356 20 8.25 1.1427 21 8.05 1.1481 22 7.85 1.1518 23 7.65 1.1538 24 7.45 1.1542 25 7.25 1.1534 26 7.05 1.1523 27 6.84 1.1505 28 6.64 1.1475 29 6.44 1.1436 30 6.24 1.1386 31 6.04 1.1324 32 5.84 1.1265 Note: Top and Bottom 10% Excluded Beaver Valley Unit 1 5.1 - 12 3000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1361 1.1320 1.1291 1.1248 1.1197 1.1138 1.1092 1.1084 1.1084 1.1157 1.1267 1.1347 1.1413 1.1462 1.1494 1.1508 1.1506 1.1493 1.1476 1.1453 1.1417 1.1372 1.1316 1.1251 1.1176 10000 18000 MWD/MTU MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2445 1.2372 1.2289 1.2199 1.2095 1.2008 1.1950 1.1897 1.1881 1.1930 1.2046 1.2137 1.2207 1.2253 1.2275 1.2273 1.2248 1.2201 1.2145 1.2080 1.2003 1.1910 1.1801 1.1681 1.1544 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2326 1.2152 1.1939 1.1758 1.1743 1.1775 1.1804 1.1817 1.1862 1.1898 1.1954 1.2067 1.2184 1.2276 1.2341 1.2379 1.2392 1.2382 1.2350 1.2306 1.2254 1.2187 1.2101 1.1998 1.1879 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual Table 5.1-1 (Page 2 of 2)
Core Operating Limits Report 5.1 Fa Surveillance W(Z) Function versus Burn up at 100% RTP Exclusion Axial Elevation 150 Zone Point (feet)
MWD/MTU 33 5.64 1.1230 34 5.44 1.1229 35 5.23 1.1255 36 5.03 1.1309 37 4.83 1.1370 38 4.63 1.1422 39 4.43 1.1469 40 4.23 1.1511 41 4.03 1.1547 42 3.83 1.1577 43 3.62 1.1604 44 3.42 1.1629 45 3.22 1.1633 46 3.02 1.1693 47 2.82 1.1856 48 2.62 1.2048 49 2.42 1.2240 50 2.21 1.2450 51 2.01 1.2672 52 1.81 1.2886 53 1.61 1.3090 54 1.41 1.3278 55 1.21 1.0000 56 1.01 1.0000 57 0.81 1.0000 58 0.60 1.0000 59 0.40 1.0000 60 0.20 1.0000 61 0.00 1.0000 Note: Top and Bottom 10% Excluded Beaver Valley Unit 1 5.1 - 13 3000 MWD/MTU 1.1120 1.1122 1.1154 1.1192 1.1222 1.1247 1.1268 1.1285 1.1298 1.1309 1.1317 1.1327 1.1376 1.1532 1.1788 1.2044 1.2304 1.2568 1.2827 1.3080 1.3322 1.3543 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 10000 18000 MWD/MTU MWD/MTU 1.1402 1.1285 1.1185 1.1119 1.1073 1.1021 1.0978 1.0934 1.0878 1.0840 1.0840 1.0844 1.0843 1.0851 1.0900 1.0989 1.1137 1.1302 1.1459 1.1616 1.1767 1.1907 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1742 1.1599 1.1522 1.1473 1.1414 1.1345 1.1267 1.1180 1.1088 1.0989 1.0887 1.0810 1.0738 1.0750 1.0870 1.0977 1.1088 1.1205 1.1331 1.1470 1.1603 1.1730 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual Table 5.1-2 (Page 1 of 2)
Core Operating Limits Report 5.1 Fa Surveillance W(Z) Function versus Burnup at 75% RTP Exclusion Axial Zone Point 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 Note: Top and Bottom 10% Excluded Beaver Valley Unit 1 Elevation (feet) 12.08 11.88 11.68 11.47 11.27 11.07 10.87 10.67 10.47 10.27 10.07 9.86 9.66 9.46 9.26 9.06 8.86 8.66 8.46 8.25 8.05 7.85 7.65 7.45 7.25 7.05 6.84 6.64 6.44 6.24 6.04 5.84 5.1 - 14 75% RTP 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2023 1.1828 1.1630 1.1437 1.1213 1.1052 1.0972 1.0876 1.0792 1.0792 1.0834 1.0861 1.0885 1.0897 1.0899 1.0903 1.0904 1.0899 1.0895 1.0891 1.0877 1.0855 1.0826 1.0786 1.0750 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual Table 5.1-2 (Page 2 of 2)
Core Operating Limits Report 5.1 Fa Surveillance W(Z) Function versus Burnup at 75% RTP Exclusion Axial Zone Point 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 Note: Top and Bottom 10% Excluded Beaver Valley Unit 1 Elevation (feet) 5.64 5.44 5.23 5.03 4.83 4.63 4.43 4.23 4.03 3.83 3.62 3.42 3.22 3.02 2.82 2.62 2.42 2.21 2.01 1.81 1.61 1.41 1.21 1.01 0.81 0.60 0.40 0.20 0.00 5.1 - 15 75% RTP 1.0736 1.0753 1.0799 1.0875 1.0963 1.1045 1.1123 1.1197 1.1268 1.1332 1.1399 1.1465 1.1509 1.1607 1.1806 1.2028 1.2251 1.2495 1.2754 1.3008 1.3253 1.3482 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-3(Page1of1)
Fa(Z) Penalty Factor versus Burnup Cycle Burnup (MWD/MTU)
Fa(Z) Penalty Factor
>O 1.0200 Note: The Penalty Factor, to be applied to Fa(Z) in accordance with Technical Specification Surveillance Requirement (SR) 3.2.1.2, is the maximum factor by which Fa(Z) is expected to increase over a 39 Effective Full Power Day (EFPD) interval (surveillance interval of 31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance interval per Technical Specification SR 3.0.2) starting from the burnup at which the Fa(Z) was determined.
Beaver Valley Unit 1 5.1 - 16 COLR Cycle 24 LRM Revision 89
~
FirstEnergy Nuclear Operating Company Eric A. Larson Site Vice President December 28, 2015 L-15-376 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Cycle 24-1 Core Operating Limits Report Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 724-682-5234 Fax: 724-643-8069 Pursuant to the requirements of Beaver Valley Power Station, Unit No. 1 Technical Specification 5.6.3, "CORE OPERATING LIMITS REPORT (COLR)," FirstEnergy Nuclear Operating Company hereby submits the COLR for Cycle 24-1. Technical Specification 5.6.3.d requires, in part, that the COLR be provided to the Nuclear Regulatory Commission upon issuance for any midcycle revision. The Cycle 24-1 COLR was made effective on December 3, 2015.
The COLR was revised for Cycle 24 to require that additional specified uncertainty be applied 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 between 50 and 75 percent of the total number of thimbles. When the number of measured thimbles is between 50 and 75 percent, at least 4 measured thimbles per core quadrant are also required.
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.
Eric A. Larson
Enclosure:
Beaver Valley Power Station, Unit No. 1, Core Operating Limits Report, Cycle 24-1
Beaver Valley Power Station, Unit No. 1 L-15-376 Page 2 cc:
NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative
Enclosure L-15-376 Beaver Valley Power Station, Unit No. 1 Core Operating Limits Report, Cycle 24-1 (16 Pages Follow)
Licensing Requirements Manual 5.0 ADMINISTRATIVE CONTROLS 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 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% L'lk/k. <1l
- b.
Prior to manually blocking the Low Pressurizer Pressure Safety Injection Signal, the Reactor Coolant System shall be borated to;;:: the MODE 5 boron concentration and shall remain ;;:: this boron concentration at all times when this signal is blocked.
- c.
In MODE 5, SHUTDOWN MARGIN shall be;;:: 1.0% L'lk/k.
5.1.3 LCO 3.1.3 Moderator Temperature Coefficient (MTC)
- a.
Upper Limit - MTC shall be maintained within the acceptable operation limit specified in Technical Specification Figure 3.1.3-1.
- b.
Lower Limit - MTC shall be maintained less negative than - 4.4 x 10-4 L'lk/k/°F at RATED THERMAL POWER.
- c.
300 ppm Surveillance Limit: (- 37 pcm/°F)
- d.
The revised predicted near-EOL 300 ppm MTC shall be calculated using Figure 5.1-5 and the following algorithm from Reference 11 :
Revised Predicted MTC = Predicted MTC* + AFD Correction** + Predictive Correction***
- where,
- Predicted MTC is calculated from Figure 5.1-5 at the burnup corresponding to the measurement of 300 ppm at RTP conditions,
- AFD Correction is the more negative value of :
{O pcm/°F or (~AFD
- AFD Sensitivity)}
where: ~AFD 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).
Beaver Valley Unit 1 5.1 - 1 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report If the revised predicted MTG 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 MTG 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.<2J
- c.
Sequence Limits - The sequence of withdrawal shall be A, B, C and D bank, in that order.
- d.
Overlap Limits<2J - 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:
Fa(Z) s [ c:o]*K(Z)
F (Z) s [CFQ]*K(Z)
Q 0.5 for P > 0.5 for P s 0.5 Where:
CFQ = 2.40 THERMAL POWER p = RATED THERMAL POWER K(Z) = the function obtained from Figure 5.1-3.
F8(Z) = F~(Z)
- 1.0815$
F;f' (Z) = F8(Z)
- W(Z)
(2) As indicated by the group demand counter For Cycle 24 of Unit 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 ((75-T)/(75-50))*0.12 is added to the measurement uncertainty, 1.05, where T is the percentage of measured thimbles. This adjusted measurement uncertainty is then multiplied by 1.03 to obtain the total uncertainty to be applied. At least four measured thimbles per core quadrant are also required.
Beaver Valley Unit 1 5.1 - 2 COLR Cycle 24-1 LRM Revision 90
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 Piss 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 5.1-3.
5.1. 7 LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( F~H)
F~H ~ CFt.H * (1 + PFt.H (1-P))$
Where:
CFt.H = 1.62 PFt.H = 0.3 THERMAL POWER p = RATED THERMAL POWER 5.1.8 LCO 3.2.3 Axial Flux Difference (AFD)
The AFD acceptable operation limits are provided in Figure 5.1-4.
5.1.9 LCO 3.3.1 Reactor Trip System Instrumentation - Overtemperature and Overpower AT Parameter Values from Table Notations 1 and 2
- a.
Overtemperature AT Setpoint Parameter Values:
Parameter Overtemperature AT reactor trip setpoint Overtemperature AT reactor trip setpoint Tavg coefficient Overtemperature AT reactor trip setpoint pressure coefficient Tavg at RATED THERMAL POWER K1s1.242 K2 ~ 0.01831°F K3 ~ 0.001/psia T'S 577.9°F(1)
For Cycle 24 of Unit 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 ((75-T)/(75-50))*0.06 is added to the standard uncertainty on F~H of 1.04., where Tis the percentage of measured thimbles. At least four measured thimbles per core quadrant are also required.
(1)
T' represents the cycle-specific Full Power Tavg value used in core design.
Beaver Valley Unit 1 5.1 - 3 COLR Cycle 24-1 LRM Revision 90
Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report Nominal pressurizer pressure P' ;:::: 2250 psia Measured reactor vessel average temperature lead/lag
-r1 ;:::: 30 secs time constants
-r2 ~ 4 secs Measured reactor vessel AT lag time constant
't4 ~ 6 secs Measured reactor vessel average temperature lag
-rs ~ 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 + 15%, f(AI) = O (where qt and qb are percent RA TED THERMAL POWER in the top and bottom halves of the core respectively, and qt+ qb is total THERMAL POWER in percent of RATED THERMAL POWER).
(ii)
For each percent that the magnitude of (qt - qb) exceeds -37%, the AT trip setpoint shall be automatically reduced by 2.52% of its value at RATED THERMAL POWER.
(iii)
For each percent that the magnitude of (q1 - qb) exceeds +15%, the AT trip setpoint shall be automatically reduced by 1.47% of its value at RATED THERMAL POWER.
- b.
Overpower AT Setpoint Parameter Values:
Beaver Valley Unit 1 Parameter Overpower AT reactor trip setpoint Overpower AT reactor trip setpoint Tavg rate/lag coefficient Overpower AT reactor trip setpoint Tavg heatup coefficient Tavg at RATED THERMAL POWER Measured reactor vessel average temperature rate/lag time constant Measured reactor vessel AT lag time constant Measured reactor vessel average temperature lag time constant Value K4 ~ 1.085 K5 ;:::: 0.02/°F for increasing average temperature K5 = 0/°F for decreasing average temperature K6;:::: 0.0021/°F for T > T" K6 = 0/°F for T ~ T" T" ~ 577.9°F<2>
't3::::: 10 secs
- 4 ~ 6 secs
-rs~ 2 secs (2)
T" represents the cycle-specific Full Power Tavg value used in core design.
5.1 - 4 COLR Cycle 24-1 LRM Revision 90
Licensing Requirements Manual 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 5.1.1 O LCO 3.4.1. RCS Pressure. Temperature. and Flow Departure from Nucleate Boiling (DNB) Limits 5.1.11 Parameter Indicated Value Reactor Coolant System Tavg Tavg::; 581.5°F<1>
Pressurizer Pressure Pressure~ 2218 psia<2>
Reactor Coolant System Total Flow Rate Flow~ 267,300 gpm<3>
LCO 3.9.1 Boron Concentration (MODE 6)
The boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained ~ 2400 ppm. This value includes a 50 ppm conservative allowance for uncertainties.
(1)
The Reactor Coolant System (RCS) indicated Tavg value is determined by adding the appropriate allowances for rod control operation and verification via control board indication (3.6°F) to the cycle specific full power Tavg used in the core design.
(2)
The pressurizer pressure value includes allowances for pressurizer pressure control operation and verification via control board indication.
(3)
The RCS total flow rate includes allowances for normalization of the cold leg elbow taps with a beginning of cycle precision RCS flow calorimetric measurement and verification on a periodic basis via control board indication.
Beaver Valley Unit 1 5.1 - 5 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual 5.1 Core Operating Limits Report 5.1. 12 References Core Operating Limits Report 5.1
- 1.
WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 19B5 (Westinghouse Proprietary).
- 2.
WCAP-B745-P-A, "Design Bases for the Thermal Overpower Li T and Thermal Overtemperature Li T Trip Functions," September 19B6.
- 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 199B (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.
B.
Caldon, Inc. Engineering Report-BOP, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM-V' System," Revision 0, March 1997.
- 9.
Caldon, Inc. Engineering Report-160P, "Supplement to Topical Report ER-BOP: Basis for a Power Uprate With the LEFM-V' System," Revision 0, May 2000.
- 10.
WCAP-16009-P-A, "Realistic Large Break LOCA Evaluation Methodology Using Automated Statistical Treatment of Uncertainty Method (ASTRUM),"
Revision 0, January 2005.
- 11.
WCAP-137 49-P-A, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement," March 1997 (Westinghouse Proprietary).
- 12.
WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON," August 2004.
- 13.
WCAP-16045-P-A, Addendum 1-A, "Qualification of the NEXUS Nuclear Data Methodology," August 2007.
Beaver Valley Unit 1 5.1 - 6 COLR Cycle 24 LRM Revision B9
Licensing Requirements Manual Core Operating Limits Report 5.1 G:' 630 Ol)
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REACTOR CORE SAFETY LIMIT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1) 5.1 - 7 1.2 1.4 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual 200
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CONTROL ROD INSERTION LIMITS 5.1 - 8 80 100 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual 1.2 1.0 I o.o, 1.00 I 0.8
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Figure 5.1-3 (Page 1 of 1)
Core Operating Limits Report 5.1 I
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Beaver Valley Unit 1 5.1 - 9 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual Core Operating Limits Report 5.1 120 110 1(-8, 10 0)
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Figure 5.1-4 (Page 1 of 1)
AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RATED THERMAL POWER FOR RAOC Beaver Valley Unit 1 5.1 - 10 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual Core Operating Limits Report 5.1
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Figure 5.1-5(Page1of1)
HOT FULL POWER PREDICTED MODERATOR TEMPERATURE COEFFICIENT AS A FUNCTION OF CYCLE BURNUP WHEN 300 PPM IS ACHIEVED 5.1 - 11 17000 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual Table 5.1-1(Page1of2)
Core Operating Limits Report 5.1 Fa Surveillance W(Z) Function versus Burn up at 100% RTP Exclusion Axial Elevation 150 Zone Point (feet)
MWD/MTU 1
12.08 1.0000 2
11.88 1.0000 3
11.68 1.0000 4
11.47 1.0000 5
11.27 1.0000 6
11.07 1.0000 7
10.87 1.0000 8
10.67 1.1358 9
10.47 1.1294 10 10.27 1.1223 11 10.07 1.1151 12 9.86 1.1058 13 9.66 1.1023 14 9.46 1.1055 15 9.26 1.1061 16 9.06 1.1071 17 8.86 1.1154 18 8.66 1.1271 19 8.46 1.1356 20 8.25 1.1427 21 8.05 1.1481 22 7.85 1.1518 23 7.65 1.1538 24 7.45 1.1542 25 7.25 1.1534 26 7.05 1.1523 27 6.84 1.1505 28 6.64 1.1475 29 6.44 1.1436 30 6.24 1.1386 31 6.04 1.1324 32 5.84 1.1265 Note: Top and Bottom 10% Excluded Beaver Valley Unit 1 5.1 - 12 3000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1361 1.1320 1.1291 1.1248 1.1197 1.1138 1.1092 1.1084 1.1084 1.1157 1.1267 1.1347 1.1413 1.1462 1.1494 1.1508 1.1506 1.1493 1.1476 1.1453 1.1417 1.1372 1.1316 1.1251 1.1176 10000 18000 MWD/MTU MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2445 1.2372 1.2289 1.2199 1.2095 1.2008 1.1950 1.1897 1.1881 1.1930 1.2046 1.2137 1.2207 1.2253 1.2275 1.2273 1.2248 1.2201 1.2145 1.2080 1.2003 1.1910 1.1801 1.1681 1.1544 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2326 1.2152 1.1939 1.1758 1.1743 1.1775 1.1804 1.1817 1.1862 1.1898 1.1954 1.2067 1.2184 1.2276 1.2341 1.2379 1.2392 1.2382 1.2350 1.2306 1.2254 1.2187 1.2101 1.1998 1.1879 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual Table 5.1-1 (Page 2 of 2)
Core Operating Limits Report 5.1 Fa Surveillance W(Z) Function versus Burn up at 100% RTP Exclusion Axial Elevation 150 Zone Point (feet)
MWD/MTU 33 5.64 1.1230 34 5.44 1.1229 35 5.23 1.1255 36 5.03 1.1309 37 4.83 1.1370 38 4.63 1.1422 39 4.43 1.1469 40 4.23 1.1511 41 4.03 1.1547 42 3.83 1.1577 43 3.62 1.1604 44 3.42 1.1629 45 3.22 1.1633 46 3.02 1.1693 47 2.82 1.1856 48 2.62 1.2048 49 2.42 1.2240 50 2.21 1.2450 51 2.01 1.2672 52 1.81 1.2886 53 1.61 1.3090 54 1.41 1.3278 55 1.21 1.0000 56 1.01 1.0000 57 0.81 1.0000 58 0.60 1.0000 59 0.40 1.0000 60 0.20 1.0000 61 0.00 1.0000 Note: Top and Bottom 10% Excluded Beaver Valley Unit 1 5.1 - 13 3000 MWD/MTU 1.1120 1.1122 1.1154 1.1192 1.1222 1.1247 1.1268 1.1285 1.1298 1.1309 1.1317 1.1327 1.1376 1.1532 1.1788 1.2044 1.2304 1.2568 1.2827 1.3080 1.3322 1.3543 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 10000 18000 MWD/MTU MWD/MTU 1.1402 1.1285 1.1185 1.1119 1.1073 1.1021 1.0978 1.0934 1.0878 1.0840 1.0840 1.0844 1.0843 1.0851 1.0900 1.0989 1.1137 1.1302 1.1459 1.1616 1.1767 1.1907 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1742 1.1599 1.1522 1.1473 1.1414 1.1345 1.1267 1.1180 1.1088 1.0989 1.0887 1.0810 1.0738 1.0750 1.0870 1.0977 1.1088 1.1205 1.1331 1.1470 1.1603 1.1730 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual Table 5.1-2 (Page 1 of 2)
Core Operating Limits Report 5.1 Fa Surveillance W(Z) Function versus Burnup at 75% RTP Exclusion Axial Zone Point 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 Note: Top and Bottom 10% Excluded Beaver Valley Unit 1 Elevation (feet) 12.08 11.88 11.68 11.47 11.27 11.07 10.87 10.67 10.47 10.27 10.07 9.86 9.66 9.46 9.26 9.06 8.86 8.66 8.46 8.25 8.05 7.85 7.65 7.45 7.25 7.05 6.84 6.64 6.44 6.24 6.04 5.84 5.1 - 14 75% RTP 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2023 1.1828 1.1630 1.1437 1.1213 1.1052 1.0972 1.0876 1.0792 1.0792 1.0834 1.0861 1.0885 1.0897 1.0899 1.0903 1.0904 1.0899 1.0895 1.0891 1.0877 1.0855 1.0826 1.0786 1.0750 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual Table 5.1-2 (Page 2 of 2)
Core Operating Limits Report 5.1 Fa Surveillance W(Z) Function versus Burnup at 75% RTP Exclusion Axial Zone Point 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 Note: Top and Bottom 10% Excluded Beaver Valley Unit 1 Elevation (feet) 5.64 5.44 5.23 5.03 4.83 4.63 4.43 4.23 4.03 3.83 3.62 3.42 3.22 3.02 2.82 2.62 2.42 2.21 2.01 1.81 1.61 1.41 1.21 1.01 0.81 0.60 0.40 0.20 0.00 5.1 - 15 75% RTP 1.0736 1.0753 1.0799 1.0875 1.0963 1.1045 1.1123 1.1197 1.1268 1.1332 1.1399 1.1465 1.1509 1.1607 1.1806 1.2028 1.2251 1.2495 1.2754 1.3008 1.3253 1.3482 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 COLR Cycle 24 LRM Revision 89
Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-3(Page1of1)
Fa(Z) Penalty Factor versus Burnup Cycle Burnup (MWD/MTU)
Fa(Z) Penalty Factor
>O 1.0200 Note: The Penalty Factor, to be applied to Fa(Z) in accordance with Technical Specification Surveillance Requirement (SR) 3.2.1.2, is the maximum factor by which Fa(Z) is expected to increase over a 39 Effective Full Power Day (EFPD) interval (surveillance interval of 31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance interval per Technical Specification SR 3.0.2) starting from the burnup at which the Fa(Z) was determined.