L-15-162, Cycle 24 Core Operating Limits Report
| ML15134A444 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/14/2015 |
| From: | Emily Larson FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-15-162 | |
| Download: ML15134A444 (18) | |
Text
FENOC' ~
Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 RrstEnergy Nuclear Operating Company Eric A. Larson 724-682-5234 Site Vice President Fax: 724-643-8069 May 14, 2015 L-15-162 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 Core Operating Limits Report 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. Technical Specification 5.6.3.d requires, in part, that the COLR be provided to the Nuclear Regulatory Commission upon issuance for each reload cycle. The Cycle 24 COLR was made effective on May 7, 2015.
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, Eric A. Larson
Enclosure:
Beaver Valley Power Station, Unit No. 1, Core Operating Limits Report, Cycle 24 cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative
Enclosure L-15-162 Beaver Valley Power Station, Unit No. 1 Core Operating Limits Report, Cycle 24 (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% L.\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% 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 L.\k/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 (L.\AFD
- AFD Sensitivity)}
where: L.\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 L.\AFD
- Predictive Correction is -3 pcm/°F.
(1) The MODE 1 and MODE 2 with ke11 ~ 1.0 SOM requirements are included to address SDM 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 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.< 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:Q ]* K(Z) for P > 0.5 F (Z)
Q
~ [CFQ]
0.5
- K(Z) for P ~ 0.5 THERMAL POWER Where: CFQ = 2.40 p = RATED THERMAL POWER K(Z) =the function obtained from Figure 5.1-3.
(2) As indicated by the group demand counter COLR Cycle 24 Beaver Valley Unit 1 5.1 - 2 LRM Revision 89
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 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 AT Parameter Values from Table Notations 1 and 2
- a. Overtemperature AT Setpoint Parameter Values:
Parameter Value Overtemperature AT reactor trip setpoint K1 :::; 1.242 Overtemperature AT reactor trip setpoint Tavg K2 ~ 0.0183/°F coefficient Overtemperature AT 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
- 1~ 30 secs time constants
- 2 :::; 4 secs (1) T' represents the cycle-specific Full Power Tavg value used in core design.
COLR Cycle 24 Beaver Valley Unit 1 5.1 - 3 LRM Revision 89
Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report Measured reactor vessel ~ T lag time constant *4 s; 6 secs Measured reactor vessel average temperature lag -rs s; 2 secs time constant f (~I) is a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:
(i) For Qt - qb between -37% and +15%, f(~I) = 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 (qt - qb) exceeds -37%, the~ T trip setpoint shall be automatically reduced by 2.52% of its value at RATED THERMAL POWER.
(iii) For each percent that the magnitude of (qt - qb) exceeds +15%, the~ T trip setpoint shall be automatically reduced by 1.47% of its value at RATED THERMAL POWER.
- b. Overpower ~ T Setpoint Parameter Values:
Parameter Overpower ~ T reactor trip setpoint K4 s; 1.085 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 Ts; T" Tavg at RATED THERMAL POWER T" s; 577.9°F<2>
Measured reactor vessel average -r3 ~ 1O secs temperature rate/lag time constant Measured reactor vessel ~ T lag time *4 s; 6 secs constant Measured reactor vessel average -rs s; 2 secs temperature lag time constant (2) T" represents the cycle-specific Full Power Tavg value used in core design.
COLR Cycle 24 Beaver Valley Unit 1 5.1 - 4 LRM Revision 89
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< 1>
Pressurizer Pressure Pressure 2 2218 psia< 2 >
Reactor Coolant System Total Flow Rate Flow 2 267,300 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 2 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 Tav9 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 19B5 (Westinghouse Proprietary).
- 2. WCAP-B745-P-A, "Design Bases for the Thermal Overpower ~T and Thermal Overtemperature ~ 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'1' 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'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 B9
Licensing Requirements Manual Core Operating Limits Report 5.1 UN ACCEPTABLE OPERATION G:' 6304--~~----"o.,.----t--~~~~r---~~~-t-~--~~c--~~~--t---~~--+~~~----J OJ)
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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 I 1.0 I 12.0, 0.925 0.8
~ 0.6 0.4 0.2 0.0 0 2 4 6 8 10 12 Core Height (feet)
Figure 5.1-3(Page1of1)
Fa T 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)
F0 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
- 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 Burnup 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(Page1of2)
F0 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)
Fa 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)
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.