L-12-140, Core Operating Limits Report, Cycle 22
| ML12129A221 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/07/2012 |
| From: | Harden P FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-12-140 | |
| Download: ML12129A221 (18) | |
Text
FE DC FirstEnergy Nuclear Operating Company Paul A. Harden Site Vice President May 7, 2012 L-12-140 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 Core Operating Limits Report, Cycle 22 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 (BVPS) Technical Specification 5.6.3, "Core Operating Limits Report (COLR)," FirstEnergy Nuclear Operating Company hereby submits the BVPS, Unit No.1, Cycle 22 COLR. The COLR went effective on April 26, 2012.
There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Phil H. Lashley, Supervisor - Fleet Licensing, at (330) 315-6808.
Enclosure:
Beaver Valley Power Station, Unit No.1, Core Operating Limits Report, COLR Cycle 22 cc:
NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative
Enclosure L-12-140 Beaver Valley Power Station, Unit No.1, Core Operating Limits Report, COLR Cycle 22 (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 (SDM)
- a.
In MODES 1,2,3, and 4, SHUTDOWN MARGIN shall be ~ 1.77% flklk.(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% flklk.
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 flklkloF at RATED THERMAL POWER.
- c.
300 ppm Surveillance Limit: (- 37 pcm/oF)
- d.
60 ppm Surveillance Limit: (- 43 pcm/oF) 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 0 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 0 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 0 bank is withdrawn at least to a position equal to the all-rods-out position minus 128 steps.
(1) The MODE 1 and MODE 2 with keft ~ 1.0 SDM requirements are included to address SDM requirements (e.g., MODE 1 Required Actions to verify SDM) that are not within the applicability of LCO 3.1.1, SHUTDOWN MARGIN (SDM).
(2) As indicated by the group demand counter Beaver Valley Unit 1 5.1 - 1 COLR Cycle 22 LRM Revision 78
Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.6 LCO 3.2.1 Heat Flux Hot Channel Factor (FQ{Z>>
The Heat Flux Hot Channel Factor - FQ{Z) limit is defined by:
FQ{Z) ~ [C:Q]*K{Z) for P > 0.5 F (Z) ~ [CFQ]*K{Z)
Q 0.5 for P ~ 0.5 Where:
CFQ = 2.40 THERMAL POWER P = RATED THERMAL POWER K{Z) = the function obtained from Figure 5.1-3.
F5 (Z) = F~ (Z)
- 1.0815 F't (Z) = F5 (Z)
- W{Z)
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 P is ~ 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 FQ{Z) limit at part power conditions.
The FQ{Z) penalty function, applied when the analytic FQ{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)
Where:
CFL\\H = 1.62 PFL\\H = 0.3 THERMAL POWER P = RATED THERMAL POWER Beaver Valley Unit 1 5.1 - 2 COLR Cycle 22 LRM Revision 78
Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 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 i1 T Parameter Values from Table Notations 1 and 2
- a.
Overtemperature i1 T Setpoint Parameter Values:
Beaver Valley Unit 1 Parameter Overtemperature i1 T reactor trip setpoint Overtemperature i1 T reactor trip setpoint Tavg coefficient Overtemperature i1 T reactor trip setpoint pressure coefficient Tavg at RATED THERMAL POWER Nominal pressurizer pressure Measured reactor vessel average temperature leadllag time constants Measured reactor vessel i1 T lag time constant Measured reactor vessel average temperature lag time constant K1 s; 1.242 K3;;:: 0.001/psia P' ;;:: 2250 psia 11;;:: 30 secs 12 s; 4 secs 14 s; 6 secs 15 s; 2 secs f (i1I) 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(i1I) = 0 (where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and % + qb is total THERMAL POWER in percent of RATED THERMAL POWER).
(1)
T' represents the cycle-specific Fu" Power Tavg value used in core design.
5.1 - 3 COLR Cycle 22 LRM Revision 78
Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report (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:
Beaver Valley Unit 1 Parameter Overpower ~ T reactor trip setpoint Overpower ~ T reactor trip setpoint Tavg rate/lag coefficient K4:s; 1.085 K5 ;:::: 0.02/0F for increasing average temperature K5 = O/OF for decreasing average temperature Overpower ~ T reactor trip setpoint Tavg K6;:::: 0.0021/0F for T > Til heatup coefficient K6 = O/oF for T :s; Til Tavg at RATED THERMAL POWER T":s; 577.9°F(2)
Measured reactor vessel average 1:3 ;:::: 10 secs temperature rate/lag time constant Measured reactor vessel ~ T lag time 1:4 :s; 6 secs constant Measured reactor vessel average 1:5 :s; 2 secs temperature lag time constant (2)
Til represents the cycle-specific Full Power Tavg value used in core design.
5.1 - 4 COLR Cycle 22 LRM Revision 78
Licensing Requirements Manual 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 5.1.10 LCO 3.4.1, RCS Pressure, Temperature. and Flow Departure from Nucleate Boiling (DNB) Limits Parameter Indicated Value Reactor Coolant System Tavg Pressurizer Pressure Pressure;;::: 2218 pSia(2)
Reactor Coolant System Total Flow Rate Flow;;::: 267,300 gpm(3)
(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 22 LRM Revision 78
Licensing Requirements Manual 5.1 Core Operating Limits Report 5.1.11 LCO 3.9.1 Boron Concentration (MODE 6)
Core Operating Limits Report 5.1 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.
Beaver Valley Unit 1 5.1 - 6 COLR Cycle 22 LRM Revision 78
Licensing Requirements Manual 5.1 Core Operating Limits Report 5.1.12 References Core Operating Limits Report 5.1
- 1.
WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1985 (Westinghouse Proprietary).
- 2.
WCAP-8745-P-A, "Design Bases for the Thermal Overtemperature ~T and Thermal Overpower ~ T 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-1 0216-P-A, Revision 1A, "Relaxation of Constant Axial Offset Control-FQ 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 Predicating Critical Heat Flux in 17x17 Rod Bundles with Modified LPD Mixing Vane Grids," April 1999.
- 8.
Caldon, Inc. Engineering Report-80P, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFMf"M 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"TM 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.
Beaver Valley Unit 1 5.1 - 7 COLR Cycle 22 LRM Revision 78
Licensing Requirements Manual Core Operating Limits Report 5.1 670 660 650 640 G:;' 630
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REACTOR CORE SAFETY LIMIT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1)
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1.2 1.4 Beaver Valley Unit 1 5.1 - 8 COLR Cycle 22 LRM Revision 78
Licensing Requirements Manual 200
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CONTROL ROD INSERTION LIMITS Beaver Valley Unit 1 5.1 - 9 COLR Cycle 22 LRM Revision 78
Licensing Requirements Manual 1.2 1.0 10.0, 1.00 J 0.8
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Core Operating Limits Report 5.1 I 12.0, 0.925 I -
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Beaver Valley Unit 1 5.1 - 10 COLR Cycle 22 LRM Revision 78
Licensing Requirements Manual Core Operating Limits Report 5.1 120 110
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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 - 11 COLR Cycle 22 LRM Revision 78
Licensing Requirements Manual Table 5.1-1 (Page 1 of2)
Core Operating Limits Report 5.1 FQ Surveillance W(Z) Function versus Burnup Exclusion Axial Elevation 150 Zone Point (feet)
MWO/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 1.1364 9
10.47 1.1316 10 10.27 1.1261 11 10.06 1.1203 12 9.86 1.1149 13 9.66 1.1136 14 9.46 1.1140 15 9.26 1.1131 16 9.06 1.1135 17 8.86 1.1219 18 8.66 1.1341 19 8.45 1.1431 20 8.25 1.1506 21 8.05 1.1564 22 7.85 1.1603 23 7.65 1.1625 24 7.45 1.1630 25 7.25 1.1621 26 7.05 1.1610 27 6.84 1.1592 28 6.64 1.1560 29 6.44 1.1518 30 6.24 1.1464 31 6.04 1.1399 32 5.84 1.1331 Note: Top and Bottom 10% Excluded Beaver Valley Unit 1 5.1 - 12 3000 MWO/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1639 1.1708 1.1673 1.1671 1.1645 1.1594 1.1538 1.1465 1.1429 1.1394 1.1322 1.1266 1.1311 1.1367 1.1402 1.1423 1.1428 1.1422 1.1413 1.1398 1.1371 1.1335 1.1288 1.1231 1.1171 10000 18000 MWO/MTU MWO/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2388 1.2334 1.2287 1.2225 1.2148 1.2060 1.1965 1.1864 1.1765 1.1812 1.1941 1.2023 1.2088 1.2131 1.2150 1.2147 1.2122 1.2077 1.2024 1.1962 1.1890 1.1803 1.1701 1.1588 1.1461 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2382 1.2233 1.2088 1.2022 1.1957 1.1881 1.1798 1.1719 1.1729 1.1756 1.1819 1.1951 1.2067 1.2158 1.2225 1.2266 1.2283 1.2278 1.2252 1.2216 1.2173 1.2114 1.2037 1.1943 1.1834 COLR Cycle 22 LRM Revision 78
licensing Requirements Manual Table 5.1-1 (Page 2 of 2)
Core Operating Limits Report 5.1 FQ Surveillance W(Z) Function versus Burnup Exclusion Axial Elevation 150 Zone Point (feet)
MWO/MTU 33 5.64 1.1279 34 5.44 1.1252 35 5.23 1.1253 36 5.03 1.1272 37 4.83 1.1308 38 4.63 1.1335 39 4.43 1.1358 40 4.23 1.1376 41 4.03 1.1389 42 3.83 1.1400 43 3.62 1.1407 44 3.42 1.1411 45 3.22 1.1431 46 3.02 1.1524 47 2.82 1.1689 48 2.62 1.1847 49 2.42 1.2013 50 2.21 1.2207 51 2.01 1.2412 52 1.81 1.2608 53 1.61 1.2796 54 1.41 1.2967 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 MWO/MTU 1.1130 1.1128 1.1163 1.1209 1.1245 1.1277 1.1305 1.1329 1.1349 1.1366 1.1381 1.1393 1.1428 1.1516 1.1684 1.1936 1.2198 1.2458 1.2716 1.2967 1.3206 1.3425 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 10000 18000 MWO/MTU MWO/MTU 1.1329 1.1222 1.1135 1.1079 1.1042 1.1000 1.0966 1.0930 1.0888 1.0849 1.0827 1.0817 1.0806 1.0814 1.0909 1.1071 1.1238 1.1404 1.1571 1.1735 1.1892 1.2039 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1708 1.1577 1.1509 1.1457 1.1384 1.1306 1.1234 1.1162 1.1085 1.1002 1.0923 1.0859 1.0798 1.0782 1.0858 1.1007 1.1159 1.1306 1.1453 1.1596 1.1736 1.1868 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 COLR Cycle 22 LRM Revision 78
Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-2 (Page 1 of 1)
FQ(Z) Penalty Factor versus Burnup Cycle Burnup (MWD/MTU)
FQ(Z) Penalty Factor o to 1200 1.0337
> 1200 to < 3600 1.0200 3600 to 5400 1.0277
> 5400 1.0200 Note: The Penalty Factor, to be applied to Fo(Z) in accordance with Technical Specification Surveillance Requirement (SR) 3.2.1.2, is the maximum factor by which Fo(Z) is expected to increase over a 39 Effective Full Power Day (EFPD) interval (surveillance interval of 31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance interval per Technical Specification SR 3.0.2) starting from the burnup at which the FQ(Z) was determined.