L-10-301, Core Operating Limits Report, Cycle 21
| ML103200185 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/10/2010 |
| From: | Harden P FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-10-301 | |
| Download: ML103200185 (17) | |
Text
FENOC Beaver Valley Power Station
- '*P.O.
Box4 FirstEnergy Nuclear Operating Company Shippingport, PA 15077 Paul A. Harden 724-682-5234 Site Vice President Fax: 724-643-8069 November 10, 2010 L-10-301 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 21 Pursuant to the requirements of Beaver Valley Power Station (BVPS) Technical Specification 5.6.3, "Core Operating Limits Report (COLR)," FirstEnergy Nuclear Operating Company (FENOC) hereby submits the BVPS, Unit No. 1, Cycle 21 COLR.
The COLR went effective on October 16, 2010. Reference to the realistic large break loss of coolant evaluation methodology, automated statistical treatment of uncertainty method (ASTRUM), which the Nuclear Regulatory Commission (NRC) approved via
.License Amendment 286 (Accession No. ML101600408), was incorporated into the COLR on October 22, 2010.
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) 761-6071.
Sincerely, Paul A. Harden
Enclosure:
Beaver Valley Power Station, Unit No. 1, Core Operating Limits Report, COLR Cycle 21
Beaver Valley Power Station, Unit No. 1 L-10-301 Page 2 cc:
NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative
Enclosure L-1 0-301 Beaver Valley Power Station, Unit No. 1, Core Operating Limits Report, COLR Cycle 21 (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% Ak/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% Ak/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 1 0 -4 Ak/k/°F at RATED THERMAL POWER.
- c.
300 ppm Surveillance Limit: (- 37 pcm/°F)
- d.
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.
(1) The MODE 1 and MODE 2 with keff > 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 COLR Cycle 21 Beaver Valley Unit 1 5.1 -1 LRM Revision 69
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:
FO(Z) FCFQI-K(Z)
FQ(Z) _ E-
]-J K(Z) 0.54 K
Where:
CFQ = 2.40 for P > 0.5 for P*< 0.5 THERMAL POWER
= RATED THERMAL POWER K(Z) = the function obtained from Figure 5.1-3.
Fc(Z) = F6(Z)
- 1.0815 Fv (Z) = F6(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 l/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.
LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( FN FAH) 5.1.7 FNH <CFAH * (1 + PFAH (1-P))
Where:
CFAH = 1.62 PFAH = 0.3 THERMAL POWER RATED THERMAL POWER COLR Cycle 21 LRM Revision 69 Beaver Valley Unit 1 5.1 -2
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 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' < 577.9oF(l)
Nominal pressurizer pressure P' 2 2250 psia Measured reactor vessel average temperature lead/lag T, > 30 secs time constants T2 2 < 4 secs Measured reactor vessel AT lag time constant T4 < 6 secs Measured reactor vessel average temperature lag T5 < 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) = 0 (where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POWER in percent of RATED THERMAL POWER).
(1)
T' represents the cycle-specific Full Power Tavg value used in core design.
COLR Cycle 21 Beaver Valley Unit 1 5.1 -3 LRM Revision 69
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 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 (qt - 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:
Parameter Value 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 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"<* 577.90F(
2)
T3 Ž10 secs t1 4
6 6 secs
'15 < 2 secs (2)
T" represents the cycle-specific Full Power Tavg value used in core design.
COLR Cycle 21 LRM Revision 69 Beaver Valley Unit 1 5.1 -4
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 Pressurizer Pressure Reactor Coolant System Total Flow Rate Tavg < 581.5°F(1)
Pressure > 2218 psia(2)
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 0F) 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 21 LRM Revision 69 Beaver Valley Unit 1 5.1 -5
Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 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.
COLR Cycle 21 LRM Revision 69 Beaver Valley Unit 1 5.1 -6
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-8745-P-A, "Design Bases for the Thermal Overtemperature AT and Thermal Overpower AT Trip Functions," September 1986.
- 3.
WCAP-12945-P-A, Volume 1 (Revision 2) and Volumes 2 through 5 (Revision 1), "Code Qualification Document for Best Estimate LOCA Analysis," March 1998 (Westinghouse Proprietary).
- 4.
WCAP-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 LEFM*/M System," Revision 0, March 1997.
- 9.
Caldon, Inc. Engineering Report-1 60P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFMýTM 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.
COLR Cycle 21 Beaver Valley Unit 1 5.1 - 7 LRM Revision 70
Licensing Requirements Manual 670-660 2435 650 640 6302 620 J Core Operating Limits Report 5.1 0
0.2 0.4 0.6 0.8 1
1.2 1.4 FRACTION OF RATED THERMAL POWER Figure 5.1-1 (Page 1 of 1)
REACTOR CORE SAFETY LIMIT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1)
COLR Cycle 21 LRM Revision 69 Beaver Valley Unit 1 5.1 -8
Licensing Requirements Manual 200 150 0,114 100 50 8,0o 0-Core Operating Limits Report 5.1 0
20 40 60 80 Relative Power (Percent) 100 Figure 5.1-2 (Page 1 of 1)
CONTROL ROD INSERTION LIMITS COLR Cycle 21 LRM Revision 69 Beaver Valley Unit 1 5.1 -9
Licensing Requirements Manual 1.2 1.0 0.8 S0.6 0.4 0.2 0.0 Core Operating Limits Report 5.1 0
2 4
6 8
10 Core Height (feet)
Figure 5.1-3 (Page 1 of 1)
FQT NORMALIZED OPERATING ENVELOPE, K(Z) 12 COLR Cycle 21 LRM Revision 69 Beaver Valley Unit 1 5.1 -10
Licensing Requirements Manual Core Operating Limits Report 5.1 120 120 100 0
Q.,
4-4 0
0\\
90 80 70 60 50 40 30 20 10 40 50 60
-60
-50
-40
-30
/ -20
-10 0
10 20 30 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 21 LRM Revision 69 Beaver Valley Unit 1 5.1 -11
Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-1 (Page 1 of 2)
FQ 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 1.1457 1.1850 1.2337 1.1827 9
10.47 1.1373 1.1748 1.2225 1.1759 10 10.27 1.1301 1.1635 1.2101 1.1698 11 10.06 1.1261 1.1523 1.1977 1.1663 12 9.86 1.1240 1.1414 1.1855 1.1641 13 9.66 1.1210 1.1357 1.1723 1.1647 14 9.46 1.1173 1.1347 1.1610 1.1667 15 9.26 1.1150 1.1304 1.1551 1.1667 16 9.06 1.1135 1.1268 1.1471 1.1723 17 8.86 1.1167 1.1298 1.1516 1.1884 18 8.66 1.1246 1.1399 1.1668 1.2080 19 8.45 1.1298 1.1472 1.1805 1.2231 20 8.25 1.1338 1.1531 1.1918 1.2358 21 8.05 1.1363 1.1573 1.2007 1.2456 22 7.85 1.1412 1.1597 1.2070 1.2524 23 7.65 1.1473 1.1605
.1.2108 1.2562 24 7.45 1.1509 1.1595 1.2121 1.2572 25 7.25 1.1530 1.1573 1.2113 1.2556 26 7.05 1.1536 1.1560 1.2085 1.2518 27 6.84 1.1529 1.1544 1.2039 1.2459 28 6.64 1.1510 1.1513 1.1976 1.2381 29 6.44 1.1479 1.1469 1.1897 1.2282 30 6.24 1.1435 1.1414 1.1801 1.2168 31 6.04 1.1380 1.1348 1.1692 1.2079 32 5.84 1.1316 1.1271 1.1564 1.1998 Note: Top and Bottom 10% Excluded COLR Cycle 21 LRM Revision 69 Beaver Valley Unit 1 5.1 - 12
Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-1 (Page 2 of 2)
FQ 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 1.1241 1.1.184 1.1432 1.1891 34 5.44 1.1171 1.1100 1.1323 1.1769 35 5.23 1.1192 1.1061 1.1215 1.1667 36 5.03 1.1239 1.1059 1.1140 1.1582 37 4.83 1.1266 1.1075 1.1093 1.1509 38 4.63 1.1293 1.1098 1.1037 1.1445 39 4.43 1.1315 1.1116 1.0976 1.1369 40 4.23 1.1334 1.1131 1.0914 1.1285 41 4.03 1.1349 1.1141 1.0842 1.1196 42 3.83 1.1364 1.1154 1.0793 1.1100 43 3.62 1.1395 1.1181 1.0792 1.1002 44 3.42 1.1450 1.1214 1.0801 1.0907 45 3.22 1.1514 1.1259 1.0810 1.0798 46 3.02 1.1594 1.1344 1.0860 1.0787 47 2.82 1.1691 1.1503 1.1033 1.0909 48 2.62 1.1785 1.1744 1.1206 1.1023 49 2.42 1.1865 1.1992 1.1382 1.1140 50 2.21 1.2026 1.2235 1.1559 1.1261 51 2.01 1.2249 1.2476 1.1733 1.1381 52 1.81 1.2447 1.2708 1.1902 1.1501 53 1.61 1.2639 1.2930 1.2063 1.1630 54 1.41 1.2813 1.3131 1.2211 1.1754 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 21 LRM Revision 69 Beaver Valley Unit 1 5.1 - 13
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 0 to 1200 1.0255
> 1200 1.02 Note: The Penalty Factor, to be applied to FQ(Z) in accordance with Technical Specification Surveillance Requirement (SR) 3.2.1.2, is the maximum factor by which FQ(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.