L-13-329, Core Operating Limits Report, Cycle 23
| ML13310A965 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/04/2013 |
| From: | Emily Larson FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-13-329 | |
| Download: ML13310A965 (16) | |
Text
FE NOC' FirstEnergy Nuclear Operating Company Eric A. Larson Site Vice President November 4, 2013 L-13-329 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 23 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 23 COLR. The COLR went effective on October 17, 2013.
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, COLR Cycle 23 cc:
NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative
Enclosure L-13-329 Beaver Valley Power Station, Unit No. 1, Core Operating Limits Report, COLR Cycle 23 (14 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 21.77% ~k/k.<
1 l
- b.
Prior to manually blocking the Low Pressurizer Pressure Safety Injection Signal, the Reactor Coolant System shall be borated to 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% ~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 ~k/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.<2l 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.<2l
- b.
Control Banks C and D shall be limited in physical insertion as shown in Figure 5.1-2. <2l
- c.
Sequence Limits - The sequence of withdrawal shall be A, B, C and D bank, in that order.
- d.
Overlap Limits<2l - 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 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).
(2) As indicated by the group demand counter Beaver Valley Unit 1 5.1 - 1 COLR Cycle 23 LRM Revision 82
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 (Fo(Z))
The Heat Flux Hot Channel Factor-F0 (Z) limit is defined by:
Fo(Z) ~ [c:o}K(Z) for P > 0.5 F (Z) ~ [ CFQJ
- 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.
F3 (Z) = F~ (Z)
- 1. 0815 F~ (Z) = F3(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 Pis:::; 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 F0(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)
N F~H.:::, CF~H * (1 + PF~H (1-P))
Where:
CF~H = 1.62 THERMAL POWER p = RATED THERMAL POWER Beaver Valley Unit 1 5.1 - 2 COLR Cycle 23 LRM Revision 82
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 (AFO)
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 Li T Parameter Values from Table Notations 1 and 2
- a.
Overtemperature Li T Setpoint Parameter Values:
Beaver Valley Unit 1 Parameter Overtemperature Li T reactor trip setpoint Overtemperature LiT reactor trip setpoint Tavg coefficient Overtemperature Li T reactor trip setpoint pressure coefficient Tavg at RATED THERMAL POWER Nominal pressurizer pressure Measured reactor vessel average temperature lead/lag time constants Measured reactor vessel Li T lag time constant Measured reactor vessel average temperature lag time constant K1s1.242 K2 ~ 0.0183/°F K3 ~ 0.001/psia T's 577.9°F<1>
P' ~ 2250 psia
- 1 ~ 30 secs
- 2s 4 secs 14 s 6 secs
- s s 2 secs f (Lil) 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(Lil) = 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.
5.1 - 3 COLR Cycle 23 LRM Revision 82
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 Li 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 ilT trip setpoint shall be automatically reduced by 1.47% of its value at RATED THERMAL POWER.
- b.
Overpower Li T Setpoint Parameter Values:
Beaver Valley Unit 1 Parameter Overpower Li T reactor trip setpoint Overpower Li T reactor trip setpoint Tavg rate/lag coefficient Overpower Li T reactor trip setpoint Tavg heatup coefficient Tavg at RATED THERMAL POWER Measured reactor vessel average temperature rate/lag time constant Measured reactor vessel Li T lag time constant Measured reactor vessel average temperature lag time constant K4s1.085 K5 2 0.02/°F for increasing average temperature K5 = 0/°F for decreasing average temperature K6 z 0.0021/°F for T > T" K6 = 0/°F for Ts T" T" s 577.9°F<2>
't3 z 10 secs
't4 s 6 secs
-cs s 2 secs (2)
T" represents the cycle-specific Full Power Tavg value used in core design.
5.1 - 4 COLR Cycle 23 LRM Revision 82
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 Tavg:::; 581.5°F(1)
Pressurizer Pressure Pressure ;::: 2218 psia<2l Reactor Coolant System Total Flow Rate Flow;::: 267,300 gpm<3l (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 23 LRM Revision 82
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 23 LRM Revision 82
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 LiT and Thermal Overpower 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 1 A, "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 Predicating Critical Heat Flux in 17x17 Rod Bundles with Modified LPD Mixing Vane Grids," April 1999.
- 8.
Caldon, Inc. Engineering Report-BOP, "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{rM 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 23 LRM Revision 82
Licensing Requirements Manual Core Operating Limits Report 5.1 UNACCEPTABLE OPERATION 600 ACCEPTABLE OPERATION 0
0.2 Beaver Valley Unit 1 0.4 0.6 0.8 1
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) 5.1 - 8 1.2 1.4 COLR Cycle 23 LRM Revision 82
Licensing Requirements Manual 200
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40 60 80 100 Relative Power (Percent)
Figure 5.1-2 (Page 1 of 1)
CONTROL ROD INSERTION LIMITS Beaver Valley Unit 1 5.1 - 9 COLR Cycle 23 LRM Revision 82
Licensing Requirements Manual 1.2 1.0 I o.o, 1.00 I 0.8
§ 0.6 0.4 0.2 0.0 0
2 16.0, 1.00 I 4
6 8
Core Height (feet)
Figure 5.1-3 (Page 1 of 1)
Core Operating Limits Report 5.1 I 12.0, 0.925 t 10 12 F0 T NORMALIZED OPERA TING ENVELOPE, K(Z)
Beaver Valley Unit 1 5.1 - 10 COLR Cycle 23 LRM Revision 82
Licensing Requirements Manual Core Operating Limits Report 5.1 4-l 0
o\\o 120 110 I ( -8 1 10 0)
I ( +8 I 100) I 100 I
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-60
-50
-40
-30
-20
-10 0
10 20 30 40 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 50 60 Beaver Valley Unit 1 5.1 - 11 COLR Cycle 23 LRM Revision 82
Licensing Requirements Manual Table 5.1-1 (Page 1 of 2)
Core Operating Limits Report 5.1 Fa Surveillance W(Z) Function versus Burnup 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 1.1709 9
10.47 1.1645 10 10.27 1.1572 11 10.06 1.1490 12 9.86 1.1428 13 9.66 1.1388 14 9.46 1.1353 15 9.26 1.1304 16 9.06 1.1234 17 8.86 1.1240 18 8.66 1.1298 19 8.45 1.1348 20 8.25 1.1420 21 8.05 1.1476 22 7.85 1.1511 23 7.65 1.1531 24 7.45 1.1534 25 7.25 1.1525 26 7.05 1.1512 27 6.84 1.1492 28 6.64 1.1460 29 6.44 1.1417 30 6.24 1.1364 31 6.04 1.1303 32 5.84 1.1229 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 1.1930 1.1882 1.1825 1.1756 1.1687 1.1670 1.1675 1.1633 1.1614 1.1660 1.1763 1.1828 1.1875 1.1901 1.1906 1.1890 1.1855 1.1803 1.1737 1.1658 1.1568 1.1467 1.1356 1.1232 1.1110 10000 18000 MWD/MTU MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2357 1.2302 1.2248 1.2179 1.2096 1.2005 1.1903 1.1797 1.1771 1.1816 1.1919 1.1986 1.2035 1.2063 1.2069 1.2053 1.2018 1.1964 1.1902 1.1833 1.1754 1.1662 1.1557 1.1443 1.1315 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
. 1.0000 1.2060 1.2013 1.1960 1.1903 1.1841 1.1768 1.1708 1.1696 1.1743 1.1772 1.1822 1.1942 1.2038 1.2109 1.2158 1.2182 1.2182 1.2162 1.2122 1.2072 1.2016 1.1946 1.1859 1.1758 1.1640 COLR Cycle 23 LRM Revision 82
Licensing Requirements Manual Table 5.1-1 (Page 2 of 2)
Core Operating Limits Report 5.1 Fa Surveillance W(Z) Function versus Burnup Exclusion Axial Elevation 150 Zone Point (feet)
MWD/MTU 33 5.64 1.1153 34 5.44 1.1107 35 5.23 1.1085 36 5.03 1.1095 37 4.83 1.1122 38 4.63 1.1145 39 4.43 1.1187 40 4.23 1.1229 41 4.03 1.1265 42 3.83 1.1298 43 3.62 1.1327 44 3.42 1.1354 45 3.22 1.1372 46 3.02 1.1410 47 2.82 1.1529 48 2.62 1.1753 49 2.42 1.1985 50 2.21 1.2213 51 2.01 1.2441 52 1.81 1.2662 53 1.61 1.2872 54 1.41 1.3065 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 1.1026 1.1012 1.1008 1.1006 1.1007 1.1012 1.1024 1.1034 1.1039 1.1047 1.1066 1.1091 1.1127 1.1210 1.1354 1.1527 1.1747 1.1982 1.2211 1.2436 1.2652 1.2850 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 10000 18000 MWD/MTU MWD/MTU 1.1190 1.1106 1.1027 1.0980 1.0961 1.0935 1.0906 1.0873 1.0839 1.0819 1.0816 1.0813 1.0812 1.0826 1.0906 1.1050 1.1200 1.1350 1.1500 1.1646 1.1788 1.1918 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1515 1.1418 1.1367 1.1330 1.1283 1.1227 1.1165 1.1094 1.1022 1.0956 1.0901 1.0853 1.0799 1.0812 1.0920 1.1045 1.1191 1.1344 1.1491 1.1636 1.1776 1.1909 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 COLR Cycle 23 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)
Fo(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.