L-14-389, Submittal of Core Operating Limits Report
| ML14345A674 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/11/2014 |
| From: | Emily Larson FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-14-389 | |
| Download: ML14345A674 (31) | |
Text
FE NOC' FirstEnergy Nuclear Operating Company Eric A. Larson Site Vice President December 11, 2014 L-14-389 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit Nos. 1 and 2 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 Unit Nos. 1 and 2 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 Nos. 1 (BVPS-1) and 2 (BVPS-2) Technical Specification 5.6.3, "CORE OPERATING LIMITS REPORT (COLR),"
FirstEnergy Nuclear Operating Company (FENOC) hereby submits the BVPS-1 COLR for Cycle 23 and the BVPS-2 COLR for Cycle 18. The COLRs have been revised to implement license amendments 291 (BVPS-1) and 178 (BVPS-2) that allow the normally required near end-of-life moderator temperature coefficient measurement to not be performed under certain conditions. Technical Specification 5.6.3.d requires, in part, that the COLR be provided to the Nuclear Regulatory Commission (NRC) upon issuance for any midcycle revisions or supplements. The COLRs were effective November 14, 2014.
There are no regulatory commitments established 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, r0t~
Eric A Larson
Enclosures:
A Beaver Valley Power Station, Unit No. 1, Core Operating Limits Report, Cycle 23 B.
Beaver Valley Power Station, Unit No. 2, Core Operating Limits Report, Cycle 18 cc:
NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative
Enclosure A L-14-389 Beaver Valley Power Station, Unit No. 1 Core Operating Limits Report, 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 2 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 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% 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 -1k/k/°F at RA TED 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 (MFD
- AFD Sensitivity)}
where: MFD 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 23-1 LRM Revision 86
Licensing Requirements Manual 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 If the revised predicted MTC 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 MTC 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 (Fo(Z))
The Heat Flux Hot Channel Factor - F0 (Z) limit is defined by:
Fo(Z) ~. [ c:oJ
- 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.
F ;f (Z) = F5 (Z)
- W(Z)
(2) As indicated by the group demand counter Beaver Valley Unit 1 5.1 - 2 COLR Cycle 23-1 LRM Revision 86
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. 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 :s; 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 5.1-2.
5.1.7 LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( F~H)
F~H.::: CFAH * (1 + PFAH (1-P))
Where:
CFAH = 1.62 PFAH = 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 /1 T Parameter Values from Table Notations 1 and 2
- a.
Overtemperature /1 T Setpoint Parameter Values:
Beaver Valley Unit 1 Parameter Value Overtemperature /1 T reactor trip setpoint K1 ~ 1.242 Overtemperature /1 T reactor trip setpoint Tavg K2 ~ 0.0183/°F coefficient Overtemperature 11T 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 1 ~ 30 secs time constants 12 ~ 4 secs Measured reactor vessel /1 T lag time constant 14 ~ 6 secs (1)
T' represents the cycle-specific Full Power Tavg value used in core design.
5.1 - 3 COLR Cycle 23-1 LRM Revision 86
Licensing Requirements Manual Core Operating Limits Report S.1 S.1 Core Operating Limits Report Measured reactor vessel average temperature lag time constant
-rs:::;; 2 secs 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 +1 S%, f(~I) = 0 (where qt and qb are percent RA TED THERMAL POWER in the top and bottom halves of the core respectively, and qi+ 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.S2% of its value at RA TED THERMAL POWER.
(iii)
For each percent that the magnitude of (qt - qb) exceeds +1S%, the ~T trip setpoint shall be automatically reduced by 1.47% of its value at RA TED 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 Overpower~ T reactor trip setpoint Tavg heatup coefficient Tavg at RATED THERMAL POWER Measured reactor vessel average temperature rate/lag time constant Measured reactor vessel ~ T lag time constant Measured reactor vessel average temperature lag time constant K4:::;; 1.08S KS~ 0.02/°F for increasing average temperature KS = 0/°F for decreasing average temperature K6 ~ 0.0021/°F for T > T" K6 = 0/°F for T :::;; T" T":::;; S77.9°F<2l
-rs~ 10 secs
't4:::;; 6 secs
-rs:::;; 2 secs (2)
T" represents the cycle-specific Full Power Tavg value used in core design.
S.1 - 4 COLR Cycle 23-1 LRM Revision 86
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 5.1.11 Parameter Indicated Value Reactor Coolant System Tavg Tavg:;:; 581.5°F<1l Pressurizer Pressure Pressure~ 2218 psia<2>
Reactor Coolant System Total Flow Rate Flow~ 267,300 gpm<3l 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 23-1 LRM Revision 86
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 19S5 (Westinghouse Proprietary).
- 2.
WCAP-S745-P-A, "Design Bases for the Thermal Overpower ~T and Thermal Overtemperature ~ T Trip Functions," September 19S6.
- 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 199S (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.
S.
Caldon, Inc. Engineering Report-SOP, "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-SOP: 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, "Qualification of the NEXUS Nuclear Data Methodology," November 2005.
Beaver Valley Unit 1 5.1 - 6 COLR Cycle 23-1 LRM Revision S6
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 FRACTION OF RA TED THERMAL POWER Figure 5.1-1(Page1of1)
REACTOR CORE SAFETY LIMIT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1) 5.1 - 7 1.2 1.4 COLR Cycle 23-1 LRM Revision 86
Licensing Requirements Manual 200
/
/ v v
150
~
.f:J i3=
Vl fr r:./)
/ v
/ v
/
/
/
/,
~ 0, 114 !
"§ 100 i:Q "Cl
~
50
/
v
/ v
/
/ fu
/ v ~
0 0
20 7
I I
Core Operating Limits Report 5.1 I
/ v 54.53, 225 1 v
/
v
/
/ v 100, 187 I/
I I
/
I BANKC I
/
/
v 17
/
v
/
I/
/
/
/
/
/
BANKD f
/
/
17
/
v
/
/ v
/ v
/ /
v 40 60 80 100 Relative Power (Percent)
Figure 5.1-2(Page1of1)
CONTROL ROD INSERTION LIMITS Beaver Valley Unit 1 5.1 - 8 COLR Cycle 23-1 LRM Revision 86
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 12.0, 0.925 t 10 12 Fo T NORMALIZED OPERA Tl NG ENVELOPE, K(Z)
Beaver Valley Unit 1 5.1 - 9 COLR Cycle 23-1 LRM Revision 86
Licensing Requirements Manual Core Operating Limits Report 5.1 H
(})
120 110 100 90 fl, 80
.-1 m s
~
70
,.c::
H
]
60
.µ m
p::;
'H 50 0
o\\O 40 30 20 10 0
I ( - 8 I 10 0)
I UNACCEPTABLE I OPERATION J
I I
J I,
I (-2 5, 5 0)
I ( +8 I 10 0) I
\\
J
/,
\\ I UNACCEPTABLE OPERATION I f rcCEPTABLEI OPERATION \\
' \\
\\
\\
1 I( +2 2, 5 0)
-60
-50
-40
-30
-20
-10 0
10 20 30 40 50 60 Axial Flux Difference (Delta I)%
Figure 5.1-4 (Page 1 of 1)
AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RA TED THERMAL POWER FOR RAOC Beaver Valley Unit 1 5.1 - 10 COLR Cycle 23-1 LRM Revision 86
Licensing Requirements Manual Core Operating Limits Report 5.1 i:z...
0
~
l)
-28.00
~ -29.00
~
~
H u H
~ -30.00
~
u
~
~
p
~ -31. 00
~
~
~
E-i ti -32.00 E-i
.a::
~
~
A 0
i:i:::
-33.00
-34.00 14000 Beaver Valley Unit 1
-..... 1---.. -...........__
.......... ~
- -...._ r---.._
15000 16000 17000 CYCLE BURNUP (MWD/MTU)
Figure 5.1-5 (Page 1 of 1)
HOT FULL POWER PREDICTED MODERATOR TEMPERATURE COEFFICIENT AS A FUNCTION OF CYCLE BURNUP WHEN 300 PPM IS ACHIEVED 5.1 - 11 18000 COLR Cycle 23-1 LRM Revision 86
Licensing Requirements Manual Table 5.1-1(Page1of2)
Core Operating Limits Report 5.1 F0 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)
F0 (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.
Beaver Valley Unit 1 5.1 - 14 COLR Cycle 23 LRM Revision 82 L-14-389 Beaver Valley Power Station, Unit No. 2 Core Operating Limits Report, Cycle 18 (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;;:: 1.77% ~k/k.(
1 l
- b.
Prior to manually blocking the Low Pressurizer Pressure Safety Injection Signal, the Reactor Coolant System shall be borated to :::: 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% ~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 - 4.29 x 1 o*4
~k/k/°F at RA TED THERMAL POWER.
- c.
300 ppm Surveillance Limit: (- 35 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 1 O :
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 (MFD
- AFD Sensitivity)}
where: MFD 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 keff:::: 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 2 5.1 - 1 COLR Cycle 18-1 LRM Revision 82
Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report If the revised predicted MTC 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 MTC measurement in accordance with SR 3.1.3.2 is not required.
- e.
60 ppm Surveillance Limit: (- 41 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:
Fa(Z)::; [c:o}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 = RA TED THERMAL POWER K(Z) = the function obtained from Figure 5.1-3.
Fg (Z) = F~(Z)
- 1.0815 F 'g (Z) = Fg (Z)
- W(Z)
(2) As indicated by the group demand counter Beaver Valley Unit 2 5.1 - 2 COLR Cycle 18-1 LRM Revision 82
Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 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 s 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 Fo(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)
F~H s;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 11 T Parameter Values from Table Notations 3 and 4
- a.
Overtemperature 11 T Setpoint Parameter Values:
Parameter Overtemperature 11 T reactor trip setpoint Overtemperature 11 T reactor trip setpoint Tavg coefficient Overtemperature 11 T reactor trip setpoint pressure coefficient Tavg at RATED THERMAL POWER Nominal pressurizer pressure Measured reactor vessel 11 T lead/lag time constants
(* The response time is toggled off to meet the analysis value of zero.)
Measured reactor vessel 11 T lag time constant K1s1.239 K2 2:: 0.0183/°F K3 2:: 0.001/psia T's 574.2°F(1)
P' 2:: 2250 psia
- 1 = O sec*
12 = O sec*
13 s 6 secs (1)
T' represents the cycle-specific Full Power Tavg value used in core design.
Beaver Valley Unit 2 5.1 - 3 COLR Cycle 18-1 LRM Revision 82
Licensing Requirements Manual Core Operating Limits Report 5.1 S.1 Core Operating Limits Report Measured reactor vessel average temperature lead/lag
-.4 ~ 30 secs time constants
-.5 s 4 secs Measured reactor vessel average temperature lag time
-.6 s 2 secs 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 +1S%, f1(~1) = 0, 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 RA TED THERMAL POWER.
(ii)
For each percent that the magnitude of (qt - qb) exceeds -37%, the ~T trip setpoint shall be automatically reduced by 2.S2% 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 Overpower~ T reactor trip setpoint Tavg rate/lag coefficient Overpower~ T reactor trip setpoint Tavg heatup coefficient Tavg at RATED THERMAL POWER Measured reactor vessel ~ T lead/lag time constants K4s1.094 KS~ 0.02/°F for increasing average temperature KS = 0/°F for decreasing average temperature K6 ~ 0.0021/°F for T > T" K6 = 0/°F for T s T" T" s S74.2°F<1>
t1 = O sec*
t2 = O sec*
(*The response time is toggled off to meet the analysis value of zero.)
Measured reactor vessel ~ T lag time constant Measured reactor vessel average temperature lag time constant Measured reactor vessel average temperature rate/lag time constant
't3 s 6 secs
- es 2 secs
- ? ~ 10 secs (1)
T" represents the cycle-specific Full Power Tavg value used in core design.
Beaver Valley Unit 2 S.1 - 4 COLR Cycle 18-1 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 5.1.11 Parameter Indicated Value Reactor Coolant System Tavg Tavg ::;; 577.8°F<1>
Pressurizer Pressure Pressure~ 2214 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 2 5.1 - 5 COLR Cycle 18-1 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-87 45-P-A, "Design Bases for the Thermal Overpower Li T and Thermal Overtemperature Li 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-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.
- 8.
Caldon, Inc. Engineering Report-SOP, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM.../' 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.../' System," Revision 0, May 2000.
- 10.
WCAP-13749-P-A, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement," March 1997 (Westinghouse Proprietary).
- 11.
WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON," August 2004.
- 12.
WCAP-16045-P-A, Addendum 1, "Qualification of the NEXUS Nuclear Data Methodology," November 2005.
Beaver Valley Unit 2 5.1 - 6 COLR Cycle 18-1 LRM Revision 82
Licensing Requirements Manual Core Operating Limits Report 5.1 UNACCEPTABLE OPERATION 600 ACCEPTABLE OPERATION 0
0.2 Beaver Valley Unit 2 0.4 0.6 0.8 FRACTION OF RATED THERMAL POWER Figure 5.1-1(Page1of1)
REACTOR CORE SAFETY LIMIT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1) 5.1 - 7 1.2 1.4 COLR Cycle 18-1 LRM Revision 82
Licensing Requirements Manual Core Operating Limits Report 5.1 c
~
"O
.c
+-'
~
!}) a.
Q)
+-'
CJ) z 0
I-CJ) 0 Cl.
~
z
<(
ca 0
0 0:::
225 Vr (54.~3, 225) I
/
~,
y1 BANKC I I (100, 187) I
/
/
/
/
~
/
V'
/
200 175 150 125 / I (o, 114) I I BANK D I /
100 75 50 25 0
0
/ v
/
/
/
/
/
~ /i (8, o) I 10 20 30 40 50 60 70 PERCENT OF RATED THERMAL POWER Figure 5.1-2 (Page 1 of 1)
CONTROL ROD INSERTION LIMITS AS A FUNCTION OF RA TED POWER LEVEL 80 90 100 Beaver Valley Unit 2 5.1 - 8 COLR Cycle 18-1 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 12.0. 0.925 I 10 12 FaT NORMALIZED OPERATING ENVELOPE, K(Z)
Beaver Valley Unit 2 5.1 - 9 COLR Cycle 18-1 LRM Revision 82
Licensing Requirements Manual Core Operating Limits Report 5.1
~
0 a.
cu E
(J,)
.c:
1-
"C (J,)
cu 0:::....
0
~
120 110 i( 8 t 10 0)
I ( +8 I 10 0) I 100
\\
j I UNACCEPTABLE I I UNACCEPTABLE I
\\
OPERATION OPERATION 90 f rccEPTABLEI \\
OPERATION j
80 I
\\
\\
70 J
\\
60 I
50
(-2 5, 50)
I( +2 2 I 5 0) 40 30 20 10 0
-60
-50
-40
-30
-20
-10 0
10 20 30 40 Axial Flux Difference (Delta 1)%
Figure 5.1-4 (Page 1 of 1)
AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RA TED THERMAL POWER FOR RAOC I
50 60 Beaver Valley Unit 2 5.1 - 10 COLR Cycle 18-1 LRM Revision 82
Licensing Requirements Manual Core Operating Limits Report 5.1
~
Ii-I 0
"S
{)
P..
-28.00
.._... -29.00 E-t i:i::I H
0 H
~ -30.00 i:i::I 0
0 i:i::I i:i::
- J E-t
~
i:i::I P.l
~
i:i::I E-t i:i::
0 E-t
~
i:i::I i:::i 0
~
-31.00
-32.00
-33.00
-34.00 14000 Beaver Valley Unit 2
...... r-....
~
I'"--.....
-.............. i--.......
I'"--.....
15000 16000 17000 CYCLE BURNUP (MWD/MTU)
Figure 5.1-5 (Page 1 of 1)
HOT FULL POWER PREDICTED MODERATOR TEMPERATURE COEFFICIENT AS A FUNCTION OF CYCLE BURNUP WHEN 300 PPM IS ACHIEVED 5.1 - 11
---.......... r---_
18000 COLR Cycle 18-1 LRM Revision 82
Licensing Requirements Manual Table 5.1-1(Page1of2)
Core Operating Limits Report 5.1 Fa Surveillance W(Z) Function versus Burnup Exclusion Axial Elevation 150 3000 Zone Point (feet)
(MWD/MTU)
(MWD/MTU) 1 12.1 1.0000 1.0000 2
11.9 1.0000 1.0000 3
11.7 1.0000 1.0000 4
11.5 1.0000 1.0000 5
11.3 1.0000 1.0000 6
11.1 1.0000 1.0000 7
10.9 1.0000 1.0000 8
10.7 1.1506 1.1928 9
10.5 1.1446 1.1860 10 10.3 1.1390 1.1783 11 10.1 1.1347 1.1700 12 9.9 1.1345 1.1618 13 9.7 1.1378 1.1570 14 9.5 1.1418 1.1561 15 9.3 1.1440 1.1542 16 9.1 1.1472 1.1518 17 8.9 1.1593 1.1556 18 8.7 1.1758 1.1664 19 8.5 1.1884 1.1745 20 8.3 1.1987 1.1807 21 8.1 1.2066 1.1849 22 7.9 1.2121 1.1872 23 7.6 1.2155 1.1878 24 7.4 1.2168 1.1868 25 7.2 1.2161 1.1843 26 7.0 1.2133 1.1813 27 6.8 1.2086 1.1771 28 6.6 1.2021 1.1712 29 6.4 1.1940 1.1639 30 6.2 1.1842 1.1553 31 6.0 1.1732 1.1456 32 5.8 1.1605 1.1345 Note: Top and Bottom 10% Excluded Beaver Valley Unit 2 5.1 - 12 8000 (MWD/MTU) 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2322 1.2247 1.2162 1.2084 1.2027 1.1971 1.1907 1.1857 1.1850 1.1905 1.2013 1.2082 1.2130 1.2157 1.2162 1.2148 1.2115 1.2063 1.2002 1.1931 1.1845 1.1745 1.1630 1.1504 1.1365 12000 16000 (MWD/MTU)
(MWD/MTU) 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2296 1.2203 1.2235 1.2105 1.2162 1.2053 1.2084 1.1995 1.2000 1.1931 1.1909 1.1852 1.1815 1.1798 1.1719 1.1813 1.1607 1.1864 1.1597 1.1883 1.1647 1.1929 1.1750 1.2045 1.1825 1.2133 1.1880 1.2196 1.1917 1.2239 1.1936 1.2260 1.1937 1.2260 1.1922 1.2239 1.1889 1.2197 1.1849 1.2142 1.1803 1.2080 1.1740 1.2000 1.1662 1.1901 1.1571 1.1790 1.1468 1.1657 COLR Cycle 18 LRM Revision 80
Licensing Requirements Manual TABLE 5.1-1 (Page 2 of 2)
Core Operating Limits Report 5.1 F0 Surveillance W(Z) Function versus Burnup Exclusion Axial Elevation 150 3000 Zone Point (feet)
(MWD/MTU)
(MWD/MTU) 33 5.6 1.1477 1.1229 34 5.4 1.1386 1.1141 35 5.2 1.1308 1.1104 36 5.0 1.1258 1.1092 37 4.8 1.1233 1.1089 38 4.6 1.1206 1.1098 39 4.4 1.1172 1.1106 40 4.2 1.1167 1.1112 41 4.0 1.1194 1.1114 42 3.8 1.1234 1.1119 43 3.6 1.1266 1.1141 44 3.4 1.1294 1.1168 45 3.2 1.1329 1.1196 46 3.0 1.1377 1.1266 47 2.8 1.1466 1.1426 48 2.6 1.1642 1.1673 49 2.4 1.1855 1.1927 50 2.2 1.2075 1.2180 51 2.0 1.2290 1.2433 52 1.8 1.2500 1.2680 53 1.6 1.2701 1.2917 54 1.4 1.2887 1.3135 55 1.2 1.0000 1.0000 56 1.0 1.0000 1.0000 57 0.8 1.0000 1.0000 58 0.6 1.0000 1.0000 59 0.4 1.0000 1.0000 60 0.2 1.0000 1.0000 61 0.0 1.0000 1.0000 Note: Top and Bottom 10% Excluded Beaver Valley Unit 2 5.1 - 13 8000 (MWD/MTU) 1.1233 1.1138 1.1036 1.0963 1.0924 1.0885 1.0849 1.0810 1.0773 1.0749 1.0746 1.0743 1.0747 1.0776 1.0893 1.1068 1.1251 1.1434 1.1619 1.1800 1.1976 1.2139 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 12000 16000 (MWD/MTU)
(MWD/MTU) 1.1354 1.1523 1.1243 1.1447 1.1163 1.1414 1.1112 1.1382 1.1078 1.1336 1.1047 1.1283 1.1011 1.1222 1.0970 1.1155 1.0927 1.1084 1.0881 1.1009 1.0834 1.0933 1.0799 1.0860 1.0775 1.0773 1.0790 1.0747 1.0912 1.0839 1.1050 1.0990 1.1192 1.1143 1.1337 1.1296 1.1481 1.1447 1.1622 1.1595 1.1760 1.1739 1.1888 1.1876 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 COLR Cycle 18 LRM Revision 80
Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-2 (Page 1 of 1)
Fa(Z) Penalty Factor versus Burnup C cle Burnup (MWD/MTU)
F0 (Z) Penalt Factor
>O 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.