L-15-304, Cycle 19, Core Operating Limits Report
| ML15303A382 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/29/2015 |
| From: | Emily Larson FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-15-304 | |
| Download: ML15303A382 (18) | |
Text
~
FirstEnergy Nuclear Operating Company Eric A. Larson Site Vice President October 29, 2015 L-15-304 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Cycle 19 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 No. 2 (BVPS-2)
Technical Specification 5.6.3, "CORE OPERATING LIMITS REPORT (COLR),"
FirstEnergy Nuclear Operating Company hereby submits the BVPS-2 COLR for Cycle 19. Technical Specification 5.6.3.d requires, in part, that the COLR be provided to the Nuclear Regulatory Commission (NRC) upon issuance for each reload cycle.
The Cycle 19 BVPS-2 COLR was effective October 14, 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. 2, Cycle 19 Core Operating Limits Report cc:
NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative
Enclosure L-15-304 Beaver Valley Power Station, Unit No.2, Cycle 19 Core Operating Limits Report (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 (SDM)
- a.
In MODES 1, 2, 3, and 4, SHUTDOWN MARGIN shall be;::: 1.77% L\\klk.<1l
- 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 - 4.29 x 10-4 L\\klk/°F at RATED 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 10 :
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 :
{0 pcm/°F or (L\\AFD
- AFD Sensitivity)}
where: LlAFD 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/oF /LlAFD
- Predictive Correction is -3 pcm/°F.
(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).
Beaver Valley Unit 2 5.1 - 1 COLR Cycle 19 LRM Revision 85
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.<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. <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<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.
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) s [C:Q]*K(Z) for P > 0.5 F (Z) s [CFQ]
- K(Z)
Q 0.5 for P s 0.5 Where:
CFQ = 2.40 THERMAL POWER p = RATED THERMAL POWER K(Z) = the function obtained from Figure 5.1-3.
F~(Z) = F~(Z)
- 1.0815 F~ (Z) = F~(Z)
- W(Z)
(2) As indicated by the group demand counter Beaver Valley Unit 2 5.1 - 2 COLR Cycle 19 LRM Revision 85
Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report The W(Z) values are provided in Tables 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 a 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 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 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 5.1-3.
5.1. 7 LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( F~H)
F~H~CF *(1+PF (1-P))
Ll
{j,H
{j,H Where:
CF{j,H
= 1.62 PF{j,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~ T Parameter Values from Table Notations 3 and 4
- a.
Overtemperature ~ T Setpoint Parameter Values:
Parameter Value Overtemperature ~T reactor trip setpoint K1 ::; 1.239 Overtemperature ~ T reactor trip setpoint Tavg K2 ~ 0.0183/°F coefficient Overtemperature ~T reactor trip setpoint pressure K3 ~ 0.001/psia coefficient Tavg at RATED THERMAL POWER T'::; 574.2oFC1>
Nominal pressurizer pressure P' ~ 2250 psia Measured reactor vessel ~ T lead/lag time constants
't1 = 0 sec*
(*The response time is toggled off to meet the analysis
, 2 = 0 sec*
value of zero.)
Measured reactor vessel ~ T lag time constant
't3 ::; 6 sees (1)
T' represents the cycle-specific Full Power Tavg value used in core design.
Beaver Valley Unit 2 5.1 - 3 COLR Cycle 19 LRM Revision 85
Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report Measured reactor vessel average temperature lead/lag r 4 :?: 30 sees time constants ts ~ 4 sees Measured reactor vessel average temperature lag time r 6 ~ 2 sees constant f (1'11) 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%, f1(1'1l) = 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.
(ii)
For each percent that the magnitude of (qt-qb) exceeds -37%, the.!1T 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.!1T trip setpoint shall be automatically reduced by 1.47% of its value at RATED THERMAL POWER.
- b.
Overpower 1'1 T Setpoint Parameter Values:
Parameter Overpower 1'1 T reactor trip setpoint Overpower 1'1 T reactor trip setpoint Tavg rate/lag coefficient Overpower.!1T reactor trip setpoint Tavg heatup coefficient Tavg at RATED THERMAL POWER Measured reactor vessel 1'1 T lead/lag time constants K4 ~ 1.094 K5 :?: 0.02/oF for increasing average temperature K5 = 0/°F for decreasing average temperature K6:?: 0.0021/oF forT> T" K6 = OfOF forT ~ T" T" ~ 574.2°F(1) t1 = 0 sec*
t2 = 0 sec*
(*The response time is toggled off to meet the analysis value of zero.)
Measured reactor vessel 1'1 T lag time constant Measured reactor vessel average temperature lag time constant Measured reactor vessel average temperature rate/lag time constant t3 ~ 6 sees ts ~ 2 sees ty:?: 10 sees (1)
T" represents the cycle-specific Full Power Tavg value used in core design.
Beaver Valley Unit 2 5.1-4 COLR Cycle 19 LRM Revision 85
Licensing Requirements Manual 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 5.1.1 0 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 Pressurizer Pressure Pressure :::: 2214 psia<2l 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 2 5.1 - 5 COLR Cycle 19 LRM Revision 85
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 Overpower L1T and Thermal Overtemperature L1 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," April1999.
- 8.
Caldon, Inc. Engineering Report-BOP, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM-Y' 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-Y'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-A, "Qualification of the NEXUS Nuclear Data Methodology," August 2007.
Beaver Valley Unit 2 5.1 - 6 COLR Cycle 19 LRM Revision 85
Licensing Requirements Manual Core Operating Limits Report 5.1 670 660 650 640
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0 0.2 0.4 0.6 0.8 FRACTION OF RATED THERMAL POWER Figure 5.1-1 (Page 1 of 1)
REACTOR CORE SAFETY LIMIT THREE LOOP OPERATION (Technical Specification Safety Limit2.1.1)
~
1.2 I
1.4 Beaver Valley Unit 2 5.1 - 7 COLR Cycle 19 LRM Revision 85
Licensing Requirements Manual Core Operating Limits Report 5.1 c
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~ 150
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~ 125 225
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- 0 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.
Beaver Valley Unit 2 5.1 - 16 COLR Cycle 19 LRM Revision 85
~
FirstEnergy Nuclear Operating Company Eric A. Larson Site Vice President October 29, 2015 L-15-304 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
- a.
- b.
- c.
- a.
- b.
- c.
- d.
- 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 :
- AFD Sensitivity)}
- Predictive Correction is -3 pcm/°F.
- e.
- a.
- b.
- c.
- d.
- K(Z)
- 1.0815 F~ (Z) = F~(Z)
- W(Z)
- a.
- b.
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
- 10.
- 11.
- 12.
SUBJECT:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Cycle 19 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 No. 2 (BVPS-2)
Technical Specification 5.6.3, "CORE OPERATING LIMITS REPORT (COLR),"
FirstEnergy Nuclear Operating Company hereby submits the BVPS-2 COLR for Cycle 19. Technical Specification 5.6.3.d requires, in part, that the COLR be provided to the Nuclear Regulatory Commission (NRC) upon issuance for each reload cycle.
The Cycle 19 BVPS-2 COLR was effective October 14, 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. 2, Cycle 19 Core Operating Limits Report cc:
NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative
Enclosure L-15-304 Beaver Valley Power Station, Unit No.2, Cycle 19 Core Operating Limits Report (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 (SDM)
In MODES 1, 2, 3, and 4, SHUTDOWN MARGIN shall be;::: 1.77% L\\klk.<1l
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.
In MODE 5, SHUTDOWN MARGIN shall be;::: 1.0% L\\k/k.
5.1.3 LCO 3.1.3 Moderator Temperature Coefficient (MTC)
Upper Limit-MTC shall be maintained within the acceptable operation limit specified in Technical Specification Figure 3.1.3-1.
Lower Limit - MTC shall be maintained less negative than - 4.29 x 10-4 L\\klk/°F at RATED THERMAL POWER.
300 ppm Surveillance Limit: (- 35 pcm/°F)
The revised predicted near-EOL 300 ppm MTC shall be calculated using Figure 5.1-5 and the following algorithm from Reference 10 :
Revised Predicted MTC = Predicted MTC* + AFD Correction** + Predictive Correction***
{0 pcm/°F or (L\\AFD
where: LlAFD 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/oF /LlAFD
(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).
Beaver Valley Unit 2 5.1 - 1 COLR Cycle 19 LRM Revision 85
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.
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.<2l 5.1.5 LCO 3.1.6 Control Bank Insertion Limits
Control Banks A and B shall be withdrawn to at least 225 steps. <2>
Control Banks C and D shall be limited in physical insertion as shown in Figure 5.1-2.<2>
Sequence Limits-The sequence of withdrawal shall be A, B, C and D bank, in that order.
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.
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) s [C:Q]*K(Z) for P > 0.5 F (Z) s [CFQ]
Q 0.5 for P s 0.5 Where:
CFQ = 2.40 THERMAL POWER p = RATED THERMAL POWER K(Z) = the function obtained from Figure 5.1-3.
F~(Z) = F~(Z)
(2) As indicated by the group demand counter Beaver Valley Unit 2 5.1 - 2 COLR Cycle 19 LRM Revision 85
Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report The W(Z) values are provided in Tables 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 a 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 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 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 5.1-3.
5.1. 7 LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( F~H)
F~H~CF *(1+PF (1-P))
Ll
{j,H
{j,H Where:
CF{j,H
= 1.62 PF{j,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~ T Parameter Values from Table Notations 3 and 4
Overtemperature ~ T Setpoint Parameter Values:
Parameter Value Overtemperature ~T reactor trip setpoint K1 ::; 1.239 Overtemperature ~ T reactor trip setpoint Tavg K2 ~ 0.0183/°F coefficient Overtemperature ~T reactor trip setpoint pressure K3 ~ 0.001/psia coefficient Tavg at RATED THERMAL POWER T'::; 574.2oFC1>
Nominal pressurizer pressure P' ~ 2250 psia Measured reactor vessel ~ T lead/lag time constants
't1 = 0 sec*
(*The response time is toggled off to meet the analysis
, 2 = 0 sec*
value of zero.)
Measured reactor vessel ~ T lag time constant
't3 ::; 6 sees (1)
T' represents the cycle-specific Full Power Tavg value used in core design.
Beaver Valley Unit 2 5.1 - 3 COLR Cycle 19 LRM Revision 85
Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report Measured reactor vessel average temperature lead/lag r 4 :?: 30 sees time constants ts ~ 4 sees Measured reactor vessel average temperature lag time r 6 ~ 2 sees constant f (1'11) 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%, f1(1'1l) = 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.
(ii)
For each percent that the magnitude of (qt-qb) exceeds -37%, the.!1T 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.!1T trip setpoint shall be automatically reduced by 1.47% of its value at RATED THERMAL POWER.
Overpower 1'1 T Setpoint Parameter Values:
Parameter Overpower 1'1 T reactor trip setpoint Overpower 1'1 T reactor trip setpoint Tavg rate/lag coefficient Overpower.!1T reactor trip setpoint Tavg heatup coefficient Tavg at RATED THERMAL POWER Measured reactor vessel 1'1 T lead/lag time constants K4 ~ 1.094 K5 :?: 0.02/oF for increasing average temperature K5 = 0/°F for decreasing average temperature K6:?: 0.0021/oF forT> T" K6 = OfOF forT ~ T" T" ~ 574.2°F(1) t1 = 0 sec*
t2 = 0 sec*
(*The response time is toggled off to meet the analysis value of zero.)
Measured reactor vessel 1'1 T lag time constant Measured reactor vessel average temperature lag time constant Measured reactor vessel average temperature rate/lag time constant t3 ~ 6 sees ts ~ 2 sees ty:?: 10 sees (1)
T" represents the cycle-specific Full Power Tavg value used in core design.
Beaver Valley Unit 2 5.1-4 COLR Cycle 19 LRM Revision 85
Licensing Requirements Manual 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 5.1.1 0 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 Pressurizer Pressure Pressure :::: 2214 psia<2l 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 2 5.1 - 5 COLR Cycle 19 LRM Revision 85
Licensing Requirements Manual 5.1 Core Operating Limits Report 5.1.12 References Core Operating Limits Report 5.1
WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1985 (Westinghouse Proprietary).
WCAP-8745-P-A, "Design Bases for the Thermal Overpower L1T and Thermal Overtemperature L1 T Trip Functions," September 1986.
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).
WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset Control-Fa Surveillance Technical Specification," February 1994.
WCAP-14565-P-A, "VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis,"
October 1999.
WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report,"
April 1995 (Westinghouse Proprietary).
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," April1999.
Caldon, Inc. Engineering Report-BOP, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM-Y' System," Revision 0, March 1997.
Caldon, Inc. Engineering Report-160P, "Supplement to Topical Report ER-BOP: Basis for a Power Uprate With the LEFM-Y'System," Revision 0, May 2000.
WCAP-13749-P-'A, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement," March 1997 (Westinghouse Proprietary).
WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON," August 2004.
WCAP-16045-P-A, Addendum 1-A, "Qualification of the NEXUS Nuclear Data Methodology," August 2007.
Beaver Valley Unit 2 5.1 - 6 COLR Cycle 19 LRM Revision 85
Licensing Requirements Manual Core Operating Limits Report 5.1 670 660 650 640
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1.4 Beaver Valley Unit 2 5.1 - 7 COLR Cycle 19 LRM Revision 85
Licensing Requirements Manual Core Operating Limits Report 5.1 c
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Beaver Valley Unit 2 5.1 - 16 COLR Cycle 19 LRM Revision 85