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Category:Fuel Cycle Reload Report
MONTHYEARL-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023
Cycle 24 Core Operating Limits Report
L-22-222, Cycle 29-1 Core Operating Limits Report2022-10-31031 October 2022
Cycle 29-1 Core Operating Limits Report
L-21-260, Core Operating Limits Reports2021-11-15015 November 2021
Core Operating Limits Reports
L-21-137, Cycle 28 Core Operating Limits Report2021-05-21021 May 2021
Cycle 28 Core Operating Limits Report
L-20-143, Cycle 22 Core Operating Limits Report2020-05-0808 May 2020
Cycle 22 Core Operating Limits Report
L-20-078, Cycle 27-1 Core Operating Limits Report2020-03-16016 March 2020
Cycle 27-1 Core Operating Limits Report
L-19-239, Cycle 27 Core Operating Limits Report2019-11-0808 November 2019
Cycle 27 Core Operating Limits Report
L-18-264, Cycle 21 Core Operating Limits Report2018-11-16016 November 2018
Cycle 21 Core Operating Limits Report
L-18-119, Cycle 26 Core Operating Limits Report2018-05-21021 May 2018
Cycle 26 Core Operating Limits Report
L-17-344, Cycle 25-1 Core Operating Limits Report2017-11-28028 November 2017
Cycle 25-1 Core Operating Limits Report
L-17-071, Cycle 20 Core Operating Limits Report2017-06-0606 June 2017
Cycle 20 Core Operating Limits Report
L-16-302, Cycle 25 Core Operating Limits Report2016-10-14014 October 2016
Cycle 25 Core Operating Limits Report
L-16-048, Core Operating Limits Reports Midcycle Revision2016-02-11011 February 2016
Core Operating Limits Reports Midcycle Revision
L-15-376, Cycle 24-1 Core Operating Limits Report2015-12-28028 December 2015
Cycle 24-1 Core Operating Limits Report
L-15-304, Cycle 19, Core Operating Limits Report2015-10-29029 October 2015
Cycle 19, Core Operating Limits Report
L-15-162, Cycle 24 Core Operating Limits Report2015-05-14014 May 2015
Cycle 24 Core Operating Limits Report
L-14-389, Submittal of Core Operating Limits Report2014-12-11011 December 2014
Submittal of Core Operating Limits Report
L-14-141, Pressure and Temperature Limits Reports and Unit No. 2 Cycle 18 Core Operating Limits Report2014-05-12012 May 2014
Pressure and Temperature Limits Reports and Unit No. 2 Cycle 18 Core Operating Limits Report
L-13-329, Core Operating Limits Report, Cycle 232013-11-0404 November 2013
Core Operating Limits Report, Cycle 23
L-12-358, Submission of Core Operating Limits Report, Cycle 172012-10-29029 October 2012
Submission of Core Operating Limits Report, Cycle 17
L-12-181, Submittal of Core Operating Limits Report, Cycle 16-12012-06-11011 June 2012
Submittal of Core Operating Limits Report, Cycle 16-1
L-12-140, Core Operating Limits Report, Cycle 222012-05-0707 May 2012
Core Operating Limits Report, Cycle 22
L-10-301, Core Operating Limits Report, Cycle 212010-11-10010 November 2010
Core Operating Limits Report, Cycle 21
L-10-015, Core Operating Limits Report, Cycle 20 Revised2010-02-0101 February 2010
Core Operating Limits Report, Cycle 20 Revised
L-09-293, Submission of the Core Operating Limits Report, Cycle 152009-11-0606 November 2009
Submission of the Core Operating Limits Report, Cycle 15
L-09-214, Submittal of the Core Operating Limits Report, Cycle 14-12009-08-20020 August 2009
Submittal of the Core Operating Limits Report, Cycle 14-1
L-09-112, Submittal of Core Operating Limits Report, Cycle 202009-05-12012 May 2009
Submittal of Core Operating Limits Report, Cycle 20
L-08-163, Transmittal of Revision to the Core Operating Limits Report, Cycle 142008-05-0808 May 2008
Transmittal of Revision to the Core Operating Limits Report, Cycle 14
L-07-137, Core Operating Limits Report, COLR 19 and COLR 19-12007-10-25025 October 2007
Core Operating Limits Report, COLR 19 and COLR 19-1
L-07-087, Core Operating Limits Report, COLR 18-3, Rev 3 and COLR 13-2, Rev 2, Pressure and Temperature Limits Report2007-06-25025 June 2007
Core Operating Limits Report, COLR 18-3, Rev 3 and COLR 13-2, Rev 2, Pressure and Temperature Limits Report
L-06-155, Core Operating Limits Report, Revision 132006-11-0606 November 2006
Core Operating Limits Report, Revision 13
L-06-062, Cycle 18 Core Operating Limits Report2006-04-14014 April 2006
Cycle 18 Core Operating Limits Report
L-07-043, Cycle 18-2 and Unit 2, Cycle 13-1 Core Operating Limits Mid-Cycle Revision Updates2006-03-26026 March 2006
Cycle 18-2 and Unit 2, Cycle 13-1 Core Operating Limits Mid-Cycle Revision Updates
L-05-117, Cycle 17 Core Operating Limits Report Mid-Cycle Revision2005-07-11011 July 2005
Cycle 17 Core Operating Limits Report Mid-Cycle Revision
L-05-081, Cycle 12 Reload and Core Operating Limits Report2005-04-22022 April 2005
Cycle 12 Reload and Core Operating Limits Report
L-04-147, Cycle 17 Reload and Core Operating Limits Report2004-11-0505 November 2004
Cycle 17 Reload and Core Operating Limits Report
L-03-158, Cycle 11 Reload and Core Operating Limits Report2003-10-0909 October 2003
Cycle 11 Reload and Core Operating Limits Report
L-03-051, Cycle 16 Reload and Core Operating Limits Report2003-04-17017 April 2003
Cycle 16 Reload and Core Operating Limits Report
L-02-079, Mid-Cycle Core Operating Limits Report Revision2002-07-31031 July 2002
Mid-Cycle Core Operating Limits Report Revision
2023-05-17
[Table view]
Category:Letter type:L
MONTHYEARL-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023
Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615
L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023
Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports
L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023
L-23-208, Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA00256152023-09-14014 September 2023
Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA0025615
L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report2023-09-13013 September 2023
Twenty-Third Refueling Outage Inservice Inspection Summary Report
L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023
Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023
Quality Assurance Program Manual
L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023
Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
L-23-179, Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-07-18018 July 2023
Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA0025615
L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report2023-06-13013 June 2023
Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report
L-23-055, Submittal of the Updated Final Safety Analysis Report, Revision 342023-05-23023 May 2023
Submittal of the Updated Final Safety Analysis Report, Revision 34
L-23-065, Annual Financial Report2023-05-22022 May 2023
Annual Financial Report
L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023
Cycle 24 Core Operating Limits Report
L-23-132, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-10010 May 2023
Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations
L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations2023-05-0505 May 2023
Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations
L-23-115, Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological2023-04-27027 April 2023
Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological
L-23-126, Discharge Monitoring Report (Npdes), Permit No. PA00256152023-04-22022 April 2023
Discharge Monitoring Report (Npdes), Permit No. PA0025615
L-23-053, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-04-14014 April 2023
2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023
Submittal of the Decommissioning Funding Status Reports
L-23-058, 180-Day Steam Generator Tube Inspection Report2023-03-27027 March 2023
180-Day Steam Generator Tube Inspection Report
L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023
Annual Notification of Property Insurance Coverage
L-23-036, Report of Facility Changes, Tests and Experiments2023-03-13013 March 2023
Report of Facility Changes, Tests and Experiments
L-23-086, Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0404 March 2023
Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair
L-23-087, Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027)2023-03-0404 March 2023
Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027)
L-23-073, Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0101 March 2023
Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair
L-23-016, Twenty-Eighth Refueling Outage Inservice Inspection Summary Report2023-02-21021 February 2023
Twenty-Eighth Refueling Outage Inservice Inspection Summary Report
L-23-064, Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-02-21021 February 2023
Discharge Monitoring Report, (NPDES) Permit No. PA0025615
L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023
Energy Harbor Nuclear Corp Retrospective Premium Guarantee
L-22-193, Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H2023-02-14014 February 2023
Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H
L-22-286, Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time2023-02-14014 February 2023
Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
L-23-032, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Second Half of 20222023-01-23023 January 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Second Half of 2022
L-22-281, Discharge Monitoring Report (NPDES) Permit No. PA00256152022-12-16016 December 2022
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-22-246, Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO2022-12-0707 December 2022
Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO
L-22-217, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-11-21021 November 2022
Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-22-226, Emergency Preparedness Plan2022-11-0404 November 2022
Emergency Preparedness Plan
L-22-222, Cycle 29-1 Core Operating Limits Report2022-10-31031 October 2022
Cycle 29-1 Core Operating Limits Report
L-22-228, Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2022-10-26026 October 2022
Independent Spent Fuel Storage Installation Changes, Tests, and Experiments
L-22-200, Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage2022-10-21021 October 2022
Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage
L-22-232, Withdrawal of a License Amendment Request Associated with Fire Protection Program Changes2022-10-21021 October 2022
Withdrawal of a License Amendment Request Associated with Fire Protection Program Changes
L-22-238, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-10-20020 October 2022
Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-22-227, Revised August 2022 Outfall 003 & 004 NPDES Discharge Monitoring Report (Dmr), Revised Daily Effluent Monitoring Report Forms for Outfalls 003 & 004 and Corrective Action Letter from Eurofins2022-10-0303 October 2022
Revised August 2022 Outfall 003 & 004 NPDES Discharge Monitoring Report (Dmr), Revised Daily Effluent Monitoring Report Forms for Outfalls 003 & 004 and Corrective Action Letter from Eurofins
L-22-219, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-09-26026 September 2022
Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-22-204, Submittal of Evacuation Time Estimates2022-09-0707 September 2022
Submittal of Evacuation Time Estimates
L-22-137, Request for Fire Protection Program Changes2022-09-0606 September 2022
Request for Fire Protection Program Changes
L-21-238, License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident2022-08-31031 August 2022
License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident
L-22-188, Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage2022-08-22022 August 2022
Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage
L-22-191, Spent Fuel Storage Cask Registration2022-08-17017 August 2022
Spent Fuel Storage Cask Registration
2023-09-14
[Table view] |
Text
FENOC FirstEnergy Nuclear Operating Company James H. Lasjh 724-682-5234 Site Vice President Fax: 724-643-8069 April iZ- 2006 L-06-062 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Cycle 18 Core Operating Limits Report Beaver Valley Power Station, Unit No. 1 completed the seventeenth cycle of operation on February 13, 2006. This letter provides a copy of the Cycle 18 Core Operating Limits Report (COLR) in accordance with Technical Specification 6.9.5.d.
This revision of the COLR includes changes due to the Cycle 18 reload design and changes due to four Unit No. 1 license amendments implemented during the Spring 2006 refueling outage. These license amendments are 271 (Containment Conversion), 272 (Best Estimate LOCA), both of which were issued on February 6, 2006, 273 (Replacement Steam Generators) which was issued on February 9, 2006, and 274 (Relaxed Axial Offset Control) which was issued on February 27, 2006.
The Cycle 18 COLR is being submitted in accordance with Technical Specification 6.9.5.d. The COLR has been updated for this cycle by incorporating the changes related to license amendments 271, 272, 273 and 274, as well as the reload-specific axial flux difference limits and FQ Surveillance W(Z) factors associated with the Relaxed Axial Offset Control License Amendment.
No new regulatory commitments are contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Gregory A. Dunn, Manager, FENOC Fleet Licensing, at (330) 315-7243.
Sincerely, ames H. Lash
Beaver Valley Power Station, Unit No. 1 Unit 1 Cycle 18 Reload and Core Operating Limits Report L-06-062 Page 2
Enclosure:
Beaver Valley Power Station Unit No. 1 Cycle 18 Core Operating Limits Report c: Mr. T. G. Colburn, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Senior Resident Inspector Mr. S. J. Collins, NRC Region I Administrator Mr. D. A. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)
Beaver Valley Power Station Unit No.1 Cycle 18 Core Operating Limits Report
BVPS-I LICENSING REQUIREMENTS MANUAL 4.1 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 6.9.5.
Specification 3.1.3.5 Shutdown Rod Insertion Limits The shutdown rods shall be withdrawn to at least 225 steps.*
Specification 3.1.3.6 Control Rod Insertion Limits Control Banks A and B shall be withdrawn to at least 225 steps.*
Control Banks C and D shall be limited in physical insertion as shown in Figure 4.1-1.*
Specification 3.2.1 Axial Flux Difference The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 4.1-2.
Specification 3.2.2 Heat Flux Hot Channel Factor - Fp(Z) Limits The Eleat Flux Hot Channel Factor - FQ(Z) limit is defined by:
FQ(Z) < [CFQ
- K(Z) for P > 0.5 FQ(Z) <ICFQ *K(Z) for P < 0.5
[ 0.5 J Where: CFQ = 2.40 P THERMAL POWER RATED THERMAL POWER K(Z) = the function obtained from Figure 4.1-3.
F (Z) = FM (Z)
FQ (Z) = F (Z)
The W(Z) values are provided in Table 4.1-1.
The FQ(Z) penalty function, applied when the analytic FQ(Z) function increases from one monthly measurement to the next, is provided in Table 4.1-2.
- As indicated by the group demand counter BEAVER VALLEY- UNIT 1 4.1-1 COLR 18 Revision 51
BVPS-1 LICENSING REQUIREMENTS MANUAL Specification 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor FNAH I FNAAH: CFAH * ( + PFH (I-P))
Where: CFAH = 1.62 PFH = 0.3 P= THERMAL POWER RATED THERMAL POWER BEAVER VALLEY - UNIT 1 4.1-2 COLR 1;3 Revision 51
BVPS-I LICENSING REQUIREMENTS MANUAL 200 150 I-.
100 50 0
0 20 40 60 80 100 Relative Power (Percent)
FIGURE 4.1-1 CONTROL ROD INSERTION LIMITS BEAVER VALLEY - UNIT I 4.1-3 COLR 1.3 Revision 51
BVPS-1 LICENSING REQUIREMENTS MANUAL 120
- I I1~ -1 11- !f 110 100 I I
(-14, 10)(+10, I I 100)
UNACCEPTABLE I - l lUNACCEPTABLE 90 OPERATION PERATION 80 70 N ACCEPTABLE l lOPERAIN L
zI1 60
_ lI I 1 \____
50
(-31,50) (2,0 40 I II_ I II I I I 3(0 2(1
_ II 1( __ 1 lH I _T I ___
c _ _ _ I I - -1 - _ _
-60 -40 -20 0 20 40 6(
Axial Flux Difference (Delta 1)%
FIGURE 4.1-2 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RATED THERMAL POWER FOR RAOC I BEAVE:R VALLEY - UNIT 1 4.1-4 COLR 1.3 Revision 51
BVPS-1 LICENSING REQUIREMENTS MANUAL 1.2 1.0 0.8 9 0.6 0.4 0.2 0.0 C0 2 4 6 8 10 12 Core Height (feet)
FIGURE 4.1-3 FQT NORMALIZED OPERATING ENVELOPE, K(Z)
BEAVER VALLEY - UNIT 1 4.1-5 COLR 1.3 Revision 51
BVPS-I LICENSING REQUIREMENTS MANUAL Specification 3.3.1.1 Reactor Trip System Instrumentation Setpoints, Table 3.3-1 Table Notations A and B Overtemperature AT Setpoint Parameter Values:
Parameter Value Overtemperature AT reactor trip setpoint KI < 1.242 Overtemperature AT reactor trip setpoint Tavg coefficient K2 2 0.0 183/ 0 F Overtemperature AT reactor trip setpoint pressure coefficient K3 2 0.001/psia Tavg at RATED THERMAL POWER T' < 580.OOF(I)
Nominal Pressurizer Pressure P' 22250 psia Measured reactor vessel average temperature lead/lag time constants T, 2 30 secs T2 < 4 secs Measured reactor vessel AT lag time constant r4 < 6 secs Measured reactor vessel average temperature lag time constant rs < 2 secs 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 percent and +15 percent, 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).
(ii) for each percent that the magnitude of (qt - qb) exceeds -37 percent, the AT trip setpoint shall be automatically reduced by 2.52 percent of its value at RATED THERMAL POWER.
(iii) For each percent that the magnitude of (qt - qb) exceeds +15 percent, the AT trip setpoint shall be automatically reduced by 1.47 percent of its value at RATED THERMAL POWER.
(1) T' represents the cycle-specific Full Power Tavg value used in core design (576.2 °F).
BEAVER VALLEY- UNIT 1 4.1-6 COLR 13 Revision 51
BVPS-1 LICENSING REQUIREMENTS MANUAL Overpower AT Setpoint Parameter Values:
Parameter Value Overpower AT reactor trip setpoint K4 < 1.085 I Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 2 0.02/0 F for increasing average temperature K5=0/0 F for decreasing average temperature I Overpower AT reactor trip setpoint Tavg heatup coefficient K6 2 0.0021/ 0 F for I T>T" K6 = 0/0 F for T < T" Tavg at RATED THERMAL POWER T" < 580.OOF(I)
Measured reactor vessel average temperature rate/lag time constant T3 2 10 secs Measured reactor vessel AT lag time constant ¶4 < 6 secs Il Measured reactor vessel average temperature lag time constant T5 < 2 secs Specification 3.2.5 DNB Parameters Parameter Indicated Value Reactor Coolant System Tavg Tavg < 583.60F( 2 ) I Pressurizer Pressure Pressure 2 2218 psia(3)
Reactor Coolant System Total Flow Rate Flow > 267,300 gpm(4)
(1) T" represents the cycle-specific Full Power Tavg value used in core design (576.2 °F). I (2) The Reactor Coolant System (RCS) Tavg value includes allowances for rod control operation and I verification via control board indication.
(3) The pressurizer pressure value includes allowances for pressurizer pressure control operation and I verification via control board indication.
(4) Th - RCS total flow rate includes allowances for normalization of the cold leg elbow taps wilh a I beginning of cycle precision RCS flow calorimetric measurement and verification on a periodic basis via control board indication.
BEAVER VALLEY - UNIT 1 4.1-7 COLR 13 Revision 51
BVPS-1 LICENSING REQUIREMENTS MANUAL on 0 0.2 0.4 0.6 0.8 1 1.2 .1.4 FRACTION OF RATED THERMAL POWER Figure 4.1-5 REACTOR CORE SAFETY LIMIT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1)
BEAVER VALLEY - UNIT 1 4.1-8 48COLR 1'3 Revision 51
BVPS-1 LICENSING REQUIREMENTS MANUAL Table 4.1-1 (Page 1 of 2)
FQ Surveillance W(Z) Function versus Burnup Exclusion Axial Elevation 150 3000 10000 16000 Zone Point (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTUJ
- 1 12.00 1.0000 1.0000 1.0000 1.0000
- 2 11.80 1.0000 1.0000 1.0000 1.0000
- 3 11.60 1.0000 1.0000 1.0000 1.0000
- 4 11.40 1.0000 1.0000 1.0000 1.0000
- 5 11.20 1.0000 1.0000 1.0000 1.0000
_ 6 11.00 1.0000 1.0000 1.0000 1.0000
- 7 10.80 1.0000 1.0000 1.0000 1.0000
- 8 10.60 1.0000 1.0000 1.0000 1.0000
- 9 10.40 1.0000 1.0000 1.0000 1.0000 10 10.20 1.2273 1.2990 1.2429 1.2529 11 10.00 1.2153 1.2811 1.2330 1.2252 12 9.80 1.2026 1.2736 1.2223 1.2088 13 9.60 1.1891 1.2688 1.2104 1.2014 14 9.40 1.1772 1.2630 1.2001 1.1940 15 9.20 1.1738 1.2536 1.1937 1.1945 16 9.00 1.1824 1.2416 1.1912 1.2163 17 8.80 1.1923 1.2424 1.1984 1.2353 18 8.60 1.2001 1.2507 1.2127 1.2504 19 8.40 1.2056 1.2584 1.2269 1.2637 20 8.20 1.2091 1.2624 1.2375 1.2742 21 8.00 1.2104 1.2637 1.2454 1.2819 22 7.80 1.2097 1.2622 1.2505 1.2868
= 23 7.60 1.2069 1.2580 1.2528 1.2889
= 24 7.40 1.2026 1.2514 1.2525 1.2883 25 7.20 1.1977 1.2426 1.2497 1.2849 26 7.00 1.1930 1.2316 1.2444 1.2789 27 6.80 1.1869 1.2187 1.2369 1.2735
= 28 6.60 1.1791 1.2040 1.2272 1.2673 29 6.40 1.1700 1.1879 1.2156 1.2581 30 6.20 1.1597 1.1706 1.2022 1.2467 Note: Top and Bottom 15% Excluded BEAVER VALLEY - UNIT 1 4.1-9 COLR 1'3 Revision 51
BVPS-1 LICENSING REQUIREMENTS MANUAL Table 4.1-1 (Page 2 of 2)
FQ Surveillance W(Z) Function versus Burnup Exclusion Axial Elevation 150 3000 10000 16000 Zone Point (feet) MWD/MTU MWD/MTITU MWD/MTU MWD/MTU 31 6.00 1.1480 1.1509 1.1871 1.2333 32 5.80 1.1371 1.1359 1.1713 1.2174 33 5.60 1.1310 1.1246 1.1565 1.2015 34 5.40 1.1295 1.1142 1.1458 1.1880 35 5.20 1.1363 1.1140 1.1434 1.1752 36 5.00 1.1436 1.1174 1.1421 1.1728 37 4.80 1.1495 - 1.1224 1.1389 1.1726 38 4.60 1.1551 1.1265 1.1364 1.1704 39 4.40 1.1601 1.1302 1.1363 1.1677 40 4.20 1.1645 1.1334 1.1364 1.1642 41 4.00 1.1683 1.1361 1.1361 1.1594 42 3.80 1.1716 1.1385 1.1355 1.1555 43 3.60 1.1743 1.1404 1.1347 1.1547 44 3.40 1.1769 1.1417 1.1344 1.1559 45 3.20 1.1806 1.1465 1.1377 1.1571 46 3.00 1.1929 1.1589 1.1494 1.1592 47 2.80 1.2141 1.1779 1.1676 1.1671 48 2.60 1.2367 1.1989 1.1881 1.1833 49 2.40 1.2596 1.2228 1.2084 1.2002 50 2.20 1.2823 1.2471 1.2282 1.2168 51 2.00 1.3047 1.2706 1.2475 1.2332 52 1.80 1.3265 1.2935 1.2660 1.2491
- 53 1.60 1.0000 1.0000 1.0000 1.0000
- 54 1.40 1.0000 1.0000 1.0000 1.0000
= 55 1.20 1.0000 1.0000 1.0000 1.0000 56 1.00 1.0000 1.0000 1.0000 1.0000
= 57 0.80 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 15% Excluded BEAVER VALLEY - UNIT I 4.1-10 COLR 18 Revision 51
C I
BVPS-1 LICENSING REQUIREMENTS MANUAL Table 4.1-2 FQ(Z) Penalty Factor versus Bumup Cycle Burnup FQ(Z)
(MT'D/MTU) Penalty Factor All Burnups 1.02 Note: The Penalty Factor, to be applied to FQ(Z) in accordance with Technical Specification Surveillance Requirement 4.2.2.3, 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 Surveillance Requirement 4.0.2) starting from the burnup at which the FQ(Z) was determined.
BEAVER VALLEY - UNIT 1 4.1-11 COLR 18 Revision 5:1