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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
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FENOC FirstEnergyNuclear Operating Company PeterP. Sena III 724-682-5234 Site Vice President Fax: 724-643-8069 May 12, 2009 L-09-112 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 Operatingq Limits Report, Cycle 20 FirstEnergy Nuclear Operating Company (FENOC) hereby submits a revision of the Core Operating Limits Report (COLR) for Beaver Valley Power Station (BVPS) Unit No. 1 as required by Section 5.6.3 of the BVPS Technical Specifications. The BVPS Unit No. 1 COLR 20, made effective on April 27, 2009, is enclosed.
No regulatory commitments are contained in this submittal. If there are questions, or additional information is required, please contact Mr. Thomas A. Lentz, Manager -
FENOC Fleet Licensing, at 330-761-6071.
Sinc Peter P. Sena III
Enclosure:
Beaver Valley Power Station Unit No. 1 Core Operating Limits Report, COLR 20 cc: NRC Region I Administrator NRC Senior Resident Inspector NRR Project Manager Director BRP/DEP Site BRP/DEP Representative 4oo0
L-09-112 Enclosure Beaver Valley Power Station Unit No. 1 Core Operating Limits Report COLR 20
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 _Ž1.77% Ak/k.(1)
- b. Prior to manually blocking the Low Pressurizer Pressure Safety Injection Signal, the Reactor Coolant System shall be borated to > the MODE 5 boron concentration and shall remain _> this boron concentration at all times when this signal is blocked.
- c. In MODE 5, SHUTDOWN MARGIN shall be _Ž1.0% Ak/k.
5.1.3 LCO 3.1.3 Moderator Temperature Coefficient (MTC)
- a. Upper Limit - MTC shall be maintained within the acceptable operation limit specified in Technical Specification Figure 3.1.3-1.
- b. Lower Limit - MTC shall be maintained less negative than - 4.4 x 10-4 Ak/k/°F at RATED THERMAL POWER.
- c. 300 ppm Surveillance Limit: (- 37 pcm/°F)
- d. 60 ppm Surveillance Limit: (- 43 pcm/°F) 5.1.4 LCO 3.1.5 Shutdown Bank Insertion Limits The Shutdown Banks shall be withdrawn to at least 225 steps.(2) 5.1.5 LCO 3.1.6 Control Bank Insertion Limits
- a. Control Banks A and B shall be withdrawn to at least 225 steps.(2)
- b. Control Banks C and D shall be limited in physical insertion as shown in Figure 5.1-2.(2)
- c. Sequence Limits - The sequence of withdrawal shall be A, B, C and D bank, in that order.
- d. Overlap Limits(2) - Overlap shall be such that step 129 on banks A, B, and C corresponds to step 1 on the following bank. When C bank is fully withdrawn, these limits are verified by confirming D bank is withdrawn at least to a position equal to the all-rods-out position minus 128 steps.
(1) The MODE 1 and MODE 2 with keff > 1.0 SDM requirements are included to address SDM requirements (e.g., MODE 1 Required Actions to verify SDM) that are not within the applicability of LCO 3.1.1, SHUTDOWN MARGIN (SDM).
(2) As indicated by the group demand counter COLR Cycle 20 Beaver Valley Unit 1 5.1 - 1 LRM Revision 67
5.censing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.6 LCO 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))
The Heat Flux Hot Channel Factor - FQ(Z) limit is defined by:
FQ (Z)
- CFQ]*KZ) for P > 0.5 FQ (Z) _ - K(Z) forP* 0.5 L 0.54 K THERMAL POWER Where: CFQ = 2.40 RATED THERMAL POWER K(Z) = the function obtained from Figure 5.1-3.
C =M FQ(Z) FQ(Z) - 1.0815 FI Q(Z) = F(Z)
The W(Z) values are provided in Table 5.1-1.
The FQ(Z) penalty function, applied when the analytic FQ(Z) function increases from one monthly measurement to the next, is provided in Table 5.1-2.
5.1.7 LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor( FNH)
FAH CFAH * (1 + PFAH (1-P))
Where: CFAH = 1.62 PFAH = 0.3 THERMAL POWER
= RATED THERMAL POWER COLR Cycle 20 Beaver Valley Unit 1 5.1 -2 LRM Revision 67
51icensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.8 LCO 3.2.3 Axial Flux Difference (AFD)
The AFD acceptable operation limits are provided in Figure 5.1-4.
5.1.9 LCO 3.3.1 Reactor Trip System Instrumentation - Overtemperature and Overoower AT Parameter Values from Table Notations 1 and 2
- a. Overtemperature AT Setpoint Parameter Values:
Parameter Value Overtemperature AT reactor trip setpoint K1 *1.242 Overtemperature AT reactor trip setpoint Tavg K2 _ 0.0183/°F coefficient Overtemperature AT reactor trip setpoint pressure K3 _ 0.001/psia coefficient Tavg at RATED THERMAL POWER T'<* 577.9°F(l)
Nominal pressurizer pressure P' > 2250 psia Measured reactor vessel average temperature lead/lag -ul _>30 secs time constants T2 *! 4 secs Measured reactor vessel AT lag time constant T4 - 6 secs Measured reactor vessel average temperature lag t5 - 2 secs time constant f (Al) is a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:
(i) For qt - qb between -37% and +15%, f(AI) = 0 (where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POWER in percent of RATED THERMAL POWER).
(1) T' represents the cycle-specific Full Power Tavg value used in core design.
COLR Cycle 20 Beaver Valley Unit 1 5.1 -3 LRM Revision 67
.Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report (ii) For each percent that the magnitude of (qt - qb) exceeds -37%, the AT trip setpoint shall be automatically reduced by 2.52% of its value at RATED THERMAL POWER.
(iii) For each percent that the magnitude of (qt - qb) exceeds +15%, the AT trip setpoint shall be automatically reduced by 1.47% of its value at RATED THERMAL POWER.
- b. Overpower AT Setpoint Parameter Values:
Parameter Value Overpower AT reactor trip setpoint K4
- 1.085 Overpower AT reactor trip setpoint Tavg K5 > 0.02/°F for increasing rate/lag coefficient average temperature K5 = 0/°F for decreasing average temperature Overpower AT reactor trip setpoint Tavg K6 _ 0.0021/OF for T > T" heatup coefficient K6 = 0/°F for T*< T" 2
)
Tavg at RATED THERMAL POWER T"<* 577.90F(
Measured reactor vessel average 13 Ž10 secs temperature rate/lag time constant Measured reactor vessel AT lag time 'r 4 6 secs constant Measured reactor vessel average T5
- 2 secs temperature lag time constant (2) T" represents the cycle-specific Full Power Tavg value used in core design.
COLR Cycle 20 Beaver Valley Unit 1 5.1 -4 LRM Revision 67
,Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.10 LCO 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boilingq (DNB) Limits Parameter Indicated Value Reactor Coolant System Tavg Tavg _<581.50F(l)
Pressurizer Pressure Pressure > 2218 psia(2)
Reactor Coolant System Total Flow Rate Flow > 267,300 gpm(3)
(1) The Reactor Coolant System (RCS) indicated Tavg value is determined by adding the appropriate allowances for rod control operation and verification via control board indication (3.6 0 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.
COLR Cycle 20 Beaver Valley Unit 1 5.1 -5 LRM Revision 67
ýLicensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.11 LCO 3.9.1 Boron Concentration (MODE 6)
The boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained > 2400 ppm. This value includes a 50 ppm conservative allowance for uncertainties.
COLR Cycle 20 Beaver Valley Unit 1 5.1 -6 LRM Revision 67
.Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.12 References
- 1. WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1985 (Westinghouse Proprietary).
- 2. WCAP-8745-P-A, "Design Bases for the Thermal Overtemperature AT and Thermal Overpower AT Trip Functions," September 1986.
- 3. WCAP-1 2945-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-FQ Surveillance Technical Specification," February 1994.
- 5. WCAP-14565-P-A, "VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis,"
October 1999.
- 6. WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report,"
April 1.995 (Westinghouse Proprietary).
- 7. WCAP-1 5025-P-A, "Modified WRB-2 Correlation, WRB-2M, for Predicating Critical Heat Flux in 17x17 Rod Bundles with Modified LPD Mixing Vane Grids," April 1999.
- 8. Caldon, Inc. Engineering Report-80P, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM4TM System," Revision 0, March 1997.
- 9. Caldon, Inc. Engineering Report-160P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFMVTM System," Revision 0, May 2000.
COLR Cycle 20 Beaver Valley Unit 1 5.1 -7 LRM Revision 67
,Licensing Requirements Manual Core Operating Limits Report 5.1 670 660 650 640
'-' 630 H.:{ 620 610 600 590 580 0 0.2 0.4 0.6 0.8 1 1.2 1.4 FRACTION OF RATED THERMAL POWER Figure 5.1-1 (Page 1 of 1)
REACTOR CORE SAFETY LIMIT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1)
COLR Cycle 20 Beaver Valley Unit 1 5.1 -8 LRM Revision 67
'Licensing Requirements Manual Core Operating Limits Report 5.1 200 150 /
I I _
100 - _
50 0-0 20 40 60 80 100 Relative Power (Percent)
Figure 5.1-2 (Page 1 of 1)
CONTROL ROD INSERTION LIMITS COLR Cycle 20 Beaver Valley Unit 1 5.1 -9 LRM Revision 67
,Licensing Requirements Manual Core Operating Limits Report 5.1 1.2 1.1 0.8 0.6 0.4 0.2 0.0 0 2 4 6 8 10 12 Core Height (feet)
Figure 5.1-3 (Page 1 of 1)
FQT NORMALIZED OPERATING ENVELOPE, K(Z)
COLR Cycle 20 Beaver Valley Unit 1 5.1 -10 LRM Revision 67
.Licensing Requirements Manual Core Operating Limits Report 5.1 120 110 100 90 80 70 08 F- '60 I--
0 50 10 40 30 20 10 0
-60 -40 -20 0 20 40 60 Axial Flux Difference (Delta 1)%
Figure 5.1-4 (Page 1 of 1)
AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RATED THERMAL POWER FOR RAOC COLR Cycle 20 Beaver Valley Unit 1 5.1 -11 LRM Revision 67
'Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-1 (Page 1 of 2)
FQ Surveillance W(Z) Function versus Burnup Exclusion Axial Elevation 150 3000 10000 18000 Zone Point (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU
- 1 12.0 1.0000 1.0000 1.0000 1.0000
- 2 11.8 1.0000 1.0000 1.0000 1.0000
- 3 11.6 1.0000 1.0000 1.0000 1.0000
- 4 11.4 1.0000 1.0000 1.0000 1.0000
- 5 11.2 1.0000 1.0000 1.0000 1.0000
- 6 11.0 1.0000 1.0000 1.0000 1.0000
- 7 10.8 1.0000 1.0000 1.0000 1.0000 8 10.6 1.1667 1.2047 1.2410 1.2484 9 10.4 1.1574 1.1944 1.2334 1.2244 10 10.2 1.1466 1.1813 1.2244 1.1976 11 10.0 1.1389 1.1695 1.2153 1.1760 12 9.8 1.1421 1.1634 1.2054 1.1751 13 9.6 1.1402 1.1571 1.1975 1.1768 14 9.4 1.1350 1.1494 1.1941 1.1771 15 9.2 1.1302 1.1411 1.1912 1.1794 16 9.0 1.1243 1.1345 1.1867 1.1962 17 8.8 1.1331 1.1432 1.1951 1.2104 18 8.6 1.1467 1.1560 1.2089 1.2226 19 8.4 1.1574 1.1652 1.2204 1.2351 20 8.2 1.1663 1.1727 1.2293 1.2466 21 8.0 1.1731 1.1780 1.2355 1.2554 22 7.8 1.1778 1.1811 1.2391 1.2615 23 7.6 1.1804 1.1821 1.2400 1.2649 24 7.4 1.1811 1.1811 1.2384 1.2658 25 7.2 1.1800 1.1784 1.2346 1.2643 26 7.0 1.1775 1.1742 1.2288 1.2603 27 6.8 1.1735 1.1685 1.2211 1.2571 28 6.6 1.1682 1.1616 1.2117 1.2536 29 6.4 1.1615 1.1534 1.2005 1.2473 30 6.2 1.1536 1.1440 1.1878 1.2389 31 6.0 1.1449 1.1337 1.1733 1.2284 32 5.8 1.1336 1.1211 1.1583 1.2158 Note: Top and Bottom 10% Excluded COLR Cycle 20 Beaver Valley Unit 1 5.1 -12 LRM Revision 67
. Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-1 (Page 2 of 2)
FQ Surveillance W(Z) Function versus Burnup Exclusion Axial Elevation 150 3000 10000 18000 Zone Point (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 33 5.6 1.1265 1.1134 1.1442 1.2018 34 5.4 1.1266 1.1136 1.1323 1.1884 35 5.2 1.1326 1.1204 1.1242 1.1768 36 5.0 1.1404 1.1272 1.1207 1.1656 37 4.8 1.1480 1.1329 1.1186 1.1586 38 4.6 1.1548 1.1383 1.1150 1.1556 39 4.4 1.1611 1.1431 1.1115 1.1507 40 4.2 1.1667 1.1473 1.1111 1.1450 41 4.0 1.1717 1.1510 1.1112 1.1388 42 3.8 1.1761 1.1543 1.1124 1.1318 43 3.6 1.1800 1.1570 1.1154 1.1246 44 3.4 1.1834 1.1593 1.1186 1.1175 45 3.2 1.1861 1.1640 1.1217 1.1087 46 3.0 1.1899 1.1761 1.1238 1.1128 47 2.8 1.2020 1.1934 1.1314 1.1298 48 2.6 1.2259 1.2097 1.1505 1.1444 49 2.4 1.2494 1.2266 1.1692 1.1594 50 2.2 1.2720 1.2448 1.1872 1.1745 51 2.0 1.2945 1.2631 1.2052 1.1893 52 1.8 1.3160 1.2805 1.2224 1.2037 53 1.6 1.3362 1.2970 1.2387 1.2178 54 1.4 1.3545 1.3119 1.2537 1.2313
- 55 1.2 1.0000 1.0000 1.0000 1.0000
- 56 1.0 1.0000 1.0000 1.0000 1.0000
- 57 0.8 1.0000 1.0000 1.0000 1.0000
- 58 0.6 1.0000 1.0000 1.0000 1.0000
- 59 0.4 1.0000 1.0000 1.0000 1.0000
- 60 0.2 1.0000 1.0000 1.0000 1.0000
- 61 0.0 1.0000 1.0000 1.0000 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 20 Beaver Valley Unit 1 5.1 - 13 LRM Revision 67
Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-2 (Page 1 of 1)
FQ(Z) Penalty Factor versus Burnup Cycle Burnup (MWD/MTU) F0 (Z) Penalty Factor 0 to 1350 1.0321
> 1350 1.02 Note: The Penalty Factor, to be applied to FQ(Z) in accordance with Technical Specification Surveillance Requirement (SR) 3.2.1.2, is the maximum factor by which FQ(Z) is expected to increase over a 39 Effective Full Power Day (EFPD) interval (surveillance interval of 31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance interval per Technical Specification SR 3.0.2) starting from the burnup at which the FQ(Z) was determined.
COLR Cycle 20 Beaver Valley Unit 1 5.1 -14 LRM Revision 67