|
---|
Category:Fuel Cycle Reload Report
MONTHYEARL-2023-048, Core Operating Limits Report (COLR) Cycle 40 (U2C40)2023-03-18018 March 2023 Core Operating Limits Report (COLR) Cycle 40 (U2C40) NRC 2021-0012, Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41)2022-04-0707 April 2022 Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41) NRC 2021-0046, Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40)2021-10-28028 October 2021 Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40) NRC 2020-0039, Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40)2020-11-0202 November 2020 Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40) NRC 2020-0007, Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38)2020-03-27027 March 2020 Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38) NRC 2019-0013, Core Operating Limits Report (COLR) Unit 1 Cycle 39 (U1C39)2019-04-12012 April 2019 Core Operating Limits Report (COLR) Unit 1 Cycle 39 (U1C39) NRC 2018-0051, Core Operating Limits Report (COLR) Unit 2 Cycle 37 (U2C37)2018-11-0606 November 2018 Core Operating Limits Report (COLR) Unit 2 Cycle 37 (U2C37) NRC 2017-0056, Core Operating Limits Report (COLR) Cycle 38 (U1C38)2017-11-10010 November 2017 Core Operating Limits Report (COLR) Cycle 38 (U1C38) NRC 2017-0018, Core Operating Limits Report (COLR) Unit 2 Cycle 36 (U2C36)2017-04-14014 April 2017 Core Operating Limits Report (COLR) Unit 2 Cycle 36 (U2C36) NRC 2016-0011, Core Operating Limits Report (COLR) Cycle 37 (U1C37)2016-03-29029 March 2016 Core Operating Limits Report (COLR) Cycle 37 (U1C37) NRC 2015-0067, Core Operating Limits Report (COLR) Unit 2 Cycle 35 (U2C35) and Correction to Unit 1 Cycle 36 (U1C36)2015-11-0404 November 2015 Core Operating Limits Report (COLR) Unit 2 Cycle 35 (U2C35) and Correction to Unit 1 Cycle 36 (U1C36) NRC 2014-0070, Core Operating Limits Report Cycle 36 (U1C36)2014-10-30030 October 2014 Core Operating Limits Report Cycle 36 (U1C36) NRC 2014-0028, Core Operating Limits Reports (COLR) Unit 2 Cycle 34 (U2C34)2014-04-11011 April 2014 Core Operating Limits Reports (COLR) Unit 2 Cycle 34 (U2C34) NRC 2013-0040, Core Operating Limits Report (COLR) Unit 1 Cycle 35 (U1C35)2013-04-18018 April 2013 Core Operating Limits Report (COLR) Unit 1 Cycle 35 (U1C35) NRC 2012-0108, Cycle 33 (U2C33) Core Operating Limits Report2012-11-27027 November 2012 Cycle 33 (U2C33) Core Operating Limits Report NRC 2011-0100, Transmittal of Core Operating Limits Report, Revision 132011-11-0202 November 2011 Transmittal of Core Operating Limits Report, Revision 13 NRC 2011-0075, Cycle 32 (U2C32) Core Operating Limits Report2011-08-0505 August 2011 Cycle 32 (U2C32) Core Operating Limits Report NRC 2011-0055, Units I and 2, Transmittal of Core Operating Limits and Pressure and Temperature Limits Reports2011-05-19019 May 2011 Units I and 2, Transmittal of Core Operating Limits and Pressure and Temperature Limits Reports NRC 2010-0041, Cycle 33 (U1C33) Core Operating Limits Report2010-03-22022 March 2010 Cycle 33 (U1C33) Core Operating Limits Report NRC 2009-0112, Cycle 31 (U2C31) Core Operating Limits Report2009-11-0202 November 2009 Cycle 31 (U2C31) Core Operating Limits Report NRC 2009-0052, Submittal of Cycle 32 (U1C32) Core Operating Limit Report2009-04-30030 April 2009 Submittal of Cycle 32 (U1C32) Core Operating Limit Report ML0830102312008-10-24024 October 2008 Cycle 32 (U1C32) Core Operating Limits Report. NRC 2008-0081, Point Beach, Unit 1, Cycle 32 (U1C32) Core Operating Limits Report.2008-10-24024 October 2008 Point Beach, Unit 1, Cycle 32 (U1C32) Core Operating Limits Report. NRC 2008-0020, Cycle 30 (U2C30) Core Operating Limits Report2008-04-24024 April 2008 Cycle 30 (U2C30) Core Operating Limits Report NRC 2007-0018, Cycle 31 (U1C31) Core Operating Limits Report2007-04-16016 April 2007 Cycle 31 (U1C31) Core Operating Limits Report NRC 2006-0079, Cycle 29 (U2C29) Core Operating Limits Report2006-11-10010 November 2006 Cycle 29 (U2C29) Core Operating Limits Report 2023-03-18
[Table view] Category:Letter type:NRC
MONTHYEARNRC 2023-0013, Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-07-0707 July 2023 Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations NRC 2023-0006, Post-Exam Submittal Cover Letter2023-03-0101 March 2023 Post-Exam Submittal Cover Letter NRC 2023-0005, Report of Changes to Emergency Plan2023-02-21021 February 2023 Report of Changes to Emergency Plan NRC 2022-0032, Sixth 10-Year Interval Inservice Testing (1ST) Program Plan2022-09-30030 September 2022 Sixth 10-Year Interval Inservice Testing (1ST) Program Plan NRC 2022-0025, License Amendment Request 295, Beacon Power Distribution Monitoring System2022-09-26026 September 2022 License Amendment Request 295, Beacon Power Distribution Monitoring System NRC 2022-0019, Report of Changes to Emergency Plan2022-07-13013 July 2022 Report of Changes to Emergency Plan NRC 2022-0022, Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2,2022-07-11011 July 2022 Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, NRC 2022-0015, Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report2022-04-27027 April 2022 Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report NRC 2022-0014, 2021 Annual Monitoring Report2022-04-14014 April 2022 2021 Annual Monitoring Report NRC 2021-0012, Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41)2022-04-0707 April 2022 Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41) NRC 2022-0003, License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process2022-03-25025 March 2022 License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process NRC 2022-0006, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2022-02-22022 February 2022 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections NRC 2022-0004, Report of Changes to Emergency Plan2022-02-0909 February 2022 Report of Changes to Emergency Plan NRC 2022-0005, Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2022-02-0101 February 2022 Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2022-0001, Report of Changes to Emergency Plan2022-01-11011 January 2022 Report of Changes to Emergency Plan NRC 2021-0046, Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40)2021-10-28028 October 2021 Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40) NRC 2021-0031, Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-0562021-07-15015 July 2021 Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-056 NRC 2021-0027, Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-0532021-06-30030 June 2021 Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-053 NRC 2021-0028, Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism2021-06-23023 June 2021 Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism NRC 2021-0021, 2020 Annual Monitoring Report2021-04-29029 April 2021 2020 Annual Monitoring Report NRC 2021-0019, Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations2021-04-22022 April 2021 Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations NRC-2021-0010, CFR 50.59 Evaluation and Commitment Change Summary Report2021-04-0202 April 2021 CFR 50.59 Evaluation and Commitment Change Summary Report NRC-2021-0011, Technical Specification Bases and Technical Requirement Manual Change Summary2021-04-0202 April 2021 Technical Specification Bases and Technical Requirement Manual Change Summary NRC 2021-0006, Report of Changes to Emergency Plan2021-03-18018 March 2021 Report of Changes to Emergency Plan NRC 2021-0005, Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-022021-02-11011 February 2021 Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-02 NRC 2021-0002, Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2021-01-21021 January 2021 Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report2021-01-21021 January 2021 Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report NRC 2021-0001, Report of Changes to Emergency Plan2021-01-13013 January 2021 Report of Changes to Emergency Plan NRC 2020-0044, Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise2020-12-0808 December 2020 Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise NRC 2020-0032, Application for Subsequent Renewed Facility Operating Licenses2020-11-16016 November 2020 Application for Subsequent Renewed Facility Operating Licenses NRC 2020-0039, Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40)2020-11-0202 November 2020 Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40) NRC 2020-0031, NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-0812020-10-0505 October 2020 NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-081 NRC 2020-0029, Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-09-15015 September 2020 Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0024, Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements2020-08-17017 August 2020 Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements NRC 2020-0020, License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-08-13013 August 2020 License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0023, NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations2020-08-12012 August 2020 NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations NRC 2020-0021, Response to NRC Inspection Report and Preliminary White Finding2020-08-12012 August 2020 Response to NRC Inspection Report and Preliminary White Finding NRC 2020-0018, Report of Changes to Emergency Plan2020-07-15015 July 2020 Report of Changes to Emergency Plan NRC-2020-0016, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-12012 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic NRC 2020-0012, Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2020-05-20020 May 2020 Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2020-0008, Report of Changes to Emergency Plan2020-04-0606 April 2020 Report of Changes to Emergency Plan NRC 2020-0007, Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38)2020-03-27027 March 2020 Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38) NRC 2020-0003, License Amendment Request 289: Tornado Missile Protection Licensing Basis2020-02-0606 February 2020 License Amendment Request 289: Tornado Missile Protection Licensing Basis NRC 2020-0001, Pressure Temperature Limits Report (PTLR)2020-01-0909 January 2020 Pressure Temperature Limits Report (PTLR) NRC 2019-0044, Report of Changes to Emergency Plan2019-11-0101 November 2019 Report of Changes to Emergency Plan NRC 2019-0036, Submittal of 2018 Update to Final Safety Analysis Report2019-10-18018 October 2019 Submittal of 2018 Update to Final Safety Analysis Report NRC 2019-0037, Technical Specification Bases Change Summary2019-10-18018 October 2019 Technical Specification Bases Change Summary NRC 2019-0034, Technical Requirements Manual Change Summary2019-10-18018 October 2019 Technical Requirements Manual Change Summary NRC 2019-0032, CFR 50.59 Evaluation and Commitment Change Summary Report2019-10-18018 October 2019 CFR 50.59 Evaluation and Commitment Change Summary Report NRC 2019-0042, NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information2019-10-17017 October 2019 NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information 2023-07-07
[Table view] |
Text
Committed to Nuclear Excellence Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC April 16,2007 NRC 2007-0018 10 CFR 50.36 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555 Point Beach Nuclear Plant Unit 1 Docket No. 50-266 License No. DPR-24 Unit 1 Cvcle 31 (U1C31) Core Oeeratina Limits Reeort In accordance with the requirements of Point Beach Nuclear Plant (PBNP)
Technical Specification 5.6.4, "Core Operating Limits Report (COLR),"
Nuclear Management Company, LLC (NMC), is submitting the Core Operating Limits Report for PBNP Unit 1 Cycle 31 (U1C31).
The PBNP U1C31 COLR was issued on April 13,2007.
This letter contains no new commitments and no revisions to existing commitments.
Dennis L. Koehl /
Site Vice-President, Point Beach Nuclear Plant Nuclear Management Company, LLC Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW 6610 Nuclear Road Two Rivers, Wisconsin 54241-9516 Telephone: 920.755.2321
ENCLOSURE CORE OPERATING LIMITS REPORT POINT BEACH NUCLEAR PLANT, UNIT 1 CYCLE 31 (UlC31)
TRM 2.1 CORE OPERATING LIMITS REPORT (COLR)
UNIT 1 CYCLE 3 1 REVISION 8
POINT BEACH NUCLEAR PLANT TRM2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 8 April 13,2007 CORE OPERATlNG LIMITS REPORT (COLR) 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Point Beach Nuclear Plant has been prepared in accordance with the requirements of Technical Specification (TS) 5.6.4.
A cross-reference between the COLR sections and the PBNP Technical Specifications affected by this report is given below:
COLR PBNP Description Section TS 2.1 2.1.1 Reactor Core Safety Limits 2.2 3.1.1 Shutdown Margin 3.1.4 Rod Group Alignment Limits 3.1.5 Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.1.8 Physics Test Exceptions 3.1.3 Moderator Temperature Coefficient 3.1.5 Shutdown Bank Insertion Limit Control Bank Insertion Limits Nuclear Heat Flux Hot Channel Factor (FQ(Z))
Nuclear Enthalpy Rise Hot Channel Factor ( F ~ ~ H )
Axial Flux Difference (AFD)
Overtemperature AT Setpoint Overpower AT Setpoint RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 2.12 Refueling Boron Concentration Figure 1 Reactor Core Safety Limits Curve Figure 2 Required Shutdown Margin Figure 3 Control Bank Insertion Limits I Figure 4 Hot Channel Factor Normalized Operating Envelope (K(Z)) for 0.422V+
Fuel I Figure 5 RAOC Summary of W(Z) with HFP AFD Band of -8/+9%
Figure 6 Flux Difference Operating Envelope Page 2 of 15
POINT BEACH NUCLEAR PLANT TRM2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 8 April 13,2007 CORE OPERATING LIMITS REPORT (COLR)
I UNIT 1 CYCLE 31 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section I .0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in Technical Specification 5.6.4.
2.1 Reactor Core Safety Limits (TS 2.1.1)
The combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in Figure 1.
Applicability: MODES 1 and 2 2.2.1 SDM shall be within the limits provided in Figure 2.
Applicability: MODES 1,2, and 3 2.2.2 SDM shall be 21 % AWk.
Applicability: MODES 4 and 5 2.3 Moderator Temperature Coefficient (TS 3.1.3) 2.3.1 The upper MTC limits shall be maintained within the limits.
2.3.2 The maximum upper MTC limits shall be:
1 5 pcmI0F for power levels 170% RTP 1 0 pcrnI0F for power levels >70% RTP Applicability: MODE 1 and MODE 2 with bff21 .O.
2.4 Shutdown Bank Insertion Limit (TS 3.1.5)
NOTE: This limit is not applicable while performing SR 3.1.4.2.
2.4.1 Each shutdown bank shall be fully withdrawn.
2.4.2 Fully withdrawn is defined as 2225 steps.
Applicability: MODES 1 and 2 Page 3 of 15
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 8 April 13,2007 CORE OPERATING LIMITS REPORT (COLR)
I UNIT 1 CYCLE 31 2.5 Control Bank Insertion Limits (TS 3.1.6)
NOTE: This limit is not applicable while performing SR 3.1.4.2.
The control banks shall be within the insertion, sequence and overlap limits specified in Figure 3.
Applicability: MODE 1 and MODE 2 with bff21.0 2.6 Nuclear Heat Flux Hot Channel Factor (Fq(Z)) (TS 3.2.1)
The Heat Flux Hot Channel Factor shall be within the following limits:
FQ(Z)5 CFQ
- K(Z) / P for P > 0.5 FQ(Z) I CFQ
- K(Z) 1 0.5 for P 1 0.5 Where P is the fraction of Rated Power at which the core is operating.
FQ(Z)is both:
Steady State FQ'(Z) = FQ(Z)
CFo = 2.60 (422V+ Fuel)
K(Z) is the function in Figure 4.
W(Z) is the function in Figure 5.
Applicability: MODE 1 2.7 Nuclear ~ n t h a l p - r n The Nuclear Enthalpy Rise Hot Channel Factor shall be within the following limit:
2.7.1 F ~ A H4 . 7 7 x [ l + 0.3(1-P)] (422V+ Fuel) where: P is the fraction of Rated Power at which the core is operating.
Applicability: MODE 1 Page 4 of 15
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 8 April 13,2007 CORE OPERATING LIMITS REPORT (COLR)
) UNIT 1 CYCLE 3 1 2.8 Axial Flux Difference (AFD) (TS 3.2.3)
NOTE: The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits.
The indicated axial flux difference in % flux difference units, shall be maintained within the allowed operational space defined by Figure 6.
Applicability: MODE 1 with THERMAL POWER 250% RTP 2.9 Overtemperature AT Setpoint (TS 3.3.1, Table 3.3.1-1 note 1)
Overtemperature AT setpoint parameter values:
indicated AT at Rated Power, OF average temperature, OF 569.0°F 2235 psig 1.16 0.0149 0.00072 25 sec 3 sec 2 sec for Rosemont or equivalent RTD 0 sec for Sostman or equivalent RTD 2 sec for Rosemont or equivalent RTD 0 sec for Sostman or equivalent RTD f(A1) is an even 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, where qt and qb are the percent power in the top and bottom halves of the core respectively, and qt + qb is total core power in percent of Rated Power, such that:
2.9.1 For qt - qb within -12, +5 percent, f(A1) = 0.
2.9.2 For each percent that the magnitude of qt - qb exceeds +5 percent, the AT trip setpoint shall be automatically reduced by an equivalent of 2.12 percent of Rated Power.
2.9.3 For each percent that the magnitude of qt - qb exceeds - 12 percent, the AT trip setpoint shall be automatically reduced by an equivalent of 2.0 percent of Rated Power.
Applicability: MODES 1 and 2 Page 5 of 15
POINT BEACH NUCLEAR PLANT TRM 2.1 U l TECHNICAL REQUIREMENTS MANUAL Revision 8 April 13, 2007 CORE OPERATING LIMITS REPORT (COLR)
I UNIT 1 CYCLE 3 1 2.10 Overpower AT Setpoint (TS 3.3.1, Table 3.3.1- 1 note 2)
Overpower AT setpoint parameter values:
indicated AT at Rated Power, OF average temperature, OF 569.0°F 1.10 of Rated Power 0.0262 for increasing T 0.0 for decreasing T 0.00103 for T 2 Tr 0.0 for T < T' 10 sec 2 sec for Rosemont or equivalent RTD 0 sec for Sostman or equivalent RTD 2 sec for Rosemont or equivalent RTD 0 sec for Sostman or equivalent RTD Applicability: MODES 1 and 2 2.1 1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (TS 3.4.1) 2.1 1.1 T,, shall be 5574°F.
2.1 1.2 Pressurizer pressure shall be maintained 22205 psig during operation.
NOTE: Pressurizer pressure limit does not apply during:
- 1) THERMAL POWER ramp >5% RTP per minute; or
- 2) THERMAL POWER step >lo% RTP.
2.1 1.3 Reactor Coolant System raw measured Total Flow Rate shall be maintained 21 82,400 gpm.
Applicability: MODE 1 2.12 Refueling Boron Concentration (TS 3.9.1)
Boron concentrations of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained 22200 ppm.
Applicability: MODE 6
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 8 April 13,2007 CORE OPERATING LIMITS REPORT (COLR)
I UNIT 1 CYCLE 31 FIGURE 1 REACTOR CORE SAFETY LIMITS CURVE (Cores containing 422V + fuel)
Unaccepbble Operation Acceptable Operation Core Pawer (fraction of 1540 1WWt)
Page 7 of 15
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 8 April 13,2007 CORE OPERATING LIMITS REPORT (COLR)
I UNIT 1 CYCLE 3 1 FIGURE 3 CONTROL BANK INSERTION LIMITS NOTE: The "fully withdrawn" parking position range 2 225 steps can be used without violating this Figure.
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 8 April 13,2007 CORE OPERATING LIMITS REPORT (COLR)
I UNIT 1 CYCLE 3 1 FIGURE 4 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (K(Z))
FOR 0.422V+ FUEL 0 1 2 3 4 5 6 7 8 9 10 11 12 CORE HEIGHT (FT)
Page 10 of 15
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 8 April 13,2007 CORE OPERATING LIMITS REPORT (COLR)
I UNIT 1 CYCLE 3 1 FIGURE 5 RAOC Summary of W(Z) with HFP AFD Band of -8/+9%
(Top 15% and Bottom 12% Excluded)
Page 11 of 15
POINT BEACH NUCLEAR PLANT TRM 2.1 U l TECHNICAL REQUIREMENTS MANUAL Revision 8 April 13,2007 CORE OPERATING LIMITS REPORT (COLR)
I UNIT 1 CYCLE 3 1 FIGURE 5 (con't)
RAOC Summary of W(Z) with HFP AFD Band of -8/+9%
(Top 15% and Bottom 12% Excluded)
Page 12 of 15
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 8 April 13,2007 CORE OPERATING LIMITS REPORT (COLR)
( UNIT 1 CYCLE 3 1 FIGURE 6 FLUX DIFFERENCE OPERATING ENVELOPE
-35.00 -30.00 -25.00 -20.00 -15.00 -10.00 -5.00 0.00 5.00 10.00 15.00 20.00 25.00 30.00 35.00 Delta I (%)
NOTE: This figure represents the Relaxed Axial Offset Control (RAOC) band used in safety analyses, it may be administratively tightened depending on in-core flux map results. Refer to Figure 2 of ROD 1.2 for administrative limit.
Page 13 of 15
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 8 April 13, 2007 CORE OPERATING LIMITS REPORT (COLR)
I UNIT 1 CYCLE 31 TABLE 1 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS Surveillance Technical Specification,"
WCAP-14449-P-A, "Application of Best Estimate Large Break LOCA Methodology to Westinghouse PWRs with Upper Plenum Injection," Revision 1, October 1999 (cores containing 422V + fuel)
WCAP-10924-P-A, "Large Break LOCA Best Estimate Methodology, Volume 2: Application to Two-Loop PWRs Equipped with Upper Plenum Injection," and Addenda, December 1988 (cores not containing 422V + fuel)
WCAP-10924-P-A, "LBLOCA Best Estimate Methodology: Model Description and Validation: Model Revisions," Volume 1, Addendum 4, August 1990 (cores not containing 422V + fuel)
WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985 WCAP-10054-P-A, Addendum 2, Revision 1, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model," July 1997 Page 14 of 15
POINT BEACH NUCLEAR PLANT TRM 2.1 U1 TECHNICAL REQUIREMENTS MANUAL Revision 8 April 13,2007 CORE OPERATING LIMITS REPORT (COLR)
I UNIT 1 CYCLE 3 1 TABLE 1 NRC APPROVED METHODOLOGIES FOR COLR PARAMETERS of Constant Axial Offset Control FQ Surveillance Technical Specification,"
AT Trip Functions,"
Overtemperature AT Trip Functions,"
2.1 1 RCS Pressure, Temperature, and WCAP- 11397-P-A, "Revised Thermal Design Flow Departure from Nucleate Procedure," April 1989, for those events Boiling (DNB) Limits analyzed using RTDP WCAP-14787-P, Rev. 2, "Westinghouse Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wisconsin Electric Power Company Point Beach Units 1
& 2 (Fuel Upgrade & Uprate to 1656 MWt-NSSS Power with Feedwater Venturis, or 1679 MWt-MSSS Power with LEFM on Feedwater Header)", October 2002.
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 for those events not utilizing RTDP 2.12 Refueling Boron Concentration WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 Page 15 of 15