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Category:Fuel Cycle Reload Report
MONTHYEARML19106A0522019-04-0404 April 2019
Submittal of Core Operating Limits Report for Cycle 21
NL-18-020, Core Operating Limits Report for Cycle 242018-04-10010 April 2018
Core Operating Limits Report for Cycle 24
NL-17-043, Core Operating Limits Report for Cycle 202017-04-13013 April 2017
Core Operating Limits Report for Cycle 20
NL-17-023, Revision to the Core Operating Limits Report2017-02-22022 February 2017
Revision to the Core Operating Limits Report
NL-16-070, Core Operating Limits Report2016-06-15015 June 2016
Core Operating Limits Report
NL-16-017, Mid-Cycle Revision to the Core Operating Limits Report for Cycle 192016-02-0404 February 2016
Mid-Cycle Revision to the Core Operating Limits Report for Cycle 19
NL-14-057, Submittal of Core Operating Limits Report Cycle 222014-04-0909 April 2014
Submittal of Core Operating Limits Report Cycle 22
NL-13-0303, Submittal of Revised Core Operating Limits Report2013-04-18018 April 2013
Submittal of Revised Core Operating Limits Report
NL-12-022, Unit. 2, Revised Core Operating Limits Report2012-04-0303 April 2012
Unit. 2, Revised Core Operating Limits Report
NL-11-049, Revised Core Operating Limits Report2011-05-0404 May 2011
Revised Core Operating Limits Report
NL-10-070, Revised Core Operating Limits Report, Mid-Cycle Revision2010-07-0707 July 2010
Revised Core Operating Limits Report, Mid-Cycle Revision
NL-10-034, Revised Core Operating Limits Report, Cycle 202010-05-0303 May 2010
Revised Core Operating Limits Report, Cycle 20
NL-09-047, Revised Core Operating Limits Report, Cycle 162009-05-14014 May 2009
Revised Core Operating Limits Report, Cycle 16
NL-08-114, Revised Core Operating Limits Report for Indian Point Unit 22008-07-11011 July 2008
Revised Core Operating Limits Report for Indian Point Unit 2
NL-06-085, 2006 Summary Reports for In-Service Inspection and Repairs or Replacements2006-08-14014 August 2006
2006 Summary Reports for In-Service Inspection and Repairs or Replacements
NL-06-069, Revised Core Operating Limits Report, Cycle 182006-06-22022 June 2006
Revised Core Operating Limits Report, Cycle 18
NL-05-069, Cycle 14 Core Operating Limit Report (Colr), Revision 142005-05-11011 May 2005
Cycle 14 Core Operating Limit Report (Colr), Revision 14
NL-05-022, Cycle 17 Core Operating Limit Report (COLR)2005-02-16016 February 2005
Cycle 17 Core Operating Limit Report (COLR)
NL-03-080, Core Operating Limits Report for Cycle 132003-05-0808 May 2003
Core Operating Limits Report for Cycle 13
NL-02-143, Cycle 16 Core Operating Limit Report (COLR)2002-11-15015 November 2002
Cycle 16 Core Operating Limit Report (COLR)
2019-04-04
[Table view]
Category:Letter type:NL
MONTHYEARNL-21-034, Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals2021-05-26026 May 2021
Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals
NL-21-039, Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary2021-05-20020 May 2021
Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary
NL-21-033, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2021-05-11011 May 2021
Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel
NL-21-032, Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center2021-05-11011 May 2021
Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center
NL-21-005, Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions2021-05-11011 May 2021
Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions
NL-21-030, Submittal of 2020 Annual Radiological Environmental Operating Report2021-05-0606 May 2021
Submittal of 2020 Annual Radiological Environmental Operating Report
NL-21-027, Registration of Spent Fuel Cask Use2021-04-20020 April 2021
Registration of Spent Fuel Cask Use
NL-21-021, Registration of Spent Fuel Cask Use2021-04-19019 April 2021
Registration of Spent Fuel Cask Use
NL-21-017, Pre-Notice of Disbursement from Decommissioning Trusts2021-04-0808 April 2021
Pre-Notice of Disbursement from Decommissioning Trusts
NL-21-010, Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2021-02-17017 February 2021
Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report
NL-21-006, Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement2021-02-10010 February 2021
Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement
NL-21-014, Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2021-01-26026 January 2021
Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device
NL-20-082, Notice of Planned Transfer of Decommissioning Funds2020-12-14014 December 2020
Notice of Planned Transfer of Decommissioning Funds
NL-20-081, Pre-Notice of Disbursement from Decommissioning Trusts2020-12-0909 December 2020
Pre-Notice of Disbursement from Decommissioning Trusts
NL-20-080, Report in Accordance with 10 CFR 71.95(a) for Failure to Comply with Certificate of Compliance No. 71-93212020-11-19019 November 2020
Report in Accordance with 10 CFR 71.95(a) for Failure to Comply with Certificate of Compliance No. 71-9321
NL-20-079, (IP2 and IP3) - Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-12012 November 2020
(IP2 and IP3) - Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic
NL-20-077, Submittal of Quality Assurance Program Manual Revision 22020-11-0909 November 2020
Submittal of Quality Assurance Program Manual Revision 2
NL-20-078, Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-11-0909 November 2020
Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device
NL-20-076, Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal2020-11-0202 November 2020
Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal
NL-20-069, One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency2020-10-0808 October 2020
One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency
NL-20-070, Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-10-0202 October 2020
Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device
NL-20-067, Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-09-16016 September 2020
Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline
NL-20-064, 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments2020-09-0101 September 2020
10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments
NL-20-060, Status of Remaining Actions for Generic Letter 2004-022020-08-11011 August 2020
Status of Remaining Actions for Generic Letter 2004-02
NL-20-057, Cancellation of Commitment Related to Large Break LOCA Reanalysis2020-07-30030 July 2020
Cancellation of Commitment Related to Large Break LOCA Reanalysis
NL-20-0851, 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material2020-07-22022 July 2020
30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material
NL-20-051, Submittal of Quality Assurance Program Manual, Revision 1 for the Indian Point Energy Center2020-07-0707 July 2020
Submittal of Quality Assurance Program Manual, Revision 1 for the Indian Point Energy Center
NL-20-052, Unsatisfactory 10 CFR 26 Fitness-For-Duty Blind Performance Testing Results2020-07-0707 July 2020
Unsatisfactory 10 CFR 26 Fitness-For-Duty Blind Performance Testing Results
NL-20-012, Application to Revise Provisional Operating License and Technical Specifications2020-06-30030 June 2020
Application to Revise Provisional Operating License and Technical Specifications
NL-20-050, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-06-24024 June 2020
Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline
NL-20-041, Registration of Unit 3 Spent Fuel Cask Use2020-05-13013 May 2020
Registration of Unit 3 Spent Fuel Cask Use
NL-20-042, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2020-05-12012 May 2020
Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel
NL-20-033, Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2020-04-28028 April 2020
Technical Specifications Proposed Change - Permanently Defueled Technical Specifications
NL-20-038, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-04-23023 April 2020
Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline
NL-20-035, Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-16016 April 2020
Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic
NL-20-034, Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-13013 April 2020
Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic
NL-20-021, Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-03-24024 March 2020
Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device
NL-20-020, Submittal of 2019 Annual Fitness for Duty Performance Data Report Update2020-02-26026 February 2020
Submittal of 2019 Annual Fitness for Duty Performance Data Report Update
NL-20-015, Submittal of 2019 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2020-02-10010 February 2020
Submittal of 2019 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report
NL-20-008, Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane2020-01-0606 January 2020
Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane
NL-19-094, 2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2019-12-16016 December 2019
2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report
NL-19-084, Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments2019-11-21021 November 2019
Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments
NL-19-093, Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.12019-11-21021 November 2019
Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.1
NL-19-092, Request for Rescission of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-11-20020 November 2019
Request for Rescission of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
NL-19-043, Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.122019-10-22022 October 2019
Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.12
NL-19-073, Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-10-22022 October 2019
Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
NL-19-078, Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2019-10-22022 October 2019
Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications
NL-19-091, Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use2019-10-17017 October 2019
Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use
NL-19-090, Registration of Unit 2 Spent Fuel Cask Use2019-10-0909 October 2019
Registration of Unit 2 Spent Fuel Cask Use
NL-19-079, 50.59(d)(2) Summary Report of Changes, Tests and Experiments2019-09-26026 September 2019
50.59(d)(2) Summary Report of Changes, Tests and Experiments
2021-05-06
[Table view] |
Text
l Entergy Nuclear Northeast Entergy Nuclear Operations, Inc Indian Point Energy Center 295 Broadway, Suite 1 PO Box 249 Buchanan, NY 10511-0249 November 15, 2002 Re: Indian Point Unit No. 2 Docket No. 50-247 NL-02-143 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station O-P1-17 Washington, DC 20555-0001
Subject:
Indian Point Unit 2 Cycle 16 Core Operating Limit Report (COLR)
Dear Sir:
In accordance with the Indian Point Unit 2 Technical Specification 6.9.1.11, enclosed is the IP2 COLR for Cycle 16.
There are no commitments contained in this letter.
Should you have any questions regarding this matter, please contact Mr. John McCann, Manager, Licensing, Indian Point Energy Center at (914) 734-5074.
Sin r Fred Dacimo Vice President - Operations Indian Point 2 cc: Hubert J. Miller Regional Administrator US Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Patrick D. Milano, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management US Nuclear Regulatory Commission Mail Stop O-8-2C Washington, DC 20555 NRC Senior Resident Inspector US Nuclear Regulatory Commission PO Box 38 Buchanan, NY 10511
INDIAN POINT 2 GRAPH RPC-6 Revision 5 OPERATIONS CYCLE 16 CORE OPERATING LIMITS REPORT Prepared by: KZAl L 2 4 dt Reviewer:
Reviewer:
Approval:
Date Effective Date BIENNIAL REVIEW Reviewer / Date Reviewer / Date For use as field copy. Valid for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
Qualified Operator Date / Time 24 Hr Extension:
Control Room Supervisor Date / Time 24 Hr Extension:
Control Room Supervisor Date / Time REFERENCE USE GRAPH RPC-6 Rev 5.wpd
CYCLE 16 CORE OPERATING LIMITS REPORT RPC-6 Rev. 5 Core Operating Limits Report COLR Note The Technical Specification references shown next to each Factor OR Limit in this COLR, are there to identify the corresponding sections in the Technical Specifications, that refer to the COLR The data presented in this report applies to Cycle 16 ONLY and may NOT be used for other cycles of operation. Any technical change to this graph requires a Safety Evaluation to be performed.
NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR Note P is the fraction of full power at which the core is operating.
FAHN<1.70 {1+0.3(1-P)} Tech. Spec. 3.10.2 HEIGHT DEPENDENT HEAT FLUX HOT CHANNEL FACTOR FOR
- 20% TUBE PLUGGING Note K(Z) is the fraction given in Figure 1 AND Z is the core height location of FQ.
IF P > .5, FQ(Z) < (2.50 /P) x K(Z) Tech. Spec. 3.10.2 IF P < .5, FQ(Z) < (5.00) x K(Z) Tech. Spec. 3.10.2 Page 1 of 4
RPC-6 CYCLE 16 CORE OPERATING LIMITS REPORT Rev. 5 AXIAL FLUX DIFFERENCE ENVELOPE LIMITS The Indicated Axial Flux Difference limit Tech. Spec. 3.10.2.6.1 is the Target Band; i.e., the Target +/- 5%
The Axial Flux Difference Envelope Limits at 90 percent power are -11%, + 11% AND increase by -1% and +1%, for each 2% of rated power below 90% power, as indicated 3.10.2.6.1 Tech. Spec.
by graph RV-10, Unit 2 Target Flux Values INSERTION LIMITS The Shutdown Banks shall be fully withdrawn Tech. Spec. 3.10.4 when the reactor is critical OR approaching criticality.
The Control Bank Insertion Limits for 3.10.4 Tech. Spec.
Criticality, are as indicated in Figure 2.
Page 2 of 4
CYCLE 16 CORE OPERATING LIM\ITS RE PORT RPC-0 Rev. 5 Figure I HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (For S. G. Tube Plugging up to 20%)
1.2 0.0,1.00 6.0,1.00 1.0 112.0, 0.925]I a)
S0.8 0
.r LiL "0 0.6 N
E 0
Z 0.4 1
E N -4 4-4-4-*-t-t-11t1 0.2 0
0 2 4 6 8 10 12 Core Elevation (feet)
Page 3 of 4
CYCLE 16 CORE OPERATING LIMITS REPORT RP*C-6 Rev. 5 Figure 2 ROD BANK INSERTION LIMITS (Four Loop Operation) 100 Step Overlap 225 1(66,223 BANK B 200 (0,20951) m
= 175 150 Co 0.
I-Co z 125 0
Co 0
100 z
0 0 75 50 25 0
0 10 20 30 40 50 60 70 80 90 100 Power Level (Percent of Rated Power)
Page 4 of 4
