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MONTHYEARML22013A7062022-01-13013 January 2022 Investigation Report of LLRW Shipment Pursuant to 10 CFR 20, Appendix G ML21056A0782021-04-0707 April 2021 Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Indian Point ISFSI (Docket: 72-51) 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 ML20259A2172020-09-14014 September 2020 Commitment Change Summary Report ML20260H0722020-06-18018 June 2020 IP-RPT-14-00013, Revision 3, Indian Point Nuclear Generating Units 2 and 3, Consequences of a Postulated Fire and Explosion Following the Release of Natural Gas from the New Aim 42 Pipeline Near Ipec ML20122A1052020-05-27027 May 2020 Letter from Margaret M. Doane to John B. Rhodes, Chair and Executive Officer, Ny State Public Service Commission: Response to Ny State Public Service Commission Regarding Natural Gas Transmission Pipelines Near Indian Point Nuclear Power Pl ML20100F6352020-04-0808 April 2020 Expert Team Final Report 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) ML19252A3182019-09-0909 September 2019 Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of Sept 2, 2019 NL-19-061, Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2019-06-13013 June 2019 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements ML19114A0742019-04-22022 April 2019 Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of April 15, 2019 NL-19-012, Request for Approval of a Certified Fuel Handler Training and Retraining Program2019-04-15015 April 2019 Request for Approval of a Certified Fuel Handler Training and Retraining Program ML18098A0882018-04-0606 April 2018 Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-18-021, Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability2018-04-0606 April 2018 Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-20-066, Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center2017-12-19019 December 2017 Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center ML17349A1562017-12-0808 December 2017 Risk Impact of One-Time Extending the ILRT Interval Associated with the Proposed Technical Specification Changes ML17279A2472017-10-0606 October 2017 2017 Annual Assessment Meeting Written Comments Compilation ML17222A2392017-10-0404 October 2017 NRC Response to Request for Deferral of Actions Related to Beyond-Design-Basis Seismic and Flooding Hazard Reevaluations ML17289A6552017-10-0202 October 2017 Attachment 6 to NL-17-115, Revised HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Energy Center, Revision 9 NL-17-122, Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,20172017-09-28028 September 2017 Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,2017 ML17096A2122017-03-23023 March 2017 Entergy Engineering Report No. IP-RPT-16-00078, Indian Point RAI CLI-16-07 SAMA Cost-Benefit Sensitivities Rev. 1 (March 23, 2017) NL-17-020, License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan2017-02-0606 February 2017 License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan ML17096A2112017-01-0404 January 2017 Entergy Engineering Report No. IP-RPT-16-00077, Indian Point RAI CLI-16-07 MACCS2 Sensitivities, Rev. 0 (Jan 4, 2017) ML16280A2282016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual NL-16-109, Indian Point 2 Technical Requirements Manual2016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual NL-16-109, HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center.2016-09-19019 September 2016 HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center. ML16250A2762016-09-13013 September 2016 Evaluation of Impacts to Proposed Critical Habitat for the Atlantic Sturgeon for Indian Point Nuclear Generating Units 2 and 3 Proposed License Renewal NL-16-083, Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 32016-08-0101 August 2016 Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 3 ML18115A0592016-06-28028 June 2016 After Action Report/Improvement Plan, Drill Date June 28, 2016 ML17052A2662015-10-0202 October 2015 Sturgeon Mobile Tracking for the New Ny Bridge at Tappan Zee NL-15-128, Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update2015-09-28028 September 2015 Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update NL-15-118, Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 32015-09-0303 September 2015 Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 3 NL-15-099, Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2015-07-30030 July 2015 Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report NL-15-072, 2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2015-06-18018 June 2015 2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements NL-15-030, Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project2015-04-0808 April 2015 Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project NL-15-029, Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 20152015-04-0606 April 2015 Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 2015 ML15062A2002015-02-19019 February 2015 NET-300067-01, Revision 1, Criticality Safety Analysis of the Indian Point, Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels. (Non-Proprietary) NL-15-013, Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval2015-01-28028 January 2015 Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval ML15061A2772014-12-31031 December 2014 WCAP-17954-NP, Revision 0, Indian Point Unit 3 Heatup and Cooldown Limit Curves for Normal Operation. NL-14-152, Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From...2014-12-22022 December 2014 Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From... ML14329A1952014-11-0404 November 2014 NET-300067-01, Rev. 0, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels NL-14-115, 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 20142014-09-18018 September 2014 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 2014 ML14304A7012014-09-16016 September 2014 Reliability Needs Assessment ML15166A0702014-08-31031 August 2014 Algonquin Incremental Market (Aim) Project, Phase 2 Acoustic Survey for Indiana Bats (Myotis Sodalis) and Northern Long-Eared Bats (Myotis Septentrionalis), August 2014 NL-14-110, Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2014-08-27027 August 2014 Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 ML14168A0592014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 5 ML14168A0602014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 ML14168A0612014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 2022-01-13
[Table view] Category:Technical
MONTHYEARNL-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 ML20259A2172020-09-14014 September 2020 Commitment Change Summary Report ML20100F6352020-04-0808 April 2020 Expert Team Final Report ML18098A0882018-04-0606 April 2018 Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-18-021, Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability2018-04-0606 April 2018 Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-20-066, Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center2017-12-19019 December 2017 Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center ML17349A1562017-12-0808 December 2017 Risk Impact of One-Time Extending the ILRT Interval Associated with the Proposed Technical Specification Changes ML17289A6552017-10-0202 October 2017 Attachment 6 to NL-17-115, Revised HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Energy Center, Revision 9 NL-17-122, Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,20172017-09-28028 September 2017 Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,2017 ML17096A2122017-03-23023 March 2017 Entergy Engineering Report No. IP-RPT-16-00078, Indian Point RAI CLI-16-07 SAMA Cost-Benefit Sensitivities Rev. 1 (March 23, 2017) ML17096A2112017-01-0404 January 2017 Entergy Engineering Report No. IP-RPT-16-00077, Indian Point RAI CLI-16-07 MACCS2 Sensitivities, Rev. 0 (Jan 4, 2017) NL-16-109, Indian Point 2 Technical Requirements Manual2016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual ML16280A2282016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual NL-16-109, HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center.2016-09-19019 September 2016 HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center. ML16250A2762016-09-13013 September 2016 Evaluation of Impacts to Proposed Critical Habitat for the Atlantic Sturgeon for Indian Point Nuclear Generating Units 2 and 3 Proposed License Renewal ML17052A2662015-10-0202 October 2015 Sturgeon Mobile Tracking for the New Ny Bridge at Tappan Zee NL-15-029, Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 20152015-04-0606 April 2015 Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 2015 ML15062A2002015-02-19019 February 2015 NET-300067-01, Revision 1, Criticality Safety Analysis of the Indian Point, Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels. (Non-Proprietary) ML15061A2772014-12-31031 December 2014 WCAP-17954-NP, Revision 0, Indian Point Unit 3 Heatup and Cooldown Limit Curves for Normal Operation. ML14304A7012014-09-16016 September 2014 Reliability Needs Assessment NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 5 NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 4 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 4 of 5 NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 ML14168A0592014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 5 ML14168A0602014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 ML14168A0632014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 5 of 5 NL-14-071, Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 4 of 52014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 4 of 5 ML14168A0612014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 ML14107A0432014-03-31031 March 2014 Enclosure 2 to NL-14-045 - Acceptable Value of the Location of the Bottom of the Expansion Transition (Bet) for Implementation of H* at Indian Point Unit 2 ML13337A5942014-01-24024 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14027A5152014-01-16016 January 2014 WCAP-17828-NP, Revision 0, Indian Point Unit 2 H* Alternate Repair Criteria for the Tubesheet Hydraulic Expansion Region (Model 44F - 4-Loop) ML14010A3312014-01-14014 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Indian Point Energy Center, Units 2 and 3, TAC Nos.: MF0744 and MF0745 NL-14-027, LTR-PAFM-13-115-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for Indian Point Generating Station Unit 3 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds.2013-11-30030 November 2013 LTR-PAFM-13-115-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for Indian Point Generating Station Unit 3 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds. NL-13-089, Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 1 of 62013-05-24024 May 2013 Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 1 of 6 NL-13-089, Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 5 of 62013-05-24024 May 2013 Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 5 of 6 NL-13-089, Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 4 of 62013-05-24024 May 2013 Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 4 of 6 NL-13-089, Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 3 of 62013-05-24024 May 2013 Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 3 of 6 NL-13-089, Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 6 of 62013-05-24024 May 2013 Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 6 of 6 ML13176A0082013-05-24024 May 2013 Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 4 of 6 NL-13-089, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 2 of 62013-05-24024 May 2013 Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 2 of 6 ML13176A0122013-05-24024 May 2013 Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 1 of 6 ML13176A0102013-05-24024 May 2013 Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 6 of 6 ML13176A0092013-05-24024 May 2013 Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 5 of 6 ML13176A0072013-05-24024 May 2013 Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 3 of 6 ML17052A3142013-03-29029 March 2013 Analysis of Potential Sedimentation Effects of Proposed Cylindrical Wedgewire Screens for Intake of Cooling Water at Indian Point Energy Center ML13072A0832013-01-31031 January 2013 12-4116.IPEC.V002, Revision 1, Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation: EA-12-051 ML12353A4662012-11-20020 November 2012 Indian Point Energy Center - Engineering Report No. IP-RPT-12-00039, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 1 of 4 NL-12-168, Indian Point Energy Center - Engineering Report No. IP-RPT-12-00039, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 2 of 42012-11-20020 November 2012 Indian Point Energy Center - Engineering Report No. IP-RPT-12-00039, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 2 of 4 NL-12-168, Indian Point Energy Center - Engineering Report No. IP-RPT-12-00039, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 1 of 42012-11-20020 November 2012 Indian Point Energy Center - Engineering Report No. IP-RPT-12-00039, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 1 of 4 2021-02-10
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0 ~~C=L2 0 ER-290N REVISION 2 NOVEMBER 2002 CALDON, INC.
ENGINEERING REPORT: ER-290N BOUNDING UNCERTAINTY ANALYSIS FOR THERMAL POWER DETERMINATION AT INDIAN POINT UNIT 2 NUCLEAR POWER STATION USING THE LEFMV SYSTEM Prepared By: Ed Madera Reviewed By: Don AugensteinA l NON-PROPRIETARY VERSION I
Engineering Report: ER-290N Revision 2 BOUNDING UNCERTAINTY ANALYSIS FOR THERMAL POWER DETERMINATION AT INDIAN POINT UNIT 2 NUCLEAR POWER STATION USING THE LEFM' SYSTEM Table of Contents
1.0 INTRODUCTION
2.0
SUMMARY
3.0 APROACH 4.0 OVERVIEW
5.0 REFERENCES
APPENDICES
- A Information Supporting Uncertainty in LEFM-/ Flow and Temperature Measurements A.1[
A.2[ ]
A.3 LEFMV/ Profile Factor and Profile Factor Uncertainty A.4[ ]
A.5[ ]
A.6[ I B Total Thermal Power Uncertainty due to the LEFMI/, Proprietary in its Entirety C LEFMV + Interface and Reconciliation Documents, Calorimetric Uncertainties with the LEFMI and LEFMI +
ER-290 Rev 2 Caldon, Inc. Page - 2
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Engineering Report: ER-290N Rev. 2 BOUNDING UNCERTAINTY ANALYSIS FOR THERMAL POWER DETERMINATION AT INDIAN POINT UNIT 2 NUCLEAR POWER STATION USING THE LEFMI/ SYSTEM
1.0 INTRODUCTION
The LEFM/ is an advanced ultrasonic system that accurately determines the mass flow and temperature of feedwater in nuclear power plants. Using feedwater pressure signal input to the LEFMv/; its mass flow and temperature outputs are used along with other plant data to compute reactor core thermal power. The technology underlying the LEFMI ultrasonic instruments and the factors affecting their performance are described in a topical report, Reference 1, and a supplement to this topical report, Reference 2. The exact amount of the uprate allowable under a recent revision to 10CFR50 Appendix K depends not only on the accuracy of the LEFMI/ output but also on the uncertainties in other inputs to the thermal power calculation.
It is the purpose of this document to provide an analysis of the uncertainty contribution of the LEFMI System in its normal operation to the overall thermal power uncertainty of Indian Point Unit 2 Nuclear Power Station. The total uncertainty contribution is documented in the Interface and Reconciliation document (included with this document as Appendix C) as the term AB. This uncertainty is the aggregate power uncertainty due to the feedwater flow, temperature and pressure measurements.
The uncertainties in mass flow and feedwater temperature are also provided. If desired, these data may be used in the calculation of the overall thermal power uncertainty. If this method is used, a special procedure is required for combining the mass flow uncertainty and the uncertainty in feedwater enthalpy due to temperature. The procedure is necessary because some elements of the temperature uncertainty are systematically related to elements of the mass flow uncertainty and others are not. For plants that require the LEFMI 's contribution to plant thermal power uncertainty be presented in just the feedwater temperature and mass flow terms, a systematic and random temperature calculation of feedwater temperature uncertainty is also provided.
Finally, this report utilizes actual dimensions for the spool piece(s), as well as system measurements for full power mass flow, final feedwater temperature and steam conditions. Bounding values for the uncertainties in length measurements, time measurements and calibration coefficient (profile factor) are employed. The commissioning tests for the LEFMI/, performed following its installation in the plant, confirmed that in fact, the time measurement uncertainties are within the bounding values used in the analysis.
ER-290 Rev 2 Caldon, Inc. Page - 3
3 AL_0 0 2.0
SUMMARY
For the Indian Point Unit 2 Nuclear Power Station, Revision I results are as follows:
- 1. The mass flow uncertainty approach is documented in Reference 3. The uncertainty in the LEFMJ 's mass flow of feedwater is as follows:
o LEFMI system mass flow uncertainty is [ ].
- 2. The uncertainty in the LEFMI feedwater temperature is as follows:
o LEFMI system temperature uncertainty is [ ]
- 3. The thermal power uncertainty approach is documented in Reference 3. The uncertainty in the LEFMI 's thermal power of feedwater is as follows:
o LEFMI/ system thermal power uncertainty is [ ].
Note: Because some elements of the temperature uncertainty are systematic, the total power uncertainty due to the LEFMI is not the root sum squares of the uncertainties due to items 1 and 2 above.
- 4. For an overall thermal power uncertainty analysis in which mass flow and temperature errors are to be treated separately (i.e., the thermal power uncertainty above is not used), the bounding mass flow and temperature errors must be [
- 3.0 APPROACH
_ [
ER-290 Rev 2 Caldon, Inc. Page - 4
LWC a0 =D=O-\ 0 I
I X/1 ER-290 Rev 2 Caldon, Inc. Page - 5
= 1=/-L20 C~---Y-
- Qz =0 4.0 OVERVIEW
[
]
Appendix A.1, LEFMI/ Inputs
- - - This Appendix is Proprietary in its Entirety - - -
[
]
Appendix A.2, LEFM/ Mass Flow and Temperature Uncertainties
- - - This Appendix is Proprietary in its Entirety ---
This appendix calculates the uncertainties in mass flow and temperature as computed by the LEFMI( using the methodology described in Appendix E of Reference 1 and Appendix A of Reference 31, with uncertainties in the elements of these measurements bounded as described in both references 2 . [
This appendix utilizes the results of the spool piece calibration test and analysis for the uncertainty in the profile factor (calibration coefficient). The engineering calculation for the spool piece calibration test is referenced in Appendix A.3 of this report.
Appendix A.3, Profile Factor (Calibration and Analysis) Uncertainties As noted above, the calibration test report and analysis for the spool piece(s) establishes the overall uncertainty in the profile factor of the LEFMI. [
- lReference 3 (ER I57P) develops the uncertainties for the LEFM / system. Because this system uses two measurement planes, the structure of its uncertainties differs somewhat that of an LEFM /.
2[
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i 0 = 0 Appendix A.4, Uncertainties in the Measurement of Time Differences (At's)
Appendix A.5, Uncertainties in the Measurement of Transit Times (t's)
[
]
Appendix A.6, Systematic and Random Temperature Uncertainties This appendix calculates the systematic and random temperature uncertainties as related to mass flow. This appendix considers that the LEFM/ temperature errors are systematic when used to compute enthalpy as well as density. It is understood that most nuclear power plant thermal power uncertainty analysis do not have the term AB, the total thermal power uncertainty due to the LEFMI/ that is defined as term AB and described in Appendix C. Therefore, Appendix A.6 computes the random and systematic feedwater temperature uncertainty in order to facilitate the nuclear power plants uncertainty analysis.
Appendix B, Total Thermal Power Uncertainty due to the LEFM/
The total thermal power uncertainty due to the LEFMI/ is calculated in this appendix, [
I Appendix C, Interface and Reconciliation Document For completeness, an Interface and Reconciliation Document for this project is included as Appendix C. An interface and reconciliation document is provided to each LEFMI and LEFMI/ customer. This document breaks down the uncertainties that Caldon will calculate and justify for a specific uprate project, as well as those outside Caldon's scope. It provides a set of uncertainties for use by the customer or the customer's agent in establishing the amount of the power uprate. Appendix C also reconciles the results of this analysis with the uncertainties calculated in the Topical Report and its supplements (References 1, 2, and 3).
ER-290 Rev 2 Caldon, Inc. Page - 7
CrL2c 0 Ad0
5.0 REFERENCES
- 1) Caldon Topical Report ER-SOP, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM Check System", Rev. 0.
- 2) Caldon Engineering Report ER-160P, "Supplement to Topical Report ER SOP: Basis for a Power Uprate with the LEFM System", May 2000
- 3) Caldon Engineering Report ER-157, "Supplement to Caldon Topical Report ER-80P: Basis for Power Uprates with an LEFM Check or an LEFM CheckPlus", dated October 2001, Revision 5
- 4) ASME PTC 19.1-1985, Measurement Uncertainty
- 5) ISA-RP67.04.02-2000, Methodologies for the Determination of Set Points for Nuclear Safety-Related Instrumentation
- 6) MPR Engineering Report MPR-1614 Rev. 0 "Feedwater Flow Measurement with LEFM Chordal Systems at Indian Point Unit 2 Configuration and Uncertainty Analysis", dated October 1995
- 7) Alden Research Laboratory Report No. 106-79/C91, "Calibration Report of Indian Point 2 18" Ultrasonic Flowrneters Serial Nos. WvP No. 2 & 3."
ER-290 Rev 2 Caldon, Inc Page - 8
Appendix A Appendix A.1, - - - Proprietary to Caldon in its Entirety ---
Appendix A.2, - - - Proprietary to Caldon in its Entirety - - -
Appendix A.3, Profile Factor (Calibration) Uncertainties Appendix A.4, - - - Proprietary to Caldon in its Entirety - - -
Appendix A.5, - - - Proprietary to Caldon in its Entirety ---
Appendix A.6, - - - Proprietary to Caldon in its Entirety - - -
R-en ER-290 Rev 2 Caldon, Inc. Appendix A
- 0 LLc2 0 Appendix A.1 is Proprietary to Caldon in its Entirety ER-290 Rev 2 Caldon, Inc. Appendix A
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Appendix A.2 is Proprietary to Caldon in its Entirety ER-290 Rev 2 Caldon, Inc. Appendix A
7fl= 0 ==C= 0 Appendix A.3 LEFM,/ Spool Piece(s) Profile Factor and Profile Factor Uncertainty Refer to:
- 1. MPR-1614 Rev. 0, Proprietary to Caldon
- 2. Alden Research Laboratory Report No. 106-79/C91, "Calibration Report of Indian Point 2 18" Ultrasonic Flow Meters Serial Nos. WMP No. 2 & 3."
ER-290 Rev 2 Caldon, Inc. Appendix A
En0 ==r- 0 Appendix A.4 is Proprietary to Caldon in its Entirety ER-290 Rev 2 Caldon, Inc. Appendix A
, L2 0 o cM0 Appendix A.5 Proprietary to Caldon in its Entirety
- ER-290 Rev 2 Caldon, Inc. Appendix A
A n0 ==r 0 Appendix A.6 Proprietary to Caldon in its Entirety ER-290 Rev 2 Caldon, Inc. Appendix A
Appendix B Proprietary to Caldon in its Entirety ER-290 Rev 2 Caldon, Inc. Appendix B
i A= = ===
Appendix C LEFMJ + Interface and Reconciliation Documents, Calorimetric Uncertainties with the LEFMI and LEFM-/ +
ER-290 Rev 2 Caldon, Inc Appendix C
LEFM Interface and Reconciliation Document Calorimetric Uncertainties with the LEFMI and LEFMI/+
Indian Point 2 I. Purpose It is the purpose of this document to define precisely the uncertainties that Caldon will calculate and justify for a specific Appendix K uprate project. The uncertainties that are outside Caldon's scope are also defined, as well as the method for combining all uncertainties to obtain a power uncertainty. This document also breaks down the relationship between the uncertainties tabulated in Caldon reports covering the operation of the LEFMI and LEFM/ + instruments and the data that Caldon will provide for a specific uprate project.
II. Background Reports covering the operation of the LEFMV/ and LEFMI + instruments describe how the use of these instruments reduces the uncertainties in feedwater mass flow and feedwater enthalpy.1 In combination with the uncertainties in the determination of other variables (steam enthalpy, for example), the uncertainties in feedwater mass flow and enthalpy establish the uncertainty in the core thermal power. The amount of a power increase allowable under an Appendix K uprate is directly dependent on achieving a thermal power uncertainty within bounds defined by the reports cited above.
The uncertainty in the mass flow, which is measured by an LEFM/ (LEFM/ +), and the uncertainty in the feedwater enthalpy, which is derived from the LEFMI 's temperature and pressure outputs, are made up of several elements. These elements relate to the LEFMI +'s measurements of time, to its dimensions, to the hydraulics of the installation and to correlations relating fluid temperature and density to sound velocity and pressure.
With respect to the correlations and the measurements of time and dimensions, some of the uncertainties in mass flow are systematically related to the uncertainties in feedwater enthalpy while others are not. The structure and combination methods for power uncertainties are described in Section III below.
III. Structure of the Thermal Power Uncertainties The core thermal power as determined by a heat balance around the steam supply is given by:
(1) QRX = WFW (hs - hFW) + QLOSS NET Where QRx is the core thermal power WFW is the mass flow rate of the feed to the steam supply, the product of feedwater volumetric flow rate and feedwater density, ICaldon Engineering Reports ER-SOP, ER-160P and ER-157P 1
hs is the enthalpy of the steam delivered by the steam supply, a function of its pressure and moisture content for saturated steam supplies and its pressure and temperature for superheated steam supplies, hFW is the enthalpy of the feedwater, a function of its temperature and pressure, and QLOSS NET is the net loss or gain in power from coolant pump heating, blowdown and/or reactor water purification, component cooling, convective and radiant losses, etc.
The contributing uncertainties to the thermal power computation are defined by differentiating equation (1):
(2) dQRx = dWFW (hs - hFW) + WFW dhs - WFW dhFw + dQLOSS NET The contributors can be expressed per unit by dividing equation (2) by QRX.
(3) dQRx/QRx = dWFW/WFW [ - (QLOSS NET/QRX)] + [dhs/ (hs - hFv)] [1 -
(QLOSS NET/QRX)] - [dhFW / (hs - hFw)1 [1 - (QLOSS NET/QRX)] +
dQLOSS NET/ QRX Since the net gains and losses term is typically less than 1% of the reactor thermal power, the term [I - (QLossNET/QRX)] may be taken as approximately 1.0. Hence, (4) dQRx/QRx = dWFW/WFW + [dhs/ (hs - hFW)] - [dhFw/ (hs - hFW)] +dQLOSS NET/ QRX It should be pointed out that equation (4) applies algebraically only if all error contributors are systematically related to each other. Most of these components are not systematically related. If all of the components were random errors or biases the power uncertainty of equation (4) would be the square root of the sum of the squares of the individual terms on the right hand side of the equation. In fact, a combination of the two procedures is appropriate as described below.
The feedwater enthalpy is a function of its temperature and pressure. Likewise, the density of the feedwater, which the LEFMI (LEFMV/ + ) combines with volumetric flow to compute mass flow, is also a function of temperature and pressure. Because of this and other factors, certain elements of the uncertainty in feedwater enthalpy are combined systematically with the mass flow uncertainty, while other elements, unrelated to the mass flow measurement, are combined randomly. For convenience in defining the combination of terms, the feedwater enthalpy will be related to its temperature and pressure by the following:
(5) hFW = bh/Ip IT(PFW - PO) + 6h/6T Ip (TFW - TO) + ho The computation of feedwater enthalpy from temperature and pressure by the plant computer-part of the thermal power computation-may be carried out by a more complex algorithm than that of equation (5), or the enthalpy may be determined from a 2
look up table. Equation (5) is used here simply as a convenience for developing the elements of the error contributors to feedwater enthalpy. Using equation (5), the uncertainty in feedwater enthalpy is:
(6) dhFW = 5h/6p IT dpFw + 5h/6T Ip dTFW + dho Here dho represents the potential bias in the enthalpy algorithm of the plant computer.
Rewriting equation (4) to incorporate equation (6), and rearranging terms:
A B (7) dQix/QRx = {dWFw/WFw} - {[1/ (hs - hFW)] [oh/6p IT dpFW + 5h'6T Ip dTFw]}
C D E
+ {[1/(hs - hFw)] dho}+ {[l/ (hs - hFW)] dhs} +{dQLoss NET/ QRX}
In the determination of overall thermal power uncertainty, terms A and B will be provided by Caldon, based in part on the uncertainty in the analog feedwater pressure signal provided to the LEFMI (LEFMI/ +) by the utility. Unless otherwise specified, this pressure will be assumed to represent the feedwater pressure at the LEFM/ spool piece(s) within +/- 11 psi (two standard deviations or 95% confidence limits). The utility will be expected to certify the accuracy of the feedwater pressure input to the LEFMV/.
To ensure that terms A and B are computed on the correct bases, the utility will also provide Caldori with thermodynamic data characterizing the operation of the nuclear steam supply at full power, pre-uprate. These data include: mass flow, final feedwater temperature and pressure, and steam enthalpy.
Terms C, D, and E are outside of Caldon's scope, are based on other plant instruments, and are to be provided by others.
Caldon will provide a single uncertainty, AB, expressed as a percentage of the rated thermal power, that encompasses terms A and B. They will also provide the thermodynamic coefficients (e.g., the elements of term B) used to compute terms A and B for the utility's review and records. Under normal circumstances, there will not be a systematic relationship between term AB, on the one hand, and terms C, D, and E, on the other. Likewise, there will normally not be systematic relationships among terms C, D, and E. Therefore, the utility will normally compute the total thermal power uncertainty from the following.
(8) dQpx/Qpx = [(AB)2 + (C) 2 + (D)2 + (E)2]1/2 3
IV. Reconciliation of Uncertainties with the Uncertainties Quoted in Caldon Engineering Reports Table 1 below compares the site-specific bounding uncertainties for Indian Point 2 to the following Caldon Engineering Reports:
- ER-80P, Rev. 0 (1997), the original Caldon topical report that requested a 1% power uprate based on an accuracy of the LEFMI/ system bounded by +/- 0.6% (two standard deviations) thermal power accuracy.
- ER-1 60P, Rev. 0, which presents instrument uncertainties identical to those in ER-80P. ER-1 60P recognizes that, in accordance with NRC Rulemaking in June 2000, a power uprate up to and including 1.4% power can be requested for the LEFMI (LEFMI +) System (since ER-SOP demonstrates that its accuracy supports a thermal power uncertainty of +/- 0.6%).
- ER-1 57P, Rev. 5, which describes Caldon's next generation LEFMI +.
ER-157P revises the uncertainty analyses of ER-80P to reflect actual LEFMI/ data as applied to a typical single flow measurement application. ER-1 57P demonstrates that the LEFMI + can support power uncertainties as small as +/- 0.3%. It also shows that the LEFMI/ system can achieve power uncertainties as low as +/- 0.5% thermal power accuracy.
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