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Category:Calculation
MONTHYEARNL-21-029, Offsite Dose Calculation Manual (Odcm), Revision 52021-04-30030 April 2021 Offsite Dose Calculation Manual (Odcm), Revision 5 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 ML16314E5982016-11-0707 November 2016 IP-CALC-16-00079, Rev. 0, Evaluation of Leak on Weld 8297 on 31 Fan Cooler Unit Return Line. NL-16-133, Indian Point, Unit 3, IP-CALC-16-00079, Rev. 0, Evaluation of Leak on Weld 8297 on 31 Fan Cooler Unit Return Line.2016-11-0707 November 2016 Indian Point, Unit 3, IP-CALC-16-00079, Rev. 0, Evaluation of Leak on Weld 8297 on 31 Fan Cooler Unit Return Line. NL-14-122, Indian Point, Unit 2 - Calculation IP-CALC-14-00028, Rev. 0, Station Battery 22 System Calculation - Analysis Variation with an Battery Aged to 80% Capaciy, Part 1 of 22014-09-15015 September 2014 Indian Point, Unit 2 - Calculation IP-CALC-14-00028, Rev. 0, Station Battery 22 System Calculation - Analysis Variation with an Battery Aged to 80% Capaciy, Part 1 of 2 ML14268A3552014-09-15015 September 2014 Calculation IP-CALC-14-00028, Rev. 0, Station Battery 22 System Calculation - Analysis Variation with an Battery Aged to 80% Capaciy, Part 2 of 2 ML14268A3542014-09-15015 September 2014 Calculation IP-CALC-14-00028, Rev. 0, Station Battery 22 System Calculation - Analysis Variation with an Battery Aged to 80% Capaciy, Part 1 of 2 ML14259A3282014-09-15015 September 2014 Enclosure to NL-14-122 - Calculation IP-CALC-14-00028-Station Battery 22 System Calculation Analysis Variation with an Battery Aged to 80% Capacity (Calculation FEX-000204-01 Rev 1 Is Also Included for Reference Purposes) NL-14-122, Indian Point, Unit 2 - Calculation IP-CALC-14-00028, Rev. 0, Station Battery 22 System Calculation - Analysis Variation with an Battery Aged to 80% Capaciy, Part 2 of 22014-09-15015 September 2014 Indian Point, Unit 2 - Calculation IP-CALC-14-00028, Rev. 0, Station Battery 22 System Calculation - Analysis Variation with an Battery Aged to 80% Capaciy, Part 2 of 2 ML14268A3562014-09-0202 September 2014 Calculation FEX-00204, Rev. 1, Station Battery 22 System Calculation, Part 1 of 2 NL-14-122, Indian Point, Unit 2 - Calculation FEX-00204, Rev. 1, Station Battery 22 System Calculation, Part 1 of 22014-09-0202 September 2014 Indian Point, Unit 2 - Calculation FEX-00204, Rev. 1, Station Battery 22 System Calculation, Part 1 of 2 NL-14-122, Calculation FEX-00204, Rev. 1, Station Battery 22 System Calculation, Part 2 of 22014-09-0202 September 2014 Calculation FEX-00204, Rev. 1, Station Battery 22 System Calculation, Part 2 of 2 ML13329A4262013-11-14014 November 2013 Enclosure 3 to NL-13-147: IP-CALC-13-00063, Rev. 2, Hydraulic Evaluation of Identified Indication in IP3 Service Water 10 Line #1093. ML13329A4252013-10-30030 October 2013 Enclosure 2 to NL-13-147: IP-CALC-13-00070, Rev. 1, Leak Repair Clamp Evaluation for Line 1093 in 32 Main Transformer Moat. ML13329A4242013-10-30030 October 2013 Enclosure 1 to NL-13-147: IP-CALC-13-00062, Rev. 1, Evaluation of Leak at Line 1093 in Unit 3 Moat. ML17104A0412013-04-19019 April 2013 IP-CALC-13-00005, Rev. 1, Engineering Evaluation of Postulated RWST Inventory Loss During the Reverse Osmosis Clean-up Skid Process in Accordance to 2-TAP-001-ROS Due to a Seismic Event ML13116A0082013-04-0909 April 2013 Engineering Evaluation of Postulated RWST Inventory Loss During the Reverse Osmosis Clean-up Skid Process in Accordance to 2-TAP-001-ROS Due to Seismic Event ML13157A1332012-08-29029 August 2012 Enclosure 2 to NL-13-028 - Offsite Dose Calculation Manual Rev. 4 ML12234A2522012-02-14014 February 2012 Enclosure 2, IP3-CALC-EG-00217, Emergency Diesel Generator Storage Tank Level Setpoints, Rev. 5 ML12234A2512012-02-0808 February 2012 Enclosure 1, IP-CALC-11-00058, IP3 Emergency Diesel Generator (EDG) Fuel Oil Consumption Licensing Basis Calculation, Rev 1 ML12060A3242012-02-0606 February 2012 IP-CALC-10-00121, Revision 1, Backup Spent Fuel Pool Cooling System (Bsfpcs) Heat Removal Capability. ML17104A0422011-11-16016 November 2011 IP-CALC-11-00091 AST Analysis of IP2 to Address the Impact of Containment Sump Solution Bazk-Leakage to the RWST After LOCA ML13239A4792011-07-25025 July 2011 Nuclear Safety Advisory Letter NSL-11-5, Westinghouse LOCA Mass & Energy Release Calculation Issues. ML11258A1162011-06-20020 June 2011 Email from M. Halter, Subj: Part 21 - Kasi MOV and AOV Software, (44 Pages) ML12132A1232011-01-18018 January 2011 Enclosure 2 to NL-12-020 - Offsite Dose Calculation Manual Rev. 3 ML0934200142009-08-27027 August 2009 Enclosure 1 to NL-09-129, Calculation IP3-CALC-ED-00207, Revision 8, 480V Buses 2A, 3A, 5A & 6A and Edg'S 31, 32 and 33 Accident Loading. NL-09-045, Indian Point, Units 1, 2, & 3, Offsite Dose Calculation Manual Changes and Justification Packages for 20082009-04-17017 April 2009 Indian Point, Units 1, 2, & 3, Offsite Dose Calculation Manual Changes and Justification Packages for 2008 ML0912602112009-04-17017 April 2009 Offsite Dose Calculation Manual Changes and Justification Packages for 2008 ML0905401572008-06-30030 June 2008 ODCM Part II - Appendix J, Groundwater Flow and Offsite Dose Calculation Details ML0930105332008-03-28028 March 2008 Calculation No. FEX-00204-01, Station Battery 22 System Calculation, Enclosure 2 to NL-09-128 ML0713005362007-01-17017 January 2007 E-Mail from S. Sandike of Entergy to J. Noggle of USNRC, Regarding RG-1.109 Dose Calc on Roseton Fish NL-06-056, Offsite Dose Calculation Manual (ODCM)2006-05-15015 May 2006 Offsite Dose Calculation Manual (ODCM) ML0613204132006-03-0909 March 2006 E-mail from D. Croulet of Entergy to J. Noggle of USNRC, Regarding March 8 IPEC Gw&Sw Dose.Doc ML0617802962006-03-0808 March 2006 E-mail from D. Croulet of Entergy to Various, Regarding IPEC Groundwater and Stormwater Dose.Pdf ML0905000702005-12-31031 December 2005 GZA - Groundwater and Tritium Flux from Catchments Calculation ML0609006452005-10-17017 October 2005 Jaf Environmental Laboratory, Tritium Activity Calculation ML0930103632005-08-26026 August 2005 Attachment K to NL-09-128, Cell Sizing Worksheet, Revised Pages ML0930103622005-08-26026 August 2005 Calculation No. FEX-000204-00, Rev 0, Load Tabulation, Attachment J to NL-09-128 ML0527705332005-08-19019 August 2005 Offsite Dose Calculation Manual, Rev. 9 NL-05-026, Additional Information Regarding Indian Point, Unit 3 License Amendment Request Alternate Source Term2005-02-22022 February 2005 Additional Information Regarding Indian Point, Unit 3 License Amendment Request Alternate Source Term ML0500300612004-12-22022 December 2004 Psat 3056CT.QA.04, Calculation Component Effect of Indian Point 3 Engineered Safety Feature Leakage Iodine Release with Boundary Layer, Revision 1 ML0435703832004-12-15015 December 2004 Enclosure B to NL-04-156, Engineering Standards Manual IES-3B, Rev 0, Instrument Loop Accuracy and Setpoint Calculation Methodology (P3) NL-04-145, Supporting Information for License Amendment Request Regarding Indian Point 3 Stretch Power Uprate2004-11-18018 November 2004 Supporting Information for License Amendment Request Regarding Indian Point 3 Stretch Power Uprate ML0812002582003-09-15015 September 2003 Condition Monitoring & Operational Assessment RFO-15 SG-SGDA-02-45 September 2003 Westinghouse Electric Co 2021-04-30
[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] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23024A0462023-01-17017 January 2023 License Amendment Request for the Independent Spent Fuel Storage Installation-Only Security, Training and Qualification, Safeguards Contingency Plan ML22332A0482022-11-22022 November 2022 New York State Alyse Peterson Comments on Completion of Emergency Planning Nd License Amendment Request Prior to Spent Fuel Transfer from Spent Fuel Pools to Casts (Dockets 50-003, 50-247, 50-286) ML22321A1482022-11-17017 November 2022 License Amendment Request to Approve the Independent Spent Fuel Storage Installation-Only Emergency Plan ML22306A1262022-11-0202 November 2022 License Amendment Request to Revise Indian Point Nuclear Generating Unit Nos. 2 and 3 Renewed Facility Licenses and Permanently Defueled Technical Specifications and IP3 Appendix C Technical Specifications to Reflect Permanent Removal of Sp ML22214A1282022-08-0202 August 2022 License Amendment Request to Revise Indian Point Nuclear Generating Unit No. 2 Permanently Defueled Technical Specifications to Modify Staffing Requirements Following Transfer of Spent Fuel to Dry Storage ML22140A1262022-05-20020 May 2022 License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements ML22035A1212022-02-0404 February 2022 Revision to Holtec Decommissioning International, LLC, License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme to Address the Permanently Defueled Condition ML21356B7042021-12-22022 December 2021 License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme to Address the Permanently Defueled Condition 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 ML20078L1402020-04-15015 April 2020 Issuance of Amendment Nos. 62, 293, and 268 Changes to Emergency Plan for Post-Shutdown and Permanently Defueled Condition ML20017A2902020-01-17017 January 2020 Supplement to 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-19-084, 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-19-053, Request for Rescission of Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)2019-06-0606 June 2019 Request for Rescission of Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) NL-19-013, Proposed Technical Specifications Change - Administrative Controls for Permanently Defueled Condition2019-04-15015 April 2019 Proposed Technical Specifications Change - Administrative Controls for Permanently Defueled Condition NL-19-026, Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2019-04-15015 April 2019 Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-19-001, License Amendment Request to Revise the Indian Point Energy Center Site Emergency Plan to Address the Permanently Shut Down and Defueled Condition2019-04-15015 April 2019 License Amendment Request to Revise the Indian Point Energy Center Site Emergency Plan to Address the Permanently Shut Down and Defueled Condition CNRO-2019-00003, Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 42019-01-31031 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 4 NL-18-034, License Amendment Request- Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2018-06-20020 June 2018 License Amendment Request- Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions NL-17-157, Amendment 19 to License Renewal Application (LRA)2017-12-14014 December 2017 Amendment 19 to License Renewal Application (LRA) NL-17-070, Additional Information for the Review of the Plants License Renewal Application (LRA) Regarding the Containment Leak Rate Program2017-05-31031 May 2017 Additional Information for the Review of the Plants License Renewal Application (LRA) Regarding the Containment Leak Rate Program NL-17-049, Unit Nos., 1, 2, and 3, License Amendment Request - Cyber Security Plan Implementation Schedule2017-04-28028 April 2017 Unit Nos., 1, 2, and 3, License Amendment Request - Cyber Security Plan Implementation Schedule NL-17-035, Proposed License Amendment Regarding Connection of Non-Seismic Boric Acid Recovery System to the Refueling Water Storage Tank2017-04-0707 April 2017 Proposed License Amendment Regarding Connection of Non-Seismic Boric Acid Recovery System to the Refueling Water Storage Tank NL-17-018, Consistency Certification for Entergy Nuclear Indian Point 2 and Entergy Nuclear Indian Point 3 License Renewal Application2017-01-31031 January 2017 Consistency Certification for Entergy Nuclear Indian Point 2 and Entergy Nuclear Indian Point 3 License Renewal Application NL-16-138, Amendment 18 to License Renewal Application2016-12-15015 December 2016 Amendment 18 to License Renewal Application NL-16-118, Indian Point Nuclear Power Plant, Units 2 & 3, Proposed License Amendment Regarding the Inter-Unit Transfer of Spent Fuel2016-12-14014 December 2016 Indian Point Nuclear Power Plant, Units 2 & 3, Proposed License Amendment Regarding the Inter-Unit Transfer of Spent Fuel ML16355A0682016-12-14014 December 2016 Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel NL-16-118, Proposed License Amendment Regarding the Inter-Unit Transfer of Spent Fuel2016-12-14014 December 2016 Proposed License Amendment Regarding the Inter-Unit Transfer of Spent Fuel CNRO-2016-00020, Application for Order to Transfer Master Decommissioning Trust from PASNY to ENO, Consenting to Amendments to Trust Agreement, and Approving Proposed License Amendments to Modify and Delete Decommissioning .2016-08-16016 August 2016 Application for Order to Transfer Master Decommissioning Trust from PASNY to ENO, Consenting to Amendments to Trust Agreement, and Approving Proposed License Amendments to Modify and Delete Decommissioning . NL-15-148, Amendment 17 to License Renewal Application (LRA)2015-12-14014 December 2015 Amendment 17 to License Renewal Application (LRA) NL-15-144, License Amendment Request - Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement2015-12-10010 December 2015 License Amendment Request - Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement NL-15-144, Indian Point, Units 2 and 3 - License Amendment Request - Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement2015-12-10010 December 2015 Indian Point, Units 2 and 3 - License Amendment Request - Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement NL-15-109, Reply to Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2015-022015-09-0101 September 2015 Reply to Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2015-02 NL-15-067, License Amendment Request - Cyber Security Plan Implementation Schedule2015-06-16016 June 2015 License Amendment Request - Cyber Security Plan Implementation Schedule NL-15-021, Proposed License Amendment Regarding a Change to Technical Specification 3.1.4 Reactivity Control Systems Indian Point Unit Number 22015-02-12012 February 2015 Proposed License Amendment Regarding a Change to Technical Specification 3.1.4 Reactivity Control Systems Indian Point Unit Number 2 NL-14-146, Amendment 16 to License Renewal Application (LRA)2014-12-15015 December 2014 Amendment 16 to License Renewal Application (LRA) NL-14-128, Proposed License Amendment Regarding Extending the Containment Type a Leak Rate Testing Frequency to 15 Years2014-12-0909 December 2014 Proposed License Amendment Regarding Extending the Containment Type a Leak Rate Testing Frequency to 15 Years ML14304A7002014-04-30030 April 2014 Annual Energy Outlook 2014 NL-13-145, Proposed License Amendment to Adopt TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Indian Point Unit Nuclear Generating Unit Nos. 2 and 32014-04-0101 April 2014 Proposed License Amendment to Adopt TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Indian Point Unit Nuclear Generating Unit Nos. 2 and 3 NL-14-035, Proposed Changes to Technical Specifications Regarding Reactor Vessel Pressure/Temperature Limit Curves2014-04-0101 April 2014 Proposed Changes to Technical Specifications Regarding Reactor Vessel Pressure/Temperature Limit Curves NL-14-016, License Amendment Request - Cyber Security Plan Implementation Schedule2014-01-30030 January 2014 License Amendment Request - Cyber Security Plan Implementation Schedule NL-13-131, Amendment 14 to License Renewal Application (LRA)2013-09-26026 September 2013 Amendment 14 to License Renewal Application (LRA) NL-13-077, License Renewal Application-Update to Electrical Meb and Structures Monitoring Program Scope, Aging Management Programs2013-05-0606 May 2013 License Renewal Application-Update to Electrical Meb and Structures Monitoring Program Scope, Aging Management Programs NL-13-015, Proposed License Amendment Regarding Connection of Non Seismic Boric Acid Recovery System to the Refueling Water Storage Tank2013-04-15015 April 2013 Proposed License Amendment Regarding Connection of Non Seismic Boric Acid Recovery System to the Refueling Water Storage Tank ML13116A0082013-04-0909 April 2013 Engineering Evaluation of Postulated RWST Inventory Loss During the Reverse Osmosis Clean-up Skid Process in Accordance to 2-TAP-001-ROS Due to Seismic Event NL-13-046, Amendment 13 to License Renewal Application (LRA) Pertaining to One-Time Inspection and Selective Leaching Programs2013-03-18018 March 2013 Amendment 13 to License Renewal Application (LRA) Pertaining to One-Time Inspection and Selective Leaching Programs ML13046A1662013-02-22022 February 2013 Issuance of Amendment Connecting Non-Seismic Purification System Piping to the Refueling Water Storage Tank NL-12-190, Amendment 12 to License Renewal Application (LRA)2012-12-27027 December 2012 Amendment 12 to License Renewal Application (LRA) NL-12-090, Proposed License Amendment Regarding Connection of Non Seismic Purification Line to Refuel Water Storage Tank2012-08-14014 August 2012 Proposed License Amendment Regarding Connection of Non Seismic Purification Line to Refuel Water Storage Tank NL-12-107, Application to Renew Operating Licenses for Indian Point Nuclear Power Reactors Unit 2 and Unit 3, General Correspondence - NL-12-1072012-08-0808 August 2012 Application to Renew Operating Licenses for Indian Point Nuclear Power Reactors Unit 2 and Unit 3, General Correspondence - NL-12-107 2023-01-17
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Entergy Nuclear Northeast Indian Point Energy Center Entergy 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel 914 734 6700 Fred Dacimo Site Vice President Administration February 22, 2005 Re: Indian Point Unit 3 Docket No. 50-286 NL-05-026 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-Pl-17 Washington, DC 20555-0001
Subject:
Additional Information Regarding Indian Point 3 License Amendment Request Alternate Source Term (TAC MC3551)
References:
- 1. Entergy letter NL-04-068 to NRC, dated June 2, 2004; regarding Alternate Source Term license amendment request.
- 2. Entergy letter NL-05-020 to NRC, dated February 11, 2005; regarding Alternate Source Term and Stretch Power Uprate license amendment requests.
Dear Sir:
Entergy Nuclear Operations, Inc (Entergy) is submitting additional information to support NRC review of the alternate source term (AST) license amendment request (Reference 1) for Indian Point 3 (IP3). This letter provides additional information regarding the recently completed tracer gas testing and also supplements the information provided in Attachment 7 of Reference 2 regarding dose consequences in the Unit 2 control room for hypothetical accidents occurring at Unit 3, and vice versa.
The additional supporting information, provided in Attachment 1, does not alter the conclusions of the no significant hazards evaluations that support the AST license amendment request. If you
- l)
NL-05-026 Docket 50-286 Page 2 of 2 have any questions or require additional information, please contact Mr. Kevin Kingsley at (914) 734-6695.
I declare under penalty of perjury that the foregoing is true and correct. Executed on Z/Z?,/20av Si e Fred R. Dacimo Site Vice President Indian Point Energy Center cc: Mr. Patrick D. Milano, Senior Project Manager Project Directorate I Division of Licensing Project Management U.S. Nuclear Regulatory Commission Mail Stop 0 8 C2 Washington, DC 20555-0001 Mr. Samuel J. Collins Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Resident Inspector's Indian Point Unit 3 U.S. Nuclear Regulatory Commission P.O. Box 337 Buchanan, NY 10511-0337 Mr. Peter R. Smith, President New York State Energy, Research and Development Authority 17 Columbia Circle Albany, NY 12203 Mr. Paul Eddy New York State Dept. of Public Service 3 Empire State Plaza Albany, NY 12223-6399
ATTACHMENT 1 TO NL-05-026 ADDITIONAL INFORMATION REGARDING AST LICENSE AMENDMENT REQUEST FOR INDIAN POINT 3 ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286
NL-05-026 Docket 50-286 Attachment 1, Page 1 of 3 NRC QUESTION:
Please discuss the impact of postulated accidents occurring at 1P3, on control room doses at the IP2 and vice versa.
ENTERGY RESPONSE:
Supplementing our response provided in letter NL-05-020 dated 2/11/05, dose calculation results are provided below for control room doses at IP3 from accidents at IP2, and for control room doses at IP2 from accidents at IP3. In addition, atmospheric diffusion factors for IP2 release points to the IP3 control room are provided. The mode of operation of the IP3 control room HVAC is the mode proposed in our AST submittal of June 2, 2004 with 1500 CFM filtered makeup in the emergency mode.
As can be seen from the results below, all dose results are well below 5 REM TEDE. Thus, it may be concluded that the requirements of GDC 19 are satisfied for accidents occurring at either unit and the effects at the other unit's control room.
Indian Point Dose (TEDE) Assumptions for Control For Comparison:
2 Event in IP3 Control Room Emergency Dose (TEDE) at IP3 Room Ventilation Mode Control Room from an Operation Event Occurring at (for column at the left) 1P3 LBLOCA 1.7 REM Switchover at 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4.4 REM Locked Rotor 0.18 REM No switchover assumed 2.5 REM Steam Line 0.14 REM No swvitchover assumed 2.1 REM Break Steam 0.37 REM No switchover assumed 2.2 REM Generator Tube Rupture Fuel 0.42 REM No switchover assumed 1.4 REM"')
Handling 2.8 REM(2)
Accident Rod Ejection 0.80 REM No switchover assumed 0.9 REM Accident SBLOCA 0.78 REM Switchover at 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2.2 REM (1) For the IP3 FHA dose of 1.4 REM, switchover at 24 minutes was assumed (2) For the IP3 FHA dose of 2.8 REM, no switchover was assumed
NL-05-026 Docket 50-286 Attachment 1, Page 2 of 3 Atmospheric Diffusion Factors for IP2 Release Points to 1P3 Control Room 95% X/Q from ARCON96 I Oto2 2to8 8to24 1 to4 4to30 ARCON96 Release Location hours hours hours days days RUN ID
- Containment Surface 6.77E-05 6.03E-05 2.44E-05 2.06E-05 1.54E-05 IP2SOIR1 Containment Vent 9.11E-05 7.84E-05 3.20E-05 2.65E-05 1.98E-05 IP2S02RI Auxiliary Boiler Feed Building Stack 9.30E-05 8.37E-05 4.15E-05 3.38E-05 2.69E-05 IP2S03R1 Auxiliary Boiler Feed Building, South side 9.25E-05 8.62E-05 4.30E-05 3.46E-05 2.77E-05 IP2S04R1
- See following pages for the ARCON96 input / output sheets for these four cases.
Indian Point Dose (TEDE) Assumptions for Control For Comparison:
3 Event in IP2 Control Room Emergency Dose (TEDE) at IP2 Room Ventilation Mode Operation Control Room from an (for column at the left) Event Occurring at 11_P2 LBLOCA 2.7 REM Switchover at 1.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 4.9 REM Locked 0.46 REM Switchover at 0.37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> 0.65 REM Rotor Steam Line 0.96 REM No switchover assumed 0.52 REM(3)
Break Steam 0.85 REM Switchover at 0.27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> 1.36 REM Generator Tube Rupture Fuel 1.4 REM No switchover assumed 3.0 REM Handling Accident Rod Ejection 0.51 REM Switchover at 0.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 1.4 REM Accident SBLOCA 1.3 REM Switchover at 0.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 3.5 REM (3) The Unit 2 Control Room dose subsequent to a SLB at Unit 3 (0.96 REM) is greater than the Unit 2 dose from a SLB at Unit 2 (0.52 REM). This is because the Unit 2 analysis does not credit switchover for an accident occurring at Unit 3, but it does credit a 60-second switchover for a SLB at Unit 2.
NL-05-026 Docket 50-286 Attachment 1, Page 3 of 3 NRC QUESTION:
The response to question 7c in Entergy letter NL-05-013, dated January 28, 2005 stated that tracer gas testing may identify the most significant sources of unfiltered inleakage. Are the X/Q values used in the AST analysis still appropriate based on inleakage source location that may have been identified during the recently completed testing?
ENTERGY RESPONSE:
The Tracer Gas Testing has been completed and the measured inleakage values were reported in Entergy Letter NL-05-020 dated February 11, 2005. Although the control room inleakage was very low in the emergency mode (less than 100 cfm), the test did indicate the major source of the leakage was associated with the pressurization fans and the air filtration unit located inside the HVAC equipment room on elevation 15 ft. Since the inlet for ventilation for this room is co-located with the inlet for the HVAC equipment for the control room, the XIQs would be identical.
l Calculation C-1109298-04 I Rev. 0l IFebruary 15, 2005 I Page 9 of l61 Program
Title:
ARCON96.
Developed For: U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date: June 25, 1997 11:00 a.m.
NRC Contacts: J. Y. Lee Phone: (301) 415 1080 e-mail: jyllgnrc.gov J. J. Hayes Phone: (301) 415 3167 e-mail: jjhgnrc.gov L. A Brown Phone: (301) 415 1232 e-mail: lab29nrc.gov Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: jramsdelllpnl.gov Code Documentation: NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.
Program Run 2/15/2005 at 11:56:47
-* AMCON
.- INPUT ..........
Number of Meteorological Data Files = 3 Meteorological Data File Names C:\IP3Prime\IPl995.MET C:\IP3Prime\IP-1996.MET C:\IP3Prime\IP_1997.MET Height of lower wind instrument (m)
- 10.0 Height of upper wind instrument (m) 60.0 Wind speeds entered as miles per hour Ground-level release Release height (m)
- 40.3 Building Area (m^2) - 3059.3 Effluent vertical velocity (mWs) - .00 Vent or stack flow (mi3/s) - .00 Vent or stack radius (m) - .00 Direction .. intake to source (deg) - 039 Wind direction sector width (deg) - 90 Wind direction window (deg)
- 354 - 084 Distance to intake (m) = 283.1 Intake height (m) = 2.3 Terrain elevation difference (m) - .0 Output file names ip2sOlrl.log ip2sOlrl.cfd Minimum Wind Speed (m/s) - .5 Surface roughness length (m) . .10 Sector averaging constant = 4.0 Initial value of sigma y = 7.32 Initial value of sigma z
- 13.31 Expanded output for code testing not selected Total number of hours of data processed - 26304 Hours of missing data 8170 Hours direction in window 8388 Hours elevated plume w/ dir. in window 0 a
Hours of calm winds
- 361 Hours direction not in window or calm - 17385 DISTRIBUTION
SUMMARY
DATA BY AVERAGING INTERVAL AVER. PER. 1 2 4 a 12 24 96 168 360 720 UPPER LIM. 1.00E-04 1.00E-04 1.OCE-04 1.00E-04 1.00E-04 1.00E-04 1.00E-04 1.OOE-04 1.00E-04 1.00E-04 LOW LIM. 1.OOE-08 1.00E-08 1.00E-08 1.OOE-08 1.00E-08 1.00E-08 1.00E-08 1.OOE-08 1.OOE-08 1.OOE-08 ABOVE RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.
IN RANGE 8749. 10120. 11940. 14553. 16663. 20420. 25538. 25549. 25378. 25002.
BELOW RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.
ZERO 17385. 15998. 14148. 11475. 9385. 5591. 303. 46. 0. 0.
TOTAL X/Qs 26134. 26118. 26088. 26028. 26048. 26011. 25841. 25595. 25378. 25002.
% NON ZERO 33.48 38.75 45.77 55.91 63.97 78.51 98.83 99.82 100.00 100.00 95th PERCENTILE X/Q VALUES 6.77E-05 6.73E-05 6.61E-05 6.22E-05 5.11E-05 3.70E-05 2.47E-05 2.10E-05 1.83E-05 1.66E-05 95% X/Q for standard averaging intervals 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 6.77E-05 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 6.03E-05 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 2.44E-05 1 to 4 days 2.06E-05 4 to 30 days 1.54E-05
ICalculation C-1109298-04 I Rev. 0 February15, 2005 I PagelOofl6 HOURLY VALUE RANGE MAX X/Q MIN X/Q CENTERLINE 8.18E-05 4.94E-06 SECTOR-AVERAGE S.13E-05 3.10E-06 NORMAL PROGRAM COMPLETION
Calculation C-1109298-04 l Rev. 0° February 15, 2005 Page l of 16 Program
Title:
ARCON96.
Developed For: U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date: June 25, 1997 11:00 a.m.
NRC Contacts: J. Y. Lee Phone: (301) 415 1080 e-mail: jyll@nrc.gov J. J. Hayes Phone: (301) 415 3167 e-mail: jjh9nrc.gov L. A Brown Phone: (301) 415 1232 e-mail: lab20nrc.gov Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: jramsdell~pnl.gov Code Documentation: NUREC/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.
Program Run 2/15/2005 at 11:56:48 ARCON INPUT ..........
Number of Meteorological Data Files
- 3 Meteorological Data File Names C:\IP3Prime\IP_1995.MNE C:\IP3Prime\IP_1996.MET C:\XP3Prime\IP_1997.MET Height of lower wind instrument (m) . 10.0 Height of upper wind instrument (m) . 60.0 Wind speeds entered as miles per hour Ground-level release Release height (m)
- 76.2 Building Area (m2) . 3059.3 Effluent vertical velocity (m/s) * .00 Vent or stack flow (m^3/s) - .00 Vent or stack radius (m) * .00 Direction .. intake to source (degl . 039 Wind direction sector width (deg) . 90 Wind direction window (deg)
- 354 - 084 Distance to intake {m) . 289.9 Intake height (m) . 2.3 Terrain elevation difference (m) * .0 Output file names ip2sO2rl.log ip2sO2rl.cfd Minimum Wind speed (m/s) * .5 Surface roughness length {m) . .10 Sector averaging constant
- 4.0 Initial value of sigma y * .26 Initial value of sigma z . .00 Expanded output for code testing not selected Total number of hours of data processed . 26304 Hours of missing data - 170 Hours direction in window . 8417 Hours elevated plume w/ dir. in window = 0 Hours of calm winds
- 293 Hours direction not in window or calm
SUMMARY
DATA BY AVERAGING INTERVAL AVER. PER. 1 2 4 8 12 24 96 168 360 720 UPPER LIM. 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-04 1.00E-04 1.OOE-04 1.00E-04 l.OOE-04 1.0OE-04 LOW LIM. 1.OOE-07 1.OOE-07 1.00E-07 1.OOE-07 l.OOE-08 1.00E-08 1.OOE-08 1.00E-08 1.OOE-08 1.00E-08 ABOVE RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.
IN RANGE 8710. 10072. 11885. 14483. 16586. 20332. 25516. 25549. 25378. 25002.
BELOW RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.
ZERO 17424. 16046. 14203. 11545. 9462. 5679. 325. 46. 0. 0.
TOTAL X/Qs 26134. 26118. 26088. 26028. 26048. 26011. 25841. 25595. 25378. 25002.
% NON ZERO 33.33 38.56 45.56 55.64 63.67 78.17 98.74 99.82 100.00 100.00 95th PERCENTILE X/Q VALUES 9.11E-05 8.94E-05 8.69E-05 8.16E-05 6.72E-05 4.85E-05 3.20E-05 2.71E-05 2.34E-05 2.14E-05 95% X/Q for standard averaging intervals 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 9.11E-05 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 7.84E-05 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 3.20E-05 1 to 4 days 2.65E-05 4 to 30 days 1.98E-05
I Calculation C-1109298-04 I Rev. 01 February 15, 2005 Page 12 of 161 HOURLY VALUE RANGE MAX X/Q MEN X/Q CENTERLINE 1.11E-04 5.12E-06 SECTOR-AVERAGE 6.98E-05 3.21E-06 NORMAL PROGRAM COMPLETION
l Calculation C-1109298-04 I Rev. 01 lFebruary I5,2005 I Page13 of 166l Program
Title:
ARCON96.
Developed For: U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date: June 25. 1997 11:00 a.m.
NRC Contacts: J. Y. Lee Phone: (301) 415 1080 e-mail: jyll~nrc.gov J. J. Hayes Phone: (301) 415 3167 e-mail: jjh~nrc.gov L. A Brown Phone: (301) 415 1232 e-mail: lab2Qnrc.gov Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: j_.ramsdellQpnl.gov Code Documentation: NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.
Program Run 2/15/2005 at 11:56:48 ARCON INPVT .........
Number of Meteorological Data Files . 3 Meteorological Data File Names C:\IP3Prime\IP.199S.MET C:\IP3Prime\IP_1996.MET C:\IP3Prime\IP.1997.MET Height of lower wind instrument (m) - 10.0 Height of upper wind instrument (m)
- 60.0 Wind speeds entered as miles per hour Ground-level release Release height (m) - 23.9 Building Area (mW2)
- 3059.3 Effluent vertical velocity (mis) - .00 Vent or stack flow (m^3/s) * .00 Vent or stack radius (mi) .00 Direction .. intake to source (deg)
- 033 Wind direction sector width (deg) - 90 Wind direction window (deg)
- 348 - 078 Distance to intake (m) - 291.1 Intake height (m) - 2.3 Terrain elevation difference (m) - .0 Output file names ip2s03rl.2og ip2sO3rl.cfd Minimum Wind Speed (mWs) * .5 Surface roughness length (m) . .10 Sector averaging constant
- 4.0 Initial value of sigma y * .28 Initial value of sigma z - .00 Expanded output for code testing not selected Total number of hours of data processed
- 26304 Hours of missing data
- 170 Hours direction in window
- 10598 Hours elevated plume w/ dir. in window - 0 Hours of calm winds - 284 Hours direction not in window or calm
SUMMARY
DATA BY AVERAGING INTERVAL AVER. PER. 1 2 4 8 12 24 96 168 360 720 UPPER LIM. 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 l.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 LOW LIM. 1.OOE-07 2.OOE-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.OOE-07 l.00E-07 1.OOE-07 ABOVE RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.
IN RANGE 10882. 12327. 14241. 16991. 19093. 22469. 25748. 25595. 25378. 25002.
BELOW RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.
ZERO 15252. 13791. 11847. 9037. 6955. 3542. 93. 0. 0. 0.
TOTAL X/Qs 26134. 26118. 26088. 26028. 26048. 26011. 25841. 25595. 25378. 25002.
% NON ZERO 41.64 47.20 54.59 65.28 73.30 86.38 99.64 100.00 100.00 100.00 95th PERCENTILE X/0 VALUES 9.30E-05 9.10E-05 8.94E-05 8.60E-05 7.30E-05 5.63E-05 3.95E-05 3.43E-05 3.10E-05 2.86E-05 95% X/Q for standard averaging intervals 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 9.30E-05 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 8.37E-05 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 4.15E-05 1 to 4 days 3.38E-05 4 to 30 days 2.69E-05
ICalculation C-1109298-04 I Rev. 0° l February 15, 2005 l Page 14 of 161 HOURLY VALUE RANGE MAX X/Q MIN X/Q CENTERLINE 1.16E-04 1.21E-05 SECTOR-AVERAGE 7.29E-05 7.59E-06 NORMAL PROGRAM COMPLETION
ICalculation C-1109298-04 I Rev. 0o lFebruary15, 2005 Page15 of 16 l Program
Title:
ARCON96.
Developed For: U.S. Nuclear Regulatory Conmission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date: June 25, 1997 11:00 a.m.
NRC Contacts: J. Y. Lee Phone: (301) 415 1080 e-mail: jyllonrc.gov
- 3. J. Hayes Phone: (301) 415 3167 e-mail: jjh9nrc.gov L. A Brown Phone: (301) 415 1232 e-mail: lab29nrc.gov Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: Jramsdell~pnl.gov Code Documentation: NuREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, rakes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.
Program Run 2/15/2005 at 11:56:48 ARCON
....... INPUT ..........
Number of Meteorological Data Files = 3 Meteorological Data File Names C:\IP3Prime\IP._l995.MET C:\IP3Prime\IPl996.MET C: \IP3Prime\IP._l997.MET Height of lower wind instrument {m)
- 10.0 Height of upper wind instrument {m) - 60.0 Wind speeds entered as miles per hour Ground-level release Release height Cm) W 13.7 Building Area (m^2) - 3059.3 Effluent vertical velocity (m/s) = .00 Vent or stack flow (m^3/s) = .00 Vent or stack radius {i) * .00 Direction .. intake to source (deg)
- 033 Wind direction sector width (deg) - 90 Wind direction window (deg) - 348 - 078 Distance to intake Cm) - 278.5 Intake height {m) = 2.3 Terrain elevation difference Cm) = .0 Output file names ip2sO4rl.log ip2sO4rl.cfd Minimum Wind Speed (m/s) - .5 Surface roughness length Cm) . .10 Sector averaging constant - 4.0 Initial value of sigma y - 1.41 Initial value of sigma z ' 1.41 Expanded output for code testing not selected Total number of hours of data processed . 26304 Hours of missing data . 170 Hours direction in window . 10598 Hours elevated plume w/ dir. in window . 0 Hours of calm winds - 284 Hours direction not in window or calm
- 15252 DISTRIBUTION SUMnMARY DATA BY AVERAGING INTERVAL AVER. PER. 1 2 4 8 12 24 96 168 360 720 UPPER LIM. 1.00E-03 1.OOE-03 1.OOE-03 1.OOE-03 1.00E-03 1.OOE-03 1.00E-03 1.OOE-03 1.OOE-03 1.OOE-03 LOW LIM. 1.00E-07 1.OOE-07 1.OOE-07 1.OOE-07 1.00E-07 1.OOE-07 1.OOE-07 1.00E-07 1.00E-07 1.00E-07 ABOVE RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.
IN RANGE 10882. 12327. 14241. 16991. 19093. 22469. 25748. 25595. 25378. 25002.
BELOW RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.
ZERO 15252. 13791. 11847. 9037. 6955. 3542. 93. 0. 0. 0.
TOTAL X/Qs 26134. 26118. 26088. 26028. 26048. 26011. 25841. 25595. 25378. 25002.
% NON ZERO 41.64 47.20 54.59 65.28 73.30 86.38 99.64 100.00 100.00 100.00 95th PERCErTILE X/Q VALUES 9.25E-05 9.12E-05 9.02E-05 8.78E-05 7.40E-05 5.80E-05 4.04E-05 3.52E-05 3.19E-05 2.94E-05 95% X/Q for standard averaging intervals 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 9.25E-05 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 8.62E-05 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 4.30E-05 1 to 4 days 3.46E-05 4 to 30 days 2.77E-05
ICalculation C-1109298-04 I Rev. 0l lFebruary 15, 2005 I Pagcl6of16l HOURLY VALUE RANGE MAX X/Q MIN X/Q CENTERLINE 1.23E-04 1.43E-05 SECTOR-AVERAGE 7.72E-05 8.94E-06 NORMAL PROGRAM COMPLETION