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Category:Graphics incl Charts and Tables
MONTHYEARML24156A1162024-06-0404 June 2024 Correction - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations CNRO-2018-00011, Submittal of Joint Plant Access Shared Information Table2018-03-19019 March 2018 Submittal of Joint Plant Access Shared Information Table ML17150A2562017-06-0505 June 2017 Entergy Fleet - 2017 Onsite Insurance Submittal Review for Entergy Operations, Inc., and Entergy Nuclear Operations, Inc. (CAC No. TM3058) ML16112A1722016-04-25025 April 2016 Indian Point Nuclear Generating Unit Nos. 2 And 3 Interim Staff Response To Reevaluated Flood Hazards Submitted In Response To 10 CFR 50.54 (f) Information Request Flood-Causing Mechanism Reevaluation (CAC NOS. MF3313 and MF3314) NL-16-035, Supplemental to Basis for Performance of the Mitigating Strategies Assessment with Flood Hazard Information & Report for Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid2016-04-0505 April 2016 Supplemental to Basis for Performance of the Mitigating Strategies Assessment with Flood Hazard Information & Report for Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports NL-15-019, Reply to Request for Additional Information 3.0.3-2 from Set 2014-01 for the Review of the License Renewal Application2015-03-10010 March 2015 Reply to Request for Additional Information 3.0.3-2 from Set 2014-01 for the Review of the License Renewal Application ML11221A3052011-08-0909 August 2011 Lr Hearing - NIA-078 NL-11-013, Revised Tables from Responses to Requests for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions2011-02-10010 February 2011 Revised Tables from Responses to Requests for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions ML0936409322009-12-30030 December 2009 Table I, Structural Heat Sinks, Table II, Containment Heat Sink Thermodynamic Data NL-09-151, Telephone Conference Call Regarding Met Tower Data for SAMA Analysis2009-11-16016 November 2009 Telephone Conference Call Regarding Met Tower Data for SAMA Analysis NL-09-018, Reply to Request for Additional Information - Miscellaneous Items2009-01-27027 January 2009 Reply to Request for Additional Information - Miscellaneous Items ML11221A3032008-12-22022 December 2008 Lr Hearing - NIA-077 NL-08-144, Program for Maintenance of Irradiated Fuel and Preliminary Decommissioning Cost Analysis in Accordance with 10 CFR 50.54 (Bb) and 10 CFR 50.75(f)(3)2008-10-23023 October 2008 Program for Maintenance of Irradiated Fuel and Preliminary Decommissioning Cost Analysis in Accordance with 10 CFR 50.54 (Bb) and 10 CFR 50.75(f)(3) ML0905604702008-08-31031 August 2008 Long-Term Monitoring Plan Position Paper ML11221A1262008-08-14014 August 2008 Lr Hearing - NIA-076, Table 1, Projections of the Population and Components of Change for Us: 2010 to 2050 ENOC-08-00040, Commitment Update Relating to Application for Order Approving Indirect Transfer of Control of Licenses2008-07-28028 July 2008 Commitment Update Relating to Application for Order Approving Indirect Transfer of Control of Licenses ML0904006772008-07-0101 July 2008 Unit 3 SBO Event: Time Line to Energize Unit 3 Bus from App R Diesel Via Gt/Bt ML0904006972008-07-0101 July 2008 SBO Event: Time Line to Energize a 480V Bus from GT-25/26 and App R Diesel ML0904100382008-07-0101 July 2008 SBO Event: Time Line to Energize 480V Bus 6A from GT-25/26 and App R Diesel (Total Time: 47 Minutes) ML0904100962008-07-0101 July 2008 ECN 7385; Attachment 7.46 - Post MOD Test Plan ML0904104002008-06-17017 June 2008 Vendor Data for 24-Hr. Run; Entergy, Buchanan, Ny ML0814804812008-05-27027 May 2008 NRC Graphics - Indian Point ML0905101052008-05-0505 May 2008 Trend Report for Nuclides: Co-60, Cs-137, H-3, Ni-63, Sr-90 ML0905101062008-05-0505 May 2008 M10 Investigation Wells NL-08-074, Amendment 4 to License Renewal Application (LRA) Letter Dated April 30, 2008 from Entergy Nuclear Northeast (NL-08-074)2008-04-30030 April 2008 Amendment 4 to License Renewal Application (LRA) Letter Dated April 30, 2008 from Entergy Nuclear Northeast (NL-08-074) ML0905401352008-01-10010 January 2008 Ground Water Monitoring Well Information Table ML0905102022008-01-0808 January 2008 Groundwater Investigation - Summary NYS Results as of 01/08/2008 ML0736200892007-12-20020 December 2007 Report for Analysis or Eight Water Samples from Set 6 from the Indian Point Power Station, Buchanan, New York Dated December 20, 2007 ENOC-07-00036, Entergy Operations, Inc. - Supplemental Information in Support of Application for Order Approving Indirect Transfer of Control of Licenses2007-10-31031 October 2007 Entergy Operations, Inc. - Supplemental Information in Support of Application for Order Approving Indirect Transfer of Control of Licenses ML0731801672007-10-18018 October 2007 Report for Analysis of Seven Water Samples from Set Five from the Indian Point Power Station, Buchanan, New York, Dtd October 18, 2007 ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0729502532007-10-10010 October 2007 Siren Schedule 11 X 17 Dtd 10/10/07 ML0728403122007-07-31031 July 2007 Report for Analysis for Samples from Set Twenty-Four from the Indian Point Power Station, Buchanan, New York. Dtd. July 31, 2007 ML0728402552007-05-0303 May 2007 Interim Report for Completed Analysis for Samples from Set Twenty-One from the Indian Point Power Station, Buchanan, New York. Dtd. May 3, 2007 ML0713102862007-03-20020 March 2007 E-Mail from D. Winslow of GZA to M. Barvenik of GZA, J. Noggle of USNRC and J. Adler of Entergy, Regarding GZA Results ML0713100562007-02-15015 February 2007 E-Mail from T. Rice of NYSDEC to Various, Regarding Latest State Results ML0713100452007-02-12012 February 2007 E-Mail from P. Donahue of Entergy to T. Rice of NYSDEC, Regarding Split Sample Data ML0713005932007-01-24024 January 2007 E-Mail from D. Gray of Entergy to J. Noggle of USNRC, Regarding Historical Sr Data ML0709405042007-01-12012 January 2007 Ltr from Orise Dtd 01/12/2007, Final Letter Report for Requested Analyses of Six Water Samples, Set Eleven, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006-007) (Rfta No. 06-001) IR 05000247/20060072007-01-0404 January 2007 Ltr from Orise Dtd 01/04/2007, Final Letter Report for Requested Analyses of Nine Water Samples, Set Nine, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006007) (Rfta No. 06-001) ML0709406182007-01-0404 January 2007 Ltr from Orise Dtd 01/04/2007, Final Letter Report for Requested Analyses of Nine Water Samples, Set Nine, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006007) (Rfta No. 06-001) ML0701105612006-12-15015 December 2006 Interim Report for Completed Analyses for Samples from Sets Fifteen and Sixteen, from the Indian Point Power Station, Buchanan, New York. (Inspection Report No. 050-247/2006-007) (Rfta No. 06-001) ML0704003112006-12-0404 December 2006 E-Mail from T. Rice of Department of Environmental Conservation to J. Adler of Entergy, and J. Noggle and J. White of USNRC, Regarding Latest State Data ML0704002992006-11-28028 November 2006 E-Mail from T. Rice of Department of Environmental Conservation to Various, Regarding Latest State Results ML0701105482006-11-17017 November 2006 Interim Report for Requested Analyses for Samples from Sets Eleven Through Fourteen, from the Indian Point Power Station, Buchanan, New York. (Inspection Report No. 050-247/2006-007) (Rfta No. 06-001) ML0628302122006-06-15015 June 2006 E-mail from R. Lavera of Entergy to J. Noggle of NRC, Regarding Sample Log ML0618605182006-04-26026 April 2006 E-mail from R. Sachatello of Entergy to M. Barvenik and D. Sinslow of GZA, Regarding Pressure Test Discussion with GZA ML0620001512006-04-13013 April 2006 E-mail from K. Mcmullian, Entergy, to J. Boska, NRR, Et Al., IPEC Status Report April 13 ML0610006912006-03-27027 March 2006 Units 1 & 2 Tritium History (GL-80-10), in Nci/Ml 2024-06-04
[Table view] Category:Letter type:NL
MONTHYEARNL-21-034, Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals2021-05-26026 May 2021 Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals NL-21-039, Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary2021-05-20020 May 2021 Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary NL-21-033, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2021-05-11011 May 2021 Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel NL-21-032, Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center2021-05-11011 May 2021 Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center NL-21-005, Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions2021-05-11011 May 2021 Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions NL-21-030, Submittal of 2020 Annual Radiological Environmental Operating Report2021-05-0606 May 2021 Submittal of 2020 Annual Radiological Environmental Operating Report NL-21-027, Registration of Spent Fuel Cask Use2021-04-20020 April 2021 Registration of Spent Fuel Cask Use NL-21-021, Registration of Spent Fuel Cask Use2021-04-19019 April 2021 Registration of Spent Fuel Cask Use NL-21-017, Pre-Notice of Disbursement from Decommissioning Trusts2021-04-0808 April 2021 Pre-Notice of Disbursement from Decommissioning Trusts NL-21-010, Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2021-02-17017 February 2021 Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report NL-21-006, Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement2021-02-10010 February 2021 Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement NL-21-014, Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2021-01-26026 January 2021 Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-082, Notice of Planned Transfer of Decommissioning Funds2020-12-14014 December 2020 Notice of Planned Transfer of Decommissioning Funds NL-20-081, Pre-Notice of Disbursement from Decommissioning Trusts2020-12-0909 December 2020 Pre-Notice of Disbursement from Decommissioning Trusts NL-20-080, Report in Accordance with 10 CFR 71.95(a) for Failure to Comply with Certificate of Compliance No. 71-93212020-11-19019 November 2020 Report in Accordance with 10 CFR 71.95(a) for Failure to Comply with Certificate of Compliance No. 71-9321 NL-20-079, (IP2 and IP3) - Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-12012 November 2020 (IP2 and IP3) - Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NL-20-077, Submittal of Quality Assurance Program Manual Revision 22020-11-0909 November 2020 Submittal of Quality Assurance Program Manual Revision 2 NL-20-078, Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-11-0909 November 2020 Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-076, Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal2020-11-0202 November 2020 Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal NL-20-069, One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency2020-10-0808 October 2020 One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency NL-20-070, Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-10-0202 October 2020 Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-067, Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-09-16016 September 2020 Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-064, 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments2020-09-0101 September 2020 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments NL-20-060, Status of Remaining Actions for Generic Letter 2004-022020-08-11011 August 2020 Status of Remaining Actions for Generic Letter 2004-02 NL-20-057, Cancellation of Commitment Related to Large Break LOCA Reanalysis2020-07-30030 July 2020 Cancellation of Commitment Related to Large Break LOCA Reanalysis NL-20-0851, 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material2020-07-22022 July 2020 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material NL-20-051, Submittal of Quality Assurance Program Manual, Revision 1 for the Indian Point Energy Center2020-07-0707 July 2020 Submittal of Quality Assurance Program Manual, Revision 1 for the Indian Point Energy Center NL-20-052, Unsatisfactory 10 CFR 26 Fitness-For-Duty Blind Performance Testing Results2020-07-0707 July 2020 Unsatisfactory 10 CFR 26 Fitness-For-Duty Blind Performance Testing Results NL-20-012, Application to Revise Provisional Operating License and Technical Specifications2020-06-30030 June 2020 Application to Revise Provisional Operating License and Technical Specifications NL-20-050, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-06-24024 June 2020 Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-041, Registration of Unit 3 Spent Fuel Cask Use2020-05-13013 May 2020 Registration of Unit 3 Spent Fuel Cask Use NL-20-042, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2020-05-12012 May 2020 Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel NL-20-033, Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2020-04-28028 April 2020 Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-20-038, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-04-23023 April 2020 Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-035, Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-16016 April 2020 Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic NL-20-034, Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-13013 April 2020 Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic NL-20-021, Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-03-24024 March 2020 Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-020, Submittal of 2019 Annual Fitness for Duty Performance Data Report Update2020-02-26026 February 2020 Submittal of 2019 Annual Fitness for Duty Performance Data Report Update NL-20-015, Submittal of 2019 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2020-02-10010 February 2020 Submittal of 2019 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report NL-20-008, Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane2020-01-0606 January 2020 Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane NL-19-094, 2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2019-12-16016 December 2019 2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report NL-19-084, Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments2019-11-21021 November 2019 Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments NL-19-093, Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.12019-11-21021 November 2019 Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.1 NL-19-092, Request for Rescission of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-11-20020 November 2019 Request for Rescission of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) NL-19-043, Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.122019-10-22022 October 2019 Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.12 NL-19-073, Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-10-22022 October 2019 Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) NL-19-078, Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2019-10-22022 October 2019 Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-19-091, Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use2019-10-17017 October 2019 Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use NL-19-090, Registration of Unit 2 Spent Fuel Cask Use2019-10-0909 October 2019 Registration of Unit 2 Spent Fuel Cask Use NL-19-079, 50.59(d)(2) Summary Report of Changes, Tests and Experiments2019-09-26026 September 2019 50.59(d)(2) Summary Report of Changes, Tests and Experiments 2021-05-06
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Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box249 Buchanan, NY 10511-0249 Tel 914 254 6700 Lawrence Coyle Site Vice President NL-16-035 April 5, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11545 Rockville Pike, TWFN-2F1
- ' Rockville, MD 20852-2738
SUBJECT:
Entergy Supplement to Basis For Performance of the Mitigating Strategies Assessment with the Flood Hazard Information And Report For Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Indian Point Units 2 and 3 Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and 64
REFERENCES:
- 1. Entergy Letter to NRC, NL-16-029, "Entergy Basis For Performance of the Mitigating Strategies Assessment with the Flood Hazard Information And Report For Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 21, 2016.
Dear Sir or Madam:
The purpose of this letter is to supplement and clarify the information provided in reference 1 consistent with the discussions held with the NRC on March 24, 2016 and the information provided at that time.
Please be advised as follows:
- 1. The value of "3.9 ft. 0Afave)", listed in the column labeled "Wave Height/Runup" in the second row of data in Table 1 is a typographical error. The correct value is "3.0 ft. 0Afave)". The Reevaluated Hazard Elevation of 21.0 ft. is correct and does not change.
- 2. In the first two data rows of Table 1, as submitted, the values for "Stillwater Elevation" plus "Wave Height/Runup" did not sum to the "Reevaluated Hazard Elevation" value presented in the fourth column. The reason is that in these two rows, the values presented in the "Wave Height/Runup" column represent the total wave heights (full amplitude) for these locations. The total wave heights were provided for these locations to represent open areas without structures for waves to run up or reflect against. The Reevaluated Hazard Elevation values for these two columns represent the wave crest elevations, which are found by summing the stillwater elevation with the portion of the wave height which is above the stillwater level.
I I
I
NL-16-035 Docket Nos. 50-247 and 50-286 Page 2 of 3
- 3. The wave at* Location A represents a deepwater wave (i.e., the wave condition within the river near the bulkhead). Fifty percent (50%) of the total height of this wave is above the stillwater level; therefore, the Reevaluation Hazard Elevation was found as follows:
18.9 ft. [stillwater elevation]+ (0.5 x 5.7 ft. [total wave height])= 21.8 ft. NGVD29 [rounded up]
- 4. The wave in the area Between A and B (i.e., the open area of the powerblock yard inboard of the river bulkhead) is a depth-limited wave. Depth-limited waves have a deformed wave form which results in seventy percent (70%) of the total wave height above the stillwater level; therefore the Reevaluation Hazard Elevation was found as follows:
18.9 ft. [stillwater elevation]+ (0.7 x 3.0 ft. [total wave height])= 21.0 ft. NGVD29
- 5. The Reevaluated Hazard Elevations for the first two data rows, representing the wave crest elevations for these locations, are reported correctly in Table 1. For all other data rows, the values in the "Wave Height/Runup" represent the height of wave run-up above stillwater level (wave runup or reflection; collectively referred to as runup) on a vertical surface such as a building wall.
- a. The terms "Wave Height" and "Runup" were used in the column heading above the individual table cells to distinguish where information on total wave height or runup was provided in Table 1, as submitted.
- b. The Reevaluated Hazard Elevations presented in the first two data rows are for areas in or nearer to the river. The Reevaluated Hazard Elevations are lower than the elevations at the Turbine Buildings, which are farther inland, because the elevations reported for the first two data rows are only wave crest elevations whereas the elevations reported at the turbine buildings are the result of wave runup on the vertical walls of the buildings.
- 6. The Location Between A and B was described as "landward" of the U2 Intake Structure. This was intended to describe the open area of the powerblock yard located inboard of the river bulkhead and gen~rally between the U2 service water pumps and the U2 Turbine Building. The term "riverward," when used to describe Locations Band D, was intended to identify the river-facing (west) portions of the U2 and U3 Turbine Buildings which are exposed to wave action, as opposed to the east sides of the Turbine Buildings which are sheltered from wave action.
The NRC also requested additional information regarding Reevaluated Hazard Elevations at the Intake Structures for Unit 2 and Unit 3. These $tructures are located adjacent to and inboard (i.e., on the land side) of the bulkhead. The top of the river bulkhead. is nominally at elevation 15.0 feet NGVD29; therefore, the top of the bulkhead and surrounding land/paved areas are submerged when the stillwater elevation is at 18.9 ft. NGVD29. The portion of the deepwaterwave spectrum with large heights (i.e.,
> greater than the depth limited wave height) will break as they encroach the bulkhead and shallow water. The intake structures, systems, and components are set back from the edge of the bulkhead.
The broken wave component of these waves may impact these structures as wave splash and hydrodynamic loads. The portions of the wave spectrum with waves equal to or less than the depth- ,
limited wave height will propagate toward the buildings as unbroken waves and result in run-up at vertical structure faces and hydrostatic and hydrodynamic loads. The maximum runup on these vertical structures will be caused by the depth-limited waves, here with a total wave height of 3.0*feet, resulting in a total run-up of 4. 7 feet and a Reevaluated Hazard Elevation of 23.6 feet NGVD29.
NL-16-035 Docket Nos. 50-24 7 and 50-286 Page 3 of 3 A revised version of Table 1, including a row describing the Reevaluated Hazard Elevation for the river-facing (i.e. west) side of any structure inboard of the river bulkhead, including the U2 and U3 Intake Structures, is presented in the Attachment.
There are no new commitments contained in this submittal. If you have any questions regarding this confirmation of receipt, please contact Mr. Robert Walpole, Manager, Regulatory Assurance at (914) 254-6710. \ -
Respectfully, LC/sp vations For Wind - Wave Activity Effects cc: Mr. Douglas Pickett, Senior Project Manager, NRC NRR DORL Mr. Daniel H. Dorman, Regional Administrator, NRC Region 1 NRC Resident Inspector Mr. John B. Rhodes, President and CEO, NYSERDA .
Ms. Bridget Frymire, New York State Dept. of Public Service
ATTACHMENT 1 TO NL-16-035 CALCULATED WATER ELEVATIONS FOR WIND - WAVE ACTIVITY EFFECTS ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 DOCKET NOS. 50-247 AND 50-286
Attachment NL-16-035 Docket Nos. 50-247 and 50-286 Page 1of1 Table 1: IPEC Hazard Evaluation Summary Table - River Flow of 150,000 cfs Mechanism Stillwater Wave Height Reevaluated Figure Storm Surge Elevation above Stillwater/ Hazard Location (see Runup above Elevation Reference 1)
Stillwater H.3 Combined Flood Event -
Open Water in River Outboard 18.9 ft 2.9ft 21.8 ft of River Bulkhead and U2 Intake A NGVD29 NGVD29 Structure (See Note 1 below)
H.3 Combined Flood Event -
Open Areas of Powerblock Yard 18.9 ft 2.1 ft 21.0 ft Between A between U2 Intake Structure NGVD29 NGVD29 and B and U2 Turbine Building (See Notes 1 and 3 below)
H.3 Combined Flood Event Includes West River-facing Sides of Structures 18.9 ft 4.7ft 23.6 ft Sides of U2 between the River Bulkhead and NGVD29 NGVD29 and U3 Intake the Turbine Buildings Structures (See Notes 2 and 3 below)
H.3 Combined Flood Event River-Facing (West) Side of U2 18.9 ft 4.7 ft 23.6 ft B
Turbine Building NGVD29 NGVD29 (See Notes 2 and 3 below)
H.3 Combined Flood Event 18.9ft 18.9 ft East of U2 Turbine Building NGVD29 Minimal NGVD29 c
(See Note 3 below)
H.3 Combined Flood Event River-Facing (West) Side of U3 18.9 ft 4.7 ft 23.6 ft .o Turbine Building NGVD29 NGVD29 (See Notes 2 and 3 below)
H.3 Combined Flood Event 18.9 ft 18.9 ft East of U3 Turbine Building Minimal E NGVD29 NGVD29 (See Note 3 below)
Notes:
- 1. Values for Reevaluated Hazard Elevations for Open Water in River Outboard of River Bulkhead and U2 Intake Structure and Open Areas of Powerblock Yard between U2 Intake Structure and U2 Turbine Building describe the top of wave elevations (wave crest elevation) in those open areas where there is no structure for the wave to impact upon.
- 2. Wave runup on the river-facing side (i.e. west side) structures inboard (i.e., to the east) of the river bulkhead is a result of run-up or reflection of that portion of the wave spectrum propagating inland which is equal to or less than the depth limited wave height.
- 3. Conservatively, only areas behind the turbine buildings have been designated as sheltered from waves.
Other locations and systems may also be locally sheltered, partially or fully, by existing structures on the site. Examples include the Unit 2 and 3 Service Water Pumps.
Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box249 Buchanan, NY 10511-0249 Tel 914 254 6700 Lawrence Coyle Site Vice President NL-16-035 April 5, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11545 Rockville Pike, TWFN-2F1
- ' Rockville, MD 20852-2738
SUBJECT:
Entergy Supplement to Basis For Performance of the Mitigating Strategies Assessment with the Flood Hazard Information And Report For Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Indian Point Units 2 and 3 Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and 64
REFERENCES:
- 1. Entergy Letter to NRC, NL-16-029, "Entergy Basis For Performance of the Mitigating Strategies Assessment with the Flood Hazard Information And Report For Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 21, 2016.
Dear Sir or Madam:
The purpose of this letter is to supplement and clarify the information provided in reference 1 consistent with the discussions held with the NRC on March 24, 2016 and the information provided at that time.
Please be advised as follows:
- 1. The value of "3.9 ft. 0Afave)", listed in the column labeled "Wave Height/Runup" in the second row of data in Table 1 is a typographical error. The correct value is "3.0 ft. 0Afave)". The Reevaluated Hazard Elevation of 21.0 ft. is correct and does not change.
- 2. In the first two data rows of Table 1, as submitted, the values for "Stillwater Elevation" plus "Wave Height/Runup" did not sum to the "Reevaluated Hazard Elevation" value presented in the fourth column. The reason is that in these two rows, the values presented in the "Wave Height/Runup" column represent the total wave heights (full amplitude) for these locations. The total wave heights were provided for these locations to represent open areas without structures for waves to run up or reflect against. The Reevaluated Hazard Elevation values for these two columns represent the wave crest elevations, which are found by summing the stillwater elevation with the portion of the wave height which is above the stillwater level.
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NL-16-035 Docket Nos. 50-247 and 50-286 Page 2 of 3
- 3. The wave at* Location A represents a deepwater wave (i.e., the wave condition within the river near the bulkhead). Fifty percent (50%) of the total height of this wave is above the stillwater level; therefore, the Reevaluation Hazard Elevation was found as follows:
18.9 ft. [stillwater elevation]+ (0.5 x 5.7 ft. [total wave height])= 21.8 ft. NGVD29 [rounded up]
- 4. The wave in the area Between A and B (i.e., the open area of the powerblock yard inboard of the river bulkhead) is a depth-limited wave. Depth-limited waves have a deformed wave form which results in seventy percent (70%) of the total wave height above the stillwater level; therefore the Reevaluation Hazard Elevation was found as follows:
18.9 ft. [stillwater elevation]+ (0.7 x 3.0 ft. [total wave height])= 21.0 ft. NGVD29
- 5. The Reevaluated Hazard Elevations for the first two data rows, representing the wave crest elevations for these locations, are reported correctly in Table 1. For all other data rows, the values in the "Wave Height/Runup" represent the height of wave run-up above stillwater level (wave runup or reflection; collectively referred to as runup) on a vertical surface such as a building wall.
- a. The terms "Wave Height" and "Runup" were used in the column heading above the individual table cells to distinguish where information on total wave height or runup was provided in Table 1, as submitted.
- b. The Reevaluated Hazard Elevations presented in the first two data rows are for areas in or nearer to the river. The Reevaluated Hazard Elevations are lower than the elevations at the Turbine Buildings, which are farther inland, because the elevations reported for the first two data rows are only wave crest elevations whereas the elevations reported at the turbine buildings are the result of wave runup on the vertical walls of the buildings.
- 6. The Location Between A and B was described as "landward" of the U2 Intake Structure. This was intended to describe the open area of the powerblock yard located inboard of the river bulkhead and gen~rally between the U2 service water pumps and the U2 Turbine Building. The term "riverward," when used to describe Locations Band D, was intended to identify the river-facing (west) portions of the U2 and U3 Turbine Buildings which are exposed to wave action, as opposed to the east sides of the Turbine Buildings which are sheltered from wave action.
The NRC also requested additional information regarding Reevaluated Hazard Elevations at the Intake Structures for Unit 2 and Unit 3. These $tructures are located adjacent to and inboard (i.e., on the land side) of the bulkhead. The top of the river bulkhead. is nominally at elevation 15.0 feet NGVD29; therefore, the top of the bulkhead and surrounding land/paved areas are submerged when the stillwater elevation is at 18.9 ft. NGVD29. The portion of the deepwaterwave spectrum with large heights (i.e.,
> greater than the depth limited wave height) will break as they encroach the bulkhead and shallow water. The intake structures, systems, and components are set back from the edge of the bulkhead.
The broken wave component of these waves may impact these structures as wave splash and hydrodynamic loads. The portions of the wave spectrum with waves equal to or less than the depth- ,
limited wave height will propagate toward the buildings as unbroken waves and result in run-up at vertical structure faces and hydrostatic and hydrodynamic loads. The maximum runup on these vertical structures will be caused by the depth-limited waves, here with a total wave height of 3.0*feet, resulting in a total run-up of 4. 7 feet and a Reevaluated Hazard Elevation of 23.6 feet NGVD29.
NL-16-035 Docket Nos. 50-24 7 and 50-286 Page 3 of 3 A revised version of Table 1, including a row describing the Reevaluated Hazard Elevation for the river-facing (i.e. west) side of any structure inboard of the river bulkhead, including the U2 and U3 Intake Structures, is presented in the Attachment.
There are no new commitments contained in this submittal. If you have any questions regarding this confirmation of receipt, please contact Mr. Robert Walpole, Manager, Regulatory Assurance at (914) 254-6710. \ -
Respectfully, LC/sp vations For Wind - Wave Activity Effects cc: Mr. Douglas Pickett, Senior Project Manager, NRC NRR DORL Mr. Daniel H. Dorman, Regional Administrator, NRC Region 1 NRC Resident Inspector Mr. John B. Rhodes, President and CEO, NYSERDA .
Ms. Bridget Frymire, New York State Dept. of Public Service
ATTACHMENT 1 TO NL-16-035 CALCULATED WATER ELEVATIONS FOR WIND - WAVE ACTIVITY EFFECTS ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 DOCKET NOS. 50-247 AND 50-286
Attachment NL-16-035 Docket Nos. 50-247 and 50-286 Page 1of1 Table 1: IPEC Hazard Evaluation Summary Table - River Flow of 150,000 cfs Mechanism Stillwater Wave Height Reevaluated Figure Storm Surge Elevation above Stillwater/ Hazard Location (see Runup above Elevation Reference 1)
Stillwater H.3 Combined Flood Event -
Open Water in River Outboard 18.9 ft 2.9ft 21.8 ft of River Bulkhead and U2 Intake A NGVD29 NGVD29 Structure (See Note 1 below)
H.3 Combined Flood Event -
Open Areas of Powerblock Yard 18.9 ft 2.1 ft 21.0 ft Between A between U2 Intake Structure NGVD29 NGVD29 and B and U2 Turbine Building (See Notes 1 and 3 below)
H.3 Combined Flood Event Includes West River-facing Sides of Structures 18.9 ft 4.7ft 23.6 ft Sides of U2 between the River Bulkhead and NGVD29 NGVD29 and U3 Intake the Turbine Buildings Structures (See Notes 2 and 3 below)
H.3 Combined Flood Event River-Facing (West) Side of U2 18.9 ft 4.7 ft 23.6 ft B
Turbine Building NGVD29 NGVD29 (See Notes 2 and 3 below)
H.3 Combined Flood Event 18.9ft 18.9 ft East of U2 Turbine Building NGVD29 Minimal NGVD29 c
(See Note 3 below)
H.3 Combined Flood Event River-Facing (West) Side of U3 18.9 ft 4.7 ft 23.6 ft .o Turbine Building NGVD29 NGVD29 (See Notes 2 and 3 below)
H.3 Combined Flood Event 18.9 ft 18.9 ft East of U3 Turbine Building Minimal E NGVD29 NGVD29 (See Note 3 below)
Notes:
- 1. Values for Reevaluated Hazard Elevations for Open Water in River Outboard of River Bulkhead and U2 Intake Structure and Open Areas of Powerblock Yard between U2 Intake Structure and U2 Turbine Building describe the top of wave elevations (wave crest elevation) in those open areas where there is no structure for the wave to impact upon.
- 2. Wave runup on the river-facing side (i.e. west side) structures inboard (i.e., to the east) of the river bulkhead is a result of run-up or reflection of that portion of the wave spectrum propagating inland which is equal to or less than the depth limited wave height.
- 3. Conservatively, only areas behind the turbine buildings have been designated as sheltered from waves.
Other locations and systems may also be locally sheltered, partially or fully, by existing structures on the site. Examples include the Unit 2 and 3 Service Water Pumps.