Letter Sequence Request |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
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Results
Other: ML060890398, ML060950574, ML073511698, ML081200606, ML081790538, ML090980515, ML092080216, ML092440479, ML100190011, NRC 2009-0113, Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC Nos. MC4705/4706), NRC 2011-0010, Plan for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
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MONTHYEARML0515202022005-06-0202 June 2005 6/2/05, Turkey Point, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: RAI ML0515201832005-06-0202 June 2005 Request for Additional Information, Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors. Project stage: RAI ML0515202272005-06-0303 June 2005 6/3/05, Seabrook, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: RAI ML0603703962006-02-0808 February 2006 RAI, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML0603704382006-02-0808 February 2006 Request for Additional Information Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-basis Accidents at Pressurized-water Reactors Project stage: RAI ML0603801332006-02-0909 February 2006 Request for Additional Information Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML0603704912006-02-0909 February 2006 RAI - Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML0608903982006-04-11011 April 2006 Requested Extension of Completion Schedule for NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Other ML0609505742006-04-13013 April 2006 Approval of GSI-191/GL 2004-02 Extension Request Project stage: Other NRC 2007-0085, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2007-11-16016 November 2007 Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request L-2007-155, Request for Extension of Completion Date of the Generic Letter 2004-02 Actions2007-12-0707 December 2007 Request for Extension of Completion Date of the Generic Letter 2004-02 Actions Project stage: Request ML0735116982007-12-20020 December 2007 GSI-191/GL 2004-02 Extension Request Approval (Tac No. MC4705/4706) Project stage: Other L-2008-030, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-02-27027 February 2008 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request L-2008-033, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2008-02-28028 February 2008 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Request L-2008-073, NRC Generic Letter 2004-02 Request for an Extension to the Completion Date for Ex-Vessel Downstream Effects Evaluations2008-04-14014 April 2008 NRC Generic Letter 2004-02 Request for an Extension to the Completion Date for Ex-Vessel Downstream Effects Evaluations Project stage: Request ML0812006062008-04-29029 April 2008 Approval of Extension Request for GL 2004-02 Project stage: Other NRC 2008-0038, Supplemental Response to Generic Letter 2004-02, Potential Lmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-06-0909 June 2008 Supplemental Response to Generic Letter 2004-02, Potential Lmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request L-2008-137, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2008-06-30030 June 2008 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Request L-2008-138, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2008-06-30030 June 2008 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Request ML0817905382008-07-0101 July 2008 Generic Safety Issue 191/Generic Letter 2004-02, Additional Extension Request Approval Project stage: Other ML0826106902008-09-17017 September 2008 Request for Additional Information Related to GL 2004-02 Project stage: RAI ML0826107052008-09-17017 September 2008 Request for Additional Information (RAI) Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors Project stage: RAI ML0834400782008-12-19019 December 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Request for Additional Information Project stage: RAI ML0833806712008-12-22022 December 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Request for Additional Information (TAC Mc 4725) Project stage: RAI ML0833001732009-01-0707 January 2009 GSI-191/GL 2004-02 Request for Additional Information Project stage: RAI ML0836589782009-01-16016 January 2009 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Request for Additional Information Project stage: RAI ML0835800232009-01-22022 January 2009 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Request for Additional Information Project stage: RAI L-2009-063, Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2009-03-19019 March 2009 Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Response to RAI L-2009-062, Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2009-03-19019 March 2009 Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Response to RAI NRC 2009-0033, Response to Request for Additional Information GSI-191/GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2009-04-0707 April 2009 Response to Request for Additional Information GSI-191/GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Response to RAI ML0909805152009-04-0808 April 2009 SONGS - GSI-191 Chemical Effects Project stage: Other L-2009-084, Response to Nrc'S Request for Additional Information2009-04-22022 April 2009 Response to Nrc'S Request for Additional Information Project stage: Request NRC 2009-0053, Request for Extension of Unit 1 and 2 Completion Dates for Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC MC4705/4706)2009-06-12012 June 2009 Request for Extension of Unit 1 and 2 Completion Dates for Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC MC4705/4706) Project stage: Request NRC 2009-0059, Response to Request for Additional Information GSI-I91/GL 2004-02 Potential Lmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2009-06-29029 June 2009 Response to Request for Additional Information GSI-I91/GL 2004-02 Potential Lmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Response to RAI ML0920802162009-07-27027 July 2009 Notice of Forthcoming Conference Call with Florida Power and Light Concerning Turkey Point Generic Letter 2004-02 Response Project stage: Other L-2009-180, Responses to Nrc'S Request for Additional Information on Generic Letter 2004-02 Supplemental Responses, Dated 02/27/2008 and 06/30/20082009-07-30030 July 2009 Responses to Nrc'S Request for Additional Information on Generic Letter 2004-02 Supplemental Responses, Dated 02/27/2008 and 06/30/2008 Project stage: Supplement NRC 2009-0077, Response to Request for Additional Information GSI-191/GL 2004-02 (TACs MC4705/4706) Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2009-07-31031 July 2009 Response to Request for Additional Information GSI-191/GL 2004-02 (TACs MC4705/4706) Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Response to RAI ML0924404792009-09-11011 September 2009 Summary of Conference Call with Florida Power & Light, to Discuss Generic Letter 2004-02, Potential Impact of Debris Blackage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactor, Responses Project stage: Other NRC 2009-0113, Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC Nos. MC4705/4706)2009-10-27027 October 2009 Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC Nos. MC4705/4706) Project stage: Other ML1001900112010-01-19019 January 2010 Notice of Conference Call with Florida Power & Light Concerning Turkey Point Generic Letter 2004-02 Response Project stage: Other ML1003512132010-02-18018 February 2010 Request for Additional Information Regarding GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML1009700022010-04-0909 April 2010 Request for Additional Information, Regarding GL 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI NRC 2010-0046, Supplemental Response for Extension Request for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation Durian Design Basis Accidents at Pressurized-Water Reactors2010-06-11011 June 2010 Supplemental Response for Extension Request for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation Durian Design Basis Accidents at Pressurized-Water Reactors Project stage: Supplement ML1019405202010-07-14014 July 2010 Notice of Conference Call with Florida Power and Light Company to Discuss Draft Responses to NRC Requests for Additional Information for Generic Letter 2004-02 Project stage: Draft RAI ML1007407182010-07-28028 July 2010 February 3, 2010, Turkey Point, Unit 3 & 4, Summary of Meeting with Florida Power & Light, on Generic Letter 2004-02 Project stage: Meeting L-2010-205, Responses to Nrc'S Request for Additional Information Dated Feb. 18, 2010 Re Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2010-09-17017 September 2010 Responses to Nrc'S Request for Additional Information Dated Feb. 18, 2010 Re Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML1009903062010-09-22022 September 2010 Request for Additional Information Regarding GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML1025902742010-12-17017 December 2010 Summary of Teleconference Meeting with Florida Power & Light Company, on Generic Letter 2004-02 Project stage: Meeting NRC 2011-0010, Plan for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2011-02-0404 February 2011 Plan for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML1103502052011-02-0404 February 2011 Forthcoming Public Teleconference with NextEra Energy Seabrook, LLC, to Discuss Planned Testing for Seabrook Specific Erosion Project stage: Request 2009-01-07
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Category:Legal-Affidavit
MONTHYEARL-2023-034, Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)2023-02-24024 February 2023 Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) SBK-L-22094, Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)2022-10-26026 October 2022 Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) ML18151A1442018-05-31031 May 2018 Hearing File Update ML15149A2832015-05-26026 May 2015 PWROG-15042-P, Revision 0, Appendix a, NextEra Energy, Seabrook, Unit 1, Summary Report for the Cold Work Assessment (Non-Proprietary). Application for Withholding Proprietary Information from Disclosure and Affidavit ML15072A0372015-03-0909 March 2015 Enclosures 1 and 2 - Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years and Affidavit SBK-L-12176, Response to Request for Additional Information Regarding Relief Request for Service Water Piping2012-09-0707 September 2012 Response to Request for Additional Information Regarding Relief Request for Service Water Piping SBK-L-12054, Response to Request for Additional Information Regarding License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System2012-03-15015 March 2012 Response to Request for Additional Information Regarding License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System SBK-L-11190, Supplement to Request for Closed Meeting to Discuss Proprietary Test2011-09-19019 September 2011 Supplement to Request for Closed Meeting to Discuss Proprietary Test SBK-L-11184, Response to Request for Additional Information Regarding License Amendment Request 10-02, Regarding the Containment Enclosure Emergency Air Cleanup System2011-09-16016 September 2011 Response to Request for Additional Information Regarding License Amendment Request 10-02, Regarding the Containment Enclosure Emergency Air Cleanup System ML11223A4462011-08-0808 August 2011 (Friends of the Coast, New England Coalition) Declaration of Dr. Arjun Makhijani Regarding Safety and Environmental Significance of NRC Task Force Report Regarding Lessons Learned from Fukushima Daiichi Nuclear Power Station Accident ML11223A3772011-08-0808 August 2011 (Beyond Nuclear, Seacoast Antipollution League, Sierra Club of Nh) Declaration of Dr. Arjun Makhijani Safety and Environmental Significance of NRC Task Force Report Regarding Lessons Learned from Fukushima Daiichi Nuclear Power Station Acci ML1111000032011-04-20020 April 2011 Declaration and Cv of Dr. Arjun Makhijani in Support of Emergency Petition to Suspend All Pending Reactor Licensing Decisions and Related Rulemaking Decisions Pending Investigation of Lessons Learned from Fukushima Daiichi Power Station Acc ML1111000052011-04-19019 April 2011 Letter to Commissioners Transmitting Declaration and Cv of Dr. Arjun Makhijani in Support of Emergency Petition to Suspend All Pending Reactor Licensing Decisions and Related Rulemaking Decisions . . ML1110504752011-04-15015 April 2011 Certificate of Service for Emergency Petition to Suspend All Pending Reactor Licensing Decisions and Related Rulemaking Decisions Pending Investigation of Lessons Learned from Fukushima Daiichi Nuclear Power Station Accident ML1106805352011-03-0909 March 2011 Certificate of Service for Commonwealth of Massachusetts' Request to Participate as an Interested State, and Notice of Appearance of Matthew Brock on Behalf of the Commonwealth of Massachusetts SBK-L-08039, License Amendment Request 08-01, Application for Change to the Technical Specification Surveillance Requirements for Nuclear Instrumentation2008-03-0707 March 2008 License Amendment Request 08-01, Application for Change to the Technical Specification Surveillance Requirements for Nuclear Instrumentation SBK-L-08005, License Amendment Request 07-04 Application for Amendment to Delete Post-Maintenance Testing Surveillance Requirement for Containment Isolation Valves2008-02-0808 February 2008 License Amendment Request 07-04 Application for Amendment to Delete Post-Maintenance Testing Surveillance Requirement for Containment Isolation Valves SBK-L-07112, License Amendment Request 07-02, Application to Revise the Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process.2007-07-17017 July 2007 License Amendment Request 07-02, Application to Revise the Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process. SBK-L-07042, License Amendment Request 07-01 Setpoint Change for Reactor Trip System Interlock P-92007-03-29029 March 2007 License Amendment Request 07-01 Setpoint Change for Reactor Trip System Interlock P-9 SBK-L-06166, Proprietary Information to Support Response to Request for Additional Information Re License Amendment Request 05-08, Limited Inspection of Steam Generator Tube Portion within the Tubesheet.2006-08-0808 August 2006 Proprietary Information to Support Response to Request for Additional Information Re License Amendment Request 05-08, Limited Inspection of Steam Generator Tube Portion within the Tubesheet. ML0534903472005-12-12012 December 2005 Caldon Inc. Proprietary Information Package, INFO-18 SBK-L-05186, License Amendment Request 05-08, Limited Inspection of the Steam Generator Tube Portion within the Tubesheet2005-09-29029 September 2005 License Amendment Request 05-08, Limited Inspection of the Steam Generator Tube Portion within the Tubesheet SBK-L-04052, Re-submittal of Proprietary Information to Support License Amendment Request 04-03, Application for Stretch Power Uprate2004-09-13013 September 2004 Re-submittal of Proprietary Information to Support License Amendment Request 04-03, Application for Stretch Power Uprate 2023-02-24
[Table view] Category:Letter type:SBK
MONTHYEARSBK-L-23053, Radiological Emergency Plan (Ssrep), Revision 802023-06-22022 June 2023 Radiological Emergency Plan (Ssrep), Revision 80 SBK-L-23031, 2022 Annual Radioactive Effluent Release Report2023-04-28028 April 2023 2022 Annual Radioactive Effluent Release Report SBK-L-23044, 2022 Annual Radiological Environmental Operating Report2023-04-28028 April 2023 2022 Annual Radiological Environmental Operating Report SBK-L-23033, 2022 Annual Environmental Operating Report2023-04-11011 April 2023 2022 Annual Environmental Operating Report SBK-L-22093, 75 Day and 150 Day Submittal Letters2022-12-0101 December 2022 75 Day and 150 Day Submittal Letters SBK-L-22113, Radiological Emergency Plan (Ssrep), Revision 792022-11-16016 November 2022 Radiological Emergency Plan (Ssrep), Revision 79 SBK-L-22114, Independent Spent Fuel Storage Installation (Isfsi), Cask Registration2022-11-0909 November 2022 Independent Spent Fuel Storage Installation (Isfsi), Cask Registration SBK-L-22112, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2022-11-0303 November 2022 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration SBK-L-22094, Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)2022-10-26026 October 2022 Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) SBK-L-22105, Supplement to 2021 Annual Radioactive Effluent Release Report2022-10-24024 October 2022 Supplement to 2021 Annual Radioactive Effluent Release Report SBK-L-22103, 5 to the Physical Security Plan, Training and Qualification Plan and Safeguards Contingency Plan2022-10-12012 October 2022 5 to the Physical Security Plan, Training and Qualification Plan and Safeguards Contingency Plan SBK-L-22102, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2022-10-0606 October 2022 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration SBK-L-22080, Submittal of 10 CFR 72.48 Report of Changes, Tests and Experiments for August 2020 to July 20222022-08-12012 August 2022 Submittal of 10 CFR 72.48 Report of Changes, Tests and Experiments for August 2020 to July 2022 SBK-L-22054, SBK-L-22054 - License Amendment Request 22-01, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0909 June 2022 SBK-L-22054 - License Amendment Request 22-01, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections SBK-L-22044, 2021 Annual Radioactive Effluent Release Report2022-04-29029 April 2022 2021 Annual Radioactive Effluent Release Report SBK-L-22036, Steam Generator Tube Inspection Report2022-04-25025 April 2022 Steam Generator Tube Inspection Report SBK-L-22040, Radiological Emergency Plan (Ssrep), Revision 7822022-04-20020 April 2022 Radiological Emergency Plan (Ssrep), Revision 782 SBK-L-22024, Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2022-03-0707 March 2022 Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-22003, Inservice Inspection Examination Report2022-01-24024 January 2022 Inservice Inspection Examination Report SBK-L-21126, Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan2022-01-0404 January 2022 Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan SBK-L-21135, Submittal of Changes to the Seabrook Station Technical Specification Bases2021-12-29029 December 2021 Submittal of Changes to the Seabrook Station Technical Specification Bases SBK-L-21108, Core Operating Limits Report for Cycle 222021-11-0404 November 2021 Core Operating Limits Report for Cycle 22 SBK-L-21106, Transmittal of WCAP-18607-NP, Analysis of Capsule X from the NextEra Energy Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program2021-09-30030 September 2021 Transmittal of WCAP-18607-NP, Analysis of Capsule X from the NextEra Energy Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program SBK-L-21105, Withdrawal of Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink One-Time Allowed Outage Time (AOT) Extension2021-09-27027 September 2021 Withdrawal of Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink One-Time Allowed Outage Time (AOT) Extension SBK-L-21103, Request for Exercise of Enforcement Discretion2021-09-25025 September 2021 Request for Exercise of Enforcement Discretion SBK-L-21104, Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink Onetime Allowed Outage Time (AOT) Extension2021-09-25025 September 2021 Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink Onetime Allowed Outage Time (AOT) Extension SBK-L-21098, Supplement to License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2021-09-22022 September 2021 Supplement to License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-21083, NextEra Energy Seabrook, LLC - Relief Request 3IR-18 and 3IR-19 for End of Third 10-Year ISI Interval for Examinations with Limited Coverage2021-08-18018 August 2021 NextEra Energy Seabrook, LLC - Relief Request 3IR-18 and 3IR-19 for End of Third 10-Year ISI Interval for Examinations with Limited Coverage SBK-L-21067, License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2021-07-21021 July 2021 License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-21049, Revision to Updated Final Response to NRC Generic Letter 2004-022021-06-24024 June 2021 Revision to Updated Final Response to NRC Generic Letter 2004-02 SBK-L-21056, Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References:2021-05-20020 May 2021 Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References: SBK-L-21045, Submittal of 2020 Annual Radioactive Effluent Release Report2021-04-30030 April 2021 Submittal of 2020 Annual Radioactive Effluent Release Report SBK-L-21044, 2020 Annual Radiological Environmental Operating Report2021-04-30030 April 2021 2020 Annual Radiological Environmental Operating Report SBK-L-21042, Response to RIS 2021-01 Preparation and Scheduling of Operator Licensing Examinations2021-04-22022 April 2021 Response to RIS 2021-01 Preparation and Scheduling of Operator Licensing Examinations SBK-L-21033, Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements2021-03-24024 March 2021 Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements SBK-L-21023, Radiological Emergency Plan (Ssrep), Revision 772021-03-0404 March 2021 Radiological Emergency Plan (Ssrep), Revision 77 SBK-L-20154, Submittal of Changes to the Seabrook Station Technical Specification Bases2020-12-22022 December 2020 Submittal of Changes to the Seabrook Station Technical Specification Bases SBK-L-20149, Response to Request for Additional Information in Respect to 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 Pandemic2020-12-0808 December 2020 Response to Request for Additional Information in Respect to 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 SBK-L-20146, One-Time Exemption Request for the Biennial Emergency Preparedness Exercise Requirements of 10 CFR 50, Appendix E. IV.F.2.b and IV.F.2.c2020-12-0303 December 2020 One-Time Exemption Request for the Biennial Emergency Preparedness Exercise Requirements of 10 CFR 50, Appendix E. IV.F.2.b and IV.F.2.c SBK-L-20144, Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-23023 November 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic SBK-L-20143, Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 004-022020-11-19019 November 2020 Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 004-02 SBK-L-20132, Fourth Interval Inservice Testing (IST) Program2020-10-21021 October 2020 Fourth Interval Inservice Testing (IST) Program SBK-L-20127, Generator Tube Inspection Report2020-10-20020 October 2020 Generator Tube Inspection Report SBK-L-20117, Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request2020-09-23023 September 2020 Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request SBK-L-20103, Inservice Inspection Examination Report2020-07-27027 July 2020 Inservice Inspection Examination Report SBK-L-20092, Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-4182020-07-13013 July 2020 Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-418 SBK-L-20068, License Amendment Request 20-01, One-Time Change to the Seabrook Technical Specifications A.C. Sources - Operating2020-07-13013 July 2020 License Amendment Request 20-01, One-Time Change to the Seabrook Technical Specifications A.C. Sources - Operating SBK-L-20085, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-16016 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic SBK-L-20077, Core Operating Limits Report for Cycle 212020-06-0101 June 2020 Core Operating Limits Report for Cycle 21 SBK-L-20057, Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request2020-05-20020 May 2020 Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request 2023-06-22
[Table view] Category:Slides and Viewgraphs
MONTHYEARML23177A1142023-06-26026 June 2023 Annual Assessment Meeting Reactor Oversight Process 2023 ML23066A2472023-03-0707 March 2023 Presubmittal Meeting Slides for March 7, 2023, Public Meeting ML22130A1282022-05-10010 May 2022 Annual Assessment Meeting for Seabrook Station - NRC Presentation Slides ML22146A3472022-02-23023 February 2022 Slides - Pre-Submittal Meeting for February 23 with Nextera Energy Seabrook, LLC Regarding Planned Submittal of License Amendment Request to Update Pressure-Temperature Limits Curves Period of Applicability ML21168A1452021-06-22022 June 2021 Annual Assessment Meeting Slides ML20161A0812020-06-0303 June 2020 Annual Assessment Meeting June 3, 2020 Slides ML19042A1102019-02-13013 February 2019 Presentation Slides - 2019 Seabrook Public Meeting ML18136A4822018-05-0202 May 2018 Annual Assessment Meeting 05-02-2018 Presentation ML18086A7742018-02-21021 February 2018 LOR Program Biennial Inspection 71111.11B Exam Overlap Issues ML17341A0622017-11-17017 November 2017 NextEra Energy Seabrook Presentation Slides - Seabrook Station ASR Methodology LAR: Structural Deformation - LAR 16-03, Methodology and Responses to Rais D2-D8 - for November 17, 2017, Public Meeting ML17310B2322017-11-0707 November 2017 Presentation Slides - NextEra Energy/Fpl - GSI-191 Issue Resolution, Pre-submittal Meeting, September 20, 2017 ML17278A7482017-10-13013 October 2017 Summary of August 24, 2017, Meeting with NextEra Energy Regarding License Amendment Request on Alkali Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) ML17283A0402017-10-10010 October 2017 Enclosure 2 - Nrc'S Presentation Slides-Seabrook Station, License Amendment Request, Stage 3 Methodology ML17283A0412017-08-24024 August 2017 Enclosure 3 - Licensee'S Presentation-Seabrook Station, License Amendment Request 16-03 ASR Structural Evaluation Methodology ML17164A2712017-06-0707 June 2017 Presentation Slides for Annual Assessment Meeting 2017 ML16176A0542016-06-21021 June 2016 6/21/2016 - Seabrook Station Annual Assessment Meeting - NRC Presentation Slides (Assessment and ASR Update) ML16168A4122016-06-15015 June 2016 Slides for Public Meeting with NextEra Energy Regarding Seabrook Station ASR License Amendment ML16146A2002016-04-28028 April 2016 License Renewal Application, April 28, 2016, Public Meeting NextEra Presentation ML14190B0432014-07-0909 July 2014 Annual Assessment Meeting Performance Slides - June 24 2014 ML13357A0412013-12-23023 December 2013 Public Meeting on Seabrook Station Testing Program ML13357A0432013-12-23023 December 2013 ASR at Seabrook Station Update on Testing Program ML13357A0462013-12-23023 December 2013 Update on ASR ML13133A2492013-05-29029 May 2013 Slides from May 9, 2013, Meeting with NextEra Energy Seabrook, LLC on Pre-Submittal of a Fixed Incore Detector License Amendment Request ML13066A4882013-03-21021 March 2013 Summary of Meeting Held on February 21, 2013, Between the NRC and NextEra Energy Seabrook, LLS Regarding License Renewal Application, Seabrook Station ML12356A0432012-12-11011 December 2012 Safety Implications and Status of ASR Condition - Public Meeting on 12/11/2012 ML12236A3852012-08-23023 August 2012 Memo Summary of NextEra Energy Seabrook Drop in Visit and Slides, August 22, 2012 ML12132A3442012-05-11011 May 2012 NRC-AERB Bilateral Meeting Slide Presentation (Nro/De), Aerb, India - May 16-17, 2012 ML12131A4312012-05-10010 May 2012 Aam ROP-12 Slides-Safety Performance & Alkali-Silica Reaction - r9 Revised Format ML1211604142012-04-23023 April 2012 Structural Assessment of Seabrook Station - Role of Concrete Material Testing ML1204402842012-02-16016 February 2012 Public Meeting Construction Experiences - Evaluate Impact of Concrete Degradation ML12026A4592012-01-26026 January 2012 EDG Ifr ML11343A4482011-12-0909 December 2011 NextEra Drop in Meeting Summary and Slides from 11-14-2011 Meeting with Region-I SBK-L-11190, Supplement to Request for Closed Meeting to Discuss Proprietary Test2011-09-19019 September 2011 Supplement to Request for Closed Meeting to Discuss Proprietary Test ML11259A0022011-09-15015 September 2011 Meeting Slides Preliminary Site-Specific Results of the License Renewal Environmental Review for Seabrook Station. ML1116500382011-06-0808 June 2011 Aam Slides, June 8, 2011 ML12054A6412011-05-24024 May 2011 Concrete Degradation - Alkali Silica Reaction, W/Handwritten Notes ML1108206992011-03-22022 March 2011 3/22/11 Revised Pre-application Meeting Slides Regarding NFPA 805 License Amendment Request ML1022205712010-08-10010 August 2010 License Renewal Process Overview and Scoping Public Meeting Slides ML1019703702010-07-19019 July 2010 License Renewal Process Overview ML1013901282010-05-17017 May 2010 License Renewal Overview Presentation for Seabrook Station ML1011004582010-04-20020 April 2010 NRC Slides for Seabrook Annual Assessment Meeting, April 14, 2010 ML0927403042009-09-22022 September 2009 NextEra Letter and Slide Presentation to NRC Seabrook Regulatory Conference, Dated 9/22/09 ML0910604982009-04-30030 April 2009 NRC Slides for Annual Assement Meeting, 4/30/09 ML0809300252008-04-0202 April 2008 NRC Slides - Seabrook Aam 2008 ML0710002082007-03-29029 March 2007 Aam Slides for EOC 2006-07 ML0708001192007-03-21021 March 2007 Slides, End of the Presentation, from Seabrook Station Annual Assessment Meeting for EOC 2006-07 ML0727105992006-06-0505 June 2006 Viewgraphs of Use of Ultrasonic Flow Measurement to Determine Reactor Power ML0727106062006-06-0505 June 2006 Viewgraphs of Use of Ultrasonic Flow Measurement to Determine Reactor Power ML0608202482006-03-23023 March 2006 NRC Slides for Public Meeting with FPL Seabrook to Discuss Cy 2005 Performance ML0601300312005-12-16016 December 2005 Meeting Slides, Measurement Uncertainty Recapture Fple/Caldon - NRC Meeting December 16, 2005 2023-06-26
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NEXTeraM ENERGY-7MA September 19, 2011 SBK-L- 11190 Docket No. 50-443 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 Seabrook Station Supplement to Request for Closed Meeting to Discuss Proprietary Test
Reference:
Seabrook Letter SBK-L- 11176 to NRC, "Request for Closed Meeting to Discuss Proprietary Tests," dated September 13, 2011.On September 13, 2011, NextEra Energy Seabrook, LLC (NextEra), submitted a letter to the NRC requesting a closed meeting to discuss erosion testing in support of resolution of GSI-191 issues at Seabrook Station. The letter included slides proprietary to Alion Science & Technology (Alion), NextEra's contractor for conducting the testing along with the affidavit requesting withholding from public disclosure in accordance with I OCFR2.390, Public Inspections, Exemptions, Requests for Withholding, due to the proprietary nature of the material attached.The attachment to this letter is a supplement to the request for the closed meeting and includes the portioned and redacted versions of Alion's proprietary material and the accompanying affidavit requesting withholding in accordance with 1 OCFR2.390.
NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874 U.S. Nuclear Regulatory Commission SBK-L- 11190 If you have any questions regarding this submittal, please contact me at (603) 773-7745.Sincerely, NextEra Energy Seabrook, LLC Michael D. O'Keefe Licensing Manager Attachments:
cc: W.M. Dean, G. E. Miller, W. J. Raymond, NRC Region I Administrator NRC Project Manager, Project Directorate 1-2 NRC Resident Inspector Attachment to SBK-L-11190 Summary of High Velocity Erosion Testing Results ALION-PP-SEA-8142-03
[Portioned Version]*Summary of High Velocity Erosion Testing Results ALION-PP-SEA-8142-03
[Redacted Version]Affidavit of Jon W. Neuhoff Division Manager, Nuclear Services Alion Science & Technology
- Brackets [ ] outside the title of a slide in the portioned version of the material denote that the entire contents of the slide is to be redacted.
A L I 0 N ALION Science & Technology SCIENCE AlO TECHNOLOGY AFFIDAVIT I, Jon W. Neuhoff, state as follows: (1) I am Division Manager, Nuclear Services, ALION Science & Teelmology
("Alion")
and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in ALION Science & Technology presentation, "Summnary of High Velocity Erosion Testing Results, ALION-PP-SEA-8142-03" dated September 6, 2011. A portioned version of the presentation denoting the proprietary information is being provided.
Additionally, a redacted version of the presentation withholding the proprietary information is being provided.(3) In making this application for withholding of proprietary information of which it is the owner, Alion relies upon the exemption fiom disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC See. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for "trade secrets" (Exemption 4). The material for which exemption from disclosure is here sought also qualify under the narrower definition of "trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Proiect v. Nuclear Regulatory Commission, 975F2d871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704F2d1280 (DC Cir. 1983).(4) Some examples of categories of information which fit into the definition of proprietary information are: a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by Alion's competitors without license from Alion constitutes a competitive economic advantage over other companies;
- b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;c. Information which reveals aspects of past, present, or future Alion customer-funded development plans and programs, resulting in potential products to Alion;d. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4) a, and (4) b, above.Page I of 3 J14N Affidavit AL ION$CIENCIE AND TECNOLtOGY (5) To address 10 CFR 2.390 (b) (4), the information sought to be withheld is being submitted to NRC in confidence.
The information is of a sort customarily held in confidence by Alion, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by Alion, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for mnaintenance of the information in confidence.
Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7) following.
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge.
Access to such documents within Alion is limited on a "need to know" basis.(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation.
Disclosures outside Alion are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.
(8) The document identified in paragraph (2), above, is classified as proprietary because it contains "know-how" and "unique data" developed by Alion within our research and development programs.
The development of this document, supporting methods and data constitutes a major Alion asset in this current market.(9) Public disclosure of the information sought to be with-deld is likely to cause substantial harm to Alion's competitive position and foreclose or reduce the availability of profit-making opportunities.
The information is part of Alion's comprehensive BWR/PWR GSI-191 analysis base, and its commercial value extends beyond the original development cost. The value of the technology base goes beyond the extensive physical database and experimental methodology and includes development of the expertise to determine and apply the appropriate evaluation process.The research, development, engineering, analytical and experimental costs comprise a substantial investment of time and money by Alion.The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.
Page 2 of 3 JIN iAffidavit A LION$CIENCE AND TECHNOLOGY Alion's competitive advantage will be lost if its competitors are able to use the results of the Alion experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to Alion would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive Alion of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing these very valuable analytical tools.I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to the best of my knowledge, information, and belief.Executed on this 14th day of September 2011.Jon W. Neuhoff Division Manager, Nuclear Services ALION Science & Technology Page 3 of 3 JUII\N Affidavit Redacted Version Summary of High Velocity Erosion Testing Results, AL ION-PP-SEA
-8142-03 0 A LION SCIENCE AND TECHNOLOGY
© 2011 Alion Science and Technology Corporation.
All rights reserved.Any distribution or unauthorized use of this content without the express written permission of Alion Science and Technology Corporation is strictly prohibited.
Proprietary Information
-Withhold from Public Disclosure lAW 10 CFR 2.390 Updated: 9/6/2011 High Velocity and Low Velocity Tests Same test facilities and staff were used for both the high velocity and low velocity testing.* Test used" Only protocol used for the high velocity testing was consistent with protocol for low velocity testing.significant differences in testing were: I Paaee I Lo Veoct Tet I Hig Veoct Test Target Flow Velocity Actual Flow Rate Pre-filter Mesh Size 25 micron 1000 micron Not Run Confirmatory Post-Test Run All other test conditions (for example, running a pre-test, use of c-channel turbulence enhancers, configuration of flow straightener, and positioning of sample racks) were the same in both test series.Use or disclosure of this document is subject to the restriction on the Cover Page. Proprietary Information
-Withhold from Public Disclosure lAW 10 CFR 2.390 ALION-PP-SEA-8142-03 Use or disclosure of this document is subject to the restriction on the Cover Page. Proprietary Information
-Withhold from Public Disclosure lAW 10 CFR 2.390 ALION-PP-SEA-8142-03 Use or disclosure of this document is subject to the restriction on the Cover Page. Proprietary Information
-Withhold from Public Disclosure lAW 10 CFR 2.390 ALION-PP-SEA-8 142-03 Use or disclosure of this document is subject to the restriction on the Cover Page. Proprietary Information
-Withhold from Public Disclosure lAW 10 CFR 2.390 ALION-PP-SEA-8142-03 Use or disclosure of this document is subject to the restriction on the Cover Page. Proprietary Information
-Withhold from Public Disclosure lAW 10 CFR 2.390 ALION-PP-SEA-8142-03 Use or disclosure of this document is subject to the restriction on the Cover Page. Proprietary Information-Withhold from Public Disclosure lAW 10 CFR 2.390 ALION-PP-SEA-8142-03 Use or disclosure of this document is subject to the restriction on the Cover Page. Proprietary Information
-Withhold from Public Disclosure lAW 10 CFR 2.390 ALION-PP-SEA-8142-03 A *~Use or disclosure of this document is subject to the restriction on the Cover Page. Proprietary Information
-Withhold from Public Disclosure lAW 10 CFR 2.390 ALION-PP-SEA-8142-03 Use or disclosure of this document is subject to the restriction on the Cover Page. Proprietary Information
-Withhold from Public Disclosure lAW 10 CFR 2.390 ALION-PP-SEA-8 142-03 Use or disclosure of this document is subject to the restriction on the Cover Page. Proprietary Information -Withhold from Public Disclosure lAW 10 CFR 2.390 ALION-PP-SEA-8 142-03 Use or disclosure of this document is subject to the restriction on the Cover Page. Proprietary Information
-Withhold from Public Disclosure lAW 10 CFR 2.390 ALION-PP-SEA-8142-03 Use or disclosure of this document is subject to the restriction on the Cover Page. Proprietary Information
-Withhold from Public Disclosure lAW 10 CFR 2.390 ALION-PP-SEA-8142-03 Use or disclosure of this document is subject to the restriction on the Cover Page. Proprietary Information
-Withhold from Public Disclosure lAW 10 CFR 2.390 ALIO N-PP-SEA-8142-03 Use or disclosure of this document is subject to the restriction on the Cover Page. Proprietary Information
-Withhold from Public Disclosure lAW I0 CFR 2.390 ALION-PP-SEA-8142-03 Use or disclosure of this document is subject to the restriction on the Cover Page. Proprietary Information -Withhold from Public Disclosure lAW 10 CFR 2.390 ALIO N-PP-SEA-8142-03 Summary of erosion testing results Test Control Group Dissolution Sample Group Boiling Weight Loss Sample Group Drying Weight Loss Sample Group Flow Weight Loss Total Sample Group Weight Loss Erosion Fraction Cumulative Filter Capture Erosion Fraction Low Velocity 30-Day Primary Test Post-Test High Velocity 30-Day Primary Test Use or disclosure of this document is subject to the restriction on the Cover Page. Proprietary Information
-Withhold from Public Disclosure lAW 10 CFR 2.390 ALIO N-PP-SEA-8142-03 Summary Protocol for low velocity tests and high velocity tests was consistent.
Only differences were I) the target flow velocity, 2) larger mesh pre-filter and 3)not running a post-test for the high velocity test series. All other test conditions (for example, running a pre-test, use of c-channel turbulence enhancers, configuration of flow straightener, and positioning of sample racks)were the same in both test series.///S n0/Use or disclosure of this document is subject to the restriction on the Cover Page. Proprietary Information
-Withhold from Public Disclosure lAW 10 CFR 2.390 ALION-PP-SEA-8142-03 Conclusion Use or disclosure of this document is subject to the restriction on the Cover Page. Proprietary Information
-Withhold from Public Disclosure lAW 10 CFR 2.390 ALIO N-PP-SEA-8142-03