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Initiation
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Administration
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MONTHYEARML0515100172005-05-31031 May 2005 Draft RAI on Response to Generic Letter 2004-02 Project stage: Draft RAI ML0515303042005-06-0303 June 2005 6/3/05, Calvert Cliffs - RAI Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: RAI ML0603803582006-02-0909 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 ML0609500512006-04-12012 April 2006 Approval of Extension Request for Completion of Corrective Actions in Response to Generic Letter 2004-02 Project stage: Other ML0618702222006-06-30030 June 2006 Calvert Cliffs, Units 1 & 2 Update of Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Basis Accidents at Pressurized Water Reactors Project stage: Other ML0626405472006-09-20020 September 2006 Update of Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML0633407022006-12-18018 December 2006 Unit No.1 - Approval of Extension Request for Completion of Corrective Action in Response to Generic Letter 2004-02 Project stage: Other ML0712703722007-05-0202 May 2007 Calvert Cliffs Revision to Generic Letter 2004-02 Response Project stage: Other ML0734504992007-12-10010 December 2007 Attachment (1) Request for Extension of the Completion Date for Corrective Actions Related to Generic Letter 2004-02 Project stage: Request ML0734504982007-12-10010 December 2007 Request for Extension for Completion of Activities Related to Generic Letter 2004-02 Project stage: Request ML0811307392008-04-22022 April 2008 Revision to Generic Letter 2004-02 Response Project stage: Other ML0817101052008-06-18018 June 2008 Attachment 1, Request for Extension of the Completion Date for Corrective Actions Related to Generic Letter 2004-02 Project stage: Request ML0827404972008-09-30030 September 2008 Calvert Cliffs Nuclear Plant, Attachment 2, ECCS and CS System Figures Project stage: Other ML0827404892008-09-30030 September 2008 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors. Project stage: Supplement ML0833003202008-12-0404 December 2008 Request for Additional Information Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors-Calvert Cliffs Unit 1 & 2 Project stage: RAI ML0906807672009-03-0404 March 2009 Request for Additional Information: Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Supplement ML1009500782010-04-12012 April 2010 Request for Additional Information Generic Letter 2004-02 Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2-(TAC Nos. MC4672 and MC4673) Project stage: RAI ML1011903842010-05-0606 May 2010 Notice of Forthcoming Conference Call with Calvert Cliffs to Discuss Supplemental Responses to Generic Ltr. 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Request ML1014708982010-06-0707 June 2010 Summary of Meeting with Calvert Cliffs Nuclear Power Plant, LLC, to Discuss Supplement to Responses to Generic Letter 2004-02 Project stage: Meeting ML1028701002010-09-30030 September 2010 Catawba Units 1 & 2, Draft Responses to NRC Request for Additional Information Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents on Pressurized-Water.... Project stage: Request ML1029306502010-10-20020 October 2010 Notice of Forthcoming Conference Call with Duke Energy Carolinas, LLC Regarding McGuire Nuclear Station, Units 1 and 2 and Catawba Nuclear Station, Units 1 and 2, Project stage: Other ML1030810242010-11-10010 November 2010 Summary of November 1, 2010, Meeting with Duke to Discuss Responses to Generic Letter (GL) 2004-02 (Tac Nos. MC4673, MC4674, MC4692, and MC4693) Project stage: Meeting ML1031903612010-11-10010 November 2010 Response to Request for Additional Information Regarding Generic Letter 2004-02 (TAC Nos. MC4672 and MC4673) Project stage: Response to RAI ML13086A5512013-01-24024 January 2013 MC4672 & MC4673 - CCNPP-CHLE-003, Rev 0c Chemical Effects Pirt Considerations Excerpts with Respect to GL2004-02, GSI-191 Project stage: Other ML13038A5432013-01-24024 January 2013 Chemical Effects Head Loss Experiment (Chle) Test Protocol for Calvert Cliffs Nuclear Power Plant (CCNPP-CHLE-002, Revision 0d) Project stage: Request ML13050A5112013-02-19019 February 2013 MC4672-3 Corrected Notice -Public Meeting on March 20, 2013 Re-GL2004-02 Project stage: Request ML13045A1822013-02-19019 February 2013 March 20, 2013, Notice of Forthcoming Teleconference with Calvert Cliffs and Nrc/Nrr Staff to Have Additional Discussions of Licensees'S Proposed Path for Resolution of Generic Letter 2004-02 Project stage: Meeting ML13086A5502013-03-0101 March 2013 MC4672 & MC4673, CCNPP-CHLE-002, Rev 0e Chemical Effects Experimental Protocol with Respect to GL2004-02, GSI-191. Project stage: Request ML13088A2202013-03-18018 March 2013 MC4672 & MC4673 - CCNPP-CHLE-005, Rev 1 Chemical Effects Autoclave Experimental Plan with Respect to GL2004-02, GSI-1 91 Project stage: Request ML13086A5492013-03-20020 March 2013 MC4672 & MC4673 - Licensee Presentation-Category 1, Public Meeting on March 20, 2013 with Respect to GL2004-02, GSI-191 Project stage: Meeting ML13091A0552013-04-10010 April 2013 Summary of Meeting on March 20, 2013, with Calvert Cliffs Nuclear Power Plant, LLC, to Discuss the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation D Project stage: Meeting ML13149A3942013-05-20020 May 2013 Chemical Effects Head Loss Experiment (Chle) Test Protocol for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-002, Revision 0 May 20, 2013 Project stage: Request ML13149A3992013-05-20020 May 2013 Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-005, Revision 2, May 20, 2013 Project stage: Request ML13149A4052013-05-23023 May 2013 Metals BENCH-TOP Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-006, Revision 0, May 23, 2013 Project stage: Request ML13148A3962013-05-29029 May 2013 Forthcoming Meeting with Calvert Cliffs Nuclear Power Plant, LLC to Discuss Licensee'S Proposed Plan for Resolution of GL 2004-02 Project stage: Meeting ML13179A3132013-07-11011 July 2013 June 12, 2013 Summary of Meeting with Constellation Energy Group, Inc., to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculati Project stage: Meeting ML13224A0942013-08-0606 August 2013 Chemical Effects Pirt Considerations for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-003, Revision 0c Project stage: Request ML13224A1032013-08-0808 August 2013 CCNPP-CHLE-007, Revision 0c, Coatings Bench-Top Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant. Project stage: Request ML13226A0902013-08-14014 August 2013 Notice of Forthcoming Meeting with Constellation Energy Nuclear Group, LLC Project stage: Meeting ML13304B4032013-11-0101 November 2013 Notice of Forthcoming Meeting with Constellation Energy Nuclear Group, LLC, Project stage: Meeting ML13319A9392013-11-13013 November 2013 Ri GSI-191 November 2013 Meeting with NRC Rev 0 Project stage: Request ML13310B9292013-12-0606 December 2013 Summary of Meeting with Constellation Energy Group, Inc., to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During ... Project stage: Meeting ML14014A0392014-01-29029 January 2014 Summary of Meeting with Constellation Energy Group, Inc., to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During.. Project stage: Meeting ML14206B0012014-02-14014 February 2014 Long-Term Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant. CCNP-CHLE-011, Revision 2 Project stage: Request ML14142A3232014-05-22022 May 2014 NRR E-mail Capture - Calvert Cliffs May 21, 2014 Public Meeting Presentation Project stage: Request ML14206A9932014-07-25025 July 2014 Conrete Bench-Top Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant. CCNPP-CHLE-010, Revision 1 Project stage: Request ML14206B1442014-11-0606 November 2014 May 21, 2014 Summary of Meeting with Exelon Generation Company, LLC, to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02 Project stage: Meeting ML14206A2062014-11-0707 November 2014 July 2, 2014 Summary of Meeting with Exelon Generation Company, LLC to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02 Project stage: Meeting ML15154B5572015-06-17017 June 2015 May 19, 2015 Summary of Meeting with Exelon Generation Company, LLC, on Calvert Cliffs Nuclear Power Plant, Units 1 and 2 - Chemical Effects Testing for Resolution of Generic Letter 2004-02 (TAC Nos. MC4672 & MC4673) Project stage: Meeting ML15222A5472015-08-31031 August 2015 GSI 191 Program Chemical Effects Testing Update Option 2b Closure Approach Project stage: Request 2013-11-01
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Category:Report
MONTHYEARML24240A2462024-08-27027 August 2024 Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report ML23055A2842023-02-24024 February 2023 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits ML22178A1722022-06-27027 June 2022 Long Term Coupon Surveillance Program ML22147A1782022-05-27027 May 2022 Owners Activity Report (Form OAR-1) for the Calvert Cliffs Nuclear Power Plant Unit 1 Spring 2022 Refueling Outage ML21263A1862021-09-20020 September 2021 Proposed Alternative Concerning Pressure Testing of ASME Section XI Class 2 Portions of the Auxiliary Feedwater System RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2021-09-0101 September 2021 R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML21210A3252021-07-30030 July 2021 Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report RS-21-056, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld2021-05-12012 May 2021 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld ML21077A1802021-03-18018 March 2021 10 CFR 50.46 Annual Report and 30-day Report for Framatomes Protect Enhanced Accident Tolerant Fuel (Eatf) Lead Test Assembly (LTA) ML21013A5302021-01-13013 January 2021 Reactor Vessel Level Monitoring System Special Report RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML20280A5082020-10-0606 October 2020 Submittal of Relief Request CISI-03-01 Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML20034E3462020-02-0707 February 2020 Review of the Spring 2019 Steam Generator Tube Inspection Report ML19347A7792019-12-12012 December 2019 License Amendment Request to Utilize Accident Tolerant Fuel Lead Test Assemblies ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 ML19072A0962019-03-11011 March 2019 Information Regarding Dissimilar Metal Weld 2-CV-2005-30 Flaw Characteristic and Repair Weld Overlay ML17324B3692017-12-20020 December 2017 Flood Hazard Mitigation Strategies Assessment RS-16-181, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-11-0909 November 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal ML16061A0162016-02-26026 February 2016 ISFSI - Report of Changes, Tests, and Experiments - 10 CFR 50.59 and 10 CFR 72-48 ML16057A0022016-02-25025 February 2016 Report Concerning Dissimilar Metal Weld Flaw in Pressurizer Safety Relief Nozzle-to-Safe-End Weld ML16076A3522016-02-24024 February 2016 Plants, Units 1 and 2 - E-mail Re. Draft Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzel to Safe End Weld ML15350A1082016-01-19019 January 2016 Review of the 2015 Steam Generator Tube Inspections ML15281A2182015-10-21021 October 2015 Supplement to Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation RS-15-095, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2015-04-30030 April 2015 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML15077A1032015-04-16016 April 2015 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15075A3392015-03-10010 March 2015 NUH32PHB-0101, Revision 4, Design Criteria Document (DCD) for the Nuhoms 32PHB System for Storage ML15062A0432015-02-27027 February 2015 Report of Changes, Tests, and Experiments - 10 CFR 50.59 and 10 CFR 72.48 ML15042A1372015-02-0303 February 2015 Gesc, NAC International, Atlanta Corporate Headquarters, 655 Engineering Drive, Norcross, Georgia (Engineering Report #NS3-020, Effects of 1300F on Unfilled NS-3, While Bisco Products, Inc., 11/84), Enclosure 4 L-14-036, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-12-17017 December 2014 Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14212A3072014-07-25025 July 2014 NUH32PHB.0101, Rev. 2, Design Criteria Document (DCD) for Nuhoms 32PHB System for Storage. ML14212A3082014-07-25025 July 2014 NUH32PHB-011, Rev 3, Design Report for 32PHB Dsc. ML14170B0222014-06-26026 June 2014 Staff Assessment of Flooding Walkdown Reports Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Accident ML14206B0072014-05-19019 May 2014 Considerations for Using Marinite in Refined GSI-191 Chemical Effects Testing. CCNPP-CHLE-009, Revision 4 ML14206B0092014-05-12012 May 2014 Considerations for Using Zinc in Refined GSI-191 Chemical Effects Testing. CCNPP-CHLE-008, Revision 4 ML14099A1962014-03-31031 March 2014 Constellation Energy Nuclear Group, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task. ML14071A4782014-02-21021 February 2014 Response to Nrc'S Request for Cashflow Statements Regarding Application for Order Approving Transfer of Operating Authority and Conforming License Amendments ML13225A5662013-12-17017 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049(Mitigation Strategies) ML13338A6462013-12-0909 December 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, TAC Nos.: MF1142 and MF1143 ML13319B0802013-11-14014 November 2013 Proposed 10 CFR 50.55a Request for Repair of Saltwater Piping Leak (RR-ISI-04-09) ML13319A9322013-11-11011 November 2013 CCNPP-BPPlan-002, Rev 0E, Small Scale Debris Bypass-Penetration Test Plan for Calvert Cliffs Nuclear Power Plant. ML13319A6792013-10-31031 October 2013 CCNPP-CHLE-007, Appendix 1, Alkyd Coatings in Refined GSI-191 Chemical Effects Testing. ML13319A6702013-10-18018 October 2013 CCNPP-CHLE-007, Rev. G, Coatings Bench-Top Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant. ML13319A6212013-10-0404 October 2013 CCNPP-CHLE-003, Rev. 0d Chemical Effects Pirt Considerations for Calvert Cliffs Nuclear Power Plant. ML13301A6742013-09-24024 September 2013 Enclosure 1 - Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition ML13224A1032013-08-0808 August 2013 CCNPP-CHLE-007, Revision 0c, Coatings Bench-Top Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant. ML13224A0942013-08-0606 August 2013 Chemical Effects Pirt Considerations for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-003, Revision 0c ML13149A4052013-05-23023 May 2013 Metals BENCH-TOP Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-006, Revision 0, May 23, 2013 2024-08-27
[Table view] Category:Technical
MONTHYEARML24240A2462024-08-27027 August 2024 Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report ML23055A2842023-02-24024 February 2023 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits ML22178A1722022-06-27027 June 2022 Long Term Coupon Surveillance Program ML22147A1782022-05-27027 May 2022 Owners Activity Report (Form OAR-1) for the Calvert Cliffs Nuclear Power Plant Unit 1 Spring 2022 Refueling Outage RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2021-09-0101 September 2021 R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML21210A3252021-07-30030 July 2021 Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report RS-21-056, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld2021-05-12012 May 2021 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld ML21077A1802021-03-18018 March 2021 10 CFR 50.46 Annual Report and 30-day Report for Framatomes Protect Enhanced Accident Tolerant Fuel (Eatf) Lead Test Assembly (LTA) RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20280A5082020-10-0606 October 2020 Submittal of Relief Request CISI-03-01 Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML20034E3462020-02-0707 February 2020 Review of the Spring 2019 Steam Generator Tube Inspection Report ML19347A7792019-12-12012 December 2019 License Amendment Request to Utilize Accident Tolerant Fuel Lead Test Assemblies ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 ML19072A0962019-03-11011 March 2019 Information Regarding Dissimilar Metal Weld 2-CV-2005-30 Flaw Characteristic and Repair Weld Overlay ML15077A1032015-04-16016 April 2015 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15075A3392015-03-10010 March 2015 NUH32PHB-0101, Revision 4, Design Criteria Document (DCD) for the Nuhoms 32PHB System for Storage ML15042A1372015-02-0303 February 2015 Gesc, NAC International, Atlanta Corporate Headquarters, 655 Engineering Drive, Norcross, Georgia (Engineering Report #NS3-020, Effects of 1300F on Unfilled NS-3, While Bisco Products, Inc., 11/84), Enclosure 4 RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14212A3072014-07-25025 July 2014 NUH32PHB.0101, Rev. 2, Design Criteria Document (DCD) for Nuhoms 32PHB System for Storage. ML14212A3082014-07-25025 July 2014 NUH32PHB-011, Rev 3, Design Report for 32PHB Dsc. ML14206B0072014-05-19019 May 2014 Considerations for Using Marinite in Refined GSI-191 Chemical Effects Testing. CCNPP-CHLE-009, Revision 4 ML14071A4782014-02-21021 February 2014 Response to Nrc'S Request for Cashflow Statements Regarding Application for Order Approving Transfer of Operating Authority and Conforming License Amendments ML13338A6462013-12-0909 December 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, TAC Nos.: MF1142 and MF1143 ML13319B0802013-11-14014 November 2013 Proposed 10 CFR 50.55a Request for Repair of Saltwater Piping Leak (RR-ISI-04-09) ML13319A9322013-11-11011 November 2013 CCNPP-BPPlan-002, Rev 0E, Small Scale Debris Bypass-Penetration Test Plan for Calvert Cliffs Nuclear Power Plant. ML13319A6792013-10-31031 October 2013 CCNPP-CHLE-007, Appendix 1, Alkyd Coatings in Refined GSI-191 Chemical Effects Testing. ML13319A6702013-10-18018 October 2013 CCNPP-CHLE-007, Rev. G, Coatings Bench-Top Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant. ML13319A6212013-10-0404 October 2013 CCNPP-CHLE-003, Rev. 0d Chemical Effects Pirt Considerations for Calvert Cliffs Nuclear Power Plant. ML13301A6742013-09-24024 September 2013 Enclosure 1 - Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition ML13224A0942013-08-0606 August 2013 Chemical Effects Pirt Considerations for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-003, Revision 0c ML13149A4052013-05-23023 May 2013 Metals BENCH-TOP Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-006, Revision 0, May 23, 2013 ML13149A3992013-05-20020 May 2013 Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-005, Revision 2, May 20, 2013 ML13149A3942013-05-20020 May 2013 Chemical Effects Head Loss Experiment (Chle) Test Protocol for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-002, Revision 0 May 20, 2013 ML13113A2332013-04-23023 April 2013 Technical Letter Report, PNNL Evaluation of Licensee'S Alternative for Volumetric Inspection of Dissimilar Metal Butt Welds at the Calvert Cliffs Plant ML13088A2202013-03-18018 March 2013 MC4672 & MC4673 - CCNPP-CHLE-005, Rev 1 Chemical Effects Autoclave Experimental Plan with Respect to GL2004-02, GSI-1 91 ML13086A5502013-03-0101 March 2013 MC4672 & MC4673, CCNPP-CHLE-002, Rev 0e Chemical Effects Experimental Protocol with Respect to GL2004-02, GSI-191. ML13086A5512013-01-24024 January 2013 MC4672 & MC4673 - CCNPP-CHLE-003, Rev 0c Chemical Effects Pirt Considerations Excerpts with Respect to GL2004-02, GSI-191 ML13038A5432013-01-24024 January 2013 Chemical Effects Head Loss Experiment (Chle) Test Protocol for Calvert Cliffs Nuclear Power Plant (CCNPP-CHLE-002, Revision 0d) ML12339A3672012-11-27027 November 2012 Attachment (3 Cont.) Walkdown Checklists. Part 4 of 8 ML12339A3662012-11-27027 November 2012 Attachment (3 Cont.) Walkdown Checklists. Part 6 of 8 ML12339A3562012-11-27027 November 2012 Attachment (3 Cont.) Walkdown Checklists. Part 2 of 8 ML12339A3542012-11-27027 November 2012 Attachment (3 Cont.) Walkdown Checklists. Part 3 of 8 ML12339A3502012-11-27027 November 2012 Attachment (1) Seismic Walkdown Report, Attachment (2) Equipment Lists and Attachment (3) Walkdown Checklists. Part 1 of 8 ML12339A3682012-11-27027 November 2012 Attachment (3 Cont.) Walkdown Checklists. Part 5 of 8 ML12339A3692012-11-27027 November 2012 Attachment (4 Cont.) Area Walk-By Checklist, Attachment (5) Inaccessible Equipment and Peer Review and Attachment (6) Regulatory Commitments. Part 8 of 8 ML12339A3702012-11-27027 November 2012 Attachment (4) Area Walk-By Checklist. Part 7 of 8 ML12349A2822012-11-27027 November 2012 Seismic Walkdown Report - Cover Page, Table of Content - Page C-50 ML12349A2882012-11-0909 November 2012 Seismic Walkdown Checklists, 11 Containment Spray Pump - Page C-435 - Page C-504 ML12349A2932012-11-0909 November 2012 Area Walk-by Checklist, Page 91 - Page End 2024-08-27
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CHEMICAL EFFECTS AUTOCLAVE EXPERIMENT TEST PLAN for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-005, Revision 2 May 20, 2013 Prepared by: Reviewed by: Approved by:
Craig D. Sellers Andy Henni, Steve Kinsey John Swailes Helmut Kopke, Tim Sande Tom Konerth
Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-005 Revision 2, May 20, 2013 REVISION HISTORY Log Revision Description 0 Issue for initial experiment 1 Reduce aluminum concentration to 2x best estimate and revise boron & lithium concentrations to actual maximum concentrations.
2 Increased boron concentration to account for BAST discharge, reduced Lithium Hydroxide concentration, revised temperature profile, and increased level of prescriptive detail.
i
Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-005 Revision 2, May 20, 2013 Contents 1.0 Introduction ................................................................................................................................................................ 1 2.0 Purpose ......................................................................................................................................................................... 1 3.0 Overall experimental Plan ..................................................................................................................................... 1 4.0 Experimental Parameters ...................................................................................................................................... 2 4.1 Debris Quantities .................................................................................................................................................. 2 4.2 Reactive Material.................................................................................................................................................. 2 4.3 Chemistry Conditions ......................................................................................................................................... 2 4.4 Buffer ......................................................................................................................................................................... 2 4.5 Temperature Conditions ................................................................................................................................... 2 4.6 Solution Sampling ................................................................................................................................................ 4 4.7 Agitation................................................................................................................................................................... 4 4.8 Autoclave Materials ............................................................................................................................................. 4 5.0 Test Matrix ................................................................................................................................................................... 4 6.0 Chemistry Analysis ................................................................................................................................................... 5 7.0 Experimental Methods ............................................................................................................................................ 5 7.1 Debris Preparation .............................................................................................................................................. 5 8.0 Report ............................................................................................................................................................................ 6 8.1 Introduction ........................................................................................................................................................... 6 8.2 Experiment Description .................................................................................................................................... 6 8.3 Experimental Results.......................................................................................................................................... 7 8.4 Summary of Results and Conclusions .......................................................................................................... 7 8.5 References ............................................................................................................................................................... 7 8.6 Appendixes ............................................................................................................................................................. 7 : NEI Fiber Debris Preparation Protocol ............................................................ 10 Pages List of Tables Table 1: Insulation Sample Quantities ............................................................................................................................ 2 Table 2: Reactive Material Quantities ............................................................................................................................. 2 Table 3: Chemistry Conditions ........................................................................................................................................... 2 Table 4: Solution Temperature Profile ........................................................................................................................... 3 Table 5: Test Matrix ................................................................................................................................................................ 4 List of Figures Figure 1: Solution & Sump AOR Temperatures........................................................................................................... 3 ii
Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-005 Revision 2, May 20, 2013
1.0 INTRODUCTION
Calvert Cliffs Nuclear Power Plant (CCNPP) is implementing a risk-informed approach to resolving GSI-191 that includes the performance of a number of chemical effects experiments. These experiments are intended to simulate temperature, pressure, fluid, and debris conditions in containment after a loss of coolant accident (LOCA).
Temperature conditions inside containment during the initial portion of a large break LOCA peak at approximately 280°F. Simulating these temperature conditions in a chemical effects test requires the use of a pressurized test facility. Elemental release estimates using the WCAP-16530 methodology indicate at a constant temperature of 195°F for 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br />, the release of aluminum was the same as the initial 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> at the analysis of record sump temperature. The same estimate indicated a 69% increase in calcium release and a 25% increase in silicon release.
The objective of this autoclave test is to validate the WCAP-16530 release estimate and to investigate whether maintaining the test temperature at 195°F for an extended time adequately simulates the elemental release from prototypical materials during the initial 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of a design basis LOCA at CCNPP. The results of this test will influence the decision on how to simulate the high temperature portion of the accident profiles in the CCNPP Chemical Effects Head Loss Experiment (CHLE) program.
2.0 PURPOSE The purpose of this document is to describe the autoclave experiment planned for the CCNPP CHLE program. This plan presents the sequence for performing the experiment and the conditions for each experiment.
3.0 OVERALL EXPERIMENTAL PLAN The overall concept for the experiment is eight corrosion experiments, four using a temperature profile similar to the initial 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of the design basis LOCA at CCNPP and four maintained at 195°F for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, with fluid simulating the post-LOCA fluid solution in containment and corrodible materials expected in containment in the fluid. The identification and concentration of corrosion products and characterization of any precipitates will be compared to determine if there is a significant difference in corrosion and elemental release at two temperature conditions.
Materials used in the test will be representative of the materials submerged in the containment pool or exposed to containment spray and expected to dissolve and contribute to chemical effects in the initial 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of the LOCA. These include destroyed insulation, concrete, latent debris and other miscellaneous materials in containment. The material quantities will be scaled to Page 1 of 8
Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-005 Revision 2, May 20, 2013 approximate the ratio of the test fluid volume to the volume of debris materials immersed in the pool fluid or the surface area of solid materials exposed to pool at CCNPP.
The fluid chemistry will be similar to the initial post-LOCA pool chemistry expected at CCNPP. A scaled quantity of NaTB buffer will be allowed to dissolve in the test chamber to simulate the dissolution of buffer in the plant.
4.0 EXPERIMENTAL PARAMETERS 4.1 Debris Quantities Table 1: Insulation Sample Quantities Insulations Debris Test Quantity Reference Transco Thermal Wrap or NUKON (LDFG) Fiber 1.10 gram/Liter (g/L) 1&2 Mineral Wool Fiber 0.30 g/L 1&2 4.2 Reactive Material Table 2: Reactive Material Quantities Material Description Test Quantity Reference Metallic Aluminum 0.03 in2/L 3 Galvanized Steel 7.5 in2/L 4 Copper 11.8 in2/L 4 Exposed Concrete 0.1 in2/L 4 Marinite Board 2.75 in2/L 1 4.3 Chemistry Conditions Table 3: Chemistry Conditions Deionized Water with Reference Boron Concentration (H3BO3) 2800 ppm as boron1 6 Lithium Hydroxide 0.78 ppm as lithium 6 Initial pH ~5 N/A 4.4 Buffer Include 3.78 grams per liter sodium tetraborate decahydrate (NaTB) buffer.
4.5 Temperature Conditions Four experiments will be maintained at 195°F +/-5°F for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
1 The 2800 ppm boron concentration is prior to the introduction of the NaTB buffer.
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Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-005 Revision 2, May 20, 2013 The other four will simulate the temperature profile presented in Table 4 and Figure 1 +/-5°F [Ref. 5].
Table 4: Solution Temperature Profile Time (m) Temp (F) 0 280.0 10 280.0 60 271.5 120 263.0 180 254.5 240 246.0 300 237.5 360 229.0 420 220.5 480 212.0 540 203.5 600 195.0 290.0 280.0 270.0 260.0 Temperature (F) 250.0 240.0 230.0 220.0 210.0 200.0 190.0 0 100 200 300 400 500 600 Time (Minutes)
Autoclave Temp (F) AOR Sump Temp(F)
Figure 1: Solution & Sump AOR Temperatures Page 3 of 8
Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-005 Revision 2, May 20, 2013 4.6 Solution Sampling The fluid solution in the autoclave shall be sampled periodically as specified in the Test Matrix and at the conclusion of each experiment. The samples shall be stored in containers fabricated from non-reactive and corrosion resistant materials.
4.7 Agitation The autoclave shall be agitated continuously throughout the experiment to facilitate fluid flow across the contained materials.
4.8 Autoclave Materials Wetted materials of the autoclave should be type 316 stainless steel or other very corrosion resistant material. No silicate glass products may be used.
5.0 TEST MATRIX The experiment will be performed in accordance with the test matrix presented in Table 5.
Table 5: Test Matrix Materials/Chemicals Included Sample Test No. Temp (F) Duration Times Table 1 Table 2 Table 3 1 No No Yes Table 4 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 2 No No Yes 195 +/-5 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 3 Yes Yes Yes Table 4 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 4 Yes Yes Yes Table 4 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 5 Yes Yes Yes Table 4 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 6 Yes Yes Yes 195 +/-5 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 16, 18, 20, 7 Yes Yes Yes 195 +/-5 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 22, & 24 8 Yes Yes Yes 195 +/-5 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> hours Page 4 of 8
Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-005 Revision 2, May 20, 2013 6.0 CHEMISTRY ANALYSIS Mass spectrometry of the fluid used in the experiment shall be performed:
- 1. On the deionized water prior to addition of the boric acid at the beginning of each experiment, and
- 2. On the fluid solution collected during each experiment.
The concentrations of the following elemental species shall be reported:
- 1. Aluminum
- 2. Boron
- 3. Calcium
- 4. Chromium
- 5. Iron
- 6. Magnesium
- 7. Nickel
- 8. Molybdenum
- 9. Phosphorus
- 10. Silicon
- 11. Sodium
- 12. Sulfur
- 13. Zinc 7.0 EXPERIMENTAL METHODS Professional laboratory and safety practices shall be followed. Specific laboratory procedures used to implement the experiment shall be made available to Calvert Cliffs for review and comment.
The following specific experimental processes shall also be followed.
7.1 Debris Preparation 7.1.1 Fibrous Debris Fibrous debris shall be prepared in accordance with Attachment 1 [Ref. 7], with the exception of steps 6.6 and 6.7, dried, and weighed to the quantity specified. The water used for soaking in step 6.5 of Attachment 1 shall be deionized water. The fiber samples will be placed in stainless steel mesh containers and secured to remain submerged in the experimental fluid and protected from the agitation mechanism. Photographs of the fiber before preparation, after weighing, and contained in the mesh container shall be provided.
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Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-005 Revision 2, May 20, 2013 7.1.2 Reactive Materials Coupons of metal reactive materials shall be prepared from 20 gauge or thinner flat plates. The coupons shall be suspended in the autoclave fluid so that both faces are fully exposed to the fluid.
Concrete coupons may be fresh concrete or chipped from masonry block. Marinite coupons will be cut from a solid piece of Marinite board. The concrete and Marinite coupons shall not include particles which can pass through a 16 mesh sieve. The concrete and Marinite coupons will be placed in stainless steel 18 mesh containers and secured to remain submerged in the experimental fluid and protected from the agitation mechanism.
Photographs of the reactive materials before and after preparation shall be provided.
8.0 REPORT A formal report shall be provided documenting the performance of the experiment and the results of the experiment. The following topics shall be included in the report.
8.1 Introduction A brief introduction to the report shall be presented 8.2 Experiment Description A detailed description of the experiment shall be presented including at least the following sections.
8.2.1 Facility A comprehensive description of the experimental facility shall be presented with photographs. This shall include:
- 1) Autoclave(s)
- a. Volume capacity
- b. Wetted materials
- c. Heating method
- d. Agitation method
- 2) Temperature controls
- a. Heat up rate
- b. Cool down rate
- 3) Instrumentation and analysis equipment
- a. Temperature
- b. pH
- c. Mass Spectrometry Page 6 of 8
Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-005 Revision 2, May 20, 2013 8.2.2 Experiment Input Parameters A detailed description of the input parameters for each experiment shall be presented.
8.2.3 Material Preparation The methods and processes for preparing fluid solutions and corrosion samples shall be described and the results presented with photographs.
8.2.4 Autoclave Setup and Control The procedures used to setup the autoclave, control temperature conditions, take and store samples, and perform the chemistry analyses shall be described in detail.
8.3 Experimental Results The results of each test shall be presented in individual sections. These sections shall include at least the following information.
- 1) Experimental parameters used
- 2) Actual temperature profile achieved
- 3) Results of chemical analysis of samples
- 4) Deviations and Nonconformance Reports
- 5) Photographs of notable observations as appropriate 8.4 Summary of Results and Conclusions A summary of results comparing the individual tests if the experiment will be presented and any conclusion drawn presented.
8.5 References Unique references used in the preparation of the report shall be presented. This test plan shall be included as a reference.
8.6 Appendixes Appendixes shall be provided including as a minimum the following:
- 1) Test Logs
- 2) Calibration Certificates/Records
- 3) Standards Certificates Page 7 of 8
Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-005 Revision 2, May 20, 2013
9.0 REFERENCES
- 1. Design Calculation CA0xxx, Rev. 000y, ENERCON Calculation No. CNSCC016-CALC-002, Calvert Cliffs Debris Generation Calculation.
- 2. Design Calculation CA0xxx, Rev. 000y, ENERCON Calculation No. CNSCC016-CALC-005, Calvert Cliffs Risk-Informed Debris Transport Calculation.
- 3. Design Calculation CA06940, Rev. 0001, Computation of Aluminum and Marinite Board Debris Load Inputs for Containment Sump Strainer.
- 4. Design Calculation CA0xxx, Rev. 000y, ENERCON Calculation No. CNSCC016-CALC-004, Calvert Cliffs Containment Metal Calculation.
- 5. Design Calculation CA06774, Rev. 0002, Containment Response to LOCA and MSLB for Calvert Cliffs Units 1 and 2.
- 6. Design Calculation CA0xxx, Rev. 000y, MPR Calculation No. 0090-0269-01, Post-LOCA Containment Pool Boron, Lithium Hydroxide, and Silica Concentrations.
- 7. ZOI Fibrous Debris Preparation: Processing, Storage and Handling, Revision 0, Nuclear Energy Institute, October, 2011.
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Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-005 Revision 2, May 20, 2013 Attachment 1 NEI Fiber Debris Preparation Protocol 9 pages follow Page 1-1 of 1-10