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Category:E-Mail
MONTHYEARML24012A0492024-01-11011 January 2024 Request for Additional Information Regarding Final Response to Generic Letter 2004-02 ML23311A1682023-11-0707 November 2023 NRR E-mail Capture - Constellation - Fleet Request - Acceptance of Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections (L-2023-LLR-0053 and L-2023-LLR-005 ML23311A1692023-11-0707 November 2023 NRR E-mail Capture - Constellation - Fleet Request - Acceptance of Proposed Alternative for Examinations of Exam Categories B-B, B-D, and C-A SG Pressure Retaining Welds and Full Penetration Welded Nozzles (L-2023-LLR-0055 and L-2023-LLR-00 ML23304A0152023-10-30030 October 2023 NRR E-mail Capture - Final RCI - Constellation Energy Generation, LLC - Calvert Cliffs 1 & 2 - Exemption from Security Rule (L-2023-LLE-0033) ML23181A0732023-06-30030 June 2023 NRR E-mail Capture - Acceptance Review for Calvert Cliffs TSTF-59A ML23160A0222023-06-0606 June 2023 NRR E-mail Capture - Calvert Cliffs - Long Term Coupon Surveillance Program RAI ML23156A0102023-06-0404 June 2023 NRR E-mail Capture - Calvert Cliffs - RAI License Amendment Request for Emergency Desiel Generator ML23080A1002023-03-21021 March 2023 NRR E-mail Capture - Acceptance Review for Calvert Cliffs Repair Replacement of Saltwater System Buried Piping ML23080A0672023-03-21021 March 2023 NRR E-mail Capture - Acceptance Review for Calvert Cliffs Unit 1 - LAR to Modify the Long-Term Coupon Surveillance Program ML23026A1332023-01-26026 January 2023 NRR E-mail Capture - Acceptance Review for Calvert Cliffs Deletion of License Condition for Decommissioning Trust LAR ML22354A2622022-12-20020 December 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Request to Use Certain Provisions of the 2019 Edition of the ASME BPV Code, Section XI ML22342B1462022-11-21021 November 2022 NRR E-mail Capture - Acceptance Review for TSTF 295A ML22325A0052022-11-18018 November 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-273-A, Revision 2 ML22255A0132022-09-0909 September 2022 NRR E-mail Capture - NRC Acceptance Review of Braidwood, Byron, Calvert Cliffs, Ginna - License Amendment Request to Adopt TSTF-577 ML22200A0782022-07-19019 July 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request to Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22271A0772022-05-0606 May 2022 NRR E-mail Capture - Final RAIs 9.1.2021 Constellation Relief Request ML22129A0132022-05-0606 May 2022 NRR E-mail Capture - Draft RAIs for Requests for Alternatives I4R-17, I4R-23, ISI-05-018, I6R-10 ML22091A2392022-04-0101 April 2022 NRR E-mail Capture - Calvert Cliffs - Formal RAI for Proposed Alternative for Examinations of Certain Pressurizer Welds ML22091A0852022-04-0101 April 2022 NRR E-mail Capture - Braidwood and Byron - Final RAI Regarding Proposed Alternative for Various Pressurizer Welds (EPID L-2021-LLR-0035 and 0036) ML22091A2402022-03-23023 March 2022 NRR E-mail Capture - (External_Sender) Salem Generating STATION-INCIDENTAL Take of Atlantic Sturgeon Collected on 03/22/2022 ML22075A1912022-03-16016 March 2022 NRR E-mail Capture - Acceptance for Review of Proposed Alternative Repair Method for Buried Class 3 Saltwater System Piping ML22088A1562022-03-0202 March 2022 NRR E-mail Capture - Byron, Braidwood, Calvert Cliffs, and Ginna - Non-acceptance of Application to Revise Technical Specifications 5.6.5.b, the Core Operating Limits Report (COLR) ML22059B0602022-02-28028 February 2022 Change to Review Schedule Regarding Proposed Alternative for Various Pressurizer Welds ML22060A0172022-02-23023 February 2022 NRR E-mail Capture - Calvert Cliffs Nuclear Power Plant, Units 1 and 2 - Withdraw of Draft RAI Regarding Proposed Alternative for Various Pressurizer Welds ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML21281A1402022-01-14014 January 2022 Acceptance for Review of Proposed Alternative ISI-05-018 for Examinations of Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles ML21301A0672021-10-28028 October 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Amendment Request to Adopt TSTF-541 ML21295A5712021-10-22022 October 2021 NRR E-mail Capture - Acceptance for Review of Proposed Alternative ISI-05-019 for Pressure Testing of Certain Portions of ASME Section XI Class 2 Auxiliary Feedwater Piping ML21287A0322021-10-13013 October 2021 Request for Additional Information Re Proposed Alternative for Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML21286A5902021-10-0505 October 2021 Acceptance for Review of Proposed Alternative ISI-05-017 for Examinations of Examination Category C-B Steam Generator ML21287A0932021-10-0505 October 2021 Request for Additional Information: Calvert Cliffs 1 & 2 LAR to Revise Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Basis (EPID L-2021-LLA-0112) (Email) ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21214A0202021-08-0909 August 2021 License Amendment Request to Change Spent Fuel Pool Cooling Design Basis ML21215A3502021-08-0303 August 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Amendment Request to Adopt TSTF-554 ML21201A0482021-07-19019 July 2021 Acceptance of Requested Licensing Action to Change Spent Fuel Pool Cooling Design Basis ML21180A1562021-06-28028 June 2021 Request for Additional Information Regarding License Amendment Request Concerning Containment Sump ML21152A1232021-06-0101 June 2021 Acceptance for Review of Proposed Alternative ISI-05-016 Involving Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds (EPID L-2021-LLR-0037) (Email) ML21154A0132021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21154A0112021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21154A0142021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21117A0442021-04-26026 April 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21084A2532021-03-24024 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Transfer Application ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21033A8552021-02-0202 February 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet Alternative Request to Expand the Use ASME Codes Cases N-878 and N-880 ML21029A3302021-01-29029 January 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative Request to Use ASME Code Case N-885 ML21022A0092021-01-21021 January 2021 Request-Calvert Cliffs-Exelon Generation Co., LLC ML20352A3802020-12-17017 December 2020 Acceptance of Requested Licensing Action to Add Containment Sump Technical Specifications ML20350B5582020-12-14014 December 2020 NRR E-mail Capture - Exelon Generation Company, LLC -Alternative Request for Documentation of Replacement of Pressure Retaining Bolting 2024-01-11
[Table view] Category:Report
MONTHYEARML23055A2842023-02-24024 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 Owner'S 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 Framatome'S 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 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 2023-02-24
[Table view] Category:Miscellaneous
MONTHYEARML21263A1862021-09-20020 September 2021 Proposed Alternative Concerning Pressure Testing of ASME Section XI Class 2 Portions of the Auxiliary Feedwater System ML21013A5302021-01-13013 January 2021 Reactor Vessel Level Monitoring System Special Report ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting 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) ML15062A0432015-02-27027 February 2015 Report of Changes, Tests, and Experiments - 10 CFR 50.59 and 10 CFR 72.48 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 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 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. ML13225A5662013-12-17017 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049(Mitigation Strategies) ML13224A1032013-08-0808 August 2013 CCNPP-CHLE-007, Revision 0c, Coatings Bench-Top Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant. ML13078A0102013-03-12012 March 2013 Flood Hazard Reevaluation Report ML13066A1712013-02-28028 February 2013 R.E. Gina, Overall Integrated Plan for Mitigation Strategies for Beyond-Design-Basis External Events ML12055A0482012-02-22022 February 2012 Independent Spent Fuel Storage Installation, Report of Changes, Tests, and Experiments - 10 CFR 50.59 and 10 CFR 72.48 ML12027A0122012-01-24024 January 2012 Core Operating Limits Report for Unit 1, Cycle 20 ML1109400392011-03-31031 March 2011 10 CFR 50.46 30-day Report for Changes to the Emergency Core Cooling System Performance Analysis ML1024302022010-08-27027 August 2010 Reactor Vessel Water Level Monitoring System Special Report ML0935205402009-11-25025 November 2009 Submittal of Updated List of Facility Emission Inventory Registration ML0911901582009-04-24024 April 2009 Post-Accident Monitoring Report ML12220A1012008-11-24024 November 2008 Constellation Energy Group, Inc. Definitive Proxy Statement Schedule 14A ML0827602832008-10-0101 October 2008 Attachments 1 & 2, Calvert Cliffs Nuclear Power Plant Inc., Proposed Alternative ISI-020, and Proposed Alternative ISI-021 ML0827404972008-09-30030 September 2008 Calvert Cliffs Nuclear Plant, Attachment 2, ECCS and CS System Figures ML0827404952008-09-30030 September 2008 Calvert Cliffs Nuclear Plant, Attachment 1, Supplemental Response to Generic Letter 2004-02 ML0807402272008-03-12012 March 2008 Response to Request for Additional Information Control Room Habitability ML0805004452008-02-14014 February 2008 Report of Changes, Tests, and Experiments - 10 CFR 50.59 and 10 CFR 72.48 ML0709305152007-03-27027 March 2007 Core Operating Limits Report for Unit 2, Cycle 17, Revision 0 ML0703201272007-01-30030 January 2007 Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds ML0625600382006-09-0707 September 2006 Special Report: Technical Specification 4.1, Appendix B, Unusual Fish Kill IR 05000317/20040082006-06-0101 June 2006 Final Precursor Analysis - Calvert Cliffs 2, LER 318/04-001-00; IR 05000317-04-008 and 05000318-04-008 - Excessive Steam Demand - Reactor Trip Due to Low Steam Generator Water Level After Feed Pump Trip ML0611101802006-04-21021 April 2006 Enclosure 1 - Report ORNL/NRC/LTR-05/22, Results of Probabilistic Fracture Mechanics Analyses of Pressurized Thermal Shock Transients for Calvert Cliffs Nuclear Power Plant Using Favor 04.1 ML0611704292006-04-11011 April 2006 Core Operating Limits Report for Unit 1, Cycle 18, Revision 2 ML0606100812006-02-27027 February 2006 2005 Steam Generator Tube Inspection Results Report ML0513701102005-05-12012 May 2005 Days After Plant Restart Report - First Revised NRC Order EA-03-009, Interim Inspection Requirement for Reactor Pressure Vessel Heads at Pressurized Water Reactors ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement ML0421501542004-07-28028 July 2004 Special Report: Mortality of a Species Protected by the Endangered Species Act of 1973 ML0318909502003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-duty Enhancements for Nuclear Security Force Personnel for Calvert Cliffs, ML0313301332003-05-0707 May 2003 Emergency Response Data System ML0306202372003-02-26026 February 2003 Report of Changes, Tests, & Experiments - 10 CFR 50.59 ML0306202432003-02-21021 February 2003 Reactor Vessel Water Level Monitoring System Special Report ML0300805942003-01-0303 January 2003 Report of Changes, Tests, & Experiments - 10 CFR 50.59 ML0223203592002-08-13013 August 2002 Special Report Re National Pollution Discharge Elimination System Permit No. 99-DP-0187 Violation from Calvert Cliffs Units 1 & 2 ML0220001132002-07-15015 July 2002 Emergency Response Data System ML0215503102002-05-29029 May 2002 Submittal of Emergency Core Cooling System Codes and Methods Report 2021-09-20
[Table view] |
Text
From: Loomis, Thomas R:(GenCo -Nuc) <thomas.loomis@exeloncorp.com>
Sent: Wednesday, February 24, 2016 8:21 AM To: Chereskin, Alexander Cc: Villar, Enrique:(GenCo-Nuc)
Subject:
[External_Sender] Draft for 1100 Discussion Attachments: 10CFRSO SS(a) Evaluation 2016-02-23 1700 DRAFT .docx Alex Here is an unverified draft for discussion at the 1100 call.
Thanks Tom This Email message and any attachment may contain information that is proprietary, legally privileged, confidential and/or subject to copyright belonging to Exelon Corporation or its affiliates ("Exelon"). This Email is intended solely for the use of the person(s) to which it is addressed. If you are not an intended recipient, or the employee or agent responsible for delivery of this Email to the intended recipient(s), you are hereby notified that any dissemination, distribution or copying of this Email is strictly prohibited. If you have received this message in error, please immediately notify the sender and permanently delete this Email and any copies.
Exelon policies expressly prohibit employees from making defamatory or offensive statements and infringing any copyright or any other legal right by Email communication. Exelon will not accept any liability in respect of such communications. -EXCIP 1
10 CFR 50.55a February XX, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington , DC 20555-0001 Calvert Cliffs Nuclear Power Plant, Unit 1 Facility Operating License No. DPR-53 NRC Docket No. 50-317
Subject:
Report Concerning Dissimilar MetallJA*liw*cation on Pressurizer Safety Relief Nozzle to Safe End Weld Examinations performed during the curren tall8trr Plant, Unit 1 have identified a change fro pressurizer safety relief nozzle to safe en Mechanical Stress Improvement Process (M performed to meet ASME Code se N-770-1 a l=WllMl::1\1 mitigated weld whose volumetric xamination volume that exceed the marizing the evaluation , along law or flaw growth is to be than modes 5 or 6."
ilar metal (OM) butt welds within the scope
- Mmti.re eling outage using Section XI ,
ffected weld will be repaired by full structural ents i is letter. If you have any questions concerning this sat (610) 765-5510.
Respectfully, James Barstow Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC
Attachment:
Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzle to Safe End Weld
Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzle to Safe End Weld Page 1 cc: Regional Administrator, Region I, USNRC USNRC Senior Resident Inspector, CCNPP USNRC Project Manager [CCNPP]
S. T. Gray, State of Maryland
Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzle to Safe End Weld Page 2 Purpose of Evaluation:
During examinations performed to meet ASME Code Case N-770-1 and 10 CFR 50.55a(g)(6)(ii)(F) requirements, a change was obseNed from previous examinations in an axial indication in a pressurizer safety relief nozzle to safe end dissimilar metal butt weld that was mitigated by the Mechanical Stress Improvement Process (MSIP) in 2006.
10 CFR 50.55a(g)(6)(ii)(F)(6) states: "For any mitigated weld whose volumetric examination detects growth of existing flaws in the required examination volume that exceed the previous IWB-3600 flaw evaluations or new flaws, a report summ the evaluation, along with inputs, methodologies, assumptions, and causes of th aw or flaw growth is to be provided to the NRC prior to the weld being placed i ce other than modes 5 or 6."
Evaluation Id), also designated as lnseNice Inspection 0-1, Inspection Item d array ultrasonic
,.._,,_npendix VIII ,
ystems, to detect a length and
- d examination volume from the El 03-08 guidance for ry Water Stress Corrosion eet the requirements of icated in Table 1 below.
e Achieved - 2016 Exams Combined Coverage Assessment 100% 100%
100% 100%
Carbon Steel 100% 100%
Nozzle SA-508,
~ilj{ UT data identified one axially oriented defect indication, which is contained within the wel terial, exhibiting characteristics indicative of PWSCC. The measured depth of the indication was 81.6% through-wall including clad thickness. In addition, eight indications characterized as embedded fabrication flaws were detected during the data evaluation. See Figure 1 for a graphic representation of the indications in this weld as reported in 201 O along with an approximation of the 2016 flaw characteristics. To confirm that the flaw has changed since the last examination, another NOE vendor performed a manual encoded phased array UT examination and confirmed that the flaw was ID connected and had a through-wall extent of 67.2%.
Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzle to Safe End Weld Page 3 Figure 1 Annotated Figure 6-1 from 2010 EPRI Report Showing 2016 Flaw Approximate Size and Location UT .2010 Final Call in 2010 lnlU;iftj Reoortl!d Ct'CA "
grouped two embedded non-PW SCC flaws 2016 Approximate Flaw Depth RT Approximate Flaw Depth
= RT Indication (Actual Depth & Size Not Depicted on Sketch)
=UT lndication(s) 2010 View Look ing Upstream (Into pressurizer) chanic stress improvement process (MSIP) application in e application of MSIP identified an axial flaw in the same location as the 2 reported to be 8% through-wall and was acceptable per IWB-3500. UT examinat1 ely following the MSIPapplication confirmed the indication was still present and a e 8% through-wall depth. lnservice examinations in 201 O also reported the same throug all depth.
Inputs Following the examination in 2006 and application of MSIPa flaw evaluation of the axial flaw was performed and submitted to the NRC. A non-linear finite element analysis using the ANSYS Program was performed for the application of MSIP. This analysis confirmed that an axial PWSCC flaw of 8% depth would be contained within the compressive hoop stress zone of
Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzle to Safe End Weld Page 4 the post MSIP stress profile at operating conditions. The post MSIP stress profile is compressive from the ID of the pipe wall to an extent of approximately 50% of the through-wall depth. As shown in Figure 2, the hoop stress then becomes tensile out to the OD, reaching tensile stress values of about 55 ksi at 80% through-wall and reducing to about 44 ksi at the OD of the pipe.
Figure 2 2006 Post MSIP+Operating Stress Calculated Hoop Stress Through Wall at Nominal Flaw Position (Path along butter interface) '
PATH HOOP DIST STRESS inch si 0.000 2,278 0.068 -1 ,124 0.135 -7,546 0.203 -24,114 0.271 -42,931 0.338 -47,583 0.406 -49,002 0.473 -47,203 0.541 -34,280 0.609 -20,561 0.676 -8,4 0.744 -8 0.812 1.353
Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzle to Safe End Weld Page 5 80,000 60,000 40,000 20,000 0
1.4
-20,000
-40,000
-60,000 The results of the phased array performed in 201 how that the axial flaw is widest at the ID (I owe ower in the center -1 /3rd of the flaw and becomes wider in the top -1/3 below). The PWSCC flaw indication is narrower ction in the middle through-wall range of the flaw w
Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzle to Safe End Weld Page 6 Figure 3 2016 Axial Flaw Characteristics Flaw as illustrated with CAD software 0.23 in A E. N Methodologies tion history of weld 4-SR-1006-1 was reviewed to confirm fabrication repairs, construction examination and inservice examination results. The inservice examinations from 2006 (pre- and post-MSIP), 2010, and 2016 were reviewed to confirm if the flaw observed in 2016 was present and not called in the previous years. See Table 2 for a summary of exams performed. The post-MSIP stress profiles were reviewed both in 2006 and 201 Oto confirm the extent of the compressive stress region and effectiveness of the MSIP application . Physical measurements were also performed in 2010 to confirm the MSIP parameters were met.
Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzle to Safe End Weld Page 7 Table 2 4-SR-1006-1 DM Weld Ins ection Histor Liquid Radiograp Manua Auto Year Visual Penetra Comments hy I UT UT nt 1972 Yes Yes ASME Ill ; 1 PT surface re air 1973 Yes Yes Yes E XI Pre-Service Exam 1980 Yes Yes 2004 Yes 2006 Yes 2010 Yes 2016 Yes
- Circumferential scans only.
Assumptions 1.
- 2. h wall axial extent than e allowed 30% through wall re preliminary as the station will be
- 1) s ineffective allowing the existing axial flaw to grow,
- 2) A new in d in the weld , or
- 3) Prior NOE ~-a pre-existing flaw larger than 30% through-wall prior to MSIP (either -80% tt~*IFtrall or some value between -30% and 80%)
The first potential cause was ruled out due to extensive reviews of the MSIP implementation documentation and by obtaining independent field measurements to confirm the required parameters were met. The second potential cause was ruled out since the MSIP application was found to have been performed correctly. It is not plausible that a new ID flaw could initiate and grow through the compressive stress region to the currently observed flaw depth. Also, this axial indication is in the same location as the previously identified axial indication just with a larger through-wall extent, so it would not be considered a new flaw.
Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzle to Safe End Weld Page 8 The third potential cause is considered to be the most likely cause for the change in the axial indication's through wall extent from 201 O to 2016. The data collected in 2016 was reviewed by Exelon , EPRI and inspection vendor NOE personnel. After this review, the 2006 inspection vendor personnel reviewed the pre-MSIP and post-MSIP data collected in 2006 as well as the data collected in 2010. The team came to a consensus that the 2016 reported flaw is ID connected , the NOE data quality is good and the proper techniques were used.
The 2016 examination technique included a larger aperture search unit, additional angles, lower frequency, and enhanced focusing. This data imaged th viously reported axial flaw, but with a much deeper extent. After carefully reviewing t it was determined that this optimized technique may have provided sufficient d etect the connection of the flaws that were previously seen in the other examinations. rication flaws and a potential repair area made depth sizing more difficult.
Due to limitations with the data collection J4itir't *v*~~ examination, the upper portion of the flaw may not have been de ta quality was improved and some indications above the ID connect .-l&Jare not in the pre-MSIP data, but there was no clear connection re treated as two unrelated indications. The stre file indicate connected flaw and the fabricati
From: Loomis, Thomas R:(GenCo -Nuc) <thomas.loomis@exeloncorp.com>
Sent: Wednesday, February 24, 2016 8:21 AM To: Chereskin, Alexander Cc: Villar, Enrique:(GenCo-Nuc)
Subject:
[External_Sender] Draft for 1100 Discussion Attachments: 10CFRSO SS(a) Evaluation 2016-02-23 1700 DRAFT .docx Alex Here is an unverified draft for discussion at the 1100 call.
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10 CFR 50.55a February XX, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington , DC 20555-0001 Calvert Cliffs Nuclear Power Plant, Unit 1 Facility Operating License No. DPR-53 NRC Docket No. 50-317
Subject:
Report Concerning Dissimilar MetallJA*liw*cation on Pressurizer Safety Relief Nozzle to Safe End Weld Examinations performed during the curren tall8trr Plant, Unit 1 have identified a change fro pressurizer safety relief nozzle to safe en Mechanical Stress Improvement Process (M performed to meet ASME Code se N-770-1 a l=WllMl::1\1 mitigated weld whose volumetric xamination volume that exceed the marizing the evaluation , along law or flaw growth is to be than modes 5 or 6."
ilar metal (OM) butt welds within the scope
- Mmti.re eling outage using Section XI ,
ffected weld will be repaired by full structural ents i is letter. If you have any questions concerning this sat (610) 765-5510.
Respectfully, James Barstow Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC
Attachment:
Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzle to Safe End Weld
Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzle to Safe End Weld Page 1 cc: Regional Administrator, Region I, USNRC USNRC Senior Resident Inspector, CCNPP USNRC Project Manager [CCNPP]
S. T. Gray, State of Maryland
Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzle to Safe End Weld Page 2 Purpose of Evaluation:
During examinations performed to meet ASME Code Case N-770-1 and 10 CFR 50.55a(g)(6)(ii)(F) requirements, a change was obseNed from previous examinations in an axial indication in a pressurizer safety relief nozzle to safe end dissimilar metal butt weld that was mitigated by the Mechanical Stress Improvement Process (MSIP) in 2006.
10 CFR 50.55a(g)(6)(ii)(F)(6) states: "For any mitigated weld whose volumetric examination detects growth of existing flaws in the required examination volume that exceed the previous IWB-3600 flaw evaluations or new flaws, a report summ the evaluation, along with inputs, methodologies, assumptions, and causes of th aw or flaw growth is to be provided to the NRC prior to the weld being placed i ce other than modes 5 or 6."
Evaluation Id), also designated as lnseNice Inspection 0-1, Inspection Item d array ultrasonic
,.._,,_npendix VIII ,
ystems, to detect a length and
- d examination volume from the El 03-08 guidance for ry Water Stress Corrosion eet the requirements of icated in Table 1 below.
e Achieved - 2016 Exams Combined Coverage Assessment 100% 100%
100% 100%
Carbon Steel 100% 100%
Nozzle SA-508,
~ilj{ UT data identified one axially oriented defect indication, which is contained within the wel terial, exhibiting characteristics indicative of PWSCC. The measured depth of the indication was 81.6% through-wall including clad thickness. In addition, eight indications characterized as embedded fabrication flaws were detected during the data evaluation. See Figure 1 for a graphic representation of the indications in this weld as reported in 201 O along with an approximation of the 2016 flaw characteristics. To confirm that the flaw has changed since the last examination, another NOE vendor performed a manual encoded phased array UT examination and confirmed that the flaw was ID connected and had a through-wall extent of 67.2%.
Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzle to Safe End Weld Page 3 Figure 1 Annotated Figure 6-1 from 2010 EPRI Report Showing 2016 Flaw Approximate Size and Location UT .2010 Final Call in 2010 lnlU;iftj Reoortl!d Ct'CA "
grouped two embedded non-PW SCC flaws 2016 Approximate Flaw Depth RT Approximate Flaw Depth
= RT Indication (Actual Depth & Size Not Depicted on Sketch)
=UT lndication(s) 2010 View Look ing Upstream (Into pressurizer) chanic stress improvement process (MSIP) application in e application of MSIP identified an axial flaw in the same location as the 2 reported to be 8% through-wall and was acceptable per IWB-3500. UT examinat1 ely following the MSIPapplication confirmed the indication was still present and a e 8% through-wall depth. lnservice examinations in 201 O also reported the same throug all depth.
Inputs Following the examination in 2006 and application of MSIPa flaw evaluation of the axial flaw was performed and submitted to the NRC. A non-linear finite element analysis using the ANSYS Program was performed for the application of MSIP. This analysis confirmed that an axial PWSCC flaw of 8% depth would be contained within the compressive hoop stress zone of
Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzle to Safe End Weld Page 4 the post MSIP stress profile at operating conditions. The post MSIP stress profile is compressive from the ID of the pipe wall to an extent of approximately 50% of the through-wall depth. As shown in Figure 2, the hoop stress then becomes tensile out to the OD, reaching tensile stress values of about 55 ksi at 80% through-wall and reducing to about 44 ksi at the OD of the pipe.
Figure 2 2006 Post MSIP+Operating Stress Calculated Hoop Stress Through Wall at Nominal Flaw Position (Path along butter interface) '
PATH HOOP DIST STRESS inch si 0.000 2,278 0.068 -1 ,124 0.135 -7,546 0.203 -24,114 0.271 -42,931 0.338 -47,583 0.406 -49,002 0.473 -47,203 0.541 -34,280 0.609 -20,561 0.676 -8,4 0.744 -8 0.812 1.353
Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzle to Safe End Weld Page 5 80,000 60,000 40,000 20,000 0
1.4
-20,000
-40,000
-60,000 The results of the phased array performed in 201 how that the axial flaw is widest at the ID (I owe ower in the center -1 /3rd of the flaw and becomes wider in the top -1/3 below). The PWSCC flaw indication is narrower ction in the middle through-wall range of the flaw w
Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzle to Safe End Weld Page 6 Figure 3 2016 Axial Flaw Characteristics Flaw as illustrated with CAD software 0.23 in A E. N Methodologies tion history of weld 4-SR-1006-1 was reviewed to confirm fabrication repairs, construction examination and inservice examination results. The inservice examinations from 2006 (pre- and post-MSIP), 2010, and 2016 were reviewed to confirm if the flaw observed in 2016 was present and not called in the previous years. See Table 2 for a summary of exams performed. The post-MSIP stress profiles were reviewed both in 2006 and 201 Oto confirm the extent of the compressive stress region and effectiveness of the MSIP application . Physical measurements were also performed in 2010 to confirm the MSIP parameters were met.
Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzle to Safe End Weld Page 7 Table 2 4-SR-1006-1 DM Weld Ins ection Histor Liquid Radiograp Manua Auto Year Visual Penetra Comments hy I UT UT nt 1972 Yes Yes ASME Ill ; 1 PT surface re air 1973 Yes Yes Yes E XI Pre-Service Exam 1980 Yes Yes 2004 Yes 2006 Yes 2010 Yes 2016 Yes
- Circumferential scans only.
Assumptions 1.
- 2. h wall axial extent than e allowed 30% through wall re preliminary as the station will be
- 1) s ineffective allowing the existing axial flaw to grow,
- 2) A new in d in the weld , or
- 3) Prior NOE ~-a pre-existing flaw larger than 30% through-wall prior to MSIP (either -80% tt~*IFtrall or some value between -30% and 80%)
The first potential cause was ruled out due to extensive reviews of the MSIP implementation documentation and by obtaining independent field measurements to confirm the required parameters were met. The second potential cause was ruled out since the MSIP application was found to have been performed correctly. It is not plausible that a new ID flaw could initiate and grow through the compressive stress region to the currently observed flaw depth. Also, this axial indication is in the same location as the previously identified axial indication just with a larger through-wall extent, so it would not be considered a new flaw.
Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzle to Safe End Weld Page 8 The third potential cause is considered to be the most likely cause for the change in the axial indication's through wall extent from 201 O to 2016. The data collected in 2016 was reviewed by Exelon , EPRI and inspection vendor NOE personnel. After this review, the 2006 inspection vendor personnel reviewed the pre-MSIP and post-MSIP data collected in 2006 as well as the data collected in 2010. The team came to a consensus that the 2016 reported flaw is ID connected , the NOE data quality is good and the proper techniques were used.
The 2016 examination technique included a larger aperture search unit, additional angles, lower frequency, and enhanced focusing. This data imaged th viously reported axial flaw, but with a much deeper extent. After carefully reviewing t it was determined that this optimized technique may have provided sufficient d etect the connection of the flaws that were previously seen in the other examinations. rication flaws and a potential repair area made depth sizing more difficult.
Due to limitations with the data collection J4itir't *v*~~ examination, the upper portion of the flaw may not have been de ta quality was improved and some indications above the ID connect .-l&Jare not in the pre-MSIP data, but there was no clear connection re treated as two unrelated indications. The stre file indicate connected flaw and the fabricati