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Category:Drawing
MONTHYEARL-20-308, (BVPS) Pre-Draft NPDES Permit No. PA0025615, Comments Submitted in Response to Comments from DEP Received 08/10/20202020-11-18018 November 2020 (BVPS) Pre-Draft NPDES Permit No. PA0025615, Comments Submitted in Response to Comments from DEP Received 08/10/2020 ML15033A2282015-01-15015 January 2015 Drawing 8700-RM-0430-006, Piping & Instrumentation Diagram Rw/Sws Chemical Injection System. Revision 6 L-08-292, Lr Drawing 1-21-1, Rev. 7, Main Steam System (Ms).2008-10-24024 October 2008 Lr Drawing 1-21-1, Rev. 7, Main Steam System (Ms). ML0825506882008-09-0808 September 2008 Drawing, Lr Drawing 1-41C-1, Rev. 5, Domestic Water System (Pl). ML0825506862008-09-0808 September 2008 Drawing, Lr Drawing 2-34-2, Rev. 3, Station Instrument Air (Ias). ML0825506872008-09-0808 September 2008 Drawing, Lr Drawing 1-24-2, Rev. 6, Feedwater System (Fw). L-08-262, Drawing, Lr Drawing 2-31-1, Rev. 5, Demineralized Water System (Wtd).2008-09-0808 September 2008 Drawing, Lr Drawing 2-31-1, Rev. 5, Demineralized Water System (Wtd). ML0816406032008-06-0909 June 2008 Drawing Lr 2-15-6, Rev. 5, Primary Component Coolant System (Ccp). ML0816405972008-06-0909 June 2008 Drawing Lr 1-25-1, Rev. 5, Steam Generator Blowdown System (Bd). ML0816406012008-06-0909 June 2008 Drawing Lr 2-14A-1, Rev. 6, Reactor Plant Sample System, (Ssr). ML0816405932008-06-0909 June 2008 Drawing Lr 1-21-1, Rev. 6, Main Steam System (Ms). ML0816406022008-06-0909 June 2008 Drawing Lr 2-15-1, Rev. 5, Primary Component Coolant System (Ccp). ML0816405952008-06-0909 June 2008 Drawing Lr 1-24-2, Rev. 5, Feedwater System (Fw). ML0816405922008-06-0909 June 2008 Drawing Lr 1-14A-1, Rev. 8, Sample System (Ss). ML0816406002008-06-0909 June 2008 Drawing Lr 1-58E-1, Rev. 5, ERF Diesel Fuel Oil System (Rgf). ML0816405982008-06-0909 June 2008 Drawing Lr 1-32-7, Rev. 4, Water Treating System (Wt). ML0816405942008-06-0909 June 2008 Drawing Lr 1-22-1, Rev. 4, Condensate System (Cn). ML0816405962008-06-0909 June 2008 Drawing Lr 1-24-3, Rev. 4, Feedwater System (Fw). ML0816406042008-06-0909 June 2008 Drawing Lr 2-24-2A, Rev. 4, Main Feedwater System (Fws). ML0816405992008-06-0909 June 2008 Drawing Lr 1-45F-1, Rev. 5, Security Diesel Generator System (Nhs). L-08-189, Drawing Lr 2-27A-2, Rev. 4, Auxiliary Steam and Condensate System (Ass).2008-06-0909 June 2008 Drawing Lr 2-27A-2, Rev. 4, Auxiliary Steam and Condensate System (Ass). L-08-170, Drawing 2-34-11, Rev. 2, Instrument Air Standby Train (Ias).2008-05-19019 May 2008 Drawing 2-34-11, Rev. 2, Instrument Air Standby Train (Ias). ML0814407122008-05-19019 May 2008 Drawing 2-34-3, Rev. 7, Containment Instrument Air System (Iac). ML0814407112008-05-19019 May 2008 Drawing 2-34-2, Rev. 2, Station Instrument Air (Ias). ML0814407142008-05-19019 May 2008 Drawing 2-34-10, Rev. 1, Containment Instrument Air (Iac). L-08-150, Drawing, Lr Drawing LR-Structures, Rev. 2, Site Map - In-Scope Structures.2008-05-0808 May 2008 Drawing, Lr Drawing LR-Structures, Rev. 2, Site Map - In-Scope Structures. ML0814104172008-05-0808 May 2008 Drawing, Lr Drawing 2-30-1, Rev. 4, Service Water System (SWS) ML0810003242008-04-0303 April 2008 Drawing Lr 1-08-1, Rev. 4, Boron Recovery Degasifiers. ML0810003222008-04-0303 April 2008 Drawing Lr 1-07-2, Rev. 4, Chemical and Volume Control System. ML0810003302008-04-0303 April 2008 Drawing Lr 1-19-1, Rev. 5, Gaseous Waste Disposal System. ML0810003282008-04-0303 April 2008 Drawing Lr 1-14A-1, Rev. 7, Sample System. ML0810003322008-04-0303 April 2008 Drawing Lr 1-30-1, Rev. 5, River Water System. ML0810003232008-04-0303 April 2008 Drawing Lr 1-07-3, Rev. 6, Chemical and Volume Control System. ML0810003272008-04-0303 April 2008 Drawing Lr 1-12-1, Rev. 5, Containment Vacuum and Leakage Monitoring System. ML0810003292008-04-0303 April 2008 Drawing Lr 1-14A-2, Rev. 5, Sample System. ML0810003262008-04-0303 April 2008 Drawing Lr 1-09-2, Rev. 4, Vent and Drain System. ML0810003312008-04-0303 April 2008 Drawing Lr 1-24-1, Rev. 6, Feedwater System. L-08-123, Drawing Lr 1-46-2, Rev. 5, Post DBA Hydrogen Analyzer System.2008-04-0303 April 2008 Drawing Lr 1-46-2, Rev. 5, Post DBA Hydrogen Analyzer System. ML0809403972008-03-31031 March 2008 Drawing 1-44B-1, Rev. 4, Air Vent and Cooling System (Vs). ML0809403992008-03-31031 March 2008 Drawing 2-47-1, Rev. 5, Containment Air Locks & Fuel Transfer Tube System (Phs). ML0729101052007-11-0202 November 2007 Letters to Agencies, Request for List of Protected Species and Essential Fish Habitat within the Area Under Evaluation for the BVPS LRA Review ML0724302402007-08-27027 August 2007 Drawing 1-12-1, Rev. 4, Containment Vacuum and Leakage Monitoring System (Cv). ML0724302392007-08-27027 August 2007 Drawing 1-11-2, Rev. 6, Safety Injection System (Si). ML0724302382007-08-27027 August 2007 Drawing 1-11-1, Rev. 6, Safety Injection System (Si). ML0724302352007-08-27027 August 2007 Drawing 1-10-1, Rev. 5, Residual Heat Removal System (Rh). ML0724302312007-08-27027 August 2007 Drawing 1-09-3, Rev. 3, Vent and Drain System (Dv). ML0724302282007-08-27027 August 2007 Drawing 1-09-2, Rev. 3, Vent and Drain System (Dv). ML0724302152007-08-27027 August 2007 Drawing 1-08-2, Rev. 3, Boron Recovery Ion Exchangers (Br). ML0724302762007-08-27027 August 2007 Drawing 1-19-2, Rev. 3, Gaseous Waste Disposal System (Gw). ML0724302792007-08-27027 August 2007 Drawing 1-20-1, Rev. 3, Fuel Pool Cooling and Purification System (Pc). 2020-11-18
[Table view] Category:Letter type:L
MONTHYEARL-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024 License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 L-24-199, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-08-22022 August 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule L-24-182, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-23023 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-161, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-19019 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-014, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models2024-07-16016 July 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report L-24-094, Reactor Vessel Surveillance Capsule Withdrawal Schedule2024-06-24024 June 2024 Reactor Vessel Surveillance Capsule Withdrawal Schedule L-24-152, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-06-17017 June 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations L-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report L-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-107, CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair2024-05-13013 May 2024 CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2024-05-0707 May 2024 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions L-24-054, Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological)2024-04-29029 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological) L-24-089, Emergency Preparedness Plan2024-04-23023 April 2024 Emergency Preparedness Plan L-24-088, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 20242024-04-22022 April 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 2024 L-24-082, Withdrawal of Exemption Request2024-04-0303 April 2024 Withdrawal of Exemption Request L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-064, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152024-03-13013 March 2024 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee L-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023 Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-198, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0707 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation L-23-241, Submittal of the Updated Final Safety Analysis Report, Revision 272023-11-29029 November 2023 Submittal of the Updated Final Safety Analysis Report, Revision 27 L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023 L-23-208, Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA00256152023-09-14014 September 2023 Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA0025615 L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report2023-09-13013 September 2023 Twenty-Third Refueling Outage Inservice Inspection Summary Report L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-179, Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-07-18018 July 2023 Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA0025615 L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report2023-06-13013 June 2023 Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023 Cycle 24 Core Operating Limits Report L-23-132, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-10010 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations2023-05-0505 May 2023 Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations L-23-115, Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological2023-04-27027 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological L-23-126, Discharge Monitoring Report (Npdes), Permit No. PA00256152023-04-22022 April 2023 Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-053, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-04-14014 April 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-23-058, 180-Day Steam Generator Tube Inspection Report2023-03-27027 March 2023 180-Day Steam Generator Tube Inspection Report L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023 Annual Notification of Property Insurance Coverage L-23-036, Report of Facility Changes, Tests and Experiments2023-03-13013 March 2023 Report of Facility Changes, Tests and Experiments L-23-086, Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0404 March 2023 Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair 2024-09-17
[Table view] Category:Report
MONTHYEARL-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-22-154, Pressure and Temperature Limits Report Revision2022-07-0606 July 2022 Pressure and Temperature Limits Report Revision L-22-054, Steam Generator Inspection Report- Fall 2021 Refueling Outage2022-02-10010 February 2022 Steam Generator Inspection Report- Fall 2021 Refueling Outage IR 05000334/20210052021-09-0101 September 2021 Updated Inspection Plan for the Beaver Valley Power Station, Units 1 and 2 (Report 05000334/2021005 and 05000412/2021005) ML21131A0242021-05-17017 May 2021 Review of Reactor Pressure Vessel Capsule Y Analysis Report ML21055A0582021-03-10010 March 2021 Review of the Refueling Outage 21 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and F* Reports L-21-063, Facility Id 04-13361, Unit 2 Emergency Diesel Generator Day Tanks2021-02-0101 February 2021 Facility Id 04-13361, Unit 2 Emergency Diesel Generator Day Tanks ML21026A3372021-01-26026 January 2021 Steam Generator Inspection Report Revision - Spring 2020 Refueling Outage L-20-257, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic2020-09-22022 September 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic ML21127A1652020-07-17017 July 2020 ODCM: Index, Matrix and History of ODCM Changes L-21-135, ODCM: Liquid Effluents2020-07-17017 July 2020 ODCM: Liquid Effluents ML21127A1482020-07-17017 July 2020 ODCM: Controls for RETS and REMP Programs L-20-116, CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency2020-04-0101 April 2020 CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency ML19280A0382019-10-22022 October 2019 Ti 2515-191 Summary of Findings ML21127A1562019-07-17017 July 2019 ODCM: Gaseous Effluents ML19051A1092019-02-20020 February 2019 LTR-SDA-18-054-NP, Revision 0 - Technical Justification to Support the Extended Volumetric Examination Interval for Beaver Valley Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds L-19-053, Emergency Response Data System Data Point Library Update2019-02-20020 February 2019 Emergency Response Data System Data Point Library Update L-18-037, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2018-06-18018 June 2018 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-18-017, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado.2018-03-15015 March 2018 Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado. ML21127A1592018-01-22022 January 2018 ODCM: Radiological Environmental Monitoring Program L-17-277, Pressure and Temperature Limits Reports, Revisions 8 and 92017-10-0404 October 2017 Pressure and Temperature Limits Reports, Revisions 8 and 9 L-17-259, Mitigating Strategies Assessment (MSA) for Flooding2017-09-20020 September 2017 Mitigating Strategies Assessment (MSA) for Flooding ML17213A0162017-05-11011 May 2017 Enclosure a: Beaver Valley, Units 1, Seismic Probabilistic Risk Assessment in Response to 50.54(f) Letter with Regard to NTTF 2.1 ML17213A0172017-05-11011 May 2017 Enclosure B: Beaver Valley, Unit 2, Seismic Probabilistic Risk Assessment in Response to 50.54(0 Letter with Regard to NTTF 2.1 ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 ML16312A3112016-11-0707 November 2016 Spent Fuel Pool Evaluation Supplemental Report. Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Ntif) Review... L-16-327, Technical Basis for Optimization or Elimination of Liquid Penetrant Exams for the Embedded Flaw Repair2016-10-31031 October 2016 Technical Basis for Optimization or Elimination of Liquid Penetrant Exams for the Embedded Flaw Repair L-16-093, Report of Facility Changes, Tests and Experiments2016-06-0303 June 2016 Report of Facility Changes, Tests and Experiments L-16-065, Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.22016-04-0606 April 2016 Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2 L-16-006, Submittal of Annual Report Pursuant to 10 CFR 75.11, Location Information2016-01-20020 January 2016 Submittal of Annual Report Pursuant to 10 CFR 75.11, Location Information L-15-386, Post Accident Monitoring Report Regarding Inoperability of One of the Source Range Nuclear Excore Instrumentation Channel for a Period in Excess of the 30-Day Restoration Time2016-01-0505 January 2016 Post Accident Monitoring Report Regarding Inoperability of One of the Source Range Nuclear Excore Instrumentation Channel for a Period in Excess of the 30-Day Restoration Time L-15-337, Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool..2015-12-21021 December 2015 Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool.. ML16277A1142015-10-28028 October 2015 ERS-MPD-93-007, Rev. 11, BVPS-U1 Gaseous Radioactivity Monitor Emergency Action Levels. ML15274A3072015-10-0505 October 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54 Seismic Hazard Reevaluations for Recommendation 2.1of the Near-Term Task Force Review L-15-187, Submittal of 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2015-09-16016 September 2015 Submittal of 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML15132A4962015-05-22022 May 2015 Review of the 2014 Steam Generator Tube Inspection Report (TAC No. M4620) ML16277A1222015-04-20020 April 2015 ERS-LMR-14-001, Rev. 1, Liquid Monitor Alert Emergency Action Level (EAL) Set Points. ML15119A1042015-03-31031 March 2015 SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 1 of 4 L-15-091, SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 2 of 42015-03-31031 March 2015 SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 2 of 4 ML21127A1582015-02-11011 February 2015 ODCM: Bases for ODCM Controls ML16277A1152015-01-30030 January 2015 ERS-HHM-87-014, Rev. 8, Unit 1 / Unit 2 ODCM Gaseous Effluent Monitor Setpoints. ML15027A2352015-01-28028 January 2015 Regulatory Audit in Support of the License Amendment Request to Implement a Risk-Informed, Performance-Based, Fire Protection Program (Tac Nos. MF3301 & MF3302) L-14-401, First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In2014-12-19019 December 2014 First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In L-14-352, Steam Generator Tube Inspection Report - Technical Specification 5.6.6.22014-11-0505 November 2014 Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2 ML21127A1442014-10-0707 October 2014 ODCM: Information Related to 40 CFR 190 L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML14224A5772014-07-31031 July 2014 SG-SGMP-14-17, Revision 1, Beaver Valley, Unit 2, End-of-Cycle 17 Analysis and Prediction for End-of-Cycle 18 Voltage-Based Repair Criteria 90-Day Report. ML14224A5762014-07-31031 July 2014 SG-CCOE-14-1, Revision 0, Generic Letter 95-05 Tube Intersection Burst Test, Leakage Test, and Morphology Conclusions. ML14224A5752014-06-25025 June 2014 R17 Steam Generator F* (F Star) Report ML14009A0892014-02-10010 February 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Daiichi Nuclear Power Plant Accident 2023-08-07
[Table view] Category:Miscellaneous
MONTHYEARL-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments IR 05000334/20210052021-09-0101 September 2021 Updated Inspection Plan for the Beaver Valley Power Station, Units 1 and 2 (Report 05000334/2021005 and 05000412/2021005) ML21131A0242021-05-17017 May 2021 Review of Reactor Pressure Vessel Capsule Y Analysis Report ML21055A0582021-03-10010 March 2021 Review of the Refueling Outage 21 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and F* Reports L-21-063, Facility Id 04-13361, Unit 2 Emergency Diesel Generator Day Tanks2021-02-0101 February 2021 Facility Id 04-13361, Unit 2 Emergency Diesel Generator Day Tanks L-20-257, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic2020-09-22022 September 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic L-19-053, Emergency Response Data System Data Point Library Update2019-02-20020 February 2019 Emergency Response Data System Data Point Library Update L-18-037, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2018-06-18018 June 2018 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-18-017, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado.2018-03-15015 March 2018 Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado. ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 ML16312A3112016-11-0707 November 2016 Spent Fuel Pool Evaluation Supplemental Report. Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Ntif) Review... L-16-093, Report of Facility Changes, Tests and Experiments2016-06-0303 June 2016 Report of Facility Changes, Tests and Experiments L-16-065, Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.22016-04-0606 April 2016 Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2 L-16-006, Submittal of Annual Report Pursuant to 10 CFR 75.11, Location Information2016-01-20020 January 2016 Submittal of Annual Report Pursuant to 10 CFR 75.11, Location Information L-15-386, Post Accident Monitoring Report Regarding Inoperability of One of the Source Range Nuclear Excore Instrumentation Channel for a Period in Excess of the 30-Day Restoration Time2016-01-0505 January 2016 Post Accident Monitoring Report Regarding Inoperability of One of the Source Range Nuclear Excore Instrumentation Channel for a Period in Excess of the 30-Day Restoration Time L-15-337, Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool..2015-12-21021 December 2015 Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool.. ML15274A3072015-10-0505 October 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54 Seismic Hazard Reevaluations for Recommendation 2.1of the Near-Term Task Force Review L-15-187, Submittal of 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2015-09-16016 September 2015 Submittal of 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML15132A4962015-05-22022 May 2015 Review of the 2014 Steam Generator Tube Inspection Report (TAC No. M4620) ML15027A2352015-01-28028 January 2015 Regulatory Audit in Support of the License Amendment Request to Implement a Risk-Informed, Performance-Based, Fire Protection Program (Tac Nos. MF3301 & MF3302) L-14-401, First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In2014-12-19019 December 2014 First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In L-14-352, Steam Generator Tube Inspection Report - Technical Specification 5.6.6.22014-11-0505 November 2014 Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2 L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML14009A0892014-02-10010 February 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Daiichi Nuclear Power Plant Accident ML13284A0242013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3, Seismic Walkdown Report Revision 1, Appendix B, Seismic Walkdown Checklists (Swcs), Part 3 of 5 ML13284A0272013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3, Seismic Walkdown Report Revision 1, Appendix B, Seismic Walkdown Checklists (Swcs), Continued, Part 4 of 5 ML13284A0262013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3, Seismic Walkdown Report Revision 1, Appendix a, Resumes and Qualifications, Part 2 of 5 ML13284A0252013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3, Seismic Walkdown Report Revision 1, Part 1 of 5 ML13284A0232013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Revision 1, Appendix a, Resumes and Qualifications, Part 2 of 5 ML13284A0192013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Revision 1, Appendix B Seismic Walkdown Checklists (Swcs), Part 3 of 5 ML13284A0222013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Revision 1, Part 1 of 5 ML13284A0202013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Revision 1, Appendix B Seismic Walkdown Checklists (Swcs) Continued. Part 4 of 5 ML13284A0212013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Revision 1, Appendix C Area Walk-by Checklists (Awcs), Part 5 of 5 L-13-036, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedules2013-05-28028 May 2013 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedules L-13-095, Discharge Monitoring Report (NPDES) Permit No. PA00256152013-02-22022 February 2013 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-12-437, Containment Liner Random and Non-Random Examinations Report2012-12-18018 December 2012 Containment Liner Random and Non-Random Examinations Report L-12-347, FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-27027 November 2012 FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML13008A0422012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B Seismic Walkdown Checklits (Swcs), Battery 2N. Pages 1 - 82 ML13008A0412012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report. Cover Through A-40 ML13135A2382012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 1 of 513 Through Sheet 301 of 513 ML13008A0432012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B Seismic Walkdown Checklists (Swcs), Purge Valve Isolation. Pages 83 - 161 ML13008A0442012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B Seismic Walkdown Checklists (Swcs), Bus F1, Low Voltage Switchgear. Pages 162 - 240 ML13008A0452012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B Seismic Walkdown Checklists (Swcs), SGI Level Switch SP9B6. Pages 241 - 318 ML13008A0462012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B Seismic Walkdown Checklists (Swcs), Relief Valves SW 3963. Pages 319 - End ML13135A2412012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C - Area Walk-by Checklists (Awcs) and Appendix D - Component List for Anchorage Configuration Check ML13135A2402012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 302 of 513 Through Sheet 513 of 513 ML13135A2362012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report ML13135A2372012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix a - Resumes and Qualifications ML13008A0402012-10-23023 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C Area Walk-by Checklists (Awcs), Prim. Aux. Bldg 735'6. Pages 135 - 191 ML13008A0392012-10-23023 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C Area Walk-by Checklists (Awcs), Emer. Swgr. Room Train A. Pages 66 - 134 2023-08-07
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FENOC FirstEnergyNuclear OperatingCompany James H. Lash 724-682-5234 Site Vice President Fax: 724-643-8069 November 20, 2006 L-06-163 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Pressurizer Weld Overlay Examination Report By letter dated March 31, 2006 (L-06-038) and supplemented by letters dated August 8, 2006 (L-06-123), September 27, 2006 (L-06-142), and October 5, 2006 (L-06-146), the FirstEnergy Nuclear Operating Company (FENOC) requested Nuclear Regulatory Commission (NRC) approval of a proposed alternative to American Society of Mechanical Engineers (ASME) Code Section XI requirements, in support of weld overlay repairs for Beaver Valley Power Station (BVPS) Unit No. 2 pressurizer nozzles. The NRC provided verbal authorization to perform the weld overlay repairs during a teleconference on October 5, 2006.
During the Beaver Valley Unit No. 2 2R12 Refueling Outage, FENOC completed the planned pressurizer structural weld overlay workscope, which included the application of full structural weld overlays to the pressurizer spray nozzle, relief (PORV) nozzle, three safety nozzles, and
.,surge nozzle. The final weld overlay ultrasonic examinations were completed on November 6, 2006.
Attachment 1, "Indications for Beaver Valley Unit 2 Pressurizer Weld Overlays", provides detailed results of the initial ultrasonic inspections performed on the pressurizer nozzles. The initial inspection results for locations that were subsequently repaired are noted as "Pre-Repair".
The following is a summary of the results:
Weld Identifications Number of Indications Nozzle (DM/SS) Initial PDI Inspection Indication Assessment Summary Safety A 2RCS*PRE21-103C / I Laminar Indication and I The laminar indication was acceptable, the 2RCS-103-F01 Planar planar indication was unacceptable and was removed in a repair excavation.
Safety B 2RCS*PRE21-102B / No Recordable Indications N/A 2RCS-102-FOI Safety C 2RCS*PRE21-101A / 2 Laminar Indications The two laminar indications were acceptable. No 2RCS-101-FOI Repair performed.
PORV 2RCS*PRE21-107Z / I Laminar Indication The single laminar indication was acceptable. No 2RCS-107-FO1 Repair performed.
Beaver Valley Power Station, Unit No. 2 Pressurizer Weld Overlay Examination Report L-06-163 Page 2 Weld Identifictationis Number of Indications Nozzle (DIN.l/SS) Initial PDI Inspection Indication Assessment Summnary Spray 2RCSIPRE21-202Z 1 4 Laminar Indications Tlhc four laminar indications were acceptable.
2RCS-202-FOI Repair was performed in the area of indications to correct a heat input issue, Surge 2RCS*PRE21-84Z/ 3 Laminar Indications Single indication (42) and combined indications 2RCS-84-F03 (42 & #3) exceed 7.5 sq. in. area and were unacceptable andrequired repair.
As noted in the summary table above, weld repairs were performed on the Safety A, Spray, and Surge nozzle. overlays. (Note that the indications in the spray nozzle were acceptable but fell within the repair area needed to correct a heat input discrepancy).
Attachment I also provides detailed results of the final ultrasonic inspections performed on the pressurizer Safety A, Spray, and Surge nozzles following repair and are noted as "Post-Repair".
The following is a summary of the post-repair results:
Weld Identifications Number of Indications Nozzle (DM/SS) Post Repair Inspection Indication Assessment Summary Safety A 2RCS*PRE21-103C/ No Recordable Indications in Only Original Indication I & Ia not located in 2RCS-103-FOI repair area repair area exist. No recordable indications in the repair area.
Spray 2RCS*PRE21I202Z/ 3 Laminar Indications The three laminar indications were acceptable.
2RCS-202-FO I Surge 2RCS*PRE21-84Z/ No Recordable Indications in Original Indication #1 and parts of Indication 9 2 2RCS-84-F03 repair area (2a and 2b) still exist. Indication #3 located in repair area was removed. Remaining indications (Indicatioi NI and parts of Indication #2) were acceotable. contains cross-sectional sketches showing the location and orientation of all indications, pre- and post-repair.
There are no regulatory commitments in this letter. If there are any questions or if additional information is required, please contact Mr. Gregory A. Dunn, Manager FENOC Fleet Licensing at (330) 315-7243.
Sincerely, H. Lash
Beaver Valley Power Station, Unit No. 2 Pressurizer Weld Overlay Examination Report L-06-163 Page 3 Attachments:
- 1. Indications for Beaver Valley Unit 2 Pressurizer Weld Overlays.
- 2. Nozzle Weld Repair Areas.
cc: Mr. T. G. Colbum, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Senior Resident Inspector Mr. S. J. Collins, NRC Region I Administrator Mr. D. A. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)
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Attachen t I . I,-OY-163 Table I Poge 5 Indicotion. for B_ r Valley Unit 2 Presrizero Weld Oerrlas NOaNo REMARFS WnCLUOD INDICATIONDISPOSITION M_:,0 00 04001.04000 0 000.0004 4.000o 0400401100 t'rEe 0.-.- FROM 00110C0 0I OF E
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000041 P00 140040Co~g INDICATIN0 serlceo p,.reolro. 00t0025%0 . 0.s0rr5 t14 NOTES .ABBREVIATIONS RiC- Reduction n Coveraoe DM.-Nozle/Sae 6ndWeld SS- SafeEnd/NPpe Weld to L-06-163 Page 1 Safety A - Indication 1 BEAVER VALLEY 2 SAFETY NOZZLE A INDICATIONS 1 & IA EVALUATED AT 180° PROFILE
.220 -
to L-06-163 Page 2 Safety A - Indication 1 (Cont'd)
Measurd OD Surface Length, Ind. #1 = 0.9" to L-06-163 Page 3 Safety A - Indication 2 (Removed during Repair)
- Measured OD Surface Length Ind. #2 = 1.2" to L-06-163 Page 4 Safety A - Indication 2 (Removed during Repair) to L-06-163 Page 5 Safety A - Indication 2 (Removed during Repair)
BEAVER VALLEY SAFETY NOZZLE INDICATIONS 2E & 2F EVALUATED AT 0° PROFILE Z
to L-06-163 Page 6 Safety C - Indication 1 BEAVER VALLEY UNIT 2 WELD OVERLAY PRESSURIZER SAFETY NOZZLE C INDICATION 1 EVALUATED AT 900 PROFILE I
INDICATION to L-06-163 Page 7 Safety C - Indication 2 BEAVER VALLEY UNIT R WELD OVERLAY PRESSURIZER SAFETY NOZZLE C INIDICATION P EVALUATED AT 0* PROFILE INDICATION to L-06-163 Page 8 Relief- Indication 1 R4.26 Beaver Valley Unit 2 PORV Nozzle 1800 Profile to L-06-163 Page 9 Sorav. Pre-Renair - Indications 1 & 2 BEAVER VALLEY 2 SPRAY NFIZZLE INDICATION 1 (0-)
8 INDICATION IA (45*)
EVALUATED AT 180° PROFILE INDICATION 2 (0°)
INDICATION 2A (45°)
EVALUATED AT 270°PROFILE to L-06-163 Page 10 Spray, Pre-Repair - Indications 3 & 4 BEAVER VALLEY 2 SPRAY NOZZLE INDICATION 3 (0°)
INDICATION 3A (45°)
EVALUATED AT 870° PROFILE INDICATIONS 4 (0)
INDICATION 4A (45°)
EVALUATED AT 270° PROFILE to L-06-163 Page I I Spray, Post-Repair- Indication I Measured Length on OD Surface for Ind. #1A = 3.8" to L-06-163 Page 12 Sprav. Post-ReDair - Indication 2 Measured Length on 00 Surface for nd. #2A = 1.3" to L-06-163 Page 13 Spray, Post-Repair - Indication 3 Measured Length on00 Surface for Ind. #3A = 1.95" to L-06-163 Page 14 Surge, Pre-Repair - Indication 1 BEAVER
- SURGE VALLEY 2 NOIZZLE INDICATION I EVALUATED AT G' PROFILE to L-06-163 Page 15 Surge, Pre-Repair - Indications 2 & 3 BEAVER VALLEY p SURGE NOZZLE INDICATIONS 2 & 3 EVALUATED AT 270' PROFILE 1.1 -
1420
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4 to L-06-163 Page 17 Surge, Post-Repair - Indications 2A & 2B DEAVER VALLEY 2 SURGE NOZZLE INDICATIONS 2A & 2B EVALUATED AT 270 PROFILE 7
SURGL e7U°