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Category:Letter type:NOC
MONTHYEARNOC-AE-230040, Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06)2023-12-14014 December 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) NOC-AE-230039, Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/20230032023-12-12012 December 2023 Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/2023003 NOC-AE-230039, Submittal of Update Foreign Ownership, Control or Influence (FOCI)2023-07-11011 July 2023 Submittal of Update Foreign Ownership, Control or Influence (FOCI) NOC-AE-220039, Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 252023-02-0606 February 2023 Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 25 NOC-AE-220038, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2022-06-23023 June 2022 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask NOC-AE-210038, Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 252022-01-0404 January 2022 Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 25 NOC-AE-21003858, 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes2021-12-0606 December 2021 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes NOC-AE-21003853, Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-12-0303 December 2021 Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003848, Unit 1 Cycle 24 Core Operating Limits Report2021-11-18018 November 2021 Unit 1 Cycle 24 Core Operating Limits Report NOC-AE-21003846, Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-11-0404 November 2021 Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003842, 10 CFR 50.59 Summary Report2021-09-23023 September 2021 10 CFR 50.59 Summary Report NOC-AE-21003841, Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25)2021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) NOC-AE-21003832, Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-0909 September 2021 Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003812, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-08-10010 August 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003825, Update of Foreign Ownership, Control, or Influence Information (FOCI)2021-08-0505 August 2021 Update of Foreign Ownership, Control, or Influence Information (FOCI) NOC-AE-21003824, Update Foreign Ownership, Control, or Influence (FOCI)2021-07-29029 July 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003823, Update Foreign Ownership Control or Influence (FOCI)2021-07-28028 July 2021 Update Foreign Ownership Control or Influence (FOCI) NOC-AE-21003820, Nuclear Insurance Protection2021-07-20020 July 2021 Nuclear Insurance Protection NOC-AE-21003819, Inservice Inspection Summary Report - 2RE212021-07-15015 July 2021 Inservice Inspection Summary Report - 2RE21 NOC-AE-21003816, Commitment Change Summary Report2021-06-30030 June 2021 Commitment Change Summary Report NOC-AE-21003814, Technical Specification Bases Control Program2021-06-24024 June 2021 Technical Specification Bases Control Program NOC-AE-21003810, Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy NOC-AE-21003811, Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy NOC-AE-21003806, Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval2021-05-20020 May 2021 Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval NOC-AE-21003801, Annual Dose Report for 20202021-04-26026 April 2021 Annual Dose Report for 2020 NOC-AE-21003802, 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report2021-04-26026 April 2021 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report NOC-AE-21003804, Operator Licensing Examination Schedule2021-04-21021 April 2021 Operator Licensing Examination Schedule NOC-AE-21003800, Radioactive Effluent Release Report2021-04-19019 April 2021 Radioactive Effluent Release Report NOC-AE-21003799, Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan2021-04-15015 April 2021 Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan NOC-AE-21003795, Cycle 22 Core Operating Limits Report2021-04-15015 April 2021 Cycle 22 Core Operating Limits Report NOC-AE-21003796, Update Foreign Ownership, Control, or Influence (FOCI)2021-04-15015 April 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003791, Financial Assurance for Decommissioning - 2021 Update2021-03-31031 March 2021 Financial Assurance for Decommissioning - 2021 Update NOC-AE-21003790, Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter)2021-03-31031 March 2021 Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter) NOC-AE-210037, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-21003792, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-200037, License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications2021-03-11011 March 2021 License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications NOC-AE-21003784, Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing2021-03-0808 March 2021 Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing NOC-AE-21003786, Annual Fitness for Duty Performance Report for 20202021-03-0101 March 2021 Annual Fitness for Duty Performance Report for 2020 NOC-AE-21003785, Evidence of Financial Protection2021-02-23023 February 2021 Evidence of Financial Protection NOC-AE-21003781, Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts2021-01-27027 January 2021 Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts NOC-AE-21003780, Submittal of Update Foreign Ownership, Control, or Influence (FOCI)2021-01-0707 January 2021 Submittal of Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-20003778, Changes to South Texas Project Electric Generating Station Emergency Plan2020-12-17017 December 2020 Changes to South Texas Project Electric Generating Station Emergency Plan NOC-AE-20003777, STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency2020-12-10010 December 2020 STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency NOC-AE-20003766, Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan2020-12-0202 December 2020 Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan NOC-AE-20003767, Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-16016 November 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NOC-AE-20003765, Inservice Testing Program Description for the Fourth Ten-Year Interval2020-10-28028 October 2020 Inservice Testing Program Description for the Fourth Ten-Year Interval NOC-AE-20003764, 1 RE22 Inspection Summary Report for Steam Generator Tubing2020-10-0707 October 2020 1 RE22 Inspection Summary Report for Steam Generator Tubing NOC-AE-20003762, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen2020-09-22022 September 2020 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen NOC-AE-20003761, Supplement to Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic2020-09-10010 September 2020 Supplement to Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic NOC-AE-20003760, Update Foreign Ownership. Control. or Influence(FOCI)- Transmittal2020-09-0808 September 2020 Update Foreign Ownership. Control. or Influence(FOCI)- Transmittal 2023-07-11
[Table view] Category:Report
MONTHYEARNOC-AE-230040, Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06)2023-12-14014 December 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) ML23243B0562023-08-31031 August 2023 Supplemental Information to Application for Order Approving Indirect Transfer of Control of Licenses ML23229A4992023-08-17017 August 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) NOC-AE-21003841, Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25)2021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) ML21266A4262021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) NOC-AE-21003816, Commitment Change Summary Report2021-06-30030 June 2021 Commitment Change Summary Report ML21182A2412021-06-30030 June 2021 Commitment Change Summary Report ML17019A0032017-07-11011 July 2017 Attachment 2 to Safety Evaluation - In-Vessel Thermal-Hydraulic Analysis, Issuance of Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191 NOC-AE-17003468, 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes2017-05-10010 May 2017 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes ML16302A0152016-10-20020 October 2016 South Texas Project, Units 1 & 2 - Supplement 3 to Revised Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Address Generic Safety Issue (GSl)-191 and Respond to Generic Letter (GL) 2004-02 NOC-AE-16003345, LTR-PAFM-16-11-NP, Revision 0, Technical Justification to Support Extended Volumetric Examination Interval for South Texas, Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds.2016-03-31031 March 2016 LTR-PAFM-16-11-NP, Revision 0, Technical Justification to Support Extended Volumetric Examination Interval for South Texas, Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds. NOC-AE-15003249, Submittal of 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes and Annual Report2015-06-0909 June 2015 Submittal of 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes and Annual Report ML14357A1362015-01-22022 January 2015 Review of Analysis of Capsule Withdrawal Schedule from Reactor Vessel Radiation Surveillance Program NOC-AE-14003190, Attachment 2 to NOC-AE-14003190 - ALION-REP-STP-8998-14, Strainer Test Plan in Support of STP Pilot Risk-Informed GSI-191 Pilot Licensing Application2014-10-30030 October 2014 Attachment 2 to NOC-AE-14003190 - ALION-REP-STP-8998-14, Strainer Test Plan in Support of STP Pilot Risk-Informed GSI-191 Pilot Licensing Application ML14344A5462014-10-30030 October 2014 Attachment 1 to NOC-AE-14003190 - Alion REP-STP-8998-13, Strainer Test Plan in Support of STP Pilot Risk-Informed GSI-191 Pilot Licensing Application Executive Summary NOC-AE-14003178, Update Foreign Ownership, Control, or Influence (FOCI)2014-09-17017 September 2014 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-14003161, Engineering Report 1060, Rev. 1, Meter Factor Calculation & Accuracy Assessment for South Texas Project Units 1 & 2.2014-08-31031 August 2014 Engineering Report 1060, Rev. 1, Meter Factor Calculation & Accuracy Assessment for South Texas Project Units 1 & 2. ML14260A4382014-08-31031 August 2014 Engineering Report ER-1059, Rev. 1, Bounding Uncertainty Analysis for Thermal Power Determination at South Texas Project Units 1 & 2 Using LEFM System. NOC-AE-14003101, Enclosure 1 to Enclosure 6 Concerning Second Set of Responses to April 2014, Requests for Additional Information Regarding STP Risk-Informed GSI-191 Application2014-06-25025 June 2014 Enclosure 1 to Enclosure 6 Concerning Second Set of Responses to April 2014, Requests for Additional Information Regarding STP Risk-Informed GSI-191 Application ML14168A2682014-05-0101 May 2014 Texas Pollutant Discharge Elimination System Major Amendment with Renewal Application for a Major Facility Tpdes Permit No. WQ000190800 NOC-AE-14003103, University of Texas White Paper, Means of Aggregation and NUREG-1829: Geometric and Arithmetic Means, Rev. 3, Enclosure 2 to Attachment 12014-04-18018 April 2014 University of Texas White Paper, Means of Aggregation and NUREG-1829: Geometric and Arithmetic Means, Rev. 3, Enclosure 2 to Attachment 1 ML14087A0782014-04-15015 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident (TAC MF0178 & MF0179) NOC-AE-14003114, Seismic Hazard and Screening Report (CEUS Sites), Response 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..2014-03-31031 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response 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.. NOC-AE-14003082, Alternate Source Term Dose Analysis: an Estimate of Risk Attributed to GSI-191, Attachment 32014-03-11011 March 2014 Alternate Source Term Dose Analysis: an Estimate of Risk Attributed to GSI-191, Attachment 3 NOC-AE-13003067, Supplement to Seismic Walkdown Summary Report of Items Classified as Inaccessible2014-02-27027 February 2014 Supplement to Seismic Walkdown Summary Report of Items Classified as Inaccessible ML14072A0832014-02-24024 February 2014 CHLE-010, Chle Tank Test Results for Blended and NEI Fiber Beds with Aluminum Addition, Revision 3 ML14072A0872014-02-24024 February 2014 CHLE-016, Calculated Material Release to Estimate Chemical Effects, Revision 3 ML14072A0862014-02-24024 February 2014 CHLE-015, Summary of Chemical Effects Testing in 2012 for STP GSI-191 License Submittal, Revision 4 ML14072A0802014-02-24024 February 2014 CHLE-006, STP Material Calculations, Revision 2 ML14072A0822014-02-23023 February 2014 CHLE-008, Debris Bed Preparation & Formation Test Results, Revision 4 ML14072A0792014-02-22022 February 2014 CHLE-020, Test Results for 10-Day Chemical Effects Test Simulating LBLOCA Condition (T5), Revision 3 ML14072A0882014-02-22022 February 2014 CHLE-018, Results of Bench Tests to Assess Corrosion of Aluminum in STP Containment Conditions, Revision 3 ML14072A0852014-02-22022 February 2014 CHLE-014, T2 LBLOCA Test Report, Revision 3 ML14072A0842014-02-18018 February 2014 CHLE-012, T1 Mbloca Test Report, Revision 4 ML14072A0772014-02-18018 February 2014 CHLE-005, Determination of the Initial Pool Chemistry for the Chle Test, Revision 2 ML14149A4352014-02-14014 February 2014 Project, Units 1 and 2 - ALION-REP-STP-8998-02, Rev. 0, STP Casa Grande Analysis and LAR Enclosure 4-3 RAI Response, Enclosure 1 to Attachment 1 ML14072A0812014-02-13013 February 2014 CHLE-007, Debris Bed Requirements & Preparation Procedures, Revision 4 ML13339A7362014-01-29029 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13354B8332014-01-23023 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for South Texas Project, Units 1 and 2, TAC Nos.: MF0825 and MF0826 NOC-AE-13003070, Response to NRC Request for Reference Document for STP Risk-Informed GSI-191 Application2013-12-23023 December 2013 Response to NRC Request for Reference Document for STP Risk-Informed GSI-191 Application ML13323A1862013-11-12012 November 2013 Enclosure 4-1 - Risk-Informed Closure of GSI-191, Volume 1 ML13323A1912013-11-0606 November 2013 Enclosure 4-3 Risk-Informed Closure of GSI-191, Volume 3, Engineering (Casa Grande) Analysis, Page 212 of 1-122 ML13323A1902013-11-0606 November 2013 Enclosure 4-3 Risk-Informed Closure of GSI-191, Volume 3, Engineering (Casa Grande) Analysis, Cover - Page 211 of 248 ML13323A1892013-10-22022 October 2013 Enclosure 4-2 - Risk-Informed Closure of GSI-191, Volume 2 Probabilistic Risk Analysis ML13323B2092013-10-0404 October 2013 Attachment 12: CHLE-020, Rev. 2, Test Results for a 10-day Chemical Effects Test Simulating LBLOCA Conditions (T5). ML13323B2082013-09-23023 September 2013 Attachment 11: CHLE-019, Rev. 2, Test Results for Chemical Effect Tests Stimulating Corrosion and Precipitation (T3 & T4) ML13323B2072013-09-16016 September 2013 Attachment 10: CHLE-018, Rev. 2, Results of Bench Tests to Assess Corrosion of Aluminum in STP Containment Conditions. NOC-AE-13003019, Submittal of Commitment Change Summary Report for the Period June 21, 2011 Through June 21, 20132013-07-18018 July 2013 Submittal of Commitment Change Summary Report for the Period June 21, 2011 Through June 21, 2013 ML13175A2122013-06-18018 June 2013 Project, Units 1 and 2, Enclosure 4-1 to NOC-AE-13002986, Risk-Informed Closure of GSI-191 Volume 1 Project Summary NOC-AE-13002986, Enclosure 4-3 to NOC-AE-13002986, Risk-Informed Closure of GSI-191 Volume 3 Engineering Casa Grande Analysis, Page 161 of 260 Through End2013-06-0606 June 2013 Enclosure 4-3 to NOC-AE-13002986, Risk-Informed Closure of GSI-191 Volume 3 Engineering Casa Grande Analysis, Page 161 of 260 Through End 2023-08-31
[Table view] Category:Miscellaneous
MONTHYEARML23243B0562023-08-31031 August 2023 Supplemental Information to Application for Order Approving Indirect Transfer of Control of Licenses ML21182A2412021-06-30030 June 2021 Commitment Change Summary Report NOC-AE-21003816, Commitment Change Summary Report2021-06-30030 June 2021 Commitment Change Summary Report ML17019A0032017-07-11011 July 2017 Attachment 2 to Safety Evaluation - In-Vessel Thermal-Hydraulic Analysis, Issuance of Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191 NOC-AE-17003468, 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes2017-05-10010 May 2017 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes NOC-AE-15003249, Submittal of 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes and Annual Report2015-06-0909 June 2015 Submittal of 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes and Annual Report ML14357A1362015-01-22022 January 2015 Review of Analysis of Capsule Withdrawal Schedule from Reactor Vessel Radiation Surveillance Program NOC-AE-14003190, Attachment 2 to NOC-AE-14003190 - ALION-REP-STP-8998-14, Strainer Test Plan in Support of STP Pilot Risk-Informed GSI-191 Pilot Licensing Application2014-10-30030 October 2014 Attachment 2 to NOC-AE-14003190 - ALION-REP-STP-8998-14, Strainer Test Plan in Support of STP Pilot Risk-Informed GSI-191 Pilot Licensing Application ML14344A5462014-10-30030 October 2014 Attachment 1 to NOC-AE-14003190 - Alion REP-STP-8998-13, Strainer Test Plan in Support of STP Pilot Risk-Informed GSI-191 Pilot Licensing Application Executive Summary NOC-AE-14003178, Update Foreign Ownership, Control, or Influence (FOCI)2014-09-17017 September 2014 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-14003101, Enclosure 1 to Enclosure 6 Concerning Second Set of Responses to April 2014, Requests for Additional Information Regarding STP Risk-Informed GSI-191 Application2014-06-25025 June 2014 Enclosure 1 to Enclosure 6 Concerning Second Set of Responses to April 2014, Requests for Additional Information Regarding STP Risk-Informed GSI-191 Application ML14168A2682014-05-0101 May 2014 Texas Pollutant Discharge Elimination System Major Amendment with Renewal Application for a Major Facility Tpdes Permit No. WQ000190800 NOC-AE-14003103, University of Texas White Paper, Means of Aggregation and NUREG-1829: Geometric and Arithmetic Means, Rev. 3, Enclosure 2 to Attachment 12014-04-18018 April 2014 University of Texas White Paper, Means of Aggregation and NUREG-1829: Geometric and Arithmetic Means, Rev. 3, Enclosure 2 to Attachment 1 ML14087A0782014-04-15015 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident (TAC MF0178 & MF0179) NOC-AE-14003114, Seismic Hazard and Screening Report (CEUS Sites), Response 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..2014-03-31031 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response 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.. NOC-AE-13003067, Supplement to Seismic Walkdown Summary Report of Items Classified as Inaccessible2014-02-27027 February 2014 Supplement to Seismic Walkdown Summary Report of Items Classified as Inaccessible ML13323A1862013-11-12012 November 2013 Enclosure 4-1 - Risk-Informed Closure of GSI-191, Volume 1 ML13323A1912013-11-0606 November 2013 Enclosure 4-3 Risk-Informed Closure of GSI-191, Volume 3, Engineering (Casa Grande) Analysis, Page 212 of 1-122 ML13323A1902013-11-0606 November 2013 Enclosure 4-3 Risk-Informed Closure of GSI-191, Volume 3, Engineering (Casa Grande) Analysis, Cover - Page 211 of 248 ML13323A1892013-10-22022 October 2013 Enclosure 4-2 - Risk-Informed Closure of GSI-191, Volume 2 Probabilistic Risk Analysis NOC-AE-13003019, Submittal of Commitment Change Summary Report for the Period June 21, 2011 Through June 21, 20132013-07-18018 July 2013 Submittal of Commitment Change Summary Report for the Period June 21, 2011 Through June 21, 2013 NOC-AE-13003004, Revised Phase 1 Staffing Assessment Submitted in Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights2013-06-0303 June 2013 Revised Phase 1 Staffing Assessment Submitted in Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights ML13141A2852013-04-25025 April 2013 License Amendment Request, Proposed Revision to Technical Specification 5.0, Design Features NOC-AE-12002912, Submittal of 10 CFR 50.46 ECCS Evaluation Model Significant Change/Error Report2012-10-17017 October 2012 Submittal of 10 CFR 50.46 ECCS Evaluation Model Significant Change/Error Report ML12234A6042012-08-21021 August 2012 Email - Documents for NRC Public Meeting on Corrosion Head Loss Experiments (Chle) Part 1 and 2 ML1130606152011-10-31031 October 2011 LOCA Frequencies for STP Nuclear Operating Company GSI-191 ML1130506232011-10-26026 October 2011 Alion- Expected Impact of Chemical Effects on GSI-191 Risk Informed Evaluation for South Texas Project NOC-AE-11002708, 10CFR50.59 Summary Report2011-10-10010 October 2011 10CFR50.59 Summary Report ML11256A0582011-08-31031 August 2011 Documents to Support Review of the South Texas Project License Renewal Application, WR-5, Tceq Id No. 1610103/1610051 (Operation of Public Potable Water System) ML11196A0052011-08-0404 August 2011 Summary of Site Audit Related to the Review of the License Renewal Application for South Texas Project, Units 1 and 2 ML11217A0162011-07-27027 July 2011 Commitment Change Summary Report NOC-AE-09002457, Nuclear Decommissioning Trust Fund Agreements (Updated)2009-09-15015 September 2009 Nuclear Decommissioning Trust Fund Agreements (Updated) NOC-AE-09002445, Submittal of Commitment Change Summary Report for July 31, 2008 Through July 30, 20092009-07-30030 July 2009 Submittal of Commitment Change Summary Report for July 31, 2008 Through July 30, 2009 NOC-AE-09002424, Submittal of Description and Summary of the 10CFR50.59 Evaluations of Changes, Tests and Experiments Report2009-04-28028 April 2009 Submittal of Description and Summary of the 10CFR50.59 Evaluations of Changes, Tests and Experiments Report NOC-AE-08002325, Commitment Change Summary Report2008-08-11011 August 2008 Commitment Change Summary Report ML0807006992008-02-28028 February 2008 Evidence of Financial Protection NOC-AE-07002231, Request for Relaxation of Requirements from Revision 1 of Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head Penetrations (Relief Request RR-ENG-2-46)2007-11-0707 November 2007 Request for Relaxation of Requirements from Revision 1 of Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head Penetrations (Relief Request RR-ENG-2-46) NOC-AE-07002177, Proposed Alternative to ASME Section XI Requirements for Weld Overlay Hold-Time (RR-ENG-2-48)2007-06-19019 June 2007 Proposed Alternative to ASME Section XI Requirements for Weld Overlay Hold-Time (RR-ENG-2-48) NOC-AE-07002168, Summary Assessment of Pressurizer Nozzle Safe End Weld Overlays: Shrinkage and Fatigue Crack Growth (RR-ENG-2-43)2007-05-29029 May 2007 Summary Assessment of Pressurizer Nozzle Safe End Weld Overlays: Shrinkage and Fatigue Crack Growth (RR-ENG-2-43) NOC-AE-06002049, Commitment Change Summary Report2006-08-21021 August 2006 Commitment Change Summary Report NOC-AE-06001977, Submittal of Nuclear Insurance Protection2006-02-0909 February 2006 Submittal of Nuclear Insurance Protection NOC-AE-05001919, Request for Relief from ASME Boiler and Pressure Vessel Code, Section XI Requirements for the Essential Cooling Water System (Ecw Train 1A)2005-09-0808 September 2005 Request for Relief from ASME Boiler and Pressure Vessel Code, Section XI Requirements for the Essential Cooling Water System (Ecw Train 1A) NOC-AE-05001874, Transmittal of the 10CFR50.59 Summary Report2005-04-28028 April 2005 Transmittal of the 10CFR50.59 Summary Report ML0532204612004-06-14014 June 2004 Power Reactor Status Report for 6/14/04 ML0319800132003-07-18018 July 2003 Misc Report ,Stars, 6/10-11/2003 Licensing Workshop Held in Overland Park, Kansas with Strategic Teaming and Resource Sharing-Integrated Regulatory Affairs Group for Licensees of Callaway, Comanche Peak, Diablo Canyon, Palo Verde, So Texas NOC-AE-03001532, Request for One-Time Approval of an Alternative Approach for Containment Tendon Surveillances2003-05-15015 May 2003 Request for One-Time Approval of an Alternative Approach for Containment Tendon Surveillances NOC-AE-03001509, Special Report Re Power-Operated Relief Valve Actuation to Mitigate Reactor Coolant System Pressure Transient2003-04-25025 April 2003 Special Report Re Power-Operated Relief Valve Actuation to Mitigate Reactor Coolant System Pressure Transient NOC-AE-02001277, Project Comprehensive Cultural Assessment2002-04-17017 April 2002 Project Comprehensive Cultural Assessment 2023-08-31
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Nuclear Operating Company 40 IV r-South Tras Pro/ct Ekdtnc GncUratlnStabt'on P.. Box 282 Wadsworth.
T&ws 77483 ,VVV August 21., 2006 NOC-AE-06002049 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 South Texas Proiect Commitment Change Summary Report Attached is the South Texas Project (STP) Commitment Change Summary Report for the period July 14, 2005 through July 31, 2006. This report lists each commitment for which a change was made during the reporting period and provides the basis for each change.The commitments were evaluated in accordance with the requirements of STP's Regulatory Commitment Change Process, which is consistent with the guidance in the Nuclear Energy Institute's "Guideline for Managing NRC Commitments", NEI 99-04.Additional documentation is available at STP for your review.There are no new commitments in this letter.If there are any questions, please contact Marilyn Kistler at 361-972-8385 or me at 361-972-7136.
Scott M. Head Manager, Licensing mkk
Attachment:
Commitment Change Summary Report 74001 STi32034837 NOC-AE-06002049 Page 2 of 2 cc: (paper copy)(electronic copy)Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Senior Resident Inspector U. S. Nuclear Regulatory Commission P. 0. Box 289, Mail Code: MN1 16 Wadsworth, TX 77483 C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704 Richard A. Ratliff Bureau of Radiation Control Texas Department of State Health Services 1100 West 49th Street Austin, TX 78756-3189 A. H. Gutterman, Esquire Morgan, Lewis & Bockius LLP Mohan C. Thadani U. S. Nuclear Regulatory Commission Steve Winn Christine Jacobs Eddy Daniels NRG South Texas LP J. J. Nesrsta R. K. Temple E. Alarcon City Public Service Jon C. Wood Cox Smith Matthews C. Kirksey City of Austin ATTACHMENT Commitment Change Summary Report Attachment NOC-AE-06002049 Page 1 of 9 Condition Source Document Source Date of Original Commitment Description Revised Commitment Description Justification for Change Report Date Change Number 04-3365-8 NOC-AE-04001758 (Response to Generic Letter 2003-01)02/16/01 11/16/05 03/07/06 06/22/06 NOC-AE-04001758, 08/05/04 -Response To Request For Information On NRC Generic Letter 2003-01 -Control Room Habitability Revise the control room dose accident analyses to reflect the results of the control room inleakage testing. Due Date December 31, 2005 Alternative:
Revise the control room dose accident analyses to reflect the results of the control room inleakage testing. Due Date December 15, 2006.There are three commitment change evaluations for this action. Commitment evaluation one extends the original due date of December 31, 2005 to April 1, 2006, evaluation two extends due date April 1, 2006 to June 30, 2006, and extension three extends the due date June 30, 2006 to December 15, 2006.Evaluation 1 -During the course of performing the Loss Of Coolant Accident analysis using the Altemate Source Term (AST), it was determined that STP also needed to confirm the post accident sump pH. An integral part of this analysis was to determine the amount of electrical cable insulation in the containment building that contains chlorides.
Also, additional iodine re-evolution analyses were required as a result of the sump pH analysis.These unforeseen extra analyses took several months that were not planned for when the commitment was made. Also, the multiple core redesigns during the 2RE1 1 outage took away Reactor Engineering resources necessary to support the required analyses.Industry experience on the success of AST submittals has been varied. Several such submittals have been rejected by the NRC. Based on the need to be very thorough in this submittal, additional time was needed to ensure a successful submittal.
Evaluation 2 -The submittal must provide assurance that Chapter 15 analyses not performed with AST will meet the new AST dose limits when they are converted to the AST.This was planned to be done with simple scaling of radioisotope releases and atmospheric dispersion factors. This technique was successful with the Main Steam Line Break and the Steam Generator Tube Rupture accidents.
However, since the Locked Reactor Coolant Pump Rotor and the Control Rod Ejection accidents also have postulated fuel failures, the ratioing technique was not successful.
Reactor Engineering is performing explicit design calculations for these accidents to serve as bases for statements made in the submittal.
Attachment NOC-AE-06002049 Page 2 of 9 Condition Source Document Source Date of Original Commitment Description Revised Commitment Description Justification for Change Report Date Change Number Additional time is needed to ensure a thorough submittal.
Evaluation 3 -STP personnel attended an NRC workshop on their (NRC) experience with AST submittals and the contents of Regulatory Guide 1.183 on June 22, 2006.Also, a pre-submittal meeting with the NRC staff was scheduled for July 11, 2006.Four additional analyses are necessary to support the AST submittal.
A draft submittal is expected on July 24. After site review, the submittal is planned to be presented to the September 2006 Plant Operations Review Committee meeting. Additional time was needed to ensure a thorough submittal.
04-12498-11 NOC-AE-06001968 01/30/06 7/26/06 NOC-AE-06001968 -Supplement 2 to the By letter from NRC to NEI dated The original commitment to provide a status report-Supplement 2 to Response to Generic Letter 2004-02 3/3/2006 and in a NRC letter to PWR was a voluntary commitment by STPNOC for the the Response to NOC-AE-05001922
-Supplement 1 to the licensees dated March 28, 2006, the purpose of keeping the NRC informed of STP's Generic Letter Response to Generic Letter 2004-02 following agreement was made progress with regard to resolution of the sump debris 2004-02 regarding responses to GL 2004-02 issues in GL 2004-02. It is not required for compliance STPNOC will provide a supplemental and associated requests for additional or to adequately respond to the GL.NOC-AE-0S001922 08/31/05 response to Generic Letter 2004-02 upon information:
-Supplement 1 to completion of pending analyses and testing. "...for units completing their The agreement made between NEI and NRC the Response to outage to incorporate accommodates the known schedule issues and Generic Letter strainer modification in 2006 uncertainty with regard to resolution of sump design 2004-02 or earlier, information issues and establishes a mutually acceptable needed to fully address GL approach for licensees to provide the NRC with the 2004-02 will be provided to plant-specific sump design information.
In addition, the NRC by December STP's analyses depend on the completion of generic 31,2006. For units installing industry work which is not complete.strainers after 2006, information needed to fully The change was also discussed with Mohan Thadani, address GL 2004-02 will be STP's NRC Project Manager, on July 26, 2006 provided to the NRC within 90 days of outage completion but not later than December 31, 2007. STP has not completed its analysis and the You may choose to use this agreement above provides a reasonable alternative to alternative approach docketing a status report that will be of little or no consistent with your strainer value. Consequently, STP will provide the required modification schedule, or information within 90 days of completing the Unit 2 you may choose to submit a Spring 2007 outage (i.e., about July 23, 2007).
Attachment NOC-AE-06002049 Page 3 of 9 Condition Source Document Source Date of Original Commitment Description Revised Commitment Description Justification for Change Report Date Change Number response to the RAI letters originally requested..." 05-9845-1 ST-HL-AE-1060
-Response to Notice of Violation 83-22-02 ST-HL-AE-1110
-Material Control Program and User Test Program Clarifications ST-HL-AE-2480
-Response to NRC Compliance Bulletin 87-002: Fastener Testing to Determine Conformance With Applicable Material Specifications 2/21/84 12/20/05 7/30/84 1/29/88 ST-HL-AE-1 060 -Response to Notice of Violation 83-22-02 HL&P initiated a program to review previous and current material control practices and to develop additional controls that can be implemented effectively.
This program drew upon work that had already been accomplished by a materials control task force formed to evaluate some of the recommendations made by the INPO audit of STP construction activities in the fall of 1983. This task force completed work and recommended a number of improvements in mid-January 1984. The following important improvements to STP material control will be undertaken.
Item 1* Reinstitute the transfer of heat code identifies on non-ASME safety-related high strength miscellaneous structural shapes and materials when this material is cut during site fabrication. (For ASME material this is already being done).Item 2* Undertake user testing on non-ASME safety-related A36 bulk shapes and plate.Samples of each heat received from each vendor will be tested. This material will then be hard marked (stamped) to indicate that it is A36. The hard marks will be transferred during site fabrication activities.
Item 3* Undertake user testing for hardness and tensile strength on samples, by shipment, or bulk safety-related threaded fasteners.
User Testing and additional material marking requirements are not required for materials purchased through a vendor that is currently on the Approved Vendor List (or a new vendor added at a later date) provided the following conditions are met: 1) Purchase Order requires the vendor to furnish documentation (e.g., Certified Material Test Report)attesting to the material meeting the requirements of the applicable material specification;
- 2) Quality personnel review the supplied documentation and verify that the documentation indicates that the material does in fact meet the material specification requirements;
- 3) Material is marked by the vendor as required by the material specifications (e.g., ASTM A325).The original commitments were made during construction in response to industry and site deficiencies.
The commitments were considered to be necessary at the time in order to enhance a program that was in place and to put barriers in place during the construction phase when there were a multitude of suppliers and there was a substantial amount of material being purchased and received to support the construction effort. The commitments were further enhanced in response to an NRC Compliance Bulletin (87-002) that specifically addressed a concern related to fasteners.
Part of the response by STPEGS committed the station to additional redundant material testing to further substantiate that the material being supplied did in fact meet the material specifications required by our Purchase Orders and that the vendors supplied documentation as to their compliance.
The Operations Quality Assurance Plan (OQAP), in part, provides the requirements for evaluating and placing a vendor on the Approved Vendor List (AVL)and the requirements for that vendor to remain on the AVL. Measures for evaluating and selecting procurement sources are specified in procedures and include one or more of the following:
1)experience of users of identical or similar products of the prospective supplier, other utility or approved contractor audits/evaluations, audits/evaluations by cooperative utility groups, American Society of Mechanical Engineers Certificates of Authorization, STPEGS records accumulated in previous procurement actions, and STPEGS product operating experience;
- 2) evaluation of the suppliers current quality records supported by documented qualitative and quantitative information that can be objectively evaluated;
- 3) and source evaluation of the supplier's technical and quality capability as determined by a direct evaluation of facilities and personnel and aualitv poroqram implementation.
Attachment NOC-AE-06002049 Page 4 of 9 Condition Source Document Source Date of Original Commitment Description Revised Commitment Description Justification for Change Report Date Change Number Da I I These fasteners will be stamped to indicate grade (type) and class consistent with ASME III size restrictions.
Item 4* Undertake user testing for hardness and tensile strength on samples of safety-related anchor bolts by shipment.
Anchor bolts will be stamped to indicate material type. Site fabrication of all anchor bolts (safety-related and non safety-related) has been discontinued.
ST-HIL-AE-1 110 -Material Control Program and User Test Program Clarifications Item 2 from ST-HL-AE-1060 Clarification/Change
-In the event that A36 or A500 Grade B tube steel is not uniquely identifiable to an individual heat number, then testing will be performed on a periodic basis until the lot is depleted.
The frequency of testing will be established on a case basis.Item 3 from ST-HL-AE-1060 Clarification/Change
-The sentence in our letter which stated in part that threaded fasteners "will be stamped to indicated grade (type) and class" was meant to describe an existing condition and not a new commitment.
Currently we purchase fasteners which are marked per ASTM requirements.
Additional marking requirements imposed by our material control program to preclude commingling of safety and nonsafety class material include both hard marking and color coded zinc electroplating processes.
In addition, for fasteners in inventory prior to May 21, 1984, the test sample will be defined by warehouse bin rather that by shipment as indicated in our letter. This is Procurement source evaluations involve a review of technical and quality considerations to an extent considered appropriate.
Technical considerations include the design or manufacturing capability and technical ability of suppliers to produce or provide the design, service, item or component.
A documented quality assurance evaluation of a vendors quality program is performed to assure it meets the appropriate requirements of 10CFR50 Appendix B, or where applicable, other nationally recognized codes and standards.
Vendors may be placed on the AVL after passing this evaluation.
Each vendor on the AVL is periodically evaluated and is removed if the evaluation is unacceptable.
The OQAP also provides for the acceptance of procured material and services by review of written certifications and receipt inspection activities.
These OQAP requirements are based on STPEGS commitments to Regulatory Guide 1.33, Quality Assurance Program Requirements (Operations), American National Standard N 18.7-1976/ANS-3.2, Regulatory Guide 1.38, Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants, and American National Standards Institute N45.2.2-1972.
There are no regulatory requirements to repeat vendor completed testing of material at the time of receipt. It should also be noted that the additional material testing is destructive testing and STPNOC therefore has to actually procure more material than Is actually needed as the tested portion of the material is destroyed during the testing. These specification requirements should be deleted and discontinued.
STPNOC also has requirements in specifications (e.g., 3A010SS0030) which require material marking to be applied to material.
These additional
'marking'requirements (i.e., Cloverleaf stamp applied to A36 material and Arrowhead stamp applied to A500 tube steel) were part of an 'enhancement' to our program to provide additional traceability measures.The marking requirements are not required by the industry material specifications.
The OQAP requires that material traceability is maintained either 1 ) on the item or 2) on records traceable to the item. Once material has progressed through the receiving Attachment NOC-AE-06002049 Page 5 of 9 Condition Source Document Source Date of Original Commitment Description Revised Commitment Description Justification for Change Report Date Change Number I _ I due to the fact that shipment identity is not maintained during storage. For future receipts, testing will be by shipment.Item 4 from ST-HL-AE-1060 Clarification/Chanqe
-We have modified our testing program to eliminate laboratory hardness testing of A36 and A193 anchor bolts. ASTM does not define any hardness limits for A36 and A193 material, and therefore hardness test results would not be meaningful.
Tensile tests are required for this material under our program and are sufficient per ASTM to verify material type.In the event that long lead time anchor bolts do not exist in sufficient quantity to permit destructive testing per our program, we will undertake an alternate non-destructive testing program in the field to verify material type. This program will be fully documented by design specification and jobsite procedure.
The program will employ the Equotip hardness tester correlated to known tensile strengths by material type and the Texas Nuclear Alloy Analyzer which is able to distinguish material types through spectographic analysis.ST-HL-AE-2480 Response to NRC Compliance Bulletin 87-002: Fastener Testing to Determine Conformance With Applicable Material Specifications Response to Bulletin 87-02 describes details of STP's Users Test Program for bolting materials.
These commitments revised and clarified the original commitment (items 3,4) in ST-HL-AE-1060.
Bulletin Action 1: Describe a) the characteristics currently examined during receipt inspection of fasteners (i.e., head markings for grade and manufacturer symbols, review of certified material test process and located in a class bin, we have at least one of the OQAP methods to maintain traceability and in many cases, we have both. The additional
'marking' of certain materials does not provide additional traceability that justifies the manhours allotted to this activity.
Material with only the Cloverleaf or the Arrowhead would not be sufficiently traceable for use. The specification requirements for this additional marking should be deleted and discontinued.
Attachment NOC-AE-06002049 Page 6 of 9 Condition Source Document Source Date of Original Commitment Description Revised Commitment Description Justification for Change Report Date Change Number I I I I report or certificate of conformance), and b)internal controls utilized during storage and issuance from stock to assure the appropriate use of fasteners.
Response to Bulletin Action 1: The response to Action 1 for bolting materials procured by Houston Lighting & Power Company (HL&P) and Bechtel Energy Corporation (BEC) for South Texas Project Electric Generating Station (STPEGS) is described in Attachment 2.Attachment 2 -ST-HL-AE-2480 Users Test Program In May 1984, the STPEGS implemented the Users Test Program, which requires testing samples of all safety related, 1/2 inch or greater in diameter, non-ASME bulk threaded fasteners, anchor bolts, and all-thread rod.The Users Test Program for threaded material is specifically prescribed for the bolts, nuts, studs, and threaded rods furnished by the construction manager (BEC) to the constructor (Ebasco Constructors, Inc.) and/or contractors for use In field-assembled connections.
The threaded fasteners for shop-assembled connections fumished (tightened or loose)by equipment manufacturers or component fabricators are not subject to the STP Users Test Program. The control of that threaded fastener material is covered under the supplier's Quality Assurance Program (QAP). The STP contractor for HVAC ductwork typically does not furnish the threaded fasteners for field-assembled connections.
The only threaded fasteners furnished by this contractor are restricted to closure panels and other limited applications, and all those fasteners are procured under the contractor's QAP.__________
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Attachment NOC-AE-06002049 Page 7 of 9 Condition Source Document Source Date of Original Commitment Description Revised Commitment Description Justification for Change Report Date Change Number I I I Items procured to the material specifications listed below, require "User Testing" prior to being issued for field installation:
A. Threaded fasteners conforming to: ASTM A307, GR A ASTM A325, Type I ASTM A490, Type I ASTM A449 ASTM A1 94 ASTM A563 ASTM A193 The "Users Test" program requires tests of tensile properties, hardness (if specified), and chemical analysis per the applicable ASTM standard for these threaded fasteners.
B. Anchor bolts conforming to: ASTM A36 ASTM A193 Tests of tensile properties, hardness (if specified) and chemical properties are required tests in the "User Test" program for anchor bolts.C. Threaded rod conforming to: ASTM A36 ASTM A108 ASTM A193 Tests to determine the tensile and chemical properties are required in the "Users Test" program.ASTM A108 and galvanized all-thread rod which are purchased as catalog items are tested in the "Users Test" program to ensure adequate tensile strength and chemical properties.
Attachment NOC-AE-06002049 Page 8 of 9 Condition Source Document Source Date of Original Commitment Description Revised Commitment Description Justification for Change Report Date Change Number I I The sample size of threaded fasteners and anchor bolts tested is defined in the.shipping iot method" of ASTM A325.NOTE: For the initial testing of materiais in the warehouse on May 21, 1984, at least one fastener from each location was tested, or the 'shipping lot method* of ASTM A325 was utilized, whichever was greater.The sample size of all-thread red tested is as follows: 1. Threaded rod supplied by prequalified manufacturers with traceable heat numbers: One test per year or one test per five (5) heat numbers purchased for each manufacturer whichever is greater.2. Red furnished by companies other than the above, with traceable heat numbers: One test per heat number.3. Rod not traceable to manufacturer heat numbers: One test for first 250 linear feet and one test for each subsequent 1000 linear feet.D. Fastener materials requiring User Testing are segregated and Hold Tagged.The User Test Program coordinator assigns test numbers, maintains logs and records for accountability, selects test samples and tracks all tests until Quality Control accepts the test results. Fasteners that do not conform to test requirements are reported In accordance with approved site procedures.
Threaded fasteners are subject to tension testing of full size specimens furnished with the corresponding nuts in accordance with ASTM A370, subsection Si 1.1.4 or S1 1.1.5. This test is for the purpose of verifying the bolt, rod, or stud material and threads, and may be used in lieu of the proof-load tests prescribed for bolts by the L____________
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.1 Attachment NOC-AE-06002049 Page 9 of 9 Condition Source Document Source Date of Original Commitment Description Revised Commitment Description Justification for Change Report Date Change Number Anchor bolts which are of a unique type or limited quantity, designated for a specific application, and having no surplus available for destructive testing, are non-destructively tested onsite to confirm material type.Section IV -HL&P Receipt Inspection Program D. Performance of additional HL&P specified inspections or tests as required by the purchase order for the material or other documents.