|
---|
Category:Code Relief or Alternative
MONTHYEARML23270B9932023-09-29029 September 2023 Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML21299A0032021-10-28028 October 2021 and Waterford Steam Electric Station, Unit 3 - Approval of Request for Alternative EN-20-RR-003 from Certain Requirements of the ASME Code ML21258A4082021-09-21021 September 2021 Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of Boiling Water Reactor Vessel and Internals Project Guidelines CNRO-2020-00016, Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-08-12012 August 2020 Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) ML19254A6032019-09-19019 September 2019 Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1 CNRO-2019-00002, Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-01-31031 January 2019 Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 RBG-47913, Request for Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii) Proposed Alternative to CFR 50.55a Examination Requirements for Third Interval Volumetric Exams (RBS-ISI-021)2018-11-30030 November 2018 Request for Alternative in Accordance with 10 CFR 50.55a(g)(5)(iii) Proposed Alternative to CFR 50.55a Examination Requirements for Third Interval Volumetric Exams (RBS-ISI-021) ML18310A0132018-11-16016 November 2018 Relief from the Requirements of the ASME Code to Use Boiling Water Reactor Vessel Internals Guidelines as an Alternative ML18299A2732018-11-0707 November 2018 Request for Relief from Requirements of Asme Code RBS-ISI-016 from the Requirements of the ASME Code for Pressure Retaining Welds in Control Rod Housings (EPID-L-2018-LLR-0042) ML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 12017-11-17017 November 2017 Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1 ML17138A1442017-05-24024 May 2017 Relief from the Requirements of the ASME Code ML16096A2692016-06-0606 June 2016 Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1 CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D2015-06-0505 June 2015 Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, Division ML15071A1412015-03-23023 March 2015 Relief Request No. VRR-RBS-2014-1 Regarding the Third 10-Year Inservice Testing Interval ML14127A3272014-05-30030 May 2014 Relief Request RBS-ISI-019, Use of BWRVIP Guidelines in Lieu of Specific ASME Code Requirements for the Fourth 10-Year Inservice Inspection Interval) ML13353A6082014-01-28028 January 2014 Relief Request RBS-R&R-2013-001, Alternative to ASME Code Section III for Postweld Heat Treatment Exemption for the Third 10-Year Inservice Inspection Interval ML13261A3792013-09-24024 September 2013 Request for Relief RBS-ISI-018 for Reactor Pressure Vessel Support Skirt for the Second 10-Year Inservice Inspection Interval ML13038A6322013-02-20020 February 2013 Request for Relief RBS-R&R-2011-001 from ASME Code Class 3 Table ND-4622.7(b)-1 Requirements for Post-Weld Heat Treatment Exemption of Valves, Third 10-Year Inservice Inspection Interval RBG-47301, Requests for Relief Request for Relief from ASME Boiler & Pressure Vessel Code Section III2012-10-26026 October 2012 Requests for Relief Request for Relief from ASME Boiler & Pressure Vessel Code Section III RBG-47284, Request for Relief from ASME Boiler & Pressure Vessel Code Section III2012-09-20020 September 2012 Request for Relief from ASME Boiler & Pressure Vessel Code Section III ML12235A3082012-08-31031 August 2012 Relief Requests RBS-ISI-016 and RBS-ISI-017 Proposed Alternative to 10 CFR 50.55A Examination Requirements for Reactor Pressure Vessel Weld Inspections ML1017301572010-06-30030 June 2010 Relief Request RBS-ISI-013, Use of Risk-Informed, Safety-Based Inservice Inspection Program Based on ASME Code Case N-716 ML1010601582010-05-0303 May 2010 Second 10-Year Interval Inservice Inspection Program Plan Requests for Relief RBS-ISI-007, RBS-ISI-008, RBS-ISI-009, RBS-ISI-010, and RBS-ISI-011 RBG-46916, Requests for Relief from ASME Section XI Volumetric and Visual - Examination Requirements - Second 10-Year Interval2009-05-29029 May 2009 Requests for Relief from ASME Section XI Volumetric and Visual - Examination Requirements - Second 10-Year Interval ML0903708982009-03-0606 March 2009 Unit 3 - Request for Alternative CEP-ISI-012, Use Alternative Requirements in ASME Code Case N-753 CNRO-2009-00001, Relief Requests for Third 120 Month Inservice Inspection Interval2009-01-23023 January 2009 Relief Requests for Third 120 Month Inservice Inspection Interval ML0810505872008-04-29029 April 2008 Relief Request PRR-RBS-2007-1 for Standby Service Water Pumps for the Third 10-Year Inservice Testing Interval ML0712300402007-05-17017 May 2007 Request for Alternative RBS-ISI-005 Extending the Current Inservice Inspection Interval in Accordance with NRC Information Notice 98-44 ML0701200812007-02-0202 February 2007 River Bend Station, & Waterford Steam Electric Station, Unit 3 - Request for Alternative CEP-PT-001, Visual Exam of Vent & Drain Leakage Tests (TAC MD1399, MD1400, MD1401, MD1402, & MD1403) ML0605901782006-03-21021 March 2006 Relief, Request IST-2006-1, Use of Subsequent Asme/Om Code for Condition Monitoring Check Valves CNRO-2006-00010, Revised Request for Alternative to 10 CFR 50.55a Examination Requirements of Category B1.11 Reactor Pressure Vessel Welds2006-02-0808 February 2006 Revised Request for Alternative to 10 CFR 50.55a Examination Requirements of Category B1.11 Reactor Pressure Vessel Welds CNRO-2005-00036, Request for Alternative to 10 CFR 50.55a Examination Requirements of Category B1.11 Reactor Pressure Vessel Welds2005-08-24024 August 2005 Request for Alternative to 10 CFR 50.55a Examination Requirements of Category B1.11 Reactor Pressure Vessel Welds ML0521703322005-08-0202 August 2005 Request for Relief from the Requirements of the ASME and Pressure Vessel Code ML0435702742004-12-21021 December 2004 ANO Units 1 and 2; Grand Gulf; River Bend and Waterford Unit 3 CNRO-2004-00073, Withdrawal of Relief Requests RBS-ISI-001, RBS-ISI-002, and RBS-ISI-0032004-11-17017 November 2004 Withdrawal of Relief Requests RBS-ISI-001, RBS-ISI-002, and RBS-ISI-003 ML0411903302004-04-28028 April 2004 Relief, from the Requirements of the ASME Boiler and Pressure Vessel Code, Section XI Concerning Check Valve Inservice Testing Program, MC1032 CNRO-2003-00062, Request for Relief from ASME Section XI Volumetric Examination Requirements2003-12-0404 December 2003 Request for Relief from ASME Section XI Volumetric Examination Requirements ML0329406092003-10-13013 October 2003 Request to Use Alternative Testing Frequency for Inservice Testing ML0323901902003-08-26026 August 2003 Ltr. to M.A. Krupa ANO-1, Grand Gulf River Bend Station & Waterford Steam Electric Station, Unit 3, Request to Use American Society of Mechanical Engineers Boiler & Pressure Vessel (Code) Case N-663 ML0304500432003-02-13013 February 2003 Relief, Main Steam Safety/Relief Valve Inservice Testing ML0303002762003-01-29029 January 2003 Relief from Requirements of American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section XI, Concerning Check Valve Inservice Testing Program CNRO-2002-00053, Entergy Operations, Inc., Request to Use Alternate Testing Frequency for Inservice Testing Dated 11/22/20022002-11-22022 November 2002 Entergy Operations, Inc., Request to Use Alternate Testing Frequency for Inservice Testing Dated 11/22/2002 2023-09-29
[Table view] Category:Letter type:CNRO
MONTHYEARCNRO-2022-00015, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling Using the Consolidated Line-Item Improvement Process2022-05-26026 May 2022 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling Using the Consolidated Line-Item Improvement Process CNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021 Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L CNRO-2021-00002, Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-01-28028 January 2021 Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L CNRO-2020-00023, Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2020 Summary2020-12-17017 December 2020 Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2020 Summary CNRO-2020-00021, Response to Request for Additional Information Regarding Relief Requests GG-ISI-020 and RBS-ISI-0192020-11-0909 November 2020 Response to Request for Additional Information Regarding Relief Requests GG-ISI-020 and RBS-ISI-019 CNRO-2020-00016, Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-08-12012 August 2020 Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) CNRO-2020-00015, Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019)2020-06-0808 June 2020 Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) CNRO-2020-00009, Application to Revise Technical Specifications to Adopt TSTF-501 Relocate Stored Fuel Oil and Lube Oil Volumes to Licensee Control, Revision 12020-02-26026 February 2020 Application to Revise Technical Specifications to Adopt TSTF-501 Relocate Stored Fuel Oil and Lube Oil Volumes to Licensee Control, Revision 1 CNRO-2020-00006, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO, Revision 22020-01-24024 January 2020 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO, Revision 2 CNRO-2020-00008, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR-Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process2020-01-24024 January 2020 Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR-Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process CNRO-2019-00030, Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary2019-12-30030 December 2019 Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary CNRO-2019-00010, Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2019-03-28028 March 2019 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2019-00007, Grand Gulf Nuclear Station; and Waterford 3 Steam Electric Station - Decommissioning Funding Status Report2019-03-28028 March 2019 Grand Gulf Nuclear Station; and Waterford 3 Steam Electric Station - Decommissioning Funding Status Report CNRO-2019-00013, Entergy Response to Confirmatory Order EA-17-132/EA-17-1532019-03-21021 March 2019 Entergy Response to Confirmatory Order EA-17-132/EA-17-153 CNRO-2019-00009, Stations - Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR, Revision 22019-03-0707 March 2019 Stations - Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR, Revision 2 CNRO-2019-00003, Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 42019-01-31031 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 4 CNRO-2019-00002, Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-01-31031 January 2019 Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 CNRO-2018-00051, Grand Gulf Nuclear Station, Palisades Nuclear Plant, River Bend Station, Pilgrim Nuclear Station and Waterford 3 - Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K2018-12-28028 December 2018 Grand Gulf Nuclear Station, Palisades Nuclear Plant, River Bend Station, Pilgrim Nuclear Station and Waterford 3 - Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K CNRO-2018-00039, Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element J2018-09-27027 September 2018 Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element J CNRO-2018-00011, Submittal of Joint Plant Access Shared Information Table2018-03-19019 March 2018 Submittal of Joint Plant Access Shared Information Table CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 12017-11-17017 November 2017 Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1 CNRO-2017-00010, Entergy Operations, Inc. - Decommissioning Funding Status Report2017-03-31031 March 2017 Entergy Operations, Inc. - Decommissioning Funding Status Report CNRO-2017-00007, Nuclear Property Damage Insurance (10 CFR 50.54(w)(3))2017-03-30030 March 2017 Nuclear Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2016-00017, Entergy Nuclear Operations - Request for Approval of Change to the Quality Assurance Program Manual2016-07-19019 July 2016 Entergy Nuclear Operations - Request for Approval of Change to the Quality Assurance Program Manual CNRO-2016-00008, Entergy - Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2016-03-30030 March 2016 Entergy - Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2016-00005, Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM)2016-02-25025 February 2016 Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2016-00002, Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Secti2016-01-29029 January 2016 Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Section Xl, CNRO-2015-00002, Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 12015-12-0404 December 2015 Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 1 CNRO-2015-00023, Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM)2015-11-0606 November 2015 Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2015-00021, Confirmatory Order - Action H2015-11-0303 November 2015 Confirmatory Order - Action H CNRO-2015-00020, ISFSI and Waterford 3 Steam Electric Station and ISFSI Re Required Notification of Receipt of All Required Regulatory Approvals of the Proposed Transfer Actions and Documentary Evidence of Required Insurance2015-09-23023 September 2015 ISFSI and Waterford 3 Steam Electric Station and ISFSI Re Required Notification of Receipt of All Required Regulatory Approvals of the Proposed Transfer Actions and Documentary Evidence of Required Insurance CNRO-2015-00018, Entergy - Relief Request Number RR EN-15-2 - Proposed Alternative to Use ASME Code Case N-786-1, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, Section XI, Division 1.2015-08-20020 August 2015 Entergy - Relief Request Number RR EN-15-2 - Proposed Alternative to Use ASME Code Case N-786-1, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, Section XI, Division 1. CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D2015-06-0505 June 2015 Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, Division CNRO-2015-00012, Arkansas, Units 1 & 2, Grand Gulf, River Bend, Waterford, Unit 3, Indian Point, Units 1, 2, & 3, Pilgrim, James A. FitzPatrick, Big Rock, Palisades - Submittal of Revision of Quality Assurance Program Manual2015-04-30030 April 2015 Arkansas, Units 1 & 2, Grand Gulf, River Bend, Waterford, Unit 3, Indian Point, Units 1, 2, & 3, Pilgrim, James A. FitzPatrick, Big Rock, Palisades - Submittal of Revision of Quality Assurance Program Manual CNRO-2015-00011, Grand Gulf Nuclear Station Unit 1 and Waterford 3 Steam Electric Station Submittal of Decommssioning Funding Status Report for 20142015-03-27027 March 2015 Grand Gulf Nuclear Station Unit 1 and Waterford 3 Steam Electric Station Submittal of Decommssioning Funding Status Report for 2014 CNRO-2015-00010, Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2015-03-27027 March 2015 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2015-00003, RBS Security Confirmatory Order - Action C2015-02-0505 February 2015 RBS Security Confirmatory Order - Action C CNRO-2015-00007, ISFSI, Waterford, Unit 3, and ISFSI, Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License Amendments2015-01-30030 January 2015 ISFSI, Waterford, Unit 3, and ISFSI, Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License Amendments CNRO-2014-00009, Response to Request for Additional Information for Review of the Decommissioning Funding Plans for Entergy Operations, Inc., Independent Spent Fuel Storage Installations2014-07-24024 July 2014 Response to Request for Additional Information for Review of the Decommissioning Funding Plans for Entergy Operations, Inc., Independent Spent Fuel Storage Installations CNRO-2014-00007, ISFSI, Waterford 3 and ISFSI - Application for Order Approving Transfers of Licenses and Conforming License Amendments2014-06-10010 June 2014 ISFSI, Waterford 3 and ISFSI - Application for Order Approving Transfers of Licenses and Conforming License Amendments CNRO-2014-00003, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2014-04-25025 April 2014 Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G CNRO-2014-00004, Unit 3, Letter (CNRO-2014-00002/ENOC-14-00010) of Same Subject 03/31/20142014-04-0303 April 2014 Unit 3, Letter (CNRO-2014-00002/ENOC-14-00010) of Same Subject 03/31/2014 CNRO-2014-00001, Completion of Change to the Entergy Quality Assurance Program Manual with Regards of Confirmatory Order EA-11-0962014-02-26026 February 2014 Completion of Change to the Entergy Quality Assurance Program Manual with Regards of Confirmatory Order EA-11-096 CNRO-2013-00009, Grant Gulf, River Bend, Unit 1 and Waterford 3, Response to Request for Additional Information Regarding 2013 Decommissioning Fund Status Report - Entergy Operations, Inc2013-06-20020 June 2013 Grant Gulf, River Bend, Unit 1 and Waterford 3, Response to Request for Additional Information Regarding 2013 Decommissioning Fund Status Report - Entergy Operations, Inc CNRO-2013-00007, Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2013-04-26026 April 2013 Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G CNRO-2013-00008, Arkansas, Units 1, 2 & ISFSI, Grand Gulf, ESP and ISFSI, River Bend, Unit 1 and ISFSI and Waterford 3 and ISFSI, Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments2013-04-16016 April 2013 Arkansas, Units 1, 2 & ISFSI, Grand Gulf, ESP and ISFSI, River Bend, Unit 1 and ISFSI and Waterford 3 and ISFSI, Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments CNRO-2013-00006, Decommissioning Funding Status Report - Entergy Operations, Inc2013-03-29029 March 2013 Decommissioning Funding Status Report - Entergy Operations, Inc CNRO-2013-00004, Entergy Operations, Inc. and Entergy Nuclear Operations, Inc., Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2013-03-25025 March 2013 Entergy Operations, Inc. and Entergy Nuclear Operations, Inc., Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2013-00002, Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments2013-01-29029 January 2013 Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications 2022-05-26
[Table view] |
Text
Entergy Operations, Inc.
Entergy 1340 Echelon Parkway Jackson, MS 39213-8298 Tel 601 368 5758 Michael A. Krupa Director Nuclear Safety Licensing CNRO-2003-00062 December 4, 2003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Entergy Operations, Inc.
Requests for Relief from ASME Section Xl Volumetric Examination Requirements River Bend Station Docket No. 50-458 License No. NPF-47
Dear Sir or Madam:
Pursuant to 10 CFR 50.55a(g)(6)(i), Entergy Operations, Inc. (Entergy) requests relief from the requirements of ASME Section Xl pertaining to volumetric examination of pressure-retaining welds for River Bend Station. In several locations, the required coverage cannot be obtained due to interference or geometry. Relief Requests RBS-ISI-001, -002 and
-003 are provided in Enclosures 1, 2, and 3, respectively.
Entergy requests that the NRC staff grant the enclosed relief requests on or before December 4, 2004.
This letter contains no commitments.
Should you have any questions regarding these requests, please contact Guy Davant at (601) 368-5756.
Very truly yours, YK MAK/GHD/bal
Enclosures:
- 1. Relief Request RBS-ISI-001
- 2. Relief Request RBS-ISI-002
- 3. Relief Request RBS-ISI-003 cc: (see next page) 00u
CNRO-2003-00062 Page 2 of 2 cc: Mr. W. A. Eaton (ECH)
Mr. P. D. Hinnenkamp (RBS)
Mr. P. J. Alter, NRC Senior Resident Inspector (RBS)
Mr. B. S. Mallett, NRC Region IV Regional Administrator Mr. M. K. Webb, NRR Project Manager (RBS)
ENCLOSURE I CNRO-2003-00062 RELIEF REQUEST RBS-ISI-001
ENTERGY OPERATIONS, INC.
RELIEF REQUEST RBS-ISI-001 COMPONENTS Components/Numbers: Class 1 B-J welds listed in Table 1, below.
ASME Code Class: I
References:
- 1. ASME Section XI 1992 Edition, Table IWB-2500-1
- 2. ASME Section XI 1980 Edition with the Winter of 1981 Addenda for ultrasonic examinations
- 3. ASME Section XI, Appendix VIII, Supplements 2 and 3 of the 1995 Edition with 1996 Addenda
- 4. ASME Code Case N-460 - Alternative Examination Coverage for Class 1 and 2 Welds,Section XI, Division 1
- 5. Letter from the NRC to Entergy Operations, Inc.,
Evaluation of Entergy Operations, Inc. Request for Authorization to Update Inservice Inspection Programs to the 1992 and Portions of the 1993 ASME Boiler and Pressure Vessel Code, Section Xl forArkansas Nuclear One, Units 1 and 2, Grand Gulf Nuclear Station, River Bend Station, and Waterford Steam Electric Station, Unit 3 (TAC Nos. M94472, M94471, M94454, M94473, and M94488), dated December 12,1996 Examination Category: B-J Item Numbers: B9.11, B9.31
Description:
Pressure-retaining welds in piping Unit / Inspection River Bend Station - Second (2nd) 10-year interval Interval Applicability:
II. CODE REQUIREMENT(S)
ASME Section Xl, Table IWB-2500-1, Examination Category B-J, Items B9.11 and B9.31 require essentially 100% volumetric examination of pressure-retaining welds. However, ASME Code Case N-460 allows a reduction in coverage for Class 1 and 2 welds due to interference or geometry as long as the overall coverage is greater than 90%.
III. RELIEF REQUESTED Pursuant to 10 CFR 50.55a(g)(6)(i), Entergy Operations, Inc. (Entergy) requests relief from achieving the Code-required coverage (> 90%) when performing volumetric examinations of the components identified in Table 1, below.
Page 1 of 9
Table 1 Limited B-J Examinations Item Item ID Description Coverage Reason for
(%) Limitation B9.11 1RCS-900B-FWB06 Nozzle-to-Pipe 60.5 Weld configuration and weld build-up on the ID and OD B9.11 I RCS-90OC-FWB15 Pipe-to-Cross 70 Sweep-O-Let to Pipe configuration B9.11 1RCS-900C-FWB16 Pipe-to-Cross 70 Sweep-O-Let to Pipe configuration B9.11 I RCS-900CX-SW014BC Pipe-to-Cross 71.5 Sweep-O-Let to Pipe configuration B9.31 1RCS-900CX-SWO14CB Sweep-O-Let to 71.5 Sweep-O-Let to Pipe Pipe configuration B9.31 1WCS-001A1-X-FW005 Sweep-O-Let tc 40 Pipe-to-Valve Pipe configuration B9.31 IWCS-001A3-XI-FW011 Sweep-O-Let to 58 Pipe-to-Reducer Pipe configuration IV. Basis for Relief The identified ASME Class 1 piping and components were designed with welded joint configurations, such as sweep-o-let-to-pipe, pipe-to-valve, and pipe-to-reducer, which physically obstruct part of the required examination area. The subject welds were examined to the maximum extent practical; however, greater than 90% of the required examination volume as allowed by ASME Code Case N-460 could not be achieved. The ultrasonic examination coverage calculation sheets are provided in the attachment to this relief request. Although these welds were examined prior to May 22, 2000 (mandatory implementation of Appendix Vil), the examination procedures, personnel, and equipment were certified through the Performance Demonstrative Initiative (PDI).
During the PDI qualification process for examination of austenitic welds, single-side examination with a shear wave was proven unsatisfactory on the far side of the weld due to attenuation and distortion of the sound wave. The refracted longitudinal wave demonstrated better penetration on the far side with evidence of crack detection; however, it was not fully qualified. Entergy performs a "best effort" examination by extending a shear wave and/or a refracted longitudinal wave into the far side of the weld, looking for evidence of cracking.
Entergy has used the best available techniques demonstrated through the PDI process.
Weld selection has been optimized to minimize the number of welds requiring relief. To perform the Code-required examination, modification and/or replacement of the component would be required. Consistent with the ASME Section XI sampling approach, Page 2 of 9
examination of the subject welds as described within, combined with examinations of other welds within the same examination category, is adequate to identify any generic degradation that may exist.
V. PROPOSED ALTERNATIVE EXAMINATIONS As stated above, Entergy has examined these welds to the extent practical using PDI-qualified procedures, personnel, and equipment. Entergy will continue to perform pressure testing on these welds as required by ASME Section Xl.
VI. CONCLUSION 10 CFR 50.55a(g)(6)(i) states:
The Commission will evaluate determinations under paragraph (g)(5) of this section that code requirements are impractical. The Commission may grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Due to design configuration, it is impractical to obtain greater than 90% coverage on these welds, as discussed in Section IV, above. To obtain the required coverage would necessitate modifying and/or replacing components. The examinations performed on the subject welds, in addition to the examination of similar welds contained in the program, would detect generic degradation if it existed, thereby demonstrating an acceptable level of integrity. Therefore, Entergy requests the NRC staff authorize the proposed alternative pursuant to 10 CFR 50.55a(g)(6)(i).
Page 3 of 9
ATTACHMENT RELIEF REQUEST RBS-ISI-001 EXAMINATION COVERAGE CALCULATION SHEETS Page 4 of 9
~Entergy EXAMINATION COVERAGE CALCULATION SHEET Attachment #: A 0 ANO 1 l3 ANO 2 0 Grand Gulf River Bend l3 Waterford 3 Component ID:RCS - 900B - FWB06 Report No.: 00lR20319 Material Type: SS Pipe Diameter.: 20" SchI T: 1.3" Angle's Used: 450 S - 2 V, 450 RL - 1/2 V. 600 RL NOTES:
I This Is an approximate percent of the examination volume for which coverage was obtained.
2 The plot shown is a representation of the actual profile and not to scale.
Nozzle F-1 No Coverage Direction #1 Direction #2 TOTAL EXAM VOLUME OBTAINED: 60.5 %
COMMENTS: Single side exam due to configuration (pipe to Nozzle). Scanned from pipe side only. Used 450 RL to scan with due to ID & OD overlay. Also used 450 shear per the procedure and 600 RL for best effort, all angles calibrated for % V path. The 450 RL and Shear were used for coverage calculation to obtain the most coverage. Exam performed on 3/12/00.
Page 5 of 9
~Entergy EXAMINATION COVERAGE CALCULATION SHEET Attachment #: B l3 ANO 1 ° ANO 2 0 Grand Gulf IX River Bend 03 Waterford 3 Component ID:IRCS-900C- FWB15 & FWB16 Report No.: 00IR20253 Material Type: SS Pipe Diameter.: 10" Sch/ T: 0.63" Angle's Used: 450 S - % V. 600 L - % V NOTES:
- 1. This is an approximate percent of the examination volume for which coverage was obtained.
- 2. The plot shown is a representation of the actual profile and not to scale.
F[1 No Coverage Direction #1 Direction #2 TOTAL EXAM VOLUME OBTAINED: 70 %
COMMENTS: Single side exam due to configuration (pipe to sweep-o-let). Scanned from pipe side only. This plot represents the profile for both IRCS - 900C-FW1B15 and IRCS - 900C-FWB16. 450 S and 600 RL were calibrated for % V path and used for coverage per the procedure. Exam performed on 3/9/00 Page 6 of 9
l Entergy EXAMINATION COVERAGE CALCULATION SHEET Attachment #: C l3 ANO1 3 ANO 2 0 Grand Gulf IU River Bend l3 Waterford3 Component ID:1 RCS - 900CX - SWO14 CB & SWO14 BC Report No.: 00IR20252 Material Type: SS Pipe Diameter.: 16" SchI T: 1.0" Angle's Used: 450 S - % V. 600 RL - /2 V NOTES:
- 1. This is an approximate percent of the examination volume for which coverage was obtained.
- 2. The plot shown is a representation of the actual profile and not to scale.
600 RL 55 sS SWEEP-0-LET 1 No Coverage Direction #1 Direction #2 TOTAL EXAM VOLUME OBTAINED: 71.5 %
COMMENTS: Single side exam due to configuration (pipe to sweep-o-let). Scanned from pipe side only. This plot represents the profile for both IRCS - 900CX-SW014-CB and RCS - 900CX-SWO14-BC. 450 S and 600 RL were calibrated for to V path and used for coverage per the procedure. Exam performed on 3/9/00 Page 7 of 9
l Entergy EXAMINATION COVERAGE CALCULATION SHEET Attachment #: D l3 ANO 1 13 ANO 2 0 Grand Gulf River Bend 0 Waterford 3 Component ID:IWCS - 001A1 - Xl - FW005 Report No.: 00IR20283 Material Type: SS Pipe Diameter.: 4" Sch/ T: 0.53" Angle's Used: 700 S - 1/2 V NOTES:
- 1. This is an approximate percent of the examination volume for which coverage was obtained.
- 2. The plot shown is a representation of the actual profile and not to scale.
70" S VALVE X ~~~~PIPE EZ No Coverage Direction #1 Direction #2 TOTAL EXAM VOLUME OBTAINED: 40 %
COMMENTS: Single side exam due to configuration (pipe to valve). Scanned from pipe side only. This plot represents the profile for IWCS - OO1AI-XI-FW005. 7 0 0 S was calibrated for % V path and used to obtain max coverage per the procedure. Exam performed on 3/14/00.
Page 8 of 9
CEnteg EXAMINATION COVERAGE CALCULATION SHEET Attachment #: E l3 ANO 1 0 ANO 2 0 Grand Gulf I
- River Bend 0 Waterford 3 Component ID:lWCS - 001A3 - Xl - FW011 Report No.: 001R20281 Material Type: SS Pipe Diameter.: 4" Sch/ T: 337" Angle's Used: 450 S - % V. 700 S - % V NOTES:
- 1. This is an approximate percent of the examination volume for which coverage was obtained.
- 2. The plot shown is a representation of the actual profile and not to scale.
45 70 S 451/70"S REDUCER (DS)
F 1 No Coverage Direction #1 Direction #2 TOTAL EXAM VOLUME OBTAINED: 58 %
COMMENTS: Axial exam from DS side limited to scan path of 0.25 x 3600, credit taken for first leg on DS side only due to irregular ID. This plot represents the profile for IWCS - 001A3-XI-FW011. 450 Sand 7 0 S were calibrated for 1/2 V path and used for coverage per the procedure. Exam performed on 3/11/00.
Page 9 of 9
ENCLOSURE 2 CNRO-2003-00062 RELIEF REQUEST RBS-ISI-002
ENTERGY OPERATIONS, INC.
REQUEST FOR RELIEF RBS-ISI-002 COMPONENTS Component/Number: RHR heat exchanger vessel shell-to-flange weld E12-EB001A-3.706 (pressure-retaining weld)
ASME Code Class: 2
References:
- 1. ASME Section Xl 1992 Edition, Table IWC-2500-1
- 2. ASME Section Xi 1980 Edition with the Winter of 1981 Addenda for ultrasonic examinations
- 3. ASME Code Case N-460 - Alternative Examination Coverage for Class 1 and 2 Welds,Section XI, Division 1
- 4. Letter from the NRC to Entergy Operations, Inc.,
Evaluation of Entergy Operations, Inc. Request for Authorization to Update Inservice Inspection Programs to the 1992 and Portions of the 1993 ASME Boiler and Pressure Vessel Code,Section XI for Arkansas Nuclear One, Units 1 and 2, Grand Gulf Nuclear Station, River Bend Station, and Waterford Steam Electric Station, Unit 3 (TAC Nos. M94472, M94471, M94454, M94473, and M94488), dated December 12,1996 Examination Category: C-A Item Numbers: C1.10 Unit I Inspection River Bend Station - Second ( 2nd) 10-year interval Interval Applicability:
II. CODE REQUIREMENT(S)
ASME Section Xi, Table IWC-2500-1, Examination Category C-A, Item C1.10 requires essentially 100% volumetric examination of the pressure retaining welds. However, ASME Code Case N-460 allows a reduction in coverage for Class 1 and 2 welds due to interference or geometry as long as the overall coverage is greater than 90%.
Ill. RELIEF REQUESTED Pursuant to 10 CFR 50.55a(g)(6)(i), Entergy Operations, Inc. (Entergy) requests relief from achieving the Code-required coverage (> 90%) when performing volumetric examinations of weld E12-EBOOIA-3.706. See Table 1, below.
Page 1 of 4
Table I
_. _-,_ Limited C-A Examinations Item # Item ID Item Description Coverage Reason for Limitation C1.10 E12-EBOOIA-3.706 Shell circumferential 61 Not examined from flange weld - Shell to flange side due to configuration weld and nozzle interference IV. BASIS FOR RELIEF Entergy has examined weld E12-EBOOIA-3.706 to the maximum extent possible utilizing examination techniques and equipment qualified in accordance with the requirements of ASME Section Xl. However, Entergy can obtain only 61 % coverage of the weld due to configuration rather than the 90% allowed by ASME Code Case N-460. Specifically, examination from the flange side of the weld is not possible due to component configuration. Additionally, approximately ten (10) inches of the weld circumference cannot be scanned from either side of the weld due to the close proximity of the nozzle weld. The ultrasonic examination coverage calculation sheet is provided in the attachment to this relief request.
V. PROPOSED ALTERNATIVE EXAMINATIONS As stated above, Entergy has examined weld E12-EB001A-3.706 to the maximum extent practical using qualified procedures, personnel and equipment. Entergy will continue to perform pressure testing on E12-EB001A-3.706 as required by ASME Section Xl.
VI. CONCLUSION 10 CFR 50.55a(g)(6)(i) states:
The Commission will evaluate determinations under paragraph (g)(5) of this section that code requirements are impractical. The Commission may grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Due to design configuration, it is impractical to obtain greater than 90% coverage on weld E12-EB001A-3.706. To obtain the required coverage would necessitate modification and/or replacement of the component. The examinations performed on this weld, in addition to the examination of similar welds contained in the program, would detect generic degradation, if it existed, thereby demonstrating an acceptable level of integrity.
Therefore, Entergy requests the NRC staff authorize the proposed alternative pursuant to 10 CFR 50.55a(g)(6)(i).
Page 2 of 4
ATTACHMENT RELIEF REQUEST RBS-ISI-002 EXAMINATION COVERAGE CALCULATION SHEET Page 3 of 4
Ak "Entmgy EXAMINATION COVERAGE CALCULATION SHEET 0
Attachment #: F l 03 ANO 1 0 ANO 2 l D Grand Gulf I
- River Bend r3 Waterford3 0
Component D:E12-EB001A-3.706 Report No.: 991R20301 Material Type: CS Pipe Diameter.: 53" Sch/ T: .875" Angle's Used: 450 S - 1% V NOTES:
- 1. The .25" dimension on each side of the weld Is for non-risk Informed ISI, for risk informed ISI the exam volume will be determined by the risk Informed program.
- 2. This is an approximate percent of the examination volume for which coverage was obtained.
- 3. The plot shown is a representation of the actual profile and not to scale..
E12EB001A 3 743 FLANGE SHL E12-EBOOIA-3.706 FjJ No Coverage Direction #1 Direction #2 TOTAL EXAM VOLUME OBTAINED: 61 %
COMMENTS: No exam from flange side due to configuration. 45° S calibrated for 1% Vpath and used for coverage per the procedure. Approximately 10" of this weld was not scanned from either side due to the close proximity of nozzle weld EB12-EBOOIA-3.743. This plot represents the profile for E12-EB001A-3.706. Exam performed on 4/10199.
Page 4 of 4
ENCLOSURE 3 CNRO-2003-00062 RELIEF REQUEST RBS-ISI-003
ENTERGY OPERATIONS, INC.
REQUEST FOR RELIEF RBS-ISI-003 COMPONENTS Component/Number: RHR heat exchanger vessel shell-to-nozzle weld E12-EB001A-3.743 (pressure-retaining weld)
ASME Code Class: 1
References:
- 1. ASME Section XI 1992 Edition, Table IWC-2500-1
- 2. ASME Section Xl 1980 Edition with the Winter of 1981 Addenda for ultrasonic examinations
- 3. ASME Code Case N-460 - Alternative Examination Coverage for Class 1 and 2 Welds, Section Xl, Division 1
- 4. Letter from the NRC to Entergy Operations, Inc.,
Evaluation of Entergy Operations, Inc. Request for Authorization to Update Inservice Inspection Programs to the 1992 and Portions of the 1993 ASME Boiler and Pressure Vessel Code, Section Xl for Arkansas Nuclear One, Units 1 and 2, Grand Gulf Nuclear Station, River Bend Station, and Waterford Steam Electric Station, Unit 3 (TAC Nos. M94472, M94471, M94454, M94473, and M94488), dated December 12, 1996 Examination Category: C-B Item Numbers: C2.21 Unit / Inspection River Bend Station - Second (2nd) 10-year interval Interval Applicability:
II. CODE REQUIREMENT(S)
ASME Section Xl, Table IWC-2500-1, Examination Category C-B, Item C2.21 requires essentially 100% volumetric examination of the pressure retaining welds. However, ASME Code Case N-460 allows a reduction in coverage for Class 1 and 2 welds due to interference or geometry as long as the overall coverage is greater than 90%.
Ill. RELIEF REQUESTED Pursuant to 10 CFR 50.55a(g)(6)(i), Entergy Operations, Inc. (Entergy) requests relief from achieving Code-required coverage (> 90%) when performing volumetric examinations of weld E12-EB001A-3.743. See Table 1, below.
Page 1 of 4
Table I Limited C-A Examinations Item # Item ID Item Description Coverage Reason for Limitation C2.21 E12-EB001A-3.743 Nozzle to Shell (or 73 Not examined due to head) weld configuration and adjacent weld interference.
IV. BASIS FOR RELIEF Entergy has examined weld E12-EB001A-3.743 to the maximum extent possible utilizing examination techniques and equipment qualified in accordance with the requirements of ASME Section Xl. However, Entergy can obtain only 73% coverage of the weld due to component configuration rather than the 90% allowed by ASME Code Case N-460.
Specifically, examination from the nozzle side of the weld is not possible. Additionally, approximately six (6) inches of the weld circumference cannot be scanned from either side of the weld due to the close proximity to an adjacent weld. The ultrasonic examination coverage calculation sheet is provided in the attachment to this relief request.
V. PROPOSED ALTERNATIVE EXAMINATIONS As stated above, Entergy has examined weld E12-EB001A-3.743 to the maximum extent practical using qualified procedures, personnel and equipment. Entergy will continue to perform pressure testing on E12-EB001A-3.743 as required by ASME Section Xi.
VI. CONCLUSION 10 CFR 50.55a(g)(6)(i) states:
The Commission will evaluate determinations under paragraph (g)(5) of this section that code requirements are impractical. The Commission may grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Due to design configuration, it is impractical to obtain greater than 90% coverage on weld E12-EB001A-3.743. To obtain the required coverage would necessitate modification and/or replacement of the component. The examinations performed on this weld, in addition to the examination of similar welds contained in the program, would detect generic degradation, if it existed, thereby demonstrating an acceptable level of integrity.
Therefore, Entergy requests the NRC staff authorize the proposed alternative pursuant to 10 CFR 50.55a(g)(6)(i).
Page 2 of 4
ATTACHMENT RELIEF REQUEST RBS-ISI-003 EXAMINATION COVERAGE CALCULATION SHEET Page 3 of 4
~~Enteg EXAMINATION COVERAGE CALCULATION SHEET Attachment #: G 0 AN01 03 ANO 2 0 Grand Gulf l River Bend 0 Waterford 3 Component D:E12-EB001A-3.743 Report No.: 991R20300 Material Type: CS Pipe Diameter.: 18" Sch/ T: .875" Angle's Used: 450 S - 1% V NOTES:
- 1. The .25" dimension on each side of the weld Is for non-risk informed ISI, for risk informed ISI the exam volume will be determined by the risk Informed program.
- 2. This is an approximate percent of the examination volume for which coverage was obtained.
- 3. The plot shown is a representation of the actual profile and not to scale.
l45 12-EBOIA-3.743 NOZZLE X// / / Il/ SHELL l (
as/ 2 ~~~~~~~~~~~~~~~~~~~~E12-EBO 706 F-1 No Coverage / Direction #1 Direction #2 TOTAL EXAM VOLUME OBTAINED: 73 %
COMMENTS: No exam from Nozzle side due to configuration. 450 S calibrated for 1 V path and used for coverage per the procedure. Approximately 6" of this weld was not scanned from either side due to the close proximity of nozzle to weld E12-EBOOIA-3.706. This plot represents the profile for E12-EB001A -3.743. exam performed on 4/10199.
Page 4 of 4