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MONTHYEARML0423100082005-01-0606 January 2005 Relief Request No. PRR-29, Relief from System Hydrostatic Test Requirements for Small Bore ASME Code Class 1 Reactor Coolant Pressure Boundary Vent, Drain and Branch Lines and Connections Project stage: Other ML0515802032005-05-26026 May 2005 Request for Relief from System Hydrostatic Test Requirements for Small Bore (5 1 Inch), ASME Code Class 1 Reactor Coolant Pressure Boundary (RCPB) Vent, Drain, and Branch (Vtdb) Lines and Connections Project stage: Request NL-05-071, Request for Relief from System Hydrostatic Test Requirements for Small Bore (Less than or Equal to 1 Inch), ASME Code Class 1 Reactor Coolant Pressure Boundary (RCPB) Vent, Drain, and Branch (Vtdb) Lines and Connections2005-06-0808 June 2005 Request for Relief from System Hydrostatic Test Requirements for Small Bore (Less than or Equal to 1 Inch), ASME Code Class 1 Reactor Coolant Pressure Boundary (RCPB) Vent, Drain, and Branch (Vtdb) Lines and Connections Project stage: Request CNRO-2006-00022, Arkansas, Unit 1 - Request for Alternative ANO1-PT-001, Visual Examination of Extended Reactor Coolant Pressure Boundary Piping During System Leakage Tests2006-04-24024 April 2006 Arkansas, Unit 1 - Request for Alternative ANO1-PT-001, Visual Examination of Extended Reactor Coolant Pressure Boundary Piping During System Leakage Tests Project stage: Request CNRO-2006-00023, Request for Alternative CEP-PT-001 Visual Examination of Vent and Drain Connections During System Leakage Tests2006-04-24024 April 2006 Request for Alternative CEP-PT-001 Visual Examination of Vent and Drain Connections During System Leakage Tests Project stage: Request 2005-05-26
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Category:Code Relief or Alternative
MONTHYEARML23142A1062023-05-24024 May 2023 Authorization and Safety Evaluation for Alternative Request No. ANO1-ISI-035 ML22073A0952022-04-0707 April 2022 Approval of Request for Alternative from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (EPID L-2021-LLR-0084) (NON-PROPRIETARY) ML21293A0962021-10-28028 October 2021 Relief ANO2-R&R-012 Concerning Proposed Alternative for Repair of Reactor Vessel Closure Head Penetration 46 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 ML21168A0562021-07-0909 July 2021 Approval of Request for Alternative from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML21118B0392021-05-19019 May 2021 Approval of Request for Alternative from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code 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) ML20121A1932020-05-0606 May 2020 Alternative Requests for the Fifth 10 Year Interval Inservice Testing of Low Pressure Safety Injection Pumps and Service Water Valves ML20119A0732020-04-29029 April 2020 Withdrawal of Requested Alternatives for the Fifth 10-Year Interval Inservice Testing of Service Water Pumps and Visual Examination of Snubbers ML20083J9682020-03-26026 March 2020 Approval of Request for Alternative ANO 2-PT-002 End-of-Internal System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping 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 2CAN071902, Request for Alternative ANO 2-PT-002 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping2019-07-25025 July 2019 Request for Alternative ANO 2-PT-002 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping ML19184A5542019-07-15015 July 2019 Request for Relief ANO1-ISI-032 from the ASME Code Section XI Visual Examination Requirements for the Fourth 10-Year Inservice Inspection Interval ML19156A4002019-06-11011 June 2019 Request for Alternative ANO2-ISI-021 to Permit Continued Application of the 2007 Edition Through the 2008 Addenda of ASME Code 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 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 1CAN041801, Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements Fourth 10-Year Interval, Second and Third Period2018-04-23023 April 2018 Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements Fourth 10-Year Interval, Second and Third Period 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 ML17174B1442017-07-12012 July 2017 Relief Request for EN-ISI-16-1 Regarding Use of Later Edition and Addenda of the ASME Code ML16130A4712016-12-0909 December 2016 Request for Alternative Test Plan to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (CAC Nos. MF7537 and MF7538) ML16237A0822016-08-29029 August 2016 Relief Request No. ANO1-ISI-025, Relief from American Society of Mechanical Engineers Section XI Table IWB-2500-1 Requirements 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 ML15070A4282015-03-16016 March 2015 Relief Request ANO2-ISI-017, Alternative to Utilize ASME Code Case N-513-4 for the Fourth 10-Year Inservice Inspection Interval ML15030A2392015-02-0909 February 2015 Correction to Relief Request ANO1-ISI-024 Issued December 23, 2014; Revises 10 CFR 50.55a Citations as a Result of Changes from Final Rule Effective December 5, 2014 ML14330A2072014-12-23023 December 2014 Relief Request ANO1-ISI-024, Alternative from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-1, Fourth 10-year Inservice Inspection Interval ML14282A4792014-10-29029 October 2014 Relief Request ANO1-ISI-023, Volumetric Examination Frequency Requirements, for the Fourth 10-Year Inservice Inspection Interval ML14150A1632014-06-0606 June 2014 Relief Request ANO2-ISI-004 - Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations ML14099A4522014-04-15015 April 2014 Relief Request ANO2-ISI-016, from ASME Code Case N-770-1 Successive Examination, for the Fourth 10-Year Inservice Inspection Interval ML13179A1162013-07-24024 July 2013 Request for Relief ANO1-ISI-022 from ASME Code Examination Requirements for Pressure-Retaining Welds in Piping; Fourth 10-Year Inservice Inspection Interval ML13179A1102013-07-16016 July 2013 Request for Relief No. ANO1-ISI-021, from ASME Volumetric Requirements for Full Penetration Welded Nozzles in Vessels - Inspection Program B; Fourth 10-Year ISI Interval ML13161A2412013-06-27027 June 2013 Relief Request ANO2-ISI-015, from Pressure Testing Requirements for Reactor Vessel Flange Seal Leak Detection Piping for the Fourth 10-Year Inservice Inspection Interval ML13071A6342013-03-22022 March 2013 Relief Request ANO2-ISI-014, from Volumetric and Surface Exam Requirements for Pressure Retaining Welds in Austenitic Stainless Steel, Third 10-Year Inservice Inspection Interval ML13071A6632013-03-21021 March 2013 Relief Request ANO2-ISI-010, from Volumetric and Surface Exam Requirements for Pressure Retaining Welds in Piping, Third 10-Year Inservice Inspection Interval ML13032A5732013-02-21021 February 2013 Relief Request Nos. ANO2-ISI-009, ANO2-ISI-011, and ANO2-ISI-012, ASME Code Volumetric and Surface Exam Requirements for Integral Attachment and Pressure-Retaining Welds, Third 10-Year Inservice Inspection Interval ML12319A3672012-11-27027 November 2012 Relief Request ANO2-ISI-007, Alternative to Use ASME Code Case N-770-1 Baseline Examination, Fourth 10-Year Inservice Inspection Interval 1CAN071202, Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements, Fourth 10-Year Interval, First Period2012-07-25025 July 2012 Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements, Fourth 10-Year Interval, First Period 2CAN111101, Use of Alternate ASME Code Case N-770-1 Baseline Examination Request for Alternative ANO2-ISI-0072011-11-30030 November 2011 Use of Alternate ASME Code Case N-770-1 Baseline Examination Request for Alternative ANO2-ISI-007 ML1117107982011-08-10010 August 2011 Relief, ANO1-R&R-016, Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05, Fourth 10-Year Interval. ME6107 ML1034301562011-01-10010 January 2011 Relief Request ANO1-R&R-013, Proposed Alternative to Requirements Associated with Repair of Components, for Duration of ANO-1 Spring 2010 Refueling Outage 1R22 ML1035005322011-01-0505 January 2011 Request for Alternative ANO2-ISI-006, Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716 for the Fourth 10-Year ISI Interval ML1025001282010-09-23023 September 2010 Relief Request ANO2-ISI-005 to Extend the Inservice Inspection Interval for the Visual Examination of Accessible Interior to Reactor Vessel Attachment Weld, for Fourth 10-Year Interval ML1024506542010-09-21021 September 2010 Relief Request ANO2-ISI-004 to Extend Third Inservice Inspection Interval from 10 to 20 Years for Reactor Vessel Weld Examinations ML1009103502010-08-19019 August 2010 Request for Relief PRR-ANO2-2010-1, Relief from the Requirements of Operation and Maintenance Code Section ISTB-5221 and ITSB-5223 for the Service Water Pumps ML1011701272010-06-0202 June 2010 Request for Alternative ANO1-ISI-014, to Implement a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716 ML1011701192010-05-0505 May 2010 Request for Relief Nos. ANO1-ISI-015, ANO1-ISI-016, ANO1-ISI-017, ANO1-ISI-018, ANO1-ISI-019, and ANO1-ISI-020, Relief from Requirements of the ASME Code, Section XI ML1009706592010-04-26026 April 2010 Request for Alternative ANO2-ISI-003 to Use 2001 Edition Through 2003 Addenda in Lieu of the 2004 Edition for Fourth 10-Year Inservice Inspection Interval 2CAN021002, Request for Relief PRR-ANO2-2010-1 from the Requirements of OM Code Section ISTB-5221 and ISTB-5223 for the Service Water Pumps2010-02-17017 February 2010 Request for Relief PRR-ANO2-2010-1 from the Requirements of OM Code Section ISTB-5221 and ISTB-5223 for the Service Water Pumps 2CAN011005, Supplement to Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-7162010-01-28028 January 2010 Supplement to Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716 ML0923005512009-08-27027 August 2009 Request for Alternative ANO2-ISI-002 to 10 CFR 50.55a(g)(6)(ii)(D) Examination Requirements, for Remainder of Current 10-Year Inservice Inspection Interval and Fourth ISI Interval Until the Head Is Replaced 2023-05-24
[Table view] Category:Letter type:CNRO
MONTHYEARCNRO-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-2020-00016, 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-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-2019-00003, 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-2016-00023, Request EN-ISI-16-1: Use of Later Edition/Addenda of Amse Section XI Code for ISI Related Activities2016-12-0101 December 2016 Request EN-ISI-16-1: Use of Later Edition/Addenda of Amse Section XI Code for ISI Related Activities 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-2016-00016, Entergy - Response to RAI Questions and Submittal of Relief Request EN-ISI-15-1 (Updated)2016-06-0202 June 2016 Entergy - Response to RAI Questions and Submittal of Relief Request EN-ISI-15-1 (Updated) 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-2015-00022, Entergy - Relief Request EN-ISI-15-1: Proposed Alternative to Maintain ISI-Related Activities to the 2001 Edition/2003 Addendum of ASME Section Xl Code2015-11-20020 November 2015 Entergy - Relief Request EN-ISI-15-1: Proposed Alternative to Maintain ISI-Related Activities to the 2001 Edition/2003 Addendum of ASME Section Xl Code 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-2015-00018, 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-2015-00010, 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-2015-00011, 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-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-2014-00003, 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-2013-00007, 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 CNRO-2012-00007, Grand Gulf Nuclear Station & Waterford 3 Steam Electric Station Status of Decommissioning Funding - Entergy Operations, Inc2012-10-15015 October 2012 Grand Gulf Nuclear Station & Waterford 3 Steam Electric Station Status of Decommissioning Funding - Entergy Operations, Inc CNRO-2012-00004, Request for Additional Information Regarding Changes to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Plant Technical Specifications Regarding Staff Qualifications2012-05-21021 May 2012 Request for Additional Information Regarding Changes to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Plant Technical Specifications Regarding Staff Qualifications CNRO-2012-00003, Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2012-04-30030 April 2012 Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G CNRO-2011-00006, Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Technical Specifications Regarding Staff Qualifications2011-12-13013 December 2011 Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Technical Specifications Regarding Staff Qualifications CNRO-2011-00007, 2011 Recertification of Foreign Ownership Control or Interest2011-10-0606 October 2011 2011 Recertification of Foreign Ownership Control or Interest CNRO-2011-00005, Response to Request for Additional Information on 2011 Decommissioning Fund Status Report2011-07-0505 July 2011 Response to Request for Additional Information on 2011 Decommissioning Fund Status Report CNRO-2011-00004, Entergy - Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2011-04-29029 April 2011 Entergy - Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G CNRO-2011-00001, Status of Decommissioning Funding for Plants Operated by Entergy Operations, Inc2011-03-31031 March 2011 Status of Decommissioning Funding for Plants Operated by Entergy Operations, Inc CNRO-2011-00002, Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2011-03-31031 March 2011 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2010-00002, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2010-04-29029 April 2010 Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G 2021-10-06
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t t Entergy Operations, Inc.
- Entergy 1340 Echelon Parkway Jackson, Mississippi 392134298 Tel 601-368-5758 F. G. Burford Acting Director Nuclear Safety & Licensing CNRO-2006-00022 April 24, 2006 U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Request for Alternative ANO1-PT-001 Visual Examination of Extended Reactor Coolant Pressure Boundary Piping during System Leakage Tests Arkansas Nuclear One, Unit 1 Docket No. 50-313 License No. DPR-51
REFERENCE:
NRC letter to Pilgrim Nuclear Power Station (TAC No. MC1472) dated January 6, 2005.
Dear Sir or Madam:
Pursuant to 10 CFR 50.55a(a)(3)(ii), Entergy Operations, Inc. (Entergy) proposes an alternative to the requirements of ASME Section Xi pertaining to system leakage tests for Arkansas Nuclear One, Unit 1 (ANO-1). Specifically, Entergy proposes to visually examine the extended reactor coolant pressure boundary (RCPB) piping between the first and second normally closed isolation valves during the Class 2 system leakage test conducted each inspection interval as an alternative to ASME Section Xl IWB-5222(b). Request for Alternative ANO1-PT-001 is provided in the enclosure to this letter.
Entergy requests the NRC staff approve AN01 -PT-001 by April 1, 2007 in order to support the spring 2007 refueling outage at ANO-1.
The NRC staff approved a similar request for the Pilgrim Nuclear Power Station via the referenced letter.
Should you have any questions regarding this submittal, please contact Guy Davant at (601) 368-5756.
,SVD4J
CNRO-2006-00022 Page 2 of 2 This letter contains no commitments.
Very truly yours, FGB/GHD/ghd
Enclosure:
Request for Alternative ANO1 -PT-001 cc: Mr. W. A. Eaton (ECH)
Mr. J. S. Forbes (ANO)
Dr. Bruce S. Mallett U. S. Nuclear Regulatory Commission, Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 U. S. Nuclear Regulatory Commission Attn: Mr. Drew Holland MS 0-7D1 Washington, DC 20555-0001 NRC Senior Resident Inspector Arkansas Nuclear One P. 0. Box 310 London, AR 72847
ENCLOSURE CNRO-2006-00022 ANOI-PT-001
ENTERGY OPERATIONS, INC.
ARKANSAS NUCLEAR ONE, UNIT I REQUEST FOR ALTERNATIVE ANOI-PT-001 COMPONENTS Components/Numbers: Reactor Coolant Pressure Boundary
- 1. Decay Heat Removal System Loop "A", between check valves DH-14A, CF-1A, DH-13A and DH-18
- 2. Decay Heat Removal System Loop "B", between check valves DH-14B, CF-1B, DH-13B and DH-17
- 3. Pressurizer Auxiliary Spray piping between check valves DH-12 and DH-16 Code Class: 1
References:
ASME Section Xl, 1992 Edition, 1993 Addenda, IWB-5222(b)
Examination Category: B-P Item Numbers: B15.50
Description:
System Pressure Test Boundary Unit / Inspection ANO-1 third (3 d) 10-year interval Interval Applicability:
II. CODE REQUIREMENT(S)
ASME Section Xl IWB-5222(b) requires, "The pressure retaining boundary during the system leakage test conducted at or near the end of each inspection interval shall extend to all Class 1 pressure retaining components within the system."
III. REQUESTED ALTERNATIVE Pursuant to 10 CFR 50.55a(a)(3)(ii), Entergy requests authorization to visually examine the extended reactor coolant pressure boundary (RCPB) between the first and second normally closed isolation valves during the Class 2 system leakage test to be conducted in the current inspection period for the components identified in Section I, above.
Section IV, below, provides the basis for applying this proposed alternative to each identified line.
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IV. BASIS FOR ALTERNATIVE Performing leakage test of the Class 1 boundary beyond the inboard isolation valves at or near the end of each inspection interval requires conditions that place the plant in abnormal configurations or requires off-normal activities in order to pressurize the subject piping. These challenges include abnormal line-ups, installing jumpers around valve operation interlocks, installing and removing piping jumpers around valves, removing valve internals, and installing plugs. Associated with each challenge come additional burdens prior to plant restart, such as:
- Multiple disassembly and reassembly of valves and control circuitry These off-normal configurations and challenges may also contribute to the risk of delaying normal plant start-up because of the critical path time and effort required to ensure system configuration is restored.
The piping subject to this request is outboard of the first isolation valve and is designed to RCPB conditions. However, its operation during normal conditions is typically not subject to RCPB operating conditions but to Class 2 system conditions of decay heat removal, auxiliary spray, or high pressure injection. While this piping is extremely difficult to test with the Class 1 leakage test, it is easily tested with the Class 2 system at Class 2 test conditions because of the check valve boundaries. Although Class 2 system pressure is lower than Class 1, it is representative of conditions for which the subject piping is exposed during both normal and accident conditions. Additionally, if the inboard valve leaked (thereby pressurizing the subject piping) and a through-wall flaw did exist that could only be detected at the higher pressure, the flaw would be discovered during the Class 1 leakage test, which is performed during each refueling outage with the inboard valve closed.
A description of each piping segment subject to this request and the burdens associated with performing the Class 1 leakage test currently required by ASME Section Xi is provided below.
A. Decay Heat Removal Loop "A" Piping between Check Valves DH-14A. CF-1A, DH-13A and DH-18 The Decay Heat Removal Loop "A"piping and valves associated with this proposed alternative are shown in Figure 1.
The Class 2 function of the piping upstream of valve DH-14A is to provide a pathway to inject borated water from pressurized Core Flood Tank T-2A directly into the reactor vessel in the event of a loss of coolant accident (LOCA). This portion of piping between valves DH-14A, CF-1A, DH-13A and DH-18 is pressurized between 580 psig and 620 psig during normal plant operation.
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Performing a ten-year Class I system leakage test of extended RCPB piping of Decay Heat Removal Loop 'A" between check valves DH-14A, CF-IA, DH-13A, and DH-18 involves the following actions:
- 1. Erect scaffolding to access the valve nearest the reactor vessel;
- 2. Disassemble the valve and install a hydro plug;
- 3. Temporarily reassemble the valve;
- 4. Perform the system leakage test;
- 5. Disassemble the valve and remove the hydro plug;
- 6. Reassemble the valve; and
- 7. Remove the scaffolding.
The radiological dose rate in the general area of the associated piping and components is approximately 60 mrem/hr. Entergy estimates the identified actions require approximately 60 man-hours to complete resulting in a radiological exposure of approximately 3.6 man-Rem.
B. Decay Heat Removal Loop "B" Pining between Check Valves DH-14B. CF-I B.
DH-13B and DH-17 The Decay Heat Removal Loop "B' piping and valves associated with this proposed alternative are shown in Figure 2.
The Class 2 function of the piping upstream of valve DH-14B is to provide a pathway to inject borated water from pressurized Core Flood Tank T-2B directly into the reactor vessel in the event of a LOCA. The portion of piping between valve DH-14B and valves CF-1 B, DH-13B, and DH-17 is pressurized between 580 psig and 620 psig during normal plant operation.
Performing a ten-year Class 1 system leakage test of extended RCPB piping of Decay Heat Removal Loop "B" between check valves DH-14B, CF-1B, DH-13B, and DH-17 involves the same actions identified in Section IV.A, above, applied to Loop "B" piping and components. The radiological dose rate in the general area of the associated components is approximately 20 mrem/hr. Entergy estimates the identified actions require approximately 60 man-hours to complete resulting in a radiological exposure of approximately 1.2 man-Rem.
C. Pressurizer Auxiliary Sprav Piping between Check Valves DH-12 and DH-16 The Pressurizer Auxiliary Spray System piping and valves associated with this proposed alternative are shown in Figure 3.
The Class 2 function of the Pressurizer Auxiliary Spray piping is to provide a boron dilution flow path to the reactor core via the pressurizer hot leg. A non-safety function provides a method to cool down and depressurize the Reactor Coolant System (RCS) using the Decay Heat Removal Auxiliary Spray System during plant shutdown. Depressurization is performed at approximately 280 psig every refueling Page 3 of 7
outage. Pressurizer Auxiliary Spray is put into service to complete the RCS cooldown. While RCS is cooled down at pressures between 200 to 250 psi, the Pressurizer Auxiliary Spray line is put into service via the Decay Heat Removal System. With the Decay Heat Removal pump discharge pressure below 400 psi, Auxiliary Spray provides a continuous, small fluid volume to the reactor vessel for approximately 2 to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Therefore, this 5-inch, non-insulated portion of the line would see approximately 280 psi during the remaining cool-down period of 2 - 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
Performing a ten-year Class 1 system leakage test of extended RCPB piping of the Pressurizer Auxiliary Spray System piping between check valves DH-12 and DH-16 requires the same actions identified in Section IV.A, above, applied to the Pressurizer Auxiliary Spray piping and components. The section of piping between check valves DH-12 and DH-16 is 5 inches long and 1% inches in diameter. The radiological dose rate in the general area of these components is approximately 10 mrem/hr. Entergy estimates the identified actions require approximately 40 man-hours to complete resulting in a radiological exposure of approximately 0.4 man-Rem.
V. CONCLUSION 10 CFR 50.55a(a)(3) states:
"Proposed alternatives to the requirements of (c), (d), (e), (f), (g), and (h) of this section or portions thereof may be used when authorized by the Director of the Office of Nuclear Reactor Regulation. The applicant shall demonstrate that:
(i) The proposed alternatives would provide an acceptable level of quality and safety, or (ii) Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety."
As discussed in Section IV above, to perform a Class 1 system leakage test of the subject piping will result in undue burden without a compensating increase in quality and safety. The proposed alternative to visually examine the extended RCPB between the first and second normally closed isolation valves that experience Class 2 pressure during the Class 2 system leakage test conducted in the current inspection period of the inspection interval provides adequate assurance of the pipe's leak tightness. Therefore, Entergy requests authorization to perform the requested alternative to the Code requirement pursuant to 10 CFR 50.55a(a)(3)(ii).
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Reactor Auxiliary Building I I Building I jt Low Pressure Injection Pump A DH-17 1- 1B DH114A DH-148 DH-13B _ ~ <
Low Pressure Injection Pump B Rx Coolant Pump A MU-34A Rx Fpressure Vessel NOTE: Test boundary shown in bold. >
High Pressure Injection Pumps FIGURE 1 DECAY HEAT REMOVAL SYSTEM LOOP "A" Page 5 of 7
Reactor Auxiliary Building Building NOTE: Test boundary shown in bold.
High Pressure Injedon Pumps FIGURE 2 DECAY HEAT REMOVAL SYSTEM LOOP "B" Page 6 of 7
Pressurizer I WFrom Decay Heat Removal System DH-12 DH-16 x
NOTE: Test boundary shown in bold.
p I d r--W Steam Steam Generator Generator A B Rx Pressure Vessel XI FIGURE 3 PRESSURIZER AUXILIARY SPRAY SYSTEM Page 7 of 7