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MONTHYEAR2CAN111101, 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 Project stage: Request ML1200303682012-01-0303 January 2012 Acceptance Review Email, Relief Request ANO2-ISI-007, Alternative to Use ASME Code Case N-770-1 Baseline Examination, Fourth 10-Year Inservice Inspection Interval Project stage: Acceptance Review ML1205410892012-02-23023 February 2012 Email, Request for Additional Information, Request to Use of Alternate ASME Code Case N-770-1 Baseline Examination, Request for Alternative ANO2-ISI-007, Project stage: RAI 2CAN051202, Additional Information Related to Request for Alternative ANO2-ISI-007 Code Case N-770-1 Baseline Examination2012-05-21021 May 2012 Additional Information Related to Request for Alternative ANO2-ISI-007 Code Case N-770-1 Baseline Examination Project stage: Request ML12241A2962012-08-28028 August 2012 RAI for the Request to Use of Alternate ASME Code Case N-770-1 Baseline Examination, Request for Alternative ANO2-ISI-007 Project stage: RAI 2CAN091205, Response to Second Request for Additional Information, Request for Alternative ANO2-ISI-007 Code Case N-770-1 Baseline Examination2012-09-10010 September 2012 Response to Second Request for Additional Information, Request for Alternative ANO2-ISI-007 Code Case N-770-1 Baseline Examination Project stage: Request ML12306A2912012-11-0101 November 2012 Transmittal Email and WCAP-17128-NP, Revision 1, Flaw Evaluation of CE Design RCP Suction and Discharge Nozzle Dissimilar Metal Welds, Phase III Study, May 2010 Project stage: Other 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 Project stage: Other ML12314A0602012-12-11011 December 2012 Request for Withholding Information from Public Disclosure, Affidavit Dated 9/4/2012, Executed by Marcos Legaspi Herrera of Structural Integrity Associates, Inc. Re Second RAI Response Project stage: RAI ML12314A0492012-12-11011 December 2012 Request for Withholding Information from Public Disclosure, Affidavit Dated 8/16/12, Executed by J. Gresham of Westinghouse Electric Company LLC, Re CN-MRCDA-12-27 Project stage: Withholding Request Acceptance ML13113A2182013-04-23023 April 2013 Technical Letter Report, PNNL Evaluation and Modeling of Licensee'S Alternative for Volumetric Inspection of Dissimilar Metal Butt Welds at Arkansas Nuclear One Project stage: Other 2012-12-11
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Category:Letter type:
MONTHYEAR2CAN012401, U.S. Additional Protocol2024-01-17017 January 2024 U.S. Additional Protocol 2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42024-01-11011 January 2024 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN012401, Registration of Cask Use2024-01-10010 January 2024 Registration of Cask Use 1CAN122301, Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)2023-12-14014 December 2023 Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037) 2CAN112302, Submittal of Amendment 31 to Safety Analysis Report2023-11-16016 November 2023 Submittal of Amendment 31 to Safety Analysis Report 0CAN102303, Registration of Cask Use2023-10-24024 October 2023 Registration of Cask Use 0CAN102302, (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 32023-10-11011 October 2023 (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 3 0CAN102301, Evacuation Time Estimate (ETE) Study2023-10-0404 October 2023 Evacuation Time Estimate (ETE) Study 1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-09-21021 September 2023 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN092302, Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2023-09-14014 September 2023 Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 2CAN092301, Reply to a Notice of Violation2023-09-0808 September 2023 Reply to a Notice of Violation 0CAN092301, Emergency Plan Implementing Procedure Revision2023-09-0505 September 2023 Emergency Plan Implementing Procedure Revision 0CAN082301, Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 03412023-08-17017 August 2023 Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 0341 2CAN082301, Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29)2023-08-10010 August 2023 Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29) 0CAN072301, Registration of Cask Use2023-07-18018 July 2023 Registration of Cask Use 1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2023-06-29029 June 2023 Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 0CAN062301, Status of Actions to Return to Compliance2023-06-26026 June 2023 Status of Actions to Return to Compliance 0CAN062302, Submittal of Revision 22 of the ANO Fire Hazards Analysis2023-06-20020 June 2023 Submittal of Revision 22 of the ANO Fire Hazards Analysis 1CAN062301, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037)2023-06-0808 June 2023 Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037) 0CAN052303, Annual 10 CFR 50.46 Report for Calendar Year 20222023-05-24024 May 2023 Annual 10 CFR 50.46 Report for Calendar Year 2022 0CAN052302, Emergency Plan Rev. 482023-05-11011 May 2023 Emergency Plan Rev. 48 0CAN052301, Units 1 and 2 - Annual Radiological Environmental Operating Report for 20222023-05-0909 May 2023 Units 1 and 2 - Annual Radiological Environmental Operating Report for 2022 2CAN052301, Cycle 30 Core Operating Limits Report (COLR)2023-05-0303 May 2023 Cycle 30 Core Operating Limits Report (COLR) 0CAN042302, Annual Occupational Radiation Exposure Report for 20222023-04-27027 April 2023 Annual Occupational Radiation Exposure Report for 2022 0CAN042301, Radioactive Effluent Release Report for 20222023-04-14014 April 2023 Radioactive Effluent Release Report for 2022 2CAN042301, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-04-0505 April 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure2023-03-30030 March 2023 License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure 2CAN032303, Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032304, Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032305, 03 Post Examination Analysis2023-03-23023 March 2023 03 Post Examination Analysis 1CAN032302, Inspection Summary Report for the Thirtieth Refueling Outage (1R30)2023-03-20020 March 2023 Inspection Summary Report for the Thirtieth Refueling Outage (1R30) 1CAN012301, Responses to Request for Additional Information for Request for Relief ANO1-ISI-0352023-01-30030 January 2023 Responses to Request for Additional Information for Request for Relief ANO1-ISI-035 2CAN012303, U.S. Additional Protocol2023-01-23023 January 2023 U.S. Additional Protocol 2CAN012302, Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-01-20020 January 2023 Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 1CAN122201, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42022-12-22022 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN122202, Registration of Cask Use2022-12-21021 December 2022 Registration of Cask Use 0CAN122201, Reply to a Notice of Violation; EA-22-0992022-12-0808 December 2022 Reply to a Notice of Violation; EA-22-099 0CAN112201, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2022-11-10010 November 2022 Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2022-10-31031 October 2022 Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 1CAN102203, Cycle 31 Core Operating Limits Report2022-10-24024 October 2022 Cycle 31 Core Operating Limits Report 1CAN102201, Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-10-13013 October 2022 Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 0CAN092201, Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-09-29029 September 2022 Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN092201, Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-09-0808 September 2022 Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 0CAN082201, License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-08-30030 August 2022 License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN082201, Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-08-24024 August 2022 Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 2CAN072201, Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-07-20020 July 2022 Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods 0CAN072201, Registration of Cask Use2022-07-14014 July 2022 Registration of Cask Use 0CAN062202, Registration of Cask Use2022-06-0909 June 2022 Registration of Cask Use 1CAN062201, Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-06-0202 June 2022 Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 1CAN052201, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-0352022-05-31031 May 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-035 2024-01-17
[Table view] 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) 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 ML21293A0962021-10-28028 October 2021 Relief ANO2-R&R-012 Concerning Proposed Alternative for Repair of Reactor Vessel Closure Head Penetration 46 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
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Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4704 Stephenie L. Pyle Manager, Licensing Arkansas Nuclear One 2CAN111101 November 30, 2011 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Use of Alternate ASME Code Case N-770-1 Baseline Examination Request for Alternative ANO2-ISI-007 Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6
Dear Sir or Madam:
Pursuant to 10 CFR 50.55a(a)(3)(ii), Entergy Operations, Inc. (Entergy) hereby requests NRC approval of the attached Inservice Inspection (ISI) Request for Alternative for Arkansas Nuclear One, Unit 2 (ANO-2). This alternative is for the current fourth 10-year ISI interval.
The request is associated with the use of an alternative to the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Code Case N-770-1 as conditioned in the Final Rule 10 CFR 50.55a(g)(6)(ii)(F)(3), dated June 21, 2011.
To support the next ANO-2 refueling outage in the Fall of 2012, Entergy requests approval of this alternative by September 1, 2012.
This request does not contain any regulatory commitments.
If you have any questions or require additional information, please contact me.
Sincerely, Original signed by Stephenie L. Pyle SLP/rwc
Attachment:
Request for Alternative ANO2-ISI-007
2CAN111101 Page 2 of 2 cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam MS O-8B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852
Attachment to 2CAN111101 Request for Alternative ANO2-ISI-007
Attachment to 2CAN111101 Page 1 of 12 REQUEST FOR RELIEF ANO2-ISI-007 Components / Numbers: See Table 1 Code Classes: American Society of Mechanical Engineers (ASME) Code Class 1
References:
ANO Unit 1 Risk Informed (RI) Inservice Inspection Program (based in part on ASME Code Case N-716)
ASME Section XI 2001 Edition w/ 2003 Addenda, Table IWB-2500-1 MRP-139, Revision 1 10 CFR 50.55a ASME Code Case N-460 ASME Code Case N-770-1 Examination Category: R-A Item Number(s) R1.20
==
Description:==
Pressure Retaining Welds in Piping - Inspection Program B Unit / Inspection Interval Arkansas Nuclear One, Unit 2 (ANO-2) / Fourth (4th) 10-Year Applicability: Interval I. CODE REQUIREMENTS ASME Section XI, Table IWB-2500-1, Examination Category B-J, Pressure Retaining Welds in Piping - Inspection Program B:
- 1) Item B9.11, as allowed by the RI process, requires a volumetric examination of circumferential piping welds NPS 4 or larger, as depicted in Figures IWB-2500-8 and Risk-Informed Inservice Inspection Evaluation Procedure, EPRI Report No. TR-106706, Interim Report, June 1996.
MRP-139, Revision 1, Table 6-1 requires a volumetric examination of 100% of Category E non-resistant material, non-mitigated cold leg dissimilar metal welds on a 6-year frequency.
ASME Code Case N-460 allows a reduction in coverage due to interference or geometry as long as the overall coverage is greater than 90%.
ASME Code Case N-770-1 requires a baseline examination of all Inspection Item B welds, as defined in Table 1 of the Code Case, by the end of the next refuel outage after January 20, 2012. Previous examinations of these welds can be credited for baseline examinations if they were performed within the re-inspection period for the weld item in Table 1 using Section XI, Appendix VII requirements and met the Code required examination volume of essentially 100 percent. Other previous examinations that do not meet these requirements can be used to meet the baseline examination requirement, provided NRC approval of alternative inspection requirements in accordance with paragraphs 10 CFR 50.55a(a)(3)(i) or (a)(3)(ii) is granted prior to the end of the next refuel outage after January 20, 2012.
Attachment to 2CAN111101 Page 2 of 12 II. RELIEF REQUEST Pursuant to 10 CFR 50.55a(a)(3)(ii), Entergy Operations, Inc. (Entergy) requests relief from achieving the Code-required coverage when performing volumetric examinations of the components identified in Table 1. Note that the estimated percent coverage of Code Required Volume was obtained by utilizing previous examination data on file at ANO.
III. BASIS FOR RELIEF During past ultrasonic examination of the piping welds listed in Table 1, greater than 90%
coverage of the required examination volume could not be obtained.
Class 1 piping and components are often designed with welded joints and materials which can physically and/or metallurgically obstruct portions of the required examination volume. For examinations performed after the 10 CFR 50.55a mandatory implementation date for Appendix VIII of ASME Code Section XI, Code coverage percentages, provided in Table 1, reflect what is currently allowed by qualified Appendix VIII techniques. Appendix VIII qualified (PDI) procedures have demonstrated that sound beams may potentially be attenuated and distorted when required to pass through austenitic weld metal. Still, the PDI qualified methods employ the best available technology for maximizing examination coverage of these types of welds. Examination was extended to the far side of the weld to the extent permitted by geometry and material composition, but this portion (cast stainless steel) of the examination is not included in the reported coverage for welds examined under PDI and Appendix VIII rules.
Entergy has used the best available and EPRI approved techniques to examine the subject piping welds. To improve upon these examination coverage percentages, modification and/or replacement of the component would be required. Consistent with the ASME Section XI sampling approach, examination of the subject welds is adequate to detect generic degradation, if it existed, therefore demonstrating an acceptable level of integrity.
IV. PROPOSED ALTERNATIVE EXAMINATIONS Entergy has examined the subject items to the extent practical.
V. 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.
Entergy believes that it is impractical to obtain greater examination coverage on these areas.
To obtain additional coverage would necessitate modification and/or replacement of the component. The examinations performed on the subject areas would detect generic degradation, if it existed, therefore demonstrating an acceptable level of integrity. Therefore, Entergy requests the proposed alternative be authorized pursuant to 10 CFR 50.55a(a)(3)(ii).
Attachment to 2CAN111101 Page 3 of 12 Table 1 Limited R-A Examinations Component Description Additional Information Estimated %
Item Comp. Item Coverage of Exam Method Surface Exam Examination Summary Scan Plan Search Units Number ID Description Code Required and Limitations Examination Results Volume R1.20 08-014 Reactor Coolant 60% Component was scanned from the See the attached Manual UT Wave modalities are None No Pump (RCP) 2P- elbow side only. 100% of the required sketch (Figure 1) Phased Array longitudinal and shear. required. indications 32B Suction axial coverage and 87.2% of the derived from examination. Insonification angles were Nozzle Elbow to circumferential coverage was obtained ultrasonic test (UT) Figure 1 depicts included 0°-80° flat recorded.
Safe End (SE) excluding the SE cast stainless steel examination report the component L-wave; 25°-75° axial Circumferential (SS) material. The circumferential ISI-VE-09-039 on configuration. shear wave; and 0°-80° Weld scan was limited due to the cast SS file at ANO. circumferential L-wave and the component configuration. with +10° & -10° skew.
R1.20 09-008 RCP 2P-32B 56% Component was scanned from the See the attached Manual UT Wave modalities are None No Discharge pipe side only. 100% of the required sketch (Figure 2) Phased Array longitudinal and shear. required. indications Nozzle SE to axial coverage and 73.8% of the derived from UT examination. Insonification angles were Pipe circumferential coverage was obtained examination report Figure 2 depicts included 0°-80° flat recorded.
Circumferential excluding the SE cast SS material. ISI-VE-09-040 on the component L-wave; 25°-75° axial Weld The circumferential scan was limited file at ANO. configuration. shear wave; and 0°-80° due to the cast SS and the component circumferential L-wave configuration. with +10° & -10° skew.
R1.20 10-014 RCP 2P-32A 55% Component was scanned from the See the attached Manual UT Wave modalities are None No Suction Nozzle elbow side only. 100% of the required sketch (Figure 3) Phased Array longitudinal and shear. required. indications Elbow to SE axial coverage and 84.1% of the derived from UT examination. Insonification angles were Circumferential circumferential coverage was obtained examination report Figure 3 depicts included 0°-80° flat recorded.
Weld excluding the SE cast SS material. ISI-VE-09-041 on the component L-wave; 25°-75° axial The circumferential scan was limited file at ANO. configuration. shear wave; and 0°-80° due to the cast SS and the component circumferential L-wave configuration. with +10° & -10° skew.
R1.20 11-008 RCP 2P-32A 56.7% Component was scanned from the See the attached Manual UT Wave modalities are None No Discharge pipe side only. 100% of the required sketch (Figure 4) Phased Array longitudinal and shear. required. indications Nozzle SE to axial coverage and 76.3% of the derived from UT examination. Insonification angles were Pipe circumferential coverage was obtained examination report Figure 4 depicts included 0°-80° flat recorded.
Circumferential excluding the SE cast SS material. ISI-VE-09-042 on the component L-wave; 25°-75° axial Weld The circumferential scan was limited file at ANO. configuration. shear wave; and 0°-80° due to the cast SS and the component circumferential L-wave configuration. with +10° & -10° skew.
Attachment to 2CAN111101 Page 4 of 12 Table 1 (cont)
Limited R-A Examinations Component Description Additional Information Estimated %
Item Comp. Item Coverage of Exam Method Surface Exam Examination Summary Scan Plan Search Units Number ID Description Code Required and Limitations Examination Results Volume R1.20 12-014 RCP 2P-32C 56.3% Component was scanned from the See the attached Manual UT Wave modalities are Surface No Suction Nozzle elbow side only. 100% of the required sketch (Figure 5) Phased Array longitudinal and shear. examination indications Elbow to SE axial coverage and 85.3% of the derived from UT examination. Insonification angles not required. were Circumferential circumferential coverage was obtained examination report Figure 5 depicts included 0°-80° flat recorded.
Weld excluding the SE cast SS material. ISI-VE-09-043 on the component L-wave; 25°-75° axial The circumferential scan was limited file at ANO. configuration. shear wave; and 0°-80° due to the cast SS and the component circumferential L-wave configuration. with +10° & -10° skew.
R1.20 13-008 RCP 2P-32C 60.1% Component was scanned from the See the attached Manual UT Wave modalities are Surface No Discharge pipe side only. 100% of the required sketch (Figure 6) Phased Array longitudinal and shear. examination indications Nozzle SE to axial coverage and 89.7% of the derived from UT examination. Insonification angles not required. were Pipe circumferential coverage was obtained examination report Figure 6 depicts included 0°-80° flat recorded.
Circumferential excluding the SE cast SS material. ISI-VE-09-044 on the component L-wave; 25°-75° axial Weld The circumferential scan was limited file at ANO. configuration. shear wave; and 0°-80° due to the cast SS and the component circumferential L-wave configuration. with +10° & -10° skew.
R1.20 14-014 RCP 2P-32D 57.5% Component was scanned from the See the attached Manual UT Wave modalities are Surface No Suction Nozzle elbow side only. 100% of the required sketch (Figure 7) Phased Array longitudinal and shear. examination indications Elbow to SE axial coverage and 87% of the derived from UT examination. Insonification angles not required. were Circumferential circumferential coverage was obtained examination report Figure 7 depicts included 0°-80° flat recorded.
Weld excluding the SE cast SS material. ISI-VE-09-045 on the component L-wave; 25°-75° axial The circumferential scan was limited file at ANO. configuration. shear wave; and 0°-80° due to the cast SS and the component circumferential L-wave configuration. with +10° & -10° skew.
R1.20 15-008 RCP 2P-32D 62.8% Component was scanned from the See the attached Manual UT Wave modalities are Surface No Discharge pipe side only. 100% of the required sketch (Figure 8) Phased Array longitudinal and shear. examination indications Nozzle SE to axial coverage and 89.7% of the derived from UT examination. Insonification angles not required. were Pipe circumferential coverage was obtained examination report Figure 8 depicts included 0°-80° flat recorded.
Circumferential excluding the SE cast SS material. ISI-VE-09-046 on the component L-wave; 25°-75° axial Weld The circumferential scan was limited file at ANO. configuration. shear wave; and 0°-80° due to the cast SS and the component circumferential L-wave configuration. with +10° & -10° skew.
Attachment to 2CAN111101 Page 5 of 12 Figure 1 Scan Plan and Coverage for ISI Component 08-014 Not to Scale Safe End Side (Cast Stainless)
Attachment to 2CAN111101 Page 6 of 12 Figure 2 Scan Plan and Coverage for ISI Component 09-008 Not to Scale
Attachment to 2CAN111101 Page 7 of 12 Figure 3 Scan Plan and Coverage for ISI Component 10-014 Not to Scale
Attachment to 2CAN111101 Page 8 of 12 Figure 4 Scan Plan and Coverage for ISI Component 11-008 Not to Scale
Attachment to 2CAN111101 Page 9 of 12 Figure 5 Scan Plan and Coverage for ISI Component 12-014 Not to Scale
Attachment to 2CAN111101 Page 10 of 12 Figure 6 Scan Plan and Coverage for ISI Component 13-008 Not to Scale
Attachment to 2CAN111101 Page 11 of 12 Figure 7 Scan Plan and Coverage for ISI Component 14-014 Not to Scale
Attachment to 2CAN111101 Page 12 of 12 Figure 8 Scan Plan and Coverage for ISI Component 15-008 Not to Scale