Letter Sequence Request |
---|
|
|
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
[Table View] |
|
---|
Category:Letter
MONTHYEARIR 05000368/20253012024-09-0909 September 2024 Notification of NRC Initial Operator Licensing Examination 05000368/2025301 ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification IR 05000313/20240112024-09-0505 September 2024 Comprehensive Engineering Team Inspection Report 05000313/2024011 and 05000368/2024011 IR 05000313/20244042024-08-29029 August 2024 Cybersecurity Inspection Report 05000313/2024404 and 05000368/2024404 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000313/20240052024-08-21021 August 2024 Updated Inspection Plan for Arkansas Nuclear One – Units 1 and 2 (Report 05000313/2024005, 05000368/2024005) ML24198A0722024-08-21021 August 2024 Correction to Issuance of Amendment No. 333 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML24185A1522024-08-13013 August 2024 Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 IR 05000313/20240022024-08-0606 August 2024 Integrated Inspection Report 05000313/2024002 and 05000368/2024002 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24101A1792024-06-25025 June 2024 Issuance of Amendment No. 333 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24143A0632024-05-22022 May 2024 Notification of Inspection (NRC Inspection Report 05000368/2024003) and Request for Information IR 05000313/20240012024-05-0808 May 2024 Integrated Inspection Report 05000313/2024001 and 05000368/2024001 ML24128A2472024-05-0808 May 2024 Project Manager Assignment ML24017A2982024-04-18018 April 2024 Summary of Regulatory Audit Regarding the License Amendment Request to Revise Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b ML24107A0282024-04-17017 April 2024 Notification of Comprehensive Engineering Team Inspection (05000313/2024011 and 05000368/2024011) and Request for Information IR 05000313/20243012024-04-16016 April 2024 NRC Examination Report 05000313/2024301 ML24086A5412024-04-10010 April 2024 Authorization of Request for Alternative ANO1-ISI-037 Regarding Extension of Reactor Vessel Inservice Inspection Interval IR 05000313/20244022024-04-0808 April 2024 Security Baseline Inspection Report 05000313/2024402 and 05000368/2024402 (Full Report) ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) ML24031A6442024-03-14014 March 2024 Issuance of Amendment No. 282 to Modify Technical Specification 3.3.1, Reactor Pressure System (RPS) Instrumentation, Turbine Trip Function on Low Control Oil Pressure ML24102A1342024-03-12012 March 2024 AN1-2024-03 Post Exam Submittal IR 05000313/20230062024-02-28028 February 2024 Annual Assessment Letter for Arkansas Nuclear One- Units 1 and 2 Report 05000313/2023006 and 05000368/2023006 IR 05000313/20230042024-02-0808 February 2024 Integrated Inspection Report 05000313/2023004 and 05000368/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023002 ML24012A0502024-02-0202 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0054 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23326A0392024-01-24024 January 2024 Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24017A1582024-01-17017 January 2024 Submittal of Emergency Plan Revision 50 IR 05000313/20234202024-01-10010 January 2024 Security Baseline Inspection Report 05000313/2023420 and 05000368/2023420 IR 05000313/20234022024-01-0202 January 2024 Security Baseline Inspection Report 05000313/2023402 and 05000368/2023402 ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23354A0022023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment IR 05000313/20234052023-12-12012 December 2023 – Security Baseline Inspection Report 05000313/2023405 and 05000368/2023405 ML23341A0832023-12-11011 December 2023 – Material Control and Accounting Program Inspection Report 05000313/368/2023404- Cover Letter ML23305A0922023-12-0707 December 2023 Summary of Regulatory Audit Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23275A2072023-11-28028 November 2023 Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation IR 05000313/20230032023-11-21021 November 2023 Revised - ANO Revised Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/ 2023001 ML23325A1412023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23243B0452023-11-13013 November 2023 Request for Withholding Information from Public Disclosure ML23313A0962023-11-13013 November 2023 Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023001 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000313/20230112023-10-10010 October 2023 Commercial Grade Dedication Inspection Report 05000313/2023011 and 05000368/2023011 IR 05000313/20230052023-08-21021 August 2023 Updated Inspection Plan for Arkansas Nuclear One, Units 1 and 2 (Report 05000313/2023005 and 05000368/2023005) - Mid Cycle IR 05000313/20230022023-08-11011 August 2023 Integrated Inspection Report 05000313/2023002 and 05000368/2023002 and Notice of Violation 2024-09-09
[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
[Table view] |
Text
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 Entergy Operations, Inc. 1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4704 Stephenie L. Pyle Manager, Licensing Arkansas Nuclear One 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-2500-1MRP-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 Applicability:
Arkansas Nuclear One, Unit 2 (ANO-2) / Fourth (4th) 10-Year 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 Oper ations, 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 Item Number Comp. ID Item Description Estimated % Coverage of Code Required Volume Examination Summary Scan Plan Exam Method and Limitations Search Units Surface Examination Exam Results R1.20 08-014 Reactor Coolant Pump (RCP) 2P-32B Suction Nozzle Elbow to Safe End (SE)
Circumferential Weld 60% Component was scanned from the elbow side only. 100% of the required axial coverage and 87.2% of the circumferential coverage was obtained excluding the SE cast stainless steel (SS) material. The circumferential scan was limited due to the cast SS and the component configuration. See the attached sketch (Figure 1)
derived from ultrasonic test (UT) examination report ISI-VE-09-039 on file at ANO.
Manual UT Phased Array
examination. Figure 1 depicts the component
configuration. Wave modalities are longitudinal and shear.
Insonification angles included 0°-80° flat L-wave; 25°-75° axial shear wave; and 0°-80° circumferential L-wave with +10° & -10° skew.
None required.
No indications were recorded.
R1.20 09-008 RCP 2P-32B Discharge Nozzle SE to Pipe Circumferential Weld 56% Component was scanned from the pipe side only. 100% of the required axial coverage and 73.8% of the circumferential coverage was obtained excluding the SE cast SS material.
The circumferential scan was limited due to the cast SS and the component configuration. See the attached sketch (Figure 2) derived from UT examination report ISI-VE-09-040 on file at ANO.
Manual UT Phased Array
examination. Figure 2 depicts the component
configuration. Wave modalities are longitudinal and shear.
Insonification angles included 0°-80° flat L-wave; 25°-75° axial shear wave; and 0°-80° circumferential L-wave with +10° & -10° skew.
None required.
No indications were recorded.
R1.20 10-014 RCP 2P-32A Suction Nozzle Elbow to SE Circumferential Weld 55% Component was scanned from the elbow side only. 100% of the required axial coverage and 84.1% of the circumferential coverage was obtained excluding the SE cast SS material. The circumferential scan was limited due to the cast SS and the component
configuration. See the attached sketch (Figure 3) derived from UT examination report ISI-VE-09-041 on file at ANO.
Manual UT Phased Array examination. Figure 3 depicts the component configuration. Wave modalities are longitudinal and shear.
Insonification angles included 0°-80° flat L-wave; 25°-75° axial shear wave; and 0°-80° circumferential L-wave with +10° & -10° skew.
None required.
No indications were recorded.
R1.20 11-008 RCP 2P-32A Discharge Nozzle SE to
Pipe Circumferential Weld 56.7% Component was scanned from the pipe side only. 100% of the required axial coverage and 76.3% of the circumferential coverage was obtained excluding the SE cast SS material. The circumferential scan was limited due to the cast SS and the component configuration. See the attached sketch (Figure 4) derived from UT examination report ISI-VE-09-042 on file at ANO.
Manual UT Phased Array examination. Figure 4 depicts the component configuration. Wave modalities are longitudinal and shear.
Insonification angles included 0°-80° flat L-wave; 25°-75° axial shear wave; and 0°-80° circumferential L-wave with +10° & -10° skew.
None required.
No indications were recorded.
Attachment to 2CAN111101
Page 4 of 12 Table 1 (cont') Limited R-A Examinations Component Description Additional Information Item Number Comp. ID Item Description Estimated % Coverage of Code Required Volume Examination Summary Scan Plan Exam Method and Limitations Search Units Surface Examination Exam Results R1.20 12-014 RCP 2P-32C Suction Nozzle Elbow to SE Circumferential Weld 56.3% Component was scanned from the elbow side only. 100% of the required axial coverage and 85.3% of the circumferential coverage was obtained excluding the SE cast SS material.
The circumferential scan was limited due to the cast SS and the component configuration. See the attached sketch (Figure 5) derived from UT examination report ISI-VE-09-043 on file at ANO.
Manual UT Phased Array
examination. Figure 5 depicts the component
configuration. Wave modalities are longitudinal and shear.
Insonification angles included 0°-80° flat L-wave; 25°-75° axial shear wave; and 0°-80° circumferential L-wave with +10° & -10° skew.
Surface examination not required.
No indications were recorded.
R1.20 13-008 RCP 2P-32C Discharge Nozzle SE to Pipe Circumferential Weld 60.1% Component was scanned from the pipe side only. 100% of the required axial coverage and 89.7% of the circumferential coverage was obtained excluding the SE cast SS material.
The circumferential scan was limited due to the cast SS and the component configuration. See the attached sketch (Figure 6) derived from UT examination report ISI-VE-09-044 on file at ANO.
Manual UT Phased Array
examination. Figure 6 depicts the component
configuration. Wave modalities are longitudinal and shear.
Insonification angles included 0°-80° flat L-wave; 25°-75° axial shear wave; and 0°-80° circumferential L-wave with +10° & -10° skew.
Surface examination not required.
No indications were recorded.
R1.20 14-014 RCP 2P-32D Suction Nozzle Elbow to SE Circumferential Weld 57.5% Component was scanned from the elbow side only. 100% of the required axial coverage and 87% of the circumferential coverage was obtained excluding the SE cast SS material.
The circumferential scan was limited due to the cast SS and the component configuration. See the attached sketch (Figure 7) derived from UT examination report ISI-VE-09-045 on file at ANO.
Manual UT Phased Array
examination. Figure 7 depicts the component
configuration. Wave modalities are longitudinal and shear.
Insonification angles included 0°-80° flat L-wave; 25°-75° axial shear wave; and 0°-80° circumferential L-wave with +10° & -10° skew.
Surface examination not required.
No indications were recorded.
R1.20 15-008 RCP 2P-32D Discharge Nozzle SE to
Pipe Circumferential Weld 62.8% Component was scanned from the pipe side only. 100% of the required axial coverage and 89.7% of the circumferential coverage was obtained excluding the SE cast SS material. The circumferential scan was limited due to the cast SS and the component configuration. See the attached sketch (Figure 8) derived from UT examination report ISI-VE-09-046 on file at ANO.
Manual UT Phased Array
examination. Figure 8 depicts the component configuration. Wave modalities are longitudinal and shear.
Insonification angles included 0°-80° flat L-wave; 25°-75° axial shear wave; and 0°-80° circumferential L-wave with +10° & -10° skew.
Surface examination not required.
No indications were recorded.
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