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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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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 - 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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 - 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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 2CAN051202 May 21, 2012 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Additional Information Related to Request for Alternative ANO2-ISI-007 Code Case N-770-1 Baseline Examination Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6
REFERENCES:
- 1. Entergy letter dated November 30, 2011, Use of Alternate ASME Code Case N-770-1 Baseline Examination Request for Alternative ANO2-ISI-007 (2CAN111101) (ML113340158)
- 2. NRC email dated February 23, 2012, RAI for the Request to use Alternate ASME Code Case N-770-1 Baseline Examination, Request for Alternative ANO2-ISI-007 (TAC No. ME7646) (ML120541089)
- 3. Entergy letter dated April 13, 2012, Response to the Request for Additional Information Regarding Request for Alternative ANO2-ISI-007 Code Case N-770-1 Baseline Examination (2CAN041202)
(ML12104A066)
Dear Sir or Madam:
Entergy Operations, Inc. requested NRC approval of a Request for Alternative for Arkansas Nuclear One, Unit 2 via Reference 1. 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.
In Reference 2, the NRC determined that additional information was needed to complete the review of Reference 1. Reference 3 provided the requested information. Subsequently, a conference call was held with the NRC on April 26, 2012, to discuss the responses provided in Reference 3 and to clarify a portion of the request in Reference 2. Based on this conference call, it was determined that additional information was required. The purpose of this submittal is to provide that information.
This submittal contains no regulatory commitments.
2CAN051202 Page 2 of 2 Should you have any questions, please contact me.
Sincerely, Original signed by Stephenie L. Pyle SLP/rwc
Attachment:
Additional Information Related to Request for Additional Information -
Use of ASME Code Case N-770-1 Baseline Examination cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 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-8 B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852
Attachment to 2CAN051202 Additional Information Related to Request for Alternative ANO2-ISI-007 Code Case N-770-1 Baseline Examination
Attachment to 2CAN051202 Page 1 of 10 ADDITIONAL INFORMATION RELATED TO REQUEST FOR ALTERNATIVE ANO2-ISI-007 CODE CASE N-770-1 BASELINE EXAMINATION The NRC request is provided below in bold, followed by the response to the request.
- 1. The response to Question 5 of the Request for Additional Information (RAI) response states that the coverage limitations are the result of irregular surfaces or tapered surfaces. The staff is concerned by the different coverage which would result from these geometries; intermittent lack of coverage due to irregular weld surfaces is significantly different than a continuous lack of coverage at the root which could result from a tapered weld surface. Please describe the reason for the lack of examination coverage for the susceptible material in each weld and, if due to weld taper, whether the root of the weld is being examined.
The examination coverage estimates reported at the time of the ultrasonic examinations indicated a combination of weld surface, joint taper, and cast stainless steel being limitations to coverage. The cast stainless steel portion of the limitation is somewhat quantified by the cross sectional profiles of the weld joint geometry and related thicknesses.
It should be noted that the scan coverage estimations do not factor in the probe skew of +/- 10 degrees. The probe skew decreases the extent of the actual limitation.
The limitation due to irregular weld surfaces or weld joint taper was not specifically quantified in the ultrasonic data. The estimated coverage provided considered the net effect of all limitations. However; the coverage estimates and scan plots were reviewed to estimate the volume of susceptible material and circumferential scan coverage of that volume. Table 1 provides the results of the review. The scan plot for each weld is provided after the table.
- 2. In Table 1 of the RAI response, the coverage in the circumferential direction is identical for the ferritic material and the susceptible material. Please describe how this is occurs.
The ultrasonic examination data sheets did not quantify the exact area or extent of the circumferential scan limitation. The estimated coverage number was applied to both the susceptible material and/or the ferritic material.
Each of the weld scan plots was reviewed and the susceptible volume estimated. The approximate scan lines were extrapolated and coverage estimates re-calculated for that area only, which is what appears in Table 1 of this submittal.
Attachment to 2CAN051202 Page 2 of 10 Table 1 Coverage Estimation and Limitations Component Lower 1/3 Upper 2/3 T Sketch Location of Circumferential Coverage Number Thickness (T) Circumferential Limitation of the Susceptible Material Volume Circumferential Scan Coverage %
Scan Coverage %
08-014 100 92 Limitation in upper 2/3 T inconel weld at cast austenitic stainless steel (CASS) bevel preparation area and at cap transition to elbow.09-008 55 64 Limitation to coverage appears to be concave area near center of weld cap indicating missed scan coverage is in the inconel weld, cap to root.10-014 14 73 Limitation appears to be from weld taper and indicates the majority of the limitation is in the inconel weld and adjacent butter region with no coverage of weld root area.11-008 62 73 Limitation to coverage appears to be convex area near center of weld cap indicating missed scan coverage is in the inconel weld, cap to root.12-014 50 86 Limitation appears to be from weld taper and indicates the majority of the limitation is in the inconel weld with little coverage of weld root area.13-008 87 85 Limitation to coverage appears to be convex area near the ferritic side of the weld cap indicating missed scan coverage is in the inconel weld with most of the lower 1/3 T examined to the root.14-014 87 96 Limitation is near the CASS bevel prep area, indicating missed scan coverage cap to root on the safe end side of the weld. Most of lower 1/3 T scanned.15-008 85 89 Limitation to coverage primarily appears to be convex area near center of weld cap indicating missed scan coverage is in the inconel weld, cap to root.
Attachment to 2CAN051202 Page 3 of 10 Arkansas Nuclear One Unit 2 Reactor Coolant Pump Suction Nozzle DMV DM Weld # 08-014 Legend Green = 2/3 T Coverage Yellow = 1/3 T Coverage Pink = No Coverage Safe End Side (Cast Stainless) Elbow Side
Attachment to 2CAN051202 Page 4 of 10 Arkansas Nuclear One Unit 2 Reactor Coolant Pump Suction Nozzle DMV DM Weld # 09-008 Legend Green = 2/3 T Coverage Yellow = 1/3 T Coverage Pink = No Coverage CAST STAINLESS STEEL PIPE
Attachment to 2CAN051202 Page 5 of 10 Arkansas Nuclear One Unit 2 Reactor Coolant Pump Suction Nozzle DMV DM Weld # 10-014 Legend Green = 2/3 T Coverage Yellow = 1/3 T Coverage Pink = No Coverage Safe End Side Elbow Side (Cast Stainless)
Attachment to 2CAN051202 Page 6 of 10 Arkansas Nuclear One Unit 2 Reactor Coolant Pump Suction Nozzle DMV DM Weld # 11-008 Legend Green = 2/3 T Coverage Yellow = 1/3 T Coverage Pink = No Coverage CAST STAINLESS STEEL PIPE
Attachment to 2CAN051202 Page 7 of 10 Arkansas Nuclear One Unit 2 Reactor Coolant Pump Suction Nozzle DMV DM Weld # 12-014 Legend Green = 2/3 T Coverage Yellow = 1/3 T Coverage Pink = No Coverage CAST STAINLESS Elbow Side STEEL
Attachment to 2CAN051202 Page 8 of 10 Arkansas Nuclear One Unit 2 Reactor Coolant Pump Discharge A Nozzle 13-008 / 2P-32C Circumferential Examination Volume Legend Green = 2/3 T Coverage Yellow = 1/3 T Coverage Pink = No Coverage PIPE CAST STAINLESS STEEL
Attachment to 2CAN051202 Page 9 of 10 Arkansas Nuclear One Unit 2 Reactor Coolant Pump Suction Nozzle DMV DM Weld # 14-014 Legend Green = 2/3 T Coverage Yellow = 1/3 T Coverage Pink = No Coverage Safe End Side Elbow Side (Cast Stainless)
Attachment to 2CAN051202 Page 10 of 10 Arkansas Nuclear One Unit 2 Reactor Coolant Pump Suction Nozzle DMV DM Weld # 15-008 Legend Green = 2/3 T Coverage Yellow = 1/3 T Coverage Pink = No Coverage CAST STAINLESS STEEL PIPE