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Category:Drawing
MONTHYEAR2CAN011502, Response to Request for Additional Information Concerning the Spring 2014 Steam Generator Inspections2015-01-12012 January 2015 Response to Request for Additional Information Concerning the Spring 2014 Steam Generator Inspections 2CAN121206, Clarification on Initial Flaw Size and Qualified Examination Area, Revised Request for Alternative ANO2-ISI-007 Code Case N-770-1 Baseline Examination2012-12-17017 December 2012 Clarification on Initial Flaw Size and Qualified Examination Area, Revised Request for Alternative ANO2-ISI-007 Code Case N-770-1 Baseline Examination 1CAN041105, Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05 Relief Request ANO1-R&R-0162011-04-20020 April 2011 Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05 Relief Request ANO1-R&R-016 2CAN070807, Transmittal of Request for Alternative ANO2-PT-001 Visual Examination of Extended Reactor Coolant Pressure Boundary Piping During System Leakage Tests2008-07-31031 July 2008 Transmittal of Request for Alternative ANO2-PT-001 Visual Examination of Extended Reactor Coolant Pressure Boundary Piping During System Leakage Tests ML0407702742004-01-0808 January 2004 Draft Information Input E-Mail Dated 01/08/04 Poison Insert Sketches - Attachment 1 ML0332203102003-10-15015 October 2003 Figure 2-3, ANO Exclusion Zone and Features ML0332202982003-10-15015 October 2003 Figure 3-2, ANO 2 Transmission Line ML0329000452003-09-26026 September 2003 Drawing LRA-M-2231, Rev 0, Piping & Instrument Diagram Chemical & Volume Control System. Sheet 2 ML0329000472003-09-26026 September 2003 Drawing LRA-M-2232, Rev 0, Piping & Instrument Diagram Safety Injection System. Sheet 1 ML0329000602003-09-26026 September 2003 Drawing LRA-M-2238, Rev 0, Piping & Instrument Diagram Reactor Coolant Pump Connections. Sheet 1 ML0329000712003-09-25025 September 2003 Drawing LRA-M-2241, Rev 0, Piping & Instrument Diagram Aac Generator System Starting Air & Service Air Subsystems. Sheet 4 ML0329000692003-09-25025 September 2003 Drawing LRA-M-2241, Rev 0, Piping & Instrument Diagram Aac Generator System Fuel Oil Subsystem. Sheet 3 ML0329000722003-09-25025 September 2003 Drawing LRA-M-2241, Rev 0, Piping & Instrument Diagram Aac Generator System Lube Oil System. Sheet 5 ML0329000672003-09-25025 September 2003 Drawing LRA-M-2241, Rev 0, Piping & Instrument Diagram Aac Generator System Air Intake & Exhaust Subsystem. Sheet 2 ML0329000642003-09-25025 September 2003 Drawing LRA-M-2241, Rev 0, Piping & Instrument Diagram Aac Generator System Engine Cooling Water Subsystem. Sheet 1 ML0329000412003-09-25025 September 2003 Drawing LRA-M-2230, Rev 0, Piping & Instrument Diagram Reactor Coolant System. Sheet 2 ML0329000382003-09-25025 September 2003 Drawing LRA-M-2230, Rev 0, Piping & Instrument Diagram Reactor Coolant System. Sheet 1 ML0329000962003-09-25025 September 2003 Drawing LRA-M-2260, Rev 0, Piping & Instrument Diagram Aac Generator Building Heating, Ventilation & Air Condition Subsystem. Sheet 4 ML0329001102003-09-25025 September 2003 Drawing LRA-M-2263, Rev 0, Piping & Instrument Diagram Units 1 & 2 Control & Computer Rooms Hvac. Sheet 1 ML0329000732003-09-23023 September 2003 Drawing LRA-M-2260, Rev 0, Piping & Instrument Diagram Air Flow Diagram Heating, Ventilating & Air Conditioning Turbine Bldg. & Misc. Area. Sheet 1 ML0329000332003-09-23023 September 2003 Drawing LRA-M-2220, Rev 0, Piping & Instrument Diagram Plant Heating System. Sheet 1 ML0329000362003-09-23023 September 2003 Drawing LRA-M-2221, Rev 0, Piping & Instrument Diagram Control & Computer Room Emerg. HVAC Freon System. Sheet 2 ML0329000372003-09-23023 September 2003 Drawing LRA-M-2222, Rev 0, Piping & Instrument Diagram Chilled Water System Containment, Turbine & Aux. Bldgs. Sheet 1 ML0329001152003-09-23023 September 2003 Drawing LRA-M-2263, Rev 0, Piping & Instrument Diagram Air Flow Diagram HVAC Aux. Bldg. - Misc Rooms. Sheet 6 ML0329000442003-09-23023 September 2003 Drawing LRA-M-2231, Rev 0, Piping & Instrument Diagram Chemical & Volume Control System. Sheet 1 ML0329001142003-09-23023 September 2003 Drawing LRA-M-2263, Rev 0, Piping & Instrument Diagram Air Flow & Control Diagram Heating, Ventilating, Air Cond. Aux, Bldg. Office/CA-2 Area. Sheet 5 ML0329001082003-09-23023 September 2003 Drawing LRA-M-2262, Rev 0, Piping & Instrument Diagram Air Flow Diagram Heating Ventilating Air Conditioning Aux, Bldg. Radwaste Area. Sheet 2 ML0329000482003-09-23023 September 2003 Drawing LRA-M-2233, Rev 0, Piping & Instrument Diagram Reactor Coolant Pump Oil Collection System. Sheet 1 ML0329000512003-09-23023 September 2003 Drawing LRA-M-2234, Rev 0, Piping & Instrument Diagram Component Cooling Water System. Sheet 1 ML0329000532003-09-23023 September 2003 Drawing LRA-M-2235, Rev 0, Piping & Instrument Diagram Fuel Pool System. Sheet 1 ML0329000552003-09-23023 September 2003 Drawing LRA-M-2236, Rev 0, Piping & Instrument Diagram Containment Spray System. Sheet 1 ML0329000562003-09-23023 September 2003 Drawing LRA-M-2237, Rev 0, Piping & Instrument Diagram Sampling System. Sheet 1 ML0329001052003-09-23023 September 2003 Drawing LRA-M-2262, Rev 0, Piping & Instrument Diagram Heating, Ventilating & Air Conditioning Aux, Bldg. - Radwaste Area. Sheet 1 of 3 ML0329000612003-09-23023 September 2003 Drawing LRA-M-2239, Rev 0, Piping & Instrument Diagram Nitrogen Addition System. Sheet 1 ML0329000632003-09-23023 September 2003 Drawing M-2239, Rev 0, Piping & Instrument Diagram Electrical Penetration Nitrogen Pressurization System. Sheet 2 ML0329001022003-09-23023 September 2003 Drawing LRA-M-2261, Rev 0, Piping & Instrument Diagram Air Flow & Control Diagram Heating, Ventilating & Air Cond. Containment Building. Sheet 4 ML0329001012003-09-23023 September 2003 Drawing LRA-M-2261, Rev 0, Air Flow & Control Diagram HVAC Post Accident Hydrogen Analysis System. Sheet 3 ML0329001002003-09-23023 September 2003 Drawing LRA-M-2261, Rev 0, Flow & Control Diagram Heating, Ventilation & Air Conditioning Containment Building. Sheet 2 ML0329000982003-09-23023 September 2003 Drawing LRA-M-2261, Rev 0, Piping & Instrument Diagram Air Flow & Control Diagram Heating, Ventilating & Air Cond. Containment Building. Sheet 1 ML0211401212002-03-26026 March 2002 Attachment 8, Faxed on March 26, 2002 (Docket No. 50-368) 2015-01-12
[Table view] Category:Graphics incl Charts and Tables
MONTHYEAR2CAN012401, U.S. Additional Protocol2024-01-17017 January 2024 U.S. Additional Protocol ML22259A1222022-09-0808 September 2022 ANO Service Water KM Version ML21354A7552021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 10 of 18 CNRO-2018-00011, Submittal of Joint Plant Access Shared Information Table2018-03-19019 March 2018 Submittal of Joint Plant Access Shared Information Table ML17150A2562017-06-0505 June 2017 Entergy Fleet - 2017 Onsite Insurance Submittal Review for Entergy Operations, Inc., and Entergy Nuclear Operations, Inc. (CAC No. TM3058) ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports 2CAN011502, Response to Request for Additional Information Concerning the Spring 2014 Steam Generator Inspections2015-01-12012 January 2015 Response to Request for Additional Information Concerning the Spring 2014 Steam Generator Inspections ML13133A1382013-05-10010 May 2013 One, Unit 1, ANO1 Steam Generator Tube Inspection Discussion Points, Preventative Tube Plugging and Proximity Calls ML13133A1362013-05-10010 May 2013 One, Unit 1, ANO1 Steam Generator Tube Inspection Discussion Points, Preventative Tube to Plug and Proximity Calls 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 ML1019004182010-06-28028 June 2010 Quick View Chart 0CAN061001, Annual 10 CFR 50.46 Report for Calendar Year 2009 Emergency Core Cooling System Evaluation Changes2010-06-0303 June 2010 Annual 10 CFR 50.46 Report for Calendar Year 2009 Emergency Core Cooling System Evaluation Changes 2CAN070807, Transmittal of Request for Alternative ANO2-PT-001 Visual Examination of Extended Reactor Coolant Pressure Boundary Piping During System Leakage Tests2008-07-31031 July 2008 Transmittal of Request for Alternative ANO2-PT-001 Visual Examination of Extended Reactor Coolant Pressure Boundary Piping During System Leakage Tests 1CAN070801, Transmittal of Analysis of Proposed Technical Specification Change Sodium Hydroxide Tank Concentration2008-07-30030 July 2008 Transmittal of Analysis of Proposed Technical Specification Change Sodium Hydroxide Tank Concentration ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0710002572007-03-26026 March 2007 Attachment 5 - HI-2063601, Holtec Licensing Report for ANO Unit 2 Partial Rerack, (non-propriety) ML0519603252005-07-15015 July 2005 Attachment 3 - Recommendation and Action Item Cross Reference Table 2005-025 ML0427205342004-09-28028 September 2004 Tables to ANO-2 Amendment on Administrative Controls (Amendment No. 255) ML0426101132004-09-13013 September 2004 Plant Engineering Branch Open Items Interim Safety Basis (URI 2002003-01) ML0414101322004-04-27027 April 2004 E-mail Dated 04/27/04 ANO 1 Slides for NRC Conference Call on 04/27/04 ML0406407512004-02-20020 February 2004 Attachment 3: List of Components in Fire Zones 98J and 99M ML0406407502004-02-20020 February 2004 Equip/Cable/Reel#/Cable Type/Po#/Insulation/Material/Type ML0230501762002-09-17017 September 2002 Attachment 13, ANO-1, Units 1 and 2, Table B-1, Minimum Staffing Requirements ML0230501692002-09-16016 September 2002 Attachment 12, ANO-1, Units 1 and 2, Table B-1, Minimum Staffing Requirements 2024-01-17
[Table view] 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] |
Text
SEnterg Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4704 Stephenie L. Pyle Manager, Regulatory Assurance Arkansas Nuclear One 2CAN01 1502 January 12, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Response to Request for Additional Information Concerning the Spring 2014 Steam Generator Inspections Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6
REFERENCES:
- 1. Entergy letter to NRC, "Steam Generator Tube Inspection Report -
2R23," dated August 18, 2014 (2CAN081404) (ML14230A898)
- 2. Email from Andrea George (NRC) to David B. Bice (Entergy),
"Request for Additional Information for Spring 2014 Steam Generator Tube Inspection Report for ANO, Unit 2 (MF4653)," dated November 19, 2014 (ML14323A206)
Dear Sir or Madam:
Entergy Operations, Inc. (Entergy) inspected the Arkansas Nuclear One, Unit 2 (ANO-2) steam generator tubes during the Spring 2014 refueling outage (2R23) in accordance with ANO-2 Technical Specification (TS) 6.5.9. ANO-2 TS 6.6.7 requires a written report of the results of the inspection be submitted to the NRC. Reference 1 provided the required report.
In the course of the NRC's review of the report, it was determined that additional information was required to complete the evaluation. The purpose of this submittal is to provide the information that was requested in Reference 2 (see Attachment 1).
This correspondence contains one new commitment. This commitment is summarized in .
Aool
2CAN01 1502 Page 2 of 2 Should you have any questions regarding this submittal, please contact me.
Sincerely, 4(/
SLP/rwc Attachments: 1. Responses to Request for Additional Information Concerning the Spring 2014 Steam Generator Inspections
- 2. Regulatory Commitments cc: Mr. Marc L. Dapas 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. 0. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Ms. Andrea E. George MS O-8B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852
ATTACHMENT I TO 2CAN01 1502 RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION CONCERNING THE SPRING 2014 STEAM GENERATOR INSPECTIONS to 2CAN01 1502 Page 1 of 8 RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION CONCERNING THE SPRING 2014 STEAM GENERATOR INSPECTIONS By letter dated August 18, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14230A898), Entergy Operations, Inc. (Entergy, the licensee) submitted information summarizing the results of the Spring 2014 steam generator tube inspections performed at Arkansas Nuclear One, Unit 2. These inspections were performed during refueling outage 23 (RFO 23). In a letter dated June 23, 2014 (ADAMS Accession No. ML14170A060), the U.S. Nuclear Regulatory Commission (NRC) staff summarized a conference call that was held with the licensee during RFO 23.
In order to complete the review, the NRC staff requests responses to the follow questions:
ESGB-RAI-1 The "Cycle Effective Full Power Year (EFPY)" and "Cumulative SG EFPY" columns in Table 1-1 agree with each other up until outage "2R20." Please confirm the values for EFPY in these columns.
RESPONSE
The cumulative value following refueling outage 2R20 was listed as 8.62 which was a transcription error. The actual value should have been 8.26 or a difference of 0.36 EFPY. This was carried through the rest of the values through 2R23. See Table 1 below:
Table 1 ANO-2 Operating Cycles since SG Replacement Outage Year Cycle EFPY Cumulative Notes EFPY 2R14 2000 0 0 Baseline (PSI) 2R15 2002 1.35 1.35 ist ISI 2R16 2003 1.35 2.7 Skip 2R17 2005 1.36 4.06 54% Bobbin 2R18 2006 1.43 5.49 Skip 2R19 2008 1.35 6.84 Skip 2R20 2009 1.42 8.62 100% Bobbin 2R21 2011 1.40 10.02 Skip 2R22 2012 1.43 11.45 Skip 2R23 2014 1.39 12.84 100% Bobbin 6.84 + 1.42 = 8.26 to 2CAN01 1502 Page 2 of 8 All the EFPYs were reviewed as part of developing this response. Previously some of the values were projected values versus actual values for the outages. The table has been updated with the actual values. A corrected table with additional data is provided below (Table 2):
Table 2 ANO-2 Operating Cycles since SG Replacement Outage Year Cycle EFPD EFPY Cumulative Notes 2000 14 517.004 1.42 0.00 Baseline 2R14 (PSI) 2R15 2002 15 471.493 1.29 1.29 1st ISI 2R16 2003 16 492.902 1.35 2.64 Skip 54%
17 495.698 1.36 4.00 Bbi 2R17 2005 Bobbin 2R18 2006 18 522.796 1.43 5.43 Skip 2R19 2008 19 489.419 1.34 6.77 Skip 100%
2R20 2009 20 495.707 1.36 8.13 Bobbin 2R21 2011 21 493.944 1.35 9.48 Skip 2R22 2012 22 528.071 1.45 10.93 Skip 100%
2R23 2014 23 498.19 1.36 12.30 100%
Bobbin 2R24 2015 24 452 PROJECTED 1.24 13.53 Skip EFPD = Effective Full Power Days EFPY = Effective Full Power Years ESGB-RAI-2 The NRC staff notes that in Tables 3.6.1 and 3.6.2 of the letter dated August 18, 2014, the
"% Plugged" columns appear to be incorrect based on the number of tubes plugged in each SG. Please clarify.
RESPONSE
In the originally submitted % Plugged column, the numerical values represented did not increase the values by 100 necessary to achieve a "percent". Therefore, ifthe values are multiplied by 100, true percent values can be obtained. There are 10637 tubes per generator.
A corrected table is listed below:
to 2CAN01 1502 Page 3 of 8 Table 3 Cumulative Plugs in Service in SG A YEAR OUTAGE INSTALLED CUMULATIVE % PLUGGED 2000 Fabrication 0 0 0 2000 Baseline 0 0 0 2002 2R15 0 0 0 2005 2R17 4 4 0.04 2009 2R20 1 5 0.05 2014 2R23 5 10 0.09 Table 4 Cumulative Plugs in Service in SG B YEAR OUTAGE INSTALLED CUMULATIVE % PLUGGED 2000 Fabrication 1 1 0.009 2000 Baseline 0 1 0.009 2002 2R15 0 1 0.009 2005 2R17 7 8 0.08 2009 2R20 5 13 0.12 2014 2R23 5 18 0.17 ESGB-RAI-3 In the teleconference summary dated June 23, 2014, the NRC staff noted that "an evaluation of blockage of the top support plate will be done as part of the eddy current auto-analysis that is verifying the position of the AVBs [anti-vibration bars]." Please discuss the results of the position verification of the AVBs and the evaluation of the blockage of the top support plate.
RESPONSE
This analysis was being performed post outage utilizing the 2R23 eddy current data. The AVB design of the Westinghouse Delta 109 is complex and has resulted in difficulties in pinpointing the exact locations since there are changes in configuration within the individual AVBs by design. Therefore, the evaluation is not yet complete.
to 2CAN01 1502 Page 4 of 8 The original intent of the sludge buildup at the top tube support plate analysis was to evaluate the operating experience by the French where a tube locked into place due to excessive sludge build up and eventually severed due to fatigue. It was not anticipated that this would be the case for ANO-2 due to differences in the designs. This will be a qualitative assessment to determine if there is an excessive buildup of deposits. ANO-2 has operated 14 calendar years since the steam generators were replaced. The analysis will be of individual locations on the top support plate to determine the deposit at the top, bottom and center of the intersections.
Entergy will provide the information for both the AVB positioning and sludge evaluation within 45 days of Entergy's receipt of the AREVA report. Currently it is estimated that Entergy will have received the report from AREVA prior to mid-February 2015.
ESGB-RAI-4 Please discuss the results of the primary side channel head inspections and the tube plug inspections.
RESPONSE
Visual inspections of the primary side cladding and previously installed plugs were performed in 2R23. All four channel heads were included in the inspection. There were no irregularities identified in the cladding inspection or any issues identified in the previously installed plugs.
ESGB-RAI-5 Please provide a tubesheet map so the NRC staff can better understand the locations of the indications. In addition, please provide the thickness of the tubesheet with and without cladding.
RESPONSE
Please refer to the ANO-2 tubesheet map included in this letter. The tubesheet is a forged carbon steel plate with cladding installed on the primary side.
Tubesheet thickness without the clad 31.13 inches Tubesheet cladding thickness 0.43 inches Tubesheet thickness with clad 31.56 inches to 2CAN01 1502 Page 5 of 8 ESGB-RAI-6 In Section 3.2 of the letter dated August 18, 2014, a number of dents were reported. It was indicated that these dents were present in the preservice inspection. Please discuss whether these dents have been increasing in size (voltage). Please discuss whether these dents are service-induced or have been present since the preservice inspection. If service-induced, please discuss the cause.
RESPONSE
Dents (DNT) were reported with the bobbin coil examination at 1128 locations in 319 tubes.
The criteria for reporting DNTs are > 2.00 volts on Channel P1 (630 / 150 kHz differential mix) in the free span and at structures. All DNT signals have been compared with historical data and exhibited no change in signal formation, voltage, and/or phase.
The dents were fabrication induced due to elevated temperatures during post-weld heat treatment. There are no service induced dents identified to date.
ESGB-RAI-7 A number of possible loose part (PLP) indications were reported in both steam generators. In steam generator B, three parts were removed, reducing the number of PLP indications to one. Please discuss whether visual inspections were performed at all PLP locations. If visual inspections were performed, please discuss the results of these inspections. If any loose parts were left in the steam generators, please discuss the results of any assessments performed on the effect these parts may have on tube integrity.
RESPONSE
A Foreign Object Search and Retrieval (FOSAR) activity was performed to confirm / retrieve any potential objects identified by eddy current testing. Eddy current inspections identified PLP indications affecting 15 tubes in SGA and affecting 17 tubes in SGB; however, no wear was associated with any of the affected tube locations. Visual inspections were performed and all foreign material was either retrieved or determined to be acceptable as-is (unretrieved).
Refer to Table 8-1 (from operational assessment) of this letter, which summarizes the assessment of PLP indications and foreign objects identified during 2R23.
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p E At Drawing #: 02-6004834-E-003 DCN :121-9224603-000 S/G A TOTAL TUBES: 10637 COLD SELECTED TUBES: 10 PRIMARY FACE OUT OF SERVICE (#): 10 Manway 04 A',ý 20 40 30 -.
- 0 10 10 20 30 40 50 60 70 00 90 100 110 120 130 140 10 160 170 180 to 2CAN011502 Page 7 of 8 Table 8-1: ANO 2R23 PLP and FOSAR Summary 2R23 PLP Indications SG Row-Col. Location History 2R23 SSI Results Loose Part Wear Assessment SSI identified sludge rock at tubes 4-89, No wear identified by ECT and object not a threat 5-88, and 6-89 CL and left as-is. to tube integrity.
5-88 TSC +0.17 New PLP in 2R23 See tube R4-C89 above. See tube R4-C89 above.
6-89 TSC +0.17 New PLP in 2R23 See tube R4-C89 above. See tube R4-C89 above.
6-91 TSH +0.31 PLP in 2R20 & 2R23 SSI not performed for this historical PLP. No wear identified by ECT.
7-92 TSH +0.54 PLP in 2R20 & 2R23 SSI not performed for this historical PLP. No wear identified by ECT.
8-91 TSH +0.86 PLP in 2R20 & 2R23 SSI not performed for this historical PLP. No wear identified by ECT.
40-87 TSH +0.17 PLP in 2R20 & 2R23 SSI not performed for this historical PLP. No wear identified by ECT.
A 40-89 TSH +0.15 PLP in 2R20 & 2R23 SSI not performed for this historical PLP. No wear identified by ECT.
41-88 TSH +0.15 PLP in 2R20 & 2R23 SSI not performed for this historical PLP. No wear identified by ECT.48-151 TSH +1.62 PLP in 2R20 & 2R23 SSI not performed for this historical PLP. No wear identified by ECT.49-152 TSH +0.74 PLP in 2R20 & 2R23 SSI not performed for this historical PLP. No wear identified by ECT.
50-151 TSH +1.26 PLP in 2R20 & 2R23 SSI not performed for this historical PLP. No wear identified by ECT.
50-153 TSH +0.24 PLP in 2R20 & 2R23 SSI not performed for this historical PLP. No wear identified by ECT.51-152 TSH +0.49 PLP in 2R20 & 2R23 SSI not performed for this historical PLP. No wear identified by ECT.
128-57 03H +3.19 NDF with PlusPt SSI not required for this PLP. No wear identified by ECT.
15-42 TSH +0.63 PLP in 2R20 & 2R23 SSI not performed for this historical PLP. No wear identified by ECT.
104-67 TSC +30.02 New PLP in 2R23 SSI could not access the elevation at this Acceptable to leave as-is. PLP is in a low flow location for visual confirmation of new PLP. region and no wear was identified by ECT.
SSI could not access the elevation at this Acceptable to leave as-is. PLP is in a low flow location for visual confirmation of new PLP. region and no wear was identified by ECT.
SSI identified and removed a long machine Object was removed and no wear was identified 115-138 TSH +4.61 New PLP in 2R23 turning piece at tubes 115-138, 116-139 by ween 117-138, 117-140, 118-139, and 119-140 by ECT.
SSI identified and removed a long machine Object was removed and no wear was identified 115-146 TSH +21.52 New PLP in 2R23 turning piece at tubes 115-146, 116-145, bj ween 116-147, 117-146, 117-148. by ECT.
to 2CAN01 1502 Page 8 of 8 2R23 PLP IndicationsT SG Row-Cl.
Row-Col. Location Location History 2R23 SSI Results Loose Part Wear Assessment 116-139 TSH +4.76 New PLP in 2R23 See Tube R115-C138 above. See Tube R115-C138 above.
116-145 TSH +21.39 New PLP in 2R23 See Tube R115-C146 above. See Tube R115-C146 above.
116-147 TSH +21.00 New PLP in 2R23 See Tube R115-Cl46 above. See Tube R115-Cl46 above.
117-138 TSH +4.63 New PLP in 2R23 See Tube R 115-C138 above. See Tube R I15-C138 above.
117-140 TSH +4.98 New PLP in 2R23 See Tube Rl 15-C138 above. See Tube R1 15-C138 above.
117-146 TSH +21.49 New PLP in 2R23 See Tube R115-C146 above. See Tube R115-C146 above.
B 117-148 TSH +20.89 New PLP in 2R23 See Tube R115-C146 above. See Tube R115-C146 above.
118-139 TSH +4.72 New PLP in 2R23 See Tube R 115-C138 above. See Tube R1 15-C138 above.
119-140 TSH +5.28 New PLP in 2R23 See Tube R115-C138 above. See Tube R115-C138 above.
SSI identified and removed a long machine Object was removed and no wear was identified 137-118 TSH +33.28 PLP in 2R20 & 2R23 turning piece at tubes 137-118, 138-119, and by ECT.
139-118.
138-119 TSH +33.66 PLP in 2R20 & 2R23 See Tube R137-C118 above. See Tube R137-C 118 above.
139-118 TSH +34.05 PLP in 2R20 & 2R23 See Tube R 1 37-C 118 above. I See Tube R137-C118 above.
ATTACHMENT 2 TO 2CAN01 1502 REGULATORY COMMITMENTS to 2CAN01 1502 Page 1 of 1 List of Regulatory Commitments This table identifies actions discussed in this letter for which Entergy commits to perform. Any other actions discussed in this submittal are described for the NRC's information and are not commitments.
TYPE (Check one) SCHEDULED COMMITMENT ONE-TIME CONTINUING COMPLETION DATE ACTION COMPLIANCE (If Required)
Entergy will provide the information for both Within 45 days of the AVB (anti-rotation bar) positioning and X Entergy receipt of sludge evaluation. AREVA report