Letter Sequence Other |
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MONTHYEARW3F1-2012-0085, Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request2012-10-16016 October 2012 Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request Project stage: Request ML12310A4542012-11-0505 November 2012 E-mail, Request for Additional Information, Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request for the Third 10-Year Inservice Inspection Interval Project stage: RAI W3F1-2012-0096, Response to an NRC Request for Additional Information (RAI) Associated with W3-ISI-020, Request for Alternative to ASME Code Case N-770-1 Baseline Examination2012-11-15015 November 2012 Response to an NRC Request for Additional Information (RAI) Associated with W3-ISI-020, Request for Alternative to ASME Code Case N-770-1 Baseline Examination Project stage: Request W3F1-2012-0102, Supplemental Response to an NRC Request for Additional Information (RAI) Associated with W3-ISI-020, Request for Alternative to ASME Code Case N-770-1 Baseline Examination2012-12-16016 December 2012 Supplemental Response to an NRC Request for Additional Information (RAI) Associated with W3-ISI-020, Request for Alternative to ASME Code Case N-770-1 Baseline Examination Project stage: Supplement 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 Project stage: Request ML13085A1252013-03-26026 March 2013 Verbal Authorization on 12/18/2012, Revised Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request for the Third 10-Year Inservice Inspection Interval Project stage: Other ML13128A1292013-05-31031 May 2013 Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request for the Third 10-Year Inservice Inspection Interval Project stage: Other 2012-12-16
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Category:Code Relief or Alternative
MONTHYEARML21299A0032021-10-28028 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 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) ML20022A2582020-01-28028 January 2020 Re-Issuance of Approval of Relief Request WF3-RR-19 2, Relief from the Requirements of Asme Code Section XI Regarding Alternate Repair of Degraded Drain Line of Chemical and Volume Control ML20002A0202020-01-13013 January 2020 Approval of Relief Request WF3-RR-19-2, Relief from the Requirements of Asme Code Section XI Regarding Alternate Repair of Degraded Drain Line of Chemical and Volume Control System 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 ML19247B1972019-09-0909 September 2019 Approval of Relief Request W3-ISI-032,Relief from the Requirements of ASME Code Section XI Regarding Volumetric Examination ML19232A0252019-08-27027 August 2019 Authorization of Proposed Alternative to ASME Code Section XI, IWA-4000, Repair/Replacement Activities W3F1-2019-0052, CFR 50.55a Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 in Accordance with 10 CFR 50.55a(z)(2)2019-07-18018 July 2019 CFR 50.55a Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 in Accordance with 10 CFR 50.55a(z)(2) 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 W3F1-2018-0065, Request for Relief from ASME Section XI Volumetric Examination Requirements - Third 10-Year Interval, W3-ISI-0322018-11-30030 November 2018 Request for Relief from ASME Section XI Volumetric Examination Requirements - Third 10-Year Interval, W3-ISI-032 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 ML17341A1202017-12-11011 December 2017 Relief Request PRR-WF3-2017-3, Request for Alternative to ASME OM Code Requirements for Comprehensive Testing of High Pressure Safety Injection Pump AB (CAC No. MF9875; EPID L-2017-LLR-0049) ML17328A8822017-11-29029 November 2017 Requests for Relief GRR-1, PRR-1 and PRR-2, Alternatives to ASME OM Code Requirements for Inservice Testing for the Fourth 10-Year Program Interval (CAC Nos. MF9869, 9870, and 9871; EPID L-2017-LRM-0045-47) 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 ML17069A1872017-03-22022 March 2017 Request for Alternative to 10 CFR 50.55a(c) ASME Code Section III Code Case 1361-1, Relief Request W3-ISI-024 ML16235A2282016-12-0909 December 2016 Request for Alternative Test Plan to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML16182A2702016-07-0606 July 2016 Relief Request PRR-WF3-2016-1, Alternative to the Inservice Testing Program 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 ML14070A0082014-03-26026 March 2014 Request for Alternative W3-ISI-023, ASME Code Case N-770-1 Successive Examinations, Third 10-Year Inservice Inspection Interval ML13192A2222013-08-0202 August 2013 Request for Alternative W3-ISI-021, ASME Code Case N-770-1 Baseline Examination Request for the Third 10-Year Inservice Inspection Interval ML13128A1292013-05-31031 May 2013 Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request for the Third 10-Year Inservice Inspection Interval ML13085A1592013-03-26026 March 2013 Verbal Authorization on 12/18/2012, Request for Alternative W3-ISI-021, ASME Code Case N-770-1 Baseline Examination Request for the Third 10-Year Inservice Inspection Interval ML13085A1252013-03-26026 March 2013 Verbal Authorization on 12/18/2012, Revised Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request for the Third 10-Year Inservice Inspection Interval ML12293A3622012-11-0808 November 2012 Relief Request VRR-WF3-2012-1 Associated with Category a Leak Test of Component Cooling Water Check Valve ACC-108B for the Third 10-Year Inservice Inspection Interval W3F1-2012-0085, Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request2012-10-16016 October 2012 Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request ML12234A6352012-08-21021 August 2012 Verbal Authorization of Relief Request VRR-WF3-2012-1 ML1133301372012-01-0404 January 2012 Request for Alternative W3-CISI-002 to ASME Code, Section XI, IWE-5221 for Post-repair Testing of Steel Containment Vessel Opening, Third 10-Year Inservice Inspection Interval ML1125701682011-10-14014 October 2011 Request for Alternative W3-ISI-019 from Inservice Inspection Requirements of Reactor Vessel Head In-Core Instrument Nozzles, Third 10-Year Inservice Inspection Interval ML1125702732011-10-14014 October 2011 Request for Alternative W3-ISI-018 from Inservice Inspection Requirements of Reactor Pressure Vessel Head Control Element Drive Mechanism Nozzles, Third 10-Year Inservice Inspection Interval ML1035703922011-01-13013 January 2011 Relief Request No. W3-ISI-017, Alternative to ASME IWA-5211 Regarding Chemical Volume Control System Pipe Visual Inspection, for Third 10-Year Inservice Inspection Interval ML1029903712010-11-23023 November 2010 Correction to May 18, 2010 Safety Evaluation for Relief Request No. W3-CISI-001 Regarding Post Repair Testing of the Steel Containment Vessel Opening ML1015905742010-06-30030 June 2010 Relief Request Nos. WF3-ISI-007 to WF3-ISI-014 from ASME Code, Section XI Volumetric Examination Requirements - Second 10-Year Interval ML1008500892010-05-18018 May 2010 Relief Request W3-CISI-001, Request for Alternative to ASME IWE-5521, Post Repair Testing of the Steel Containment Vessel Opening ML1008203552010-03-23023 March 2010 Request for Additional Information Round 2, Relief Request Nos. WF3-ISI-007 to WF3-ISI-014 from ASME Code, Section XI Volumetric Examination Requirements - Second 10-Year Interval W3F1-2010-0018, Request for Alternative to ASME IWA-5211 Regarding Chemical Volume Control System Pipe Visual Inspection2010-02-22022 February 2010 Request for Alternative to ASME IWA-5211 Regarding Chemical Volume Control System Pipe Visual Inspection W3F1-2010-0002, Request for NRC Alternative to ASME IWE-5521 Regarding Post Repair Testing of Waterford 3's Steel Containment Vessel-Opening2010-02-0909 February 2010 Request for NRC Alternative to ASME IWE-5521 Regarding Post Repair Testing of Waterford 3's Steel Containment Vessel-Opening 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 ML0931604422009-11-0404 November 2009 Email Verbal Authorization of Request for Alternative W3-ISI-015 - Third 10-year Inservice Inspection Interval ML0930808142009-11-0404 November 2009 Email Verbal Authorization of Request for Alternative - W3-ISI-016 ML0912103752009-06-12012 June 2009 Relief, Request for Alternative W3-ISI-006, from Requirements of ASME Code Section XI, for Second 10-Year Inservice Inspection Interval ML0903708982009-03-0606 March 2009 Unit 3 - Request for Alternative CEP-ISI-012, Use Alternative Requirements in ASME Code Case N-753 CNRO-2009-00001, Relief Requests for Third 120 Month Inservice Inspection Interval2009-01-23023 January 2009 Relief Requests for Third 120 Month Inservice Inspection Interval CNRO-2008-00035, Follow-up to Request for Extension of Discretion for the Interim Enforcement Policy for Fire Protection Issues on 10CFR50.48(c), National Fire Protection Association Standard NFPA 8052008-11-20020 November 2008 Follow-up to Request for Extension of Discretion for the Interim Enforcement Policy for Fire Protection Issues on 10CFR50.48(c), National Fire Protection Association Standard NFPA 805 ML0809801202008-04-28028 April 2008 Request for Alternative W3-ISI-005, Request to Use ASME Code Case N-716 ML0809502732008-04-21021 April 2008 Revised Request for Alternative W3-R&R-006 to ASME Code Requirements for Weld Overlay Repairs for Second 10-Year Inservice Inspection ML0802504912008-02-15015 February 2008 Request for Alternative W3-ISI-003 to ASME Code Requirements to Allow Extension to Second 10-Year Inservice Inspection Interval Beyond That Currently Allowed by ASME Subsection IWA-2340(d) ML0725600262007-09-24024 September 2007 Withdrawal of W3-ISI-002, Request for Alternative CNRO-2007-00027, Request for Alternative W3-ISI-004 Proposed Alternative to Second Interval ISI Examinations2007-08-0707 August 2007 Request for Alternative W3-ISI-004 Proposed Alternative to Second Interval ISI Examinations ML0701200812007-02-0202 February 2007 River Bend Station, & Waterford Steam Electric Station, Unit 3 - Request for Alternative CEP-PT-001, Visual Exam of Vent & Drain Leakage Tests (TAC MD1399, MD1400, MD1401, MD1402, & MD1403) 2021-10-28
[Table view] Category:Letter
MONTHYEARIR 05000382/20230102024-01-31031 January 2024 Comprehensive Engineering Team Inspection Report 05000382/2023010 IR 05000382/20230032024-01-23023 January 2024 Acknowledgment of Reply to a Notice of Violation NRC Inspection Report 05000382/2023003 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23340A2292023-12-28028 December 2023 Withdrawal of an Amendment Request to Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability (EPID L-2022-LLA-0169)-LTR ML23349A1672023-12-21021 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 ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1442023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23312A1832023-11-14014 November 2023 Integrated Inspection Report 05000382/2023003 and Notice of Violation 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 05000382/20234012023-10-0404 October 2023 Cyber Security Inspection Report 05000382/2023401 (Cover Letter Only) IR 05000382/20230052023-08-21021 August 2023 Updated Inspection Plan for Waterford Steam Electric Station, Unit 3 - (Report 05000382/2023005) IR 05000382/20233012023-08-15015 August 2023 NRC Initial Operator Licensing Examination Approval 05000382/2023301 IR 05000382/20230022023-08-0808 August 2023 Integrated Inspection Report 05000382/2023002 IR 05000382/20234022023-08-0707 August 2023 NRC Security Inspection Report 05000382/2023402 (Full Report) IR 05000382/20230402023-07-12012 July 2023 Revised 95001 Supplemental Inspection Report 05000382/2023040, Exercise of Enforcement Discretion, and Follow-Up Assessment Letter ML23191A4562023-07-10010 July 2023 Notification of Comprehensive Engineering Team Inspection (050003822023010) and Request for Information ML23158A1042023-06-0808 June 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000382/2023401 ML23145A2272023-06-0202 June 2023 95001 Supplemental Inspection Report 05000382/2023040, and Exercise of Enforcement Discretion ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment IR 05000382/20230012023-04-24024 April 2023 Integrated Inspection Report 05000382/2023001, Independent Spent Fuel Storage Installation Report 07200075/2023001, and Exercise of Enforcement Discretion ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML23108A2542023-04-18018 April 2023 WCGS Information Request, Security IR 2023401 IR 05000382/20234032023-04-17017 April 2023 Security Baseline Inspection Report 05000382/2023403 ML23093A2122023-04-0303 April 2023 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2022 ML23089A0602023-03-30030 March 2023 Entergy Operations, Inc. - Fleet Project Manager Assignment ML23088A3922023-03-29029 March 2023 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML23080A2882023-03-21021 March 2023 Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) Entergy Operations, Inc ML23059A2592023-03-0707 March 2023 Correction to Issuance to Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23065A2002023-03-0303 March 2023 EN 56252 Update - Flow Serve - Final Notification of Potential Part 21 on Peerless 56 Frame DC Motors ML23060A1092023-03-0101 March 2023 Proof of Financial Protection (10 CFR 140.15) IR 05000382/20220062023-03-0101 March 2023 Annual Assessment Letter for Waterford Steam Electric Station, Unit 3, (Report 05000382/2022006) ML22322A1092023-02-17017 February 2023 Issuance of Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b IR 05000382/20230902023-02-0101 February 2023 Final Significance Determination of a White Finding, NOV, and Follow-Up Assessment Letter; NRC Inspection Report 05000382/2023090 ML23032A5062023-02-0101 February 2023 Technical Specification Index and Bases Update to the NRC for the Period November 11, 2021 Through July 25, 2022 ML23030A6642023-01-27027 January 2023 Flowserve, Part 21 Second Interim Notification Report Re Peerless 56 Frame DC Motors IR 05000382/20220042023-01-26026 January 2023 Integrated Inspection Report 05000382/2022004 and Independent Fuel Storage Installation Inspection Report 07200075/2022001 ML23024A0822023-01-20020 January 2023 Stephens Insurance, Entergy - 2023 Nuclear Energy Liability Evidence of Financial Protection ML23018A2202023-01-18018 January 2023 Quality Assurance Program Manual Reduction in Commitment IR 05000382/20220912023-01-12012 January 2023 Emergency Preparedness Inspection Report 05000382/2022091 and Preliminary White Finding and Apparent Violation IR 05000382/20220032023-01-0505 January 2023 Revised Integrated Inspection Report 05000382/2022003 ML22342B1402022-12-0202 December 2022 56252-EN 56252 - Flowserve - Limitorque - Interim Report Potential Part 21 on Peerless 56 Frame DC Motors ML22300A2082022-11-30030 November 2022 Issuance of Amendment No. 269 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22332A5292022-11-29029 November 2022 Notification of NRC Initial Operator Licensing Examination 05000382/2023301 IR 05000382/20220132022-11-28028 November 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000382/2022013 IR 05000382/20220022022-11-0101 November 2022 Revised Integrated Inspection Report 05000382/2022002 2024-01-31
[Table view] Category:Safety Evaluation
MONTHYEARML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML22322A1092023-02-17017 February 2023 Issuance of Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22300A2082022-11-30030 November 2022 Issuance of Amendment No. 269 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22194A9012022-07-20020 July 2022 Issuance of Amendment No. 268 Adoption of Technical Specification Task Forcetraveler TSTF-569, Revise Response Time Testing Definition, Revision 2 ML22153A4452022-07-0808 July 2022 Issuance of Amendment No. 267 for Reactor Coolant System Pressure/Temperature Limits and Low Temperature Overpressure Setpoints Applicable for 55 Effective Full Power Years ML22145A0152022-05-27027 May 2022 Issuance of Amendment No. 266 to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22075A1022022-04-29029 April 2022 Issuance of Amendment No. 264 to Relocate Chemical Detection System Technical Specifications to Technical Requirements Manual ML22083A1242022-04-28028 April 2022 Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2 ML22061A2172022-03-15015 March 2022 Revision of the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML22007A3172022-01-18018 January 2022 1, River Bend Station 1, and Waterford Steam Electric Station 3 - Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML21313A0082021-12-0808 December 2021 Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21166A1832021-09-15015 September 2021 Issuance of Amendment No. 261 Regarding Removal and Relocation of Boration System Technical Specifications ML21131A2432021-08-24024 August 2021 Issuance of Amendment No. 260 Digital Upgrade to the Core Protection and Control Element Assembly Calculator System ML21082A3022021-05-19019 May 2021 Issuance of Amendment No. 259 to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML20280A3292020-10-20020 October 2020 Issuance of Amendment No. 258 Regarding Technical Specification 3/4.8.1 Surveillance Requirements ML20205L5742020-08-25025 August 2020 Issuance of Amendment No. 257 Control Room Air Condition System Technical Specifications ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI ML20022A2582020-01-28028 January 2020 Re-Issuance of Approval of Relief Request WF3-RR-19 2, Relief from the Requirements of Asme Code Section XI Regarding Alternate Repair of Degraded Drain Line of Chemical and Volume Control ML20002A0202020-01-13013 January 2020 Approval of Relief Request WF3-RR-19-2, Relief from the Requirements of Asme Code Section XI Regarding Alternate Repair of Degraded Drain Line of Chemical and Volume Control System ML19275D4382019-10-24024 October 2019 Redacted - Issuance of Amendment No. 256 for Use of the Tranflow Code for Determining Pressure Drops Across the Steam Generator Secondary Side Internal Components ML19282D8922019-10-15015 October 2019 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule 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 ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19247B1972019-09-0909 September 2019 Approval of Relief Request W3-ISI-032,Relief from the Requirements of ASME Code Section XI Regarding Volumetric Examination ML19232A0252019-08-27027 August 2019 Authorization of Proposed Alternative to ASME Code Section XI, IWA-4000, Repair/Replacement Activities ML19164A0012019-06-28028 June 2019 Issuance of Amendment No. 254 Regarding Revision of Technical Specification 3/4.7.4, Ultimate Heat Sink, ML19157A3162019-06-12012 June 2019 Authorization of Proposed Alternative to ASME Code Case N-770-2 ML19022A3372019-02-13013 February 2019 Issuance of Amendment No. 253 to Revise Section 15.4.3.1 of the Updated Final Safety Analysis Report to Account for Fuel Misload ML18282A0302018-10-18018 October 2018 Proposed Alternative to ASME Code, Section XI, Regarding Charging Pipe Visual Inspection ML18180A2982018-07-23023 July 2018 Issuance of Amendment No. 252 Adoption of the Raptor-M3G Code for Neutron Fluence Calculations 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 ML18026B0532018-04-26026 April 2018 Issuance of Amendment No. 251 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control,(Cac No. MF9537; EPID L-2017-LLA-0205) ML17341A1202017-12-11011 December 2017 Relief Request PRR-WF3-2017-3, Request for Alternative to ASME OM Code Requirements for Comprehensive Testing of High Pressure Safety Injection Pump AB (CAC No. MF9875; EPID L-2017-LLR-0049) ML17328A8822017-11-29029 November 2017 Requests for Relief GRR-1, PRR-1 and PRR-2, Alternatives to ASME OM Code Requirements for Inservice Testing for the Fourth 10-Year Program Interval (CAC Nos. MF9869, 9870, and 9871; EPID L-2017-LRM-0045-47) ML17192A0072017-07-27027 July 2017 Issuance of Amendment No. 250 Adoption of Technical Specifications Task Force Traveler TSTF 545, Revision 3 ML17069A1872017-03-22022 March 2017 Request for Alternative to 10 CFR 50.55a(c) ASME Code Section III Code Case 1361-1, Relief Request W3-ISI-024 ML17045A1482017-03-0303 March 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16235A2282016-12-0909 December 2016 Request for Alternative Test Plan to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML16278A0172016-10-19019 October 2016 Entergy Fleet Relief Request RR-EN-ISI-15-1, Alternative to Maintain Inservice Inspection Related to Activities to the 2001 Edition/2003 Addendum of ASME Section XI Code ML16251A6202016-09-13013 September 2016 Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) ML16159A4192016-07-26026 July 2016 Issuance of Amendment No. 249 Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control ML16182A2702016-07-0606 July 2016 Relief Request PRR-WF3-2016-1, Alternative to the Inservice Testing Program ML16126A0332016-06-27027 June 2016 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) 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 ML16093A0282016-05-31031 May 2016 Entergy Services, Inc., Proposed Alternative to Utilize ASME Code Case N-789-1, Relief Request RR-EN-15-1, Revision 1 ML16077A2702016-05-10010 May 2016 Issuance of Amendment No. 247 Regarding Cyber Security Plan Milestone 8 Full Implementation Schedule ML15289A1432015-11-13013 November 2015 Redacted - Issuance of Amendment No. 246 Changes to Technical Specification 3.1.3.4 Regarding Control Element Assembly Drop Times ML15267A7972015-10-0606 October 2015 Safety Evaluation Regarding the Aging Management Program for Reactor Vessel Internals ML15139A4832015-08-31031 August 2015 Issuance of Amendment No. 245 Change to Updated Final Safety Analysis Report Clarifying Pressurizer Heaters Function for Natural Circulation at the Onset of a Loss of Offsite Power 2023-05-01
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 31. 2013 Vice President, Operations Entergy Operations, Inc.
Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - REQUEST FOR ALTERNATIVE W3-ISI-020, ASME CODE CASE N-770-1 BASELINE EXAMINATION (TAC NO. ME9801)
Dear Sir or Madam:
By letter dated October 16, 2012, as supplemented by letters dated November 15 and December 16,2012, Entergy Operations, Inc. (the licensee), submitted for the U.S. Nuclear Regulatory Commission (NRC) review and authorization Request for Alternative W3-ISI-020, "ASME [American Society of Mechanical Engineers] Code Case N-770-1 Baseline Examination Request for Alternative," for Waterford Steam Electric Station, Unit 3 (Waterford 3). The request is associated with the use of an alternative to the requirements of the ASME Boiler and Pressure Vessel Code, Code Case N-770-1, in accordance with Title 10 of the Code of Federal Regulations, Part 50 (10 CFR 50), paragraph 55a(g)(6)(ii)(F)(3), dated June 21, 2011. The licensee also stated that the alternative is for the current third 1O-year lSI interval.
Specifically, the licensee is proposing to credit a previous examination of nickel-based Alloy 82/182 dissimilar metal butt welds to satisfy the baseline examination requirement of ASME Code Case N-770-1. The licensee requested authorization to use the proposed alternative pursuant to 10 CFR 50.55a(a)(3)(ii) on the basis that complying with the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The NRC staff determined that proposed alternative W3-ISI-020 provides reasonable assurance of structural integrity and leak tightness until the scheduled refueling outage in the spring of 2014. and that complying with the speCified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(ii) and, therefore, recommends authorization to use the proposed alternative at Waterford 3, until the scheduled refueling outage in the spring of 2014. Verbal authorization for use of the proposed alternative was given in a conference call between the NRC staff and the licensee's representatives on December 18, 2012.
-2 Authorizing the use of the alternative, pursuant to 10 CFR 50.55a(a)(3)(ii), 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 that complying with the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
All other ASME Code,Section XI, requirements for which relief was not specifically requested and authorized in the subject proposed alternative remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
The NRC staff authorizes the use of the alternative, detailed in this request, until the scheduled refueling outage in the spring of 2014.
The NRC staffs safety evaluation is enclosed.
Sincerely, Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ASME CODE CASE N-770-1 BASELINE EXAMINATION ALTERNATIVE W3-ISI-020 ENTERGY OPERATIONS, INC.
WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382
1.0 INTRODUCTION
By letter dated October 16,2012, as supplemented by letters dated November 15 and December 16, 2012 (References 1, 2, and 3, respectively), Entergy Operations, Inc. (the licensee), submitted request for alternative W3-ISI-020, "ASME Code Case N-770-1 Baseline Examination Request for Alternative," for U.S. Nuclear Regulatory Commission (NRC) review and authorization. Specifically, the licensee is proposing to credit a previous examination of nickel-based Alloy 82/182 dissimilar metal butt welds (DMBW) to satisfy the baseline examination requirement of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Case N-770-1, as conditioned by Title 10 of the Code of Federal Regulations, Part 50 (10 CFR 50), paragraph 55a(g)(6)(ii)(F)(3), at Waterford Steam Electric Station, Unit 3 (Waterford 3). The licensee requested authorization to use the proposed alternative pursuant to 10 CFR 50.55a(a)(3)(ii) on the basis that complying with the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Verbal authorization for use of the proposed alternative was given in a conference call between the NRC staff and the licensee's representatives on December 18,2012 (Reference 4).
2.0 REGULATORY EVALUATION
Paragraph 55a(g)(6)(ii)(F) of 10 CFR 50 requires that licensees of existing operating pressurized-water reactors (PWRs) implement the requirements of ASME Code Case N-770-1, "Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities," subject to the conditions specified in paragraphs (g)(6)(ii)(F)(2) through (g)(6)(ii)(F)(1 0), by the first refueling outage after August 22, 2011.
Enclosure
-2 Paragraph SSa(g)(6)(ii)(F)(3) of 10 CFR SO states that Baseline examinations for welds in Table 1, Inspection Items A-1, A-2, and B, shall be completed by the end of the next refueling 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 VIII 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 (a)(3)(i) or (a)(3)(ii) of this section is granted prior to the end of the next refueling outage after January 20, 2012.
Paragraph 10 CFR SO.SSa(a)(3) states, in part, that alternatives to the requirements of 10 CFR SO.SSa(g) may be used when authorized by the NRC if the applicant demonstrates that: (i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Based on analysis of the regulatory requirements, the NRC staff concludes that regulatory authority exists to authorize the proposed alternative pursuant to 10 CFR SO.SSa(a)(3)(ii).
3.0 TECHNICAL EVALUATION
3.1 Licensee's Request for Alternative 3.1.1 Components Affected ASME Code Class 1 dissimilar metal piping welds containing Alloy 82/182, ASME Code Case N-770-1 Inspection Item B, unmitigated butt weld at cold leg operating temperature.
The dissimilar metal piping welds covered by this relief request are identified in the , "Weld Data Table," to the licensee's letter dated December 16,2012 (reproduced in the Attachment to this safety evaluation):
Reactor coolant pump (RCP) inlet weld numbers: 07-002;09-016; 11-002; and 13-016 RCP outlet weld numbers: 08-014;10-002, 12-002; and 14-002 Safety injection nozzle to safe end weld numbers: 08-009;10-008; 12-009; and 14-006 3.1.2 Code Requirements The Waterford 3, Code of record for the third 1O-year inservice inspection (lSI) interval that started on June 1, 2012 and is scheduled to end on July 1, 2017, is the 2001 Edition through the 2003 Addenda of the ASME Code,Section XI.
-3 The subject welds are classified as Inspection Item "B," "Unmitigated butt weld at Cold Leg operating temperature ~ 525 0 F and < 580 0 F" for which visual and essentially 100 percent volumetric examinations are required.
3.1.3 Licensee's Reason for Request The licensee stated that the ultrasonic testing (UT) examination of the subject welds in the fall of 2009 did not obtain essentially 100 percent of the required examination volume coverage, and to obtain additional coverage would necessitate modification or replacement of the component.
3.1.4 Licensee's Proposed Alternative and Basis for Use The licensee proposes to credit a previous examination of nickel-based dissimilar metal butt welds (DMBWs) performed in accordance with the requirements of Electric Power Research Institute (EPRI) technical report, "Material Reliability Program: Primary System Piping Butt Weld Inspection and Evaluation Guideline (MRP-139, Revision 1)," December 2008 (Reference 5), in the fall of 2009 to satisfy the baseline examination requirement of ASME Code Case N-770-1, as conditioned by 10 CFR 50.55a(g)(6)(ii)(F)(3). The licensee stated that the equipment, procedure, and personnel utilized for the examinations were qualified in accordance with the requirements of ASME Code,Section XI, Appendix VIII, as implemented through the Performance Demonstration Initiative (PDI) program, employing the best available technology for maximizing examination coverage of these types of welds, and that the examinations performed on the subject areas demonstrate an acceptable level of integrity.
The licensee has cited the following authorized relief requests as precedents:
- 1. Diablo Canyon Power Plant, Unit 1, dated February 24, 2012 (Reference 6).
- 2. Calvert Cliffs Nuclear Power Plant, Unit 1, dated December 19, 2012 (Reference 7).
3.2 NRC Staff Evaluation Primary water stress-corrosion cracking (PWSCC) of nickel-based pressure boundary materials is a safety concern. Operational experience has shown that PWSCC can occur as the result of the combination of susceptible material, corrosive environment, and tensile stresses, resulting in leakage and the potential for loss of structural integrity. The subject DMBWs meet these conditions thus may be susceptible to PWSCC. The examination requirements of ASME Code Case N-770-1, as conditioned by 10 CFR 50.55a(g)(6)(ii)(F), are intended to ensure the structural integrity and leak tightness of DMBWs through nondestructive examination.
The subject dissimilar metal butt welds (DMBWs) are PWSCC-susceptible Alloy 82/182 weld metal joining mill-clad carbon steel (SA-516, Grade 70, with SA-240-304L cladding) to cast austenitic stainless steel (CASS, SA-351, Grade CF8M) safe-ends. The subject welds are located either on the 30-inch inside diameter (lD) reactor coolant pump (RCP) suction or discharge piping, or join a 12-inch outside diameter (OD) safety injection nozzle to each RCP spool piece.
-4 The licensee stated that there is limited circumferential scan examination volume coverage for axial flaws in the susceptible material due to weld taper and the lack of access for examination from the CASS safe-end side of the welds. The licensee stated that the limitation for examination of the susceptible material is due to joint limitations and not surface conditioning; in order to obtain additional axial coverage, weld build up of the dissimilar metal butt weld would be required, along with additional contouring and an ASME Code,Section III, required radiographic (RT) examination. The NRC staff concludes that the efforts needed to obtain essentially 100 percent scan coverage of the susceptible material in the circumferential scan direction would present a hardship.
The licensee stated that the subject nozzle-to-safe-end welds were examined in accordance with MRP-139, Revision 1, in fall 2009. The UT examination was a manually-delivered non encoded phased-array single-sided UT examination from the OD of the ferritic side of the weld in both the circumferential as well as axial directions. The UT procedure SI-UT-130, "Procedure for the Phased Array Ultrasonic Examination of Dissimilar Metal Welds" (included as to Reference 2), and personnel were qualified to the requirements of ASME Code,Section XI, Appendix VIII, Supplement 10. The Performance Demonstration aualification Summary (PDaS) No. 632, configuration "PWR (Combustion Engineering Design) - Reactor Coolant Pump Safe-end to Elbow Weld (717/X)" specifies that the procedure is not qualified to detect axial flaws on the far side of a single-side access component containing a tapered weld configuration.
The licensee stated that the 2009 examination achieved 100 percent examination coverage of the required ASME Code Case N-770-1 volume for axial and circumferential scans of the ferritic material and 100 percent axial scan coverage of the susceptible material for circumferential flaws for all of the subject welds. In its letter dated December 16, 2012, in response to the NRC staff's request for additional information (RAI), the licensee noted that the tapered weld limitation described in the PDaS did not exist for the four subject safety-injection welds and, accordingly, credited the 100 percent axial and circumferential scan coverage for the susceptible material of these welds. Due to the fact that CASS is not known to be susceptible to PWSCC or other service-related cracking in the reactor coolant system environment, the NRC staff concludes that the lack of ASME Code,Section XI, Appendix VIII-compliant examination of the CASS material is not a structural integrity concern. The NRC staff concludes that the complete examination coverage of the ferritic and susceptible material of the safety-injection nozzle to safe-end DMBWs and the best effort UT examination of the CASS material provide reasonable assurance of structural integrity and leak tightness and, therefore, the examinations of the safety injection DMBWs are acceptable.
The NRC staff has examined the drawings of the RCP DMBWs submitted by the licensee (Reference 3) and chose RCP outlet weld 08-014 as the bounding case based on circumferential scan coverage obtained and wall thickness.
In addition to the circumferential scans of the susceptible material in two scan directions from the carbon steel side of the RCP welds, the susceptible material in the weld volume has been sonically examined by circumferential scans in two scan directions from the weld crown. Pacific Northwest National Laboratory (PNNL) has modeled (Reference 8) the UT response in the susceptible weld material for scans performed from the weld crown of a similar weld geometry
-5 using the parameters of the SI-UT-130 procedure. The evaluation included theoretical modeling of the sound beams based on actual phased-array design parameters and component geometry similar to that of weld 08-014. The PNNL model calculated the sound field extents and intensities for an isotropic material, as such, actual grain sizes and structures, velocity ranges, and other material variables that will affect sound beam attenuation, re-direction, and signal-to noise values have not been applied, and in some cases, are unknown.
Adequate volumetric coverage exists for sound field intensity greater than or equal to
-6 decibels (dB). The PNNL model determined that the -6 dB UT sound field did not extend to adequately interrogate the weld material at the 10 surface, but the model predicted that the -6dB sound field extended to the uppermost tip of the assumed 10 percent hypothetical flaw in weld 08-014. Based on the PNNL model results for the scans performed from the weld crown, as well as the multiple scans from the ferritic side of the weld, the NRC staff concludes that there is a high likelihood of finding the hypothetical axial flaw size proposed by the licensee. Therefore, the hypothetical 10 percent deep flaw size proposed by the licensee is acceptable.
The licensee has submitted a flaw growth calculation for a hypothetical axial flaw growing by PWSCC in response to operational stress and the weld residual stress (WRS) that would result from a repair of 50 percent of the wall thickness. The licensee's analysis includes the effects of the WRS corresponding to an 10 weld repair of 50 percent wall thickness without a subsequent post-repair heat treatment. The NRC staff concludes that the assumed 50 percent weld repair will likely bound any undocumented weld repair and that the absence of subsequent post-weld heat treatment reflects the condition of the weld. The parameters are, therefore, acceptable.
The NRC staff compared the WRS values used in the calculation to reference WRS values and concludes that the licensee's WRS values are reasonable. Therefore, the WRS values for use in axial PWSCC flaw growth analysis are acceptable.
The NRC staff examined the geometry of the subject weld and concludes that it closely approximates and the weld geometry modeled. The licensee's states that a 16.7 percent through-wall flaw, significantly deeper than the proposed hypothetical 10 percent flaw through wall flaw, would grow to the ASME Code allowable flaw size of 75 percent through-wall in approximately 54 months (Reference 7). The NRC staff notes that the safe-end length in the model is significantly longer than the actual safe-end length of weld 08-014 and that this presents a significant conservatism in the calculation.
The NRC staff performed independent confirmatory analyses using the proposed 10 percent through-wall hypothetical flaw size. The NRC staff's analyses used the licensee's calculated values for WRS for a 50 percent repair as well as reference WRS values for a 50 percent weld repair. The results of the NRC staffs analyses confirmed the licensee's calculation of 54 months to reach 75 percent through-wall ASME Code allowable size.
In summary, the NRC staff concludes that complying with the baseline examination requirements of 10 CFR 50.55a(g)(6)(ii)(F)(3) by performing an ASME Code-compliant examination of the subject RCP OMBWs would result in hardship. The NRC staff further concludes that the best effort UT examination of the CASS material and the UT scans from the carbon steel side of the weld and circumferential UT scans from the weld crown in the fall of 2009 provide reasonable assurance of structural integrity and leak tightness until the scheduled refueling outage in the spring of 2014. The NRC staff therefore concludes that complying with
-6 refueling outage in the spring of 2014. The NRC staff therefore concludes that complying with the requirements of 10 CFR 50.55a(g)(6)(ii)(F)(3) would result in hardship without a compensating increase in the level of quality and safety.
4.0 CONCLUSION
Based on the above, the NRC staff concludes that proposed alternative W3-ISI-020 provides reasonable assurance of structural integrity and leak tightness until the scheduled refueling outage in the spring of 2014, and that complying with the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(ii) and, therefore, authorizes use of the proposed alternative at Waterford until the scheduled refueling outage in the spring of 2014.
All other ASME Code,Section XI requirements for which relief was not specifically requested and authorized in the subject proposed alternative remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
5.0 REFERENCES
- 1. Mason, M. E., Entergy Operations, Inc., letter to U.S. Nuclear Regulatory Commission, "Waterford 3 Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request for Alternative," dated October 16, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12296A241).
- 2. Mason, M. E., Entergy Operations, Inc., letter to U.S. Nuclear Regulatory Commission, "Waterford 3 Response to an NRC Request for Additional Information (RAI) Associated with W3-ISI-020, Request for Alternative to ASME Code Case N-770-1 Baseline Examination [TAC No. ME9801]," dated November 15,2012 (ADAMS Accession No. ML12324A170).
- 3. Mason, M. E., Entergy Operations, Inc., letter to U.S. Nuclear Regulatory Commission, "Waterford 3 Supplemental Response to an NRC Request for Additional Information (RAj) associated with W3-ISI-020, Request for Alternative to ASME Code Case N-770-1 Baseline Examination [TAC No. ME9801]," dated December 16, 2012 (ADAMS Accession No. ML12352A172).
- 4. Kalyanam, N., U.S. Nuclear Regulatory Commission, "Waterford Steam Electric Station, Unit 3, Verbal Authorization of W3-ISI-020," dated December 18, 2012 (ADAMS Accession No. ML13085A125).
- 5. Electric Power Research Institute, "Material Reliability Program: Primary System Piping Butt Weld Inspection and Evaluation Guideline (MRP-139, Revision 1)," December 2008 (ADAMS Accession No. ML100970671).
- 6. Markley, M. T., U.S. Nuclear Regulatory Commission, letter to John T. Conway, Pacific Gas and Electric Company, "Diablo Canyon Power Plant, Unit No.1 - Approval of
-7 Request for Relief NDE-RCS-SE-LP1 CL to Allow Use of Alternative ASME Code Case N-770-1 (TAC No. ME7236)," February 24,2012 (ADAMS Accession No. ML120530680).
- 7. Pickett, D., U.S. Nuclear Regulatory Commission, e-mail to Patricia S. Furio, Calvert Cliffs Nuclear Power Plant, LLC, "NRC Verbal Approval for Calvert Cliffs RR-ISI-04-06A," dated March 26, 2012 (ADAMS Accession No. ML120860541).
- 8. Pacific Northwest National Laboratory, Technical Letter Report, "Evaluation of Licensee's Alternative to 10 CFR 50.55a(g)(6)(ii)(F) for Limitations to Volumetric Examinations of Dissimilar Metal Welds, Entergy Operations, Inc., Arkansas Nuclear One, Unit 2," April 23, 2013 (ADAMS Accession No. ML13113A218).
- 9. Pyle, S. L., Entergy Operations, Inc., "Clarification on Initial Flaw Size and Qualified Examination Area, Revised Request for Alternative AN02-ISI-007 Code Case N-770-1 Baseline Examination, Arkansas Nuclear One, Unit 2," dated December 17,2012 (ADAMS Accession No. ML12354A203).
Principal Contributor: Jay Wallace Date: May 31,2013
Attachment:
Weld Data Table
ATTACHMENT DISSIMILAR METAL PIPING WELDS COVERED BY REQUEST FOR ALTERNATIVE W3-ISI-020 WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382
Weld Data Table MRP-139 Volume N-770-1 Coverage Volume Coverage of PWSCC susceptible material Tapered Weld Fig Component Component Axial Circ Axial PDOS ID Description PDOS qualified Non-PDOS (Note1)
Scan for Scan for Scan for Limitation Circ Scan for Axial Oualified Circ Scan Circ Axial Circ Flaws for Axial Flaws Flaws Flaws Flaws 30" RCP 1A Inlet 07-002 Elbow (CS) to Safe- 100% 80% 100% 84.8% 100% Yes 501 end (Cast SS) 30" RCP 1A Outlet 08-014 Safe-end (Cast SS) to 100% 78% 100% 67% 100% Yes 502 Pipe(CS)
- i>
30" RCP 1B Inlet 09-016 Elbow(CS) to Safe- 100% 83% 100% 68% 100% Yes 501 end (Cast SS) 30" RCP 1B Outlet 10-002 Safe-end (Cast SS) to 100% 81% 100% 69% 100% Yes 502 Pipe (CS) 30" RCP 2A Inlet 11-002 Elbow (CS) to Safe- 100% 80% 100% 65% 100% Yes 501 end (Cast SS) 30" RCP 2A Outlet 12-012 Safe-end (Cast SS) to 100% 76% 100% 100% 100% No 502 Pipe (CS) 30" RCP 2B Inlet 13-016 Elbow (CS) to Safe- 100% 79% 100% 67.2% 100% Yes 501 end (Cast SS)
MRP-139 Volume N-770-1 Coverage Volume Coverage of PWSCC susceptible material Tapered Weld Fig Component Component Axial Circ Axial PoQS 10 Description PoQS qualified Non-poQS (Note1)
Scan for Scan for Scan for Limitation Circ Scan for Axial Qualified Circ Scan Circ Axial Circ Flaws for Axial Flaws Flaws Flaws Flaws 30" RCP 28 Outlet 14-002 Safe-end (Cast SS) to 100% 80% 100% 67% 100% Yes 502 Pipe (CS) 12" RCS 1A CL, SI 08-009 Nozzle to Safe-end 100% 100% 100% 100% 100% No N/A
-~~~ ---------
(Cast SS) ----------
12" RCS 18 CL, SI 10-008 Nozzle to Safe-end 100% 100% 100% 100% 100% No N/A
~ ~ ~
(Cast SS) --------- ---------
12" RCS 2A CL, SI
~
I 12-009 Nozzle to Safe-end (Cast SS) 100% 100% 100% 100% 100% No N/A 12" RCS 28 CL, SI 14-006 Nozzle to Safe-end 100% 100% 100% 100% 100% No N/A (c;ast~SL Note 1:
501 refers to Drawing 1201260.501 contained in Attachment 3 502 refers to Drawing 1201260.502 contained in Attachment 3
-2 Authorizing the use of the alternative, pursuant to 10 CFR 50.55a(a)(3)(ii), 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 that complying with the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
All other ASME Code,Section XI, requirements for which relief was not specifically' requested and authorized in the subject proposed alternative remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
The NRC staff authorizes the use of the alternative, detailed in this request, until the scheduled refueling outage in the spring of 2014.
The NRC staffs safety evaluation is enclosed.
Sincerely, IRA!
Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrLAJBurkhardt Resource LPLIV rlf RidsNrrPMWaterford 3 Resource RidsAcrsAcnw_MailCTR Resource RidsRgn4MailCenter Resource RidsNrrDeEpnb Resource JWaliace, NRR/DE/EPNB RidsNrrDorlDpr Resource DHuyck, EDO RIV RidsNrrDorlLpl4 Resource ADAMS Accession No. ML13128A129 *SE email dated 4/29/2013 OFFICE NRR/DORULPL4/PM NRR/DORULPL4/LA NRR/DE/EPNB/BC NRR/DORULPL4/BC NAME NKalyanam .1 Burkhardt TLupold* MMarkley DATE 5/14/13 5114113 4/29/13 5/31/13 OFFICIAL RECORD COpy