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Category:Code Relief or Alternative
MONTHYEARML20034E8942020-02-11011 February 2020 Relief Request Gen-ISI-ALT-2019-01 for Proposed Alternative to Use of ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 ML19192A1712019-08-0202 August 2019 Relief from Inservice Impractical ASME Code Requirements (FNP-ISI-RR-03) ML18334A2282018-12-10010 December 2018 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-03 ML18320A0572018-11-30030 November 2018 Plant, Units 1 and 2 - Proposed Inservice Inspection Alternative GEN-ISI-ALT-2017-03, Code Case N-513-4 for Moderate Pressure NL-18-0428, Withdrawal of Proposed Alternative GEN-ISI-ALT-2017-001 Implementation of Code Case N-786-12018-04-0909 April 2018 Withdrawal of Proposed Alternative GEN-ISI-ALT-2017-001 Implementation of Code Case N-786-1 ML17354A9162017-12-28028 December 2017 Inservice Inspection Alternative FNP-ISI-ALT-05-01, Version 1, to Use ASME Code N-854 (CAC Nos. MG0107 and MF0108; EPID L-2017-LLR-0086) ML17298A4162017-11-0101 November 2017 Relief Request FNP-ISI-ALT-22, Inservice Inspection Alternative for Code Case N-786-1 ML17121A0592017-05-18018 May 2017 Inservice Inspection Alternative (FNP-ISI-ALT-20) ML17006A1092017-01-26026 January 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads Inflange Inspection ML16323A3022016-12-0606 December 2016 Alternative to Inservice Inspection Regarding Spent Fuel Pool Cooling System Drain Line Weld ML16264A3212016-10-14014 October 2016 Alternatives for Pumps and Valves Inservice Testing Program NL-15-0942, Proposed Lnservice Inspection Alternative FNP-ISI-ALT-18, Version 1.02015-07-17017 July 2015 Proposed Lnservice Inspection Alternative FNP-ISI-ALT-18, Version 1.0 ML15104A1922015-05-0505 May 2015 Alternative to Inservice Inspection Regarding Reactor Closure Head Closure Head Nozzle and Partial Penetration Welds ML14262A3172014-12-0505 December 2014 (FNP-ISI-ALT-15, Version 1) Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Cold Leg Nozzle Dissimilar Metal Welds (TAC Nos. MF3687 and MF3688) ML14252A0762014-09-23023 September 2014 Alternative to Inservice Inspection for Reactor Vessel Flange Leak-off Lines ML14169A1952014-07-11011 July 2014 Alternative Request Regarding Containment Building Tendon Examination Schedule NL-11-1543, Response to NRC Request for Additional Information Proposed Relief Request FNP-ISI-RR-012011-08-11011 August 2011 Response to NRC Request for Additional Information Proposed Relief Request FNP-ISI-RR-01 ML1017504022010-07-12012 July 2010 Relief Request for Extension of the Reactor Vessel Inservice Inspection (ISI) Date to the Year 2020 (Plus or Minus One Outage) (Tac No. ME3010) ML1005603342010-03-0202 March 2010 Safety Evaluation of Relief Request FNP-ISI-ALT-08 Version 1.0 for Reactor Vessel Nozzle to Safe-end Dissimilar Metal Weld and Adjacent Austenitic Safe-end Weld Examinations NL-09-1379, Evaluation Results Associated with Relief Request RR-P-32009-09-0808 September 2009 Evaluation Results Associated with Relief Request RR-P-3 ML0917300752009-06-29029 June 2009 (Fnp), Units 1 and 2, Evaluation of Third 10-Year Interval Inservice Inspection Program Plan Requests for Relief ML0820500022008-08-0606 August 2008 Safety Evaluation on Relief Request RR-P-2, RR-P-3 from ASME OM Code Requirements NL-07-1718, Relief Request RR-60 (Version 2.0) Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(ii)2007-09-12012 September 2007 Relief Request RR-60 (Version 2.0) Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(ii) ML0713602972007-06-0505 June 2007 Relief, Evaluation of Third 10-Year Interval Inservice Inspection Program Plan Request to Relief Nos. RR-42 Through RR-45, RR- 51, RR-58, RR-59, RR-60, & RR-62 ML0705903082007-03-30030 March 2007 Safety Evaluation of Revised Relief Request RR-12 for the Third-Year Interval and Examination Program for Snubbers ML0627703592006-09-29029 September 2006 Evaluation of Relief Request ISI-GEN-ALT-06-02 NL-06-1713, Proposed Alternative for Application of Pressurizer Nozzle Full-Structural Weld Overlays2006-08-10010 August 2006 Proposed Alternative for Application of Pressurizer Nozzle Full-Structural Weld Overlays ML0608302212006-03-28028 March 2006 Request for Relief No. RR-57 and RR-58 Regarding Containment Tendon Inspections ML0511604142005-05-19019 May 2005 Relief, RR-56, Examination of RPV Lower Shell to Bottom Head Circumferential Weld No. APRI-1-1100-8 ML0510301992005-04-25025 April 2005 RR, ISI Program Intervals for Alternative Alignment of Iwe/Iwl Inspection Program (Tac No. MC4870, MC4871, MC4872, MC4873, MC4874, MC4875) ML0418401692004-06-25025 June 2004 Request for Relief No. 55 from ASME Code Repair Requirements for ASME Code Class 3 Service Water System Piping ML0414800332004-05-26026 May 2004 Relief Request, Use of Alternate Code Case ML0407002582004-03-0909 March 2004 Risk-Informed Inservice Inspection Program - ASME Code Category B-F, B-J, C-F-1, and C-F-2 Piping ML0332800372003-11-21021 November 2003 Safety Evaluation Re. Request to Use ASME Code Case N-661 ML0319904652003-07-17017 July 2003 Second and Third 10-Year Interval Inservice Inspection NL-03-0941, Additional Information Re Request for Technical Specification Changes Unit Two Pressurizer Power Operated Relief Valve Block Valve Surveillance2003-04-29029 April 2003 Additional Information Re Request for Technical Specification Changes Unit Two Pressurizer Power Operated Relief Valve Block Valve Surveillance NL-03-0684, ASME Section XI Requests for Relief Number RR-51 and RR-52 Alternative Repair Technique and Inspection Requirement - Reactor Vessel Head2003-03-28028 March 2003 ASME Section XI Requests for Relief Number RR-51 and RR-52 Alternative Repair Technique and Inspection Requirement - Reactor Vessel Head NL-03-0455, Inservice Inspection Program, Additional Information for Request for Relief No. RR-482003-03-10010 March 2003 Inservice Inspection Program, Additional Information for Request for Relief No. RR-48 L-02-023, Updated Interval (Second 10-Year Interval, Third Period and Third 10-Year Interval, First and Second Periods) Request for Relief No. RR-47 from 1989 ASME Code Requirements2002-12-0505 December 2002 Updated Interval (Second 10-Year Interval, Third Period and Third 10-Year Interval, First and Second Periods) Request for Relief No. RR-47 from 1989 ASME Code Requirements ML0231100042002-11-0707 November 2002 Relief Request, Third 10-Year Interval Inservice Inspection Program Request for Relief, TAC No. MB3776 L-02-018, ASME Section XI Relief Requests Number RR-51 and RR-52 Alternative Repair Technique and Inspection Requirement - Reactor Vessel Head2002-09-18018 September 2002 ASME Section XI Relief Requests Number RR-51 and RR-52 Alternative Repair Technique and Inspection Requirement - Reactor Vessel Head ML0220704762002-07-26026 July 2002 Relief Requests for Third 10 Year Inservice Inspection (ISI) Interval ML0220706212002-07-26026 July 2002 7/26/02, Joseph M. Farley, Unit 2, Request for Relief No. RR-46 for the Third 10-Year Inservice Inspection (ISI) Interval 2020-02-11
[Table view] Category:Letter
MONTHYEARIR 05000348/20240022024-08-12012 August 2024 – Integrated Inspection Report 05000348-2024002 and 05000364-2024002 and Exercise of Enforcement Discretion ML24215A3772024-08-0707 August 2024 2024 Farley Requal Inspection Corporate Notification Letter ML24201A2032024-08-0101 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24200A1392024-07-25025 July 2024 Regulatory Audit in Support of Review of the License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature ML24199A2072024-07-24024 July 2024 TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A3762024-07-0101 July 2024 Nonacceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Using Risk-Informed Process for Evaluations NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0230, Plants Units 1&2, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 Plants Units 1&2, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, ML24143A0412024-05-28028 May 2024 Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000348/20240012024-04-24024 April 2024 Integrated Inspection Report 05000348/2024001 and 05000364/2024001 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions ML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information ML24010A0032024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting IR 05000348/20230402024-01-24024 January 2024 95001 Supplemental Inspection Report 05000348/2023040 and Follow-Up Assessment Letter ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) ML23346A2222023-12-22022 December 2023 Transmittal of Dam Inspection Report - Public NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation ML23228A1432023-11-22022 November 2023 Issuance of Amendment Nos. 249 and 246 to Revise TS 3.6.3, Surveillance Requirement 3.6.3.5 to Eliminate Event-Based Testing of Containment Purge Valves with Resilient Seals NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection ML23318A0672023-10-31031 October 2023 1 to Updated Final Safety Analysis Report, Updated NFPA 805 Fire Protection Program Design Basis Document, Technical Specification Bases Changes, Technical Requirements Manual Changes, IR 05000348/20230032023-10-24024 October 2023 Integrated Inspection Report 05000348/2023003 and 05000364/2023003 IR 05000348/20230912023-10-19019 October 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000348/2023091 IR 05000348/20234022023-10-18018 October 2023 Security Baseline Inspection Report 05000348/2023402 and 05000364/2023402 IR 05000348/20234412023-10-12012 October 2023 Supplemental Inspection Report 05000348/2023441 and 05000364/2023441 and Follow-Up Assessment Letter (Cover Letter) ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding IR 05000348/20230902023-08-31031 August 2023 NRC Inspection Report 05000348/2023090 and Preliminary White Finding and Apparent Violation ML23240A0012023-08-30030 August 2023 Correction to Issuance of Amendment Nos. 241, 242, 243, and 244 ML23164A1202023-08-30030 August 2023 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0, to the Requirements of the ASME Code ML23235A2962023-08-24024 August 2023 Issuance of Amendment Nos. 247 and 244, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, (EPID L-2023-LLA-0116) (Emergency Circumstances) NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit 2024-08-07
[Table view] Category:Safety Evaluation
MONTHYEARML23228A1432023-11-22022 November 2023 Issuance of Amendment Nos. 249 and 246 to Revise TS 3.6.3, Surveillance Requirement 3.6.3.5 to Eliminate Event-Based Testing of Containment Purge Valves with Resilient Seals ML23164A1202023-08-30030 August 2023 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0, to the Requirements of the ASME Code ML23235A2962023-08-24024 August 2023 Issuance of Amendment Nos. 247 and 244, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, (EPID L-2023-LLA-0116) (Emergency Circumstances) ML23202A1122023-08-0202 August 2023 Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23136B1542023-07-0303 July 2023 Issuance of Amendment Nos. 246 & 243, Regarding License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis ML23164A2072023-06-14014 June 2023 Draft Safety Evaluation for License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated SFP Criticality Analysis (EPID L-2022-LLA-0138) - Draft Safety Evaluation ML23054A4552023-03-16016 March 2023 Issuance of Amendment Nos. 245 and 242, Regarding LAR to Revise Technical Specification 3.4.10, Pressurizer Safety Valves, to Decrease Low Side Setpoint Tolerance LCO Value ML22286A0742022-11-0808 November 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Relocate Augmented Piping Inspection Program Details to a Licensee-Controlled Document ML22308A0592022-11-0808 November 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Relocate Augmented Piping Inspection Program Details to a Licensee-Controlled Document ML22069A0042022-04-27027 April 2022 Issuance of Amendments Revision to TSs to Adopt TSTF-269-A, Rev. 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves ML22032A2432022-03-0707 March 2022 Issuance of Amendment Nos. 241 and 238 to Eliminate the Encapsulation Vessels Around the First Containment Spray and Residual Heat Removal / Low Head Safety Injection Recirculation Suction Isolation Valves ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage ML21344A0032022-01-26026 January 2022 Issuance of Amendments Regarding Revision to Use Beacon Power Distribution Monitoring System ML21316A0552022-01-0505 January 2022 1 & 2, and Vogtle Electric Generating Plant, 1 & 2 - Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0163 ML21270A0862021-11-18018 November 2021 Issuance of Amendments Regarding Revision to Technical Specifications 5.7, High Radiation, Administrative Controls ML21217A0912021-09-21021 September 2021 SNC Fleet, Issuance of Amendments Regarding Revision to Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML21167A3152021-07-30030 July 2021 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-541, Rev.2, Add Exceptions to Surveillance Requirements for Valves & Dampers Locked in Actuated Position ML21137A2472021-06-30030 June 2021 Issuance of Amendment Nos. 233 and 230, Regarding Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML21161A2012021-06-22022 June 2021 Associated Independent Spent Fuel Storage Facilities - Reduction in Commitment to the Quality ML20303A1192020-12-11011 December 2020 Issuance of Amendment Nos. 232 and 229 Regarding Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML20224A2852020-10-13013 October 2020 Issuance of Amendment Nos. 231 and 228 to Revise Technical Specifications 3.3.1 and 3.3.7 ML20121A2832020-10-0909 October 2020 Issuance of Amendments 230 and 227 Measurement Uncertainty Recapture Power Uprate ML20196L9292020-10-0606 October 2020 Issuance of Amendment Nos. 229 and 226 Regarding Spent Fuel Pool Criticality Safety Analysis ML20132A2072020-05-0808 May 2020 9 to the Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of the Plant and Chapter 2 (Part 1 of 3); Redacted Version ML20034E8942020-02-11011 February 2020 Relief Request Gen-ISI-ALT-2019-01 for Proposed Alternative to Use of ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 ML19337C3222020-01-29029 January 2020 Issuance of Amendments Revision to Technical Specifications to Adopt TSTF-563 ML19261A0142019-09-23023 September 2019 Correction to Safety Evaluation for Amendment Nos. 225 and 222 Regarding Implementation of NEI 06-09, Revision 0-A ML19175A2432019-08-23023 August 2019 Issuance of Amendments 225 and 222 Implementation of NEI 06-09, Risk-Informed Technical Specifications Initiative 4B, Risk-Managed Technical Specification (Rmts) Guidelines, Revision 0-A ML19213A1942019-08-0808 August 2019 Relief from Impractical American Society of Mechanical Engineers Code Requirements (FNP-ISI-RR-02) ML19192A1712019-08-0202 August 2019 Relief from Inservice Impractical ASME Code Requirements (FNP-ISI-RR-03) ML19156A2622019-07-30030 July 2019 Issuance of Amendments 224 and 221 Performance-Based Fire Protection Alternative for Thermal Insulation Material ML19071A1382019-07-16016 July 2019 Issuance of Amendments 223 and 220 Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations TSTF-51 and TSTF-471 ML19129A2322019-07-0101 July 2019 Inservice Inspection Alternative, FNP-ISI-ALT-05-04, Regarding Examination Frequency for Tendon Anchorhead Replacement ML19064A7742019-04-26026 April 2019 Issuance of Amendments Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum on Shift Staff Tables ML18334A2282018-12-10010 December 2018 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-03 ML18320A0572018-11-30030 November 2018 Plant, Units 1 and 2 - Proposed Inservice Inspection Alternative GEN-ISI-ALT-2017-03, Code Case N-513-4 for Moderate Pressure ML18271A2072018-11-0707 November 2018 Issuance of Amendments 221 and 218 Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow ML18183A0732018-07-26026 July 2018 Unites 1, 2, 3, and 4; and Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2(CAC Nos. MG0188, MG0189, MG0191, MG0192, MG0193, MG0194, and MG0195; EPID L-2017-LLA-0293) ML18151A1742018-06-27027 June 2018 Issuance of Amendment Nos. 219 and 216, Adopt Technical Specification Task Force Traveler TSTF-412, Revision 3, Provide Actions for One Steam Supply to Turbine Driven Afw/Efw Pump Inoperable ML17291A7812018-03-0101 March 2018 Issuance of Amendments to Correct Non-Conservative Technical Specification 3.7.1 (CAC Nos. MF9465 and MF9466; EPID L-2017-LLA-0181) ML17261A0872018-02-28028 February 2018 Issuance of Amendments to Revise Actions of TS 5.5.17, Containment Leakage Rate Testing Program (CAC Nos. MF8844 and MF8845; EPID No. L-2016-LLA-0015) ML18022A1072018-01-25025 January 2018 Inservice Inspection Alternative GEN-ISI-ALT-2017-02, Version 1.0, Regarding the Use of ASME Code Case N-789-1 (CAC Nos. MF9942, MF9943, MF9944, and MF9945; EPID L-2017-LLR-0059) ML17354A9162017-12-28028 December 2017 Inservice Inspection Alternative FNP-ISI-ALT-05-01, Version 1, to Use ASME Code N-854 (CAC Nos. MG0107 and MF0108; EPID L-2017-LLR-0086) ML17271A2652017-12-20020 December 2017 Issuance of Amendments Adopting Alternative Source Term, TSTF-448, and TSTF-312 (CAC Nos. MF8861, MF8862, MF8916, MF8917, MF8918, MF8919; Epids Nos. L-2016-LLA-0017,L-2016-LLA-0018, L-2016-LLA-0019) ML17269A1662017-11-0101 November 2017 Issuance of Amendments Related to NFPA 805 Supplement (CAC Nos. MG0094 and MG0095; EPID L-2017-LLA-0261) ML17298A4162017-11-0101 November 2017 Relief Request FNP-ISI-ALT-22, Inservice Inspection Alternative for Code Case N-786-1 ML17214A5462017-10-0202 October 2017 Issuance of Amendments Regarding the Adoption of TSTF-547, Revision 1, Clarification of Rod Position Requirements ML17205A0202017-09-15015 September 2017 Issuance of Amendments to Revise TS 3.8.9, Distribution Systems - Operating ML17180A4392017-07-18018 July 2017 Inservice Testing Alternative for Pumps Per Code Case OMN-20 (RR-VR-01) ML17152A2182017-06-30030 June 2017 Southern Nuclear Fleet - Issuance of Amendments Regarding the Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing (CAC Nos. MF8176 - MF8181) 2023-08-30
[Table view] |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 July 12, 2010 Mr. Mark J. Ajluni Manager, Nuclear Licensing Farley Nuclear Plant Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Birmingham, Alabama 35201 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 (FARLEY UNIT 2) -RELIEF REQUEST FOR EXTENSION OF THE REACTOR VESSEL INSERVICE INSPECTION DATE TO THE YEAR 2020 (PLUS OR MINUS ONE OUTAGE) (TAC NO. ME3010)
Dear Mr. Ajluni:
By letter dated January 4, 2010, Southern Nuclear Operating Company, Inc. (SNC), proposed an alternative to the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Asme Code), inservice inspection (lSI) interval requirements for the reactor vessel lSI. The alternative, FNP-ISI-AL T-09 for Farley Unit 2, proposes to extend the lSI interval for reactor vessel examination category B-A and B-D welds from 10 to 20 years. This would extend the next reactor vessel lSI date for these components in Farley Unit 2 to the year 2020 (plus or minus one outage). The Nuclear Regulatory Commission (NRC) staff has reviewed SNC's submittal and, based on the information provided, the NRC staff has determined that the proposed alternative provides an acceptable level of quality and safety. Therefore, pursuant to Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a(a)(3)(i), the NRC staff authorizes the use of the proposed alternative to extend the reactor vessel lSI date to the year 2020 (plus or minus one outage), thus extending the fourth lSI interval for Farley Unit 2, Category B-A and B-D components from 10 to 20 years.
M. Ajluni -2 All other requirements of ASME Code,Section XI, for which relief has not been specifically requested remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Sincerely, Gloria Kulesa, Chief Plant Licensing Branch II Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.
Safety cc w/encl: Distribution via
REGUl 0.,. UNITED STATES NUCLEAR REGULATORY COMMISSION
- ... C( .L ('l 0 WASHINGTON, D.C. 20555-0001 ;
- III 1-? ****.... SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING RELIEF REQUEST FNP-ISI-ALT-09 TO EXTEND REACTOR VESSEL WELD EXAMINATIONS SOUTHERN NUCLEAR OPERATING COMPANY, INC. JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-364
1.0 INTRODUCTION
By letter dated January 4, 2010 1 , Southern Nuclear Operating Company, Inc. (SNC), requested Nuclear Regulatory Commission (NRC) approval for Joseph M. Farley Nuclear Plant, Unit 2 (Farley Unit 2), to use an alternative, FNP-ISI-AL T-09, to the requirements of the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code),Section XI, Paragraph IWB-2412, Inspection Program B. Specifically, the alternative was requested pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a(a)(3)(i) to extend the inservice inspection (lSI) interval for examinations of the reactor pressure vessel (RPV) welds (Category B-A) as well as the nozzle-to-vessel welds and inner radius sections (Category B-D) from 10 years to 20 years. The NRC staff verbally authorized the licensee's requested alternative in a teleconference on March 25, 2010. This safety evaluation (SE) documents the basis for the staffs verbal authorization and is written consistently with the information available at the time the verbal authorization was given. 2.0 REGULATORY REQUIREMENTS In accordance with 10 CFR 50.55a(g)(4), SNC is required to perform lSI of ASME Code Class 1, 2, and 3 components and system pressure tests during the first 1 O-year interval and subsequent 1 O-year intervals that comply with the requirements in the latest edition and addenda of Section XI of the ASME Code, incorporated by reference in 10 CFR 50.55a(b), subject to the limitations and modifications listed therein. For the fourth lSI interval at Farley Unit 2, which began on December 1, 2007, the Code of record for the inspection of ASME Code Class 1, 2, and 3 components is the 2001 Edition through the 2003 addenda of the ASME Code,Section XI. The regulation in 10 CFR 50.55a(a)(3) states, in part, that the Director of the Office of Nuclear Reactor Regulation (NRR) may authorize an alternative to the requirements of 10 CFR 50.55a(g).
For an alternative to be authorized, as per 10 CFR 50.55a(a)(3)(i), the licensee must demonstrate that the proposed alternative would provide an acceptable level of quality and safety. 1 Agencywide Documents Access and Management System (ADAMS), Accession No. ML100050080 Enclosure
-2 2.1 Background The lSI of Category B-A and B-D components consists of visual and ultrasonic examinations intended to discover whether flaws have initiated, whether pre-existing flaws have extended, and whether pre-existing flaws may have been missed in prior examinations.
These examinations are required to be performed at regular intervals, as defined in Section XI of the ASME Code. 2.2 Summary ofWCAP-16168-NP, Revision 2 In 2006, the Pressurized Water Reactor (PWR) Owners Group submitted a topical report, WCAP-16168-NP, Revision 1 2 (henceforth referred to as WCAP-16168), to the NRC in support of making a risk-informed assessment of extensions to the lSI intervals for Category B-A and B-D components.
In the report, the PWR Owners Group took data associated with three different PWR plants (referred to as the pilot plants), one designed by each of the main contractors for PWR nuclear power plants in the USA, and performed the necessary studies on each of the pilot plants required to justify the proposed extension for the lSI interval for Category B-A and B-D components from 10 to 20 years. The analyses in WCAP-16168 used probabilistic fracture mechanics tools and inputs from the work described in the NRC's pressurized thermal shock (PTS) risk re-evaluation 3.4. The PWR Owners Group analyses incorporated the effects of fatigue-crack growth and inservice inspection.
Design-basis transient data was used as input to the fatigue-crack growth evaluation.
The effects of lSI were modeled consistently with the previously approved probabilistic fracture mechanics codes 5. These effects were put into evaluations performed with the Fracture Analysis of Vessels-Oak Ridge (FAVOR) code 6. All other inputs were identical to those used in the PTS risk re-evaluation.
From the results of the studies, the PWR Owners Group concluded that the ASME Code,Section XI 1 O-year inspection interval for Category B-A and B-D components in PWR RPVs can be extended to 20 years. Their conclusion from the results for the pilot plants was considered to apply to any plant designed by the three vendors (Westinghouse, Combustion Engineering, and Babcock and Wilcox) as long as the critical, plant-specific parameters (defined in Appendix A of the WCAP) are bounded by the pilot plants. 2.3 Summary of NRC SE on WCAP-16168 The staff's conclusion in its SE 7 on WCAP-16168 indicates that the methodology presented in WCAP-16168, in concert with the guidance provide by Regulatory Guide (RG) 1.174, Rev. 1 8 , is acceptable for referencing in requests to implement alternatives to ASME Code inspection requirements for PWR plants in accordance with the limitations and conditions in the SE. In 2 WCAP-16168-NP, Rev. 1, ADAMS Accession No. ML060330504 3 NUREG-1806, ADAMS Accession No. ML061580318 4 NUREG-1874, ADAMS Accession No. ML070860156 5 WCAP-14572-NP-A, ADAMS Accession No. ML012630327 6 ONRLlNRC/L TR0418, ADAMS Accession No. ML042960391 7 US NRC SE for Footnote 2, May 8,2008, ADAMS Accession Nos. ML081060051 and ML081060045 8 RG 1.174, Rev. 1, ADAMS Accession No. ML023240437
-addition to showing that the subject plant is bounded by the pilot plants' information from Appendix A in the WCAP, the key points of the May 8, 2008, SE are summarized below: The dates identified in the request for alternative should be within plus or minus one refueling cycle of the dates identified in the implementation plan provided to the NRC. Any deviations from the implementation plan 9 should be discussed in detail in the request for alternative.
The maximum proposed lSI interval is 20 years. The requirements for reporting the results of ISis found in the voluntary PTS rule apply in all cases. Licensees that do not implement the voluntary PTS rule must amend their licenses to require that the information and analyses requested in the voluntary PTS rule be submitted for NRC staff review and approval.
The amendment to the license shall be submitted at the same time as the request for alternative lSI interval. The request for alternative lSI interval can use any NRC-approved method to 10 calculate and RT MAX_X However, if the request uses the NUREG-1874 methodology to calculate T 30, then the request should include the analysis described in paragraph (6) of subsection (f) to the voluntary PTS rule. The analysis should be done for all of the materials in the beltline area with at least three surveillance data points If the subject plant is a Babcock &Wilcox designed plant: Licensees must verify that the fatigue-crack growth of 12 heat-up/cool-down transients per year bound the fatigue-crack growth for all of its design-basis transients Licensees must identify the design-basis transients that contribute to significant fatigue-crack growth If the subject plant has RPV forgings that are susceptible to underclad cracking or if the RPV includes forgings with RT MAX_F0 10 values exceeding 240°F, then the WCAP analyses are not applicable.
The licensee must submit a plant-specific evaluation for any extension to the 10-year inspection interval for ASME Code,Section XI, Category B-A and B-D RPV welds. PROPOSED FNP-ISI-AL T-09 FOR FARLEY UNIT 2 Description of Proposed Alternative In FNP-ISI-AL T-09, SNC proposes to defer the ASME Code-required Category B-A and B-D weld lSI of Farley Unit 2 until 2020 (approximately 20 years from the last inspection).
This schedule is consistent with the revised PWR Owners Group Letter, OG-09-454 11 . 9 PWR Owners Group Letter OG-06-356, ADAMS Accession No. ML082210245 10 Defined in NUREG-1874, ADAMS Accession No. ML070860156 11 PWR Owners Group Letter OG-09-454, ADAMS Accession No. ML093370133
-3.2 Components for Which Relief is Requested The affected components are the subject plant RPV and its interior attachments and core support structure.
The following examination categories and item numbers from IWB-2500 and Table IWB-2500-1 of the ASME Code,Section XI, are addressed in this request:
For Relief Request ISI-022: Examination Category Item Number Description B-A B1.11 Circumferential Shell Weld B-A B1.12 Longitudinal Shell Welds B-A B1.21 Circumferential Head Weld B-A B1.30 Shell-to-Flange Weld B-D B3.90 Nozzle-to-Vessel Welds 3.3 Basis for Proposed Alternative The basis for the alternative is found in the NRC-approved version of WCAP-16168 12 (referred to as WCAP-16168-A).
Plant-specific parameters for the subject plant are summarized in Enclosure 1 to the licensee's letter of January 4, 2010. The format of the information is patterned after that found in Appendix A of the WCAP. All of the critical parameters listed in Tables 1, 2, and 3 of Enclosure 1 to the licensee's letter of January 4,2010, are bounded by the WCAP-16168-A pilot plant. 3.4 Duration of Proposed Alternative The licensee requests that the proposed alternative (FNP-ISI-AL T-09) should be applicable for the remainder of the 4 th lSI interval at Farley Unit 2 that currently ends in 2017, but which would be extended to 2027 for the inspection of the subject RPV components.
4.0 STAFF TECHNICAL EVALUATION The NRC staff has reviewed Enclosure 1 to the licensee's letter dated January 4,2010, to make this evaluation.
In Table 1, the "Frequency and Severity of Design-Basis Transients" of Farley Unit 2 were found to be bounded by WCAP-16168-A.
Also, the Farley Unit 2 RPV was layer clad and so was bounded by WCAP-16168-A.
Table 2 of the submittal includes additional information pertaining to previous RPV inspections and the schedule for future ones. The next inspection for Farley Unit 2 would be in 2020, consistent with SNC's application of January 4, 2010. This is also consistent with the revised PWR Owners Group Letter OG-09-454.
There were a total of 14 indications detected in the most recent inservice inspection, including 8 found in the inner 3/8 inch of the RPV thickness.
All of the indications were acceptable per IWB-3500 of ASME Code,Section XI and the requirements of the proposed alternate PTS Rule (10 CFR 50.61 a), so therefore, there is no requirement for remedial action or further analysis.
12 WCAP-16168-NP-A, Rev. 2, ADAMS Accession No. ML082820046 The calculation ofTWCF95_ToTAL10 was performed using Table 3 of the submittal as a basis. The request uses RG 1.99, Rev. 2 methodology to calculate Ll T 30. The calculations were independently verified via the NRC staff's calculation and the difference between the licensee's and staff's calculations were found to be insignificant.
The TWCF95-TOTAL was found to be acceptably low as calculated through the methodology prescribed in RG 1.99, Rev. 2 and detailed in Table 3 of the submittal.
At the time of issuance of the SE for WCAP-16168-A, it was the NRC staffs intent to establish a process by which licensees could receive approval to implement 20-year lSI intervals for the subject component examinations through the end of their facility's current operating license. This objective led to the provision, as discussed in Section 4 of the SE for WCAP-16168-A, that the licensee would submit a license condition which required the licensee to evaluate future vOlumetric lSI data in accordance with the criteria in the draft and/or final alternative PTS Rule, 10 CFR 50.61 a. The NRC staff has since determined that the appropriate process for requesting further extensions of the lSI interval, beyond this granting of relief in response to SNC's application of January 4,2010, is through 10 CFR 50.55a for each subsequent lSI Interval.
Accordingly, the NRC staff considers that such a license condition as discussed above is not necessary and that requirements for future evaluation of lSI data will be addressed as a part of the review of further requests for extension of the lSI Interval for the subject components.
The NRC staff will grant lSI interval extensions for the subject components on an interval-by-interval basis, Le., only a facility's current lSI interval will be extended for up to 20 years. Licensees will have to submit updated alternatives to the NRC for review and approval to extend each following lSI interval from 10 years to 20 years, as needed. Accordingly, the requirement in WCAP-16168-A for a license condition to address the evaluation of future lSI data (see Section 2.3, item 2) is no longer necessary in conjunction with this requested alternative.
However, in order to obtain the NRC staff's approval, a subsequent updated alternative that seeks to extend an lSI interval from 10 to 20 years for the subject component examinations should include the evaluation of a facility's most recent lSI data in accordance with the criteria in the final alternative PTS Rule, 10 CFR 50.61 a. For purposes of technical and regulatory consistency, the NRC staffs SE for WCAP-16168-A will be revised to reflect these changes regarding the implementation of lSI interval extensions based on WCAP-16168-A.
Therefore, the staff approves the proposed alternative FNP-ISI-AL T-09 only for the fourth lSI interval that will now end on 2027 for the subject component examinations.
In summary, the licensee has demonstrated through the submittal that the RPV for Farley Unit 2 is bounded by WCAP-16168-A.
The submittal demonstrates that there is no significant additional risk associated with extending the lSI interval for Category B-A and B-D components from 10 years to 20 years.
5.0 CONCLUSION
The NRC staff has completed its review of the January 4, 2010, submittal for FNP-ISI-AL T-09 regarding Farley Unit 2. The staff concludes that increasing the lSI interval for Category B-A and B-D components from 10 years to 20 years results in no appreciable increase in risk. The staff comes to this conclusion based on the fact that the plant-specific information provided by SNC is bounded by the data in WCAP-16168-A and the request meets all the conditions and limitations described in WCAP-16168-A.
Therefore, Relief Request FNP-ISI-ALT-09 provides
-6 an acceptable level of quality and safety and the alternative is granted pursuant to 10 CFR 50.55a(a)(3)(i) until the end of the 4th lSI interval for Categories B-A and B-D components at Farley Unit 2 in 2027. All other requirements of the ASME Code,Section XI, not specifically included in the request for the proposed alternatives, remain in effect. Principal Contributor:
Patrick Purtscher, NRR/DCI Date: July 12, 2010 M. Ajluni -2 All other requirements of ASME Code,Section XI, for which relief has not been specifically requested remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Sincerely, IRA! Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.
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