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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 ML20365A0012021-01-19019 January 2021 Relief Request 5-8 Related to ASME Code Case N-729-4 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles ML20282A7642020-10-16016 October 2020 Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant - Relief Request 5-8 for Alternate Repair of Reactor Closure Head Penetration Nozzles ML20275A3432020-10-0101 October 2020 Verbal Authorization for Proposed Alternative (RR 5-8) Reactor Vessel Closure Head Penetration Repairs ML20272A1662020-09-30030 September 2020 Attachment 3 - Framatome Document No. ANP-3876, Revision 1Q1NP, Response to NRC Request for Additional Information of Palisades Relief Request Number RR 5-8, Repair of Reactor Pressure Vessel Head Penetration, Inservice Inspection Program, ML20267A3872020-09-23023 September 2020 Relief Request Number RR 5-8, Proposed Alternative to ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations ML20267A3882020-09-23023 September 2020 Attachment 1 - Relief Request Number RR 5-8, Proposed Alternative to ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations 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) 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 CNRO-2019-00002, Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-01-31031 January 2019 Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 ML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 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 ML21067A4982017-09-0707 September 2017 Relief Request No. RR 5-4 Proposed Alternative, Weld Reference System ML17194A8072017-08-14014 August 2017 Relief Request No. RR 4-25 Limited Coverage Examinations During the Fourth 10-Year Inservice Inspection Interval ML17137A0282017-06-29029 June 2017 Relief Request Number RR 5; 5 Proposed Alternative, Under-Vessel Leakage Examination 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 ML16022A1072016-02-0101 February 2016 Relief Request Number RR 4-23- Proposed Alternative Concerning ASME Code Depth Sizing Requirement ML15320A2442015-11-25025 November 2015 Relief Request Number 5-1, Proposed Alternative, Extend the Current ASME Code of Record Into the Fifth 10-Year ISI Interval for ISI Related Activities PNP 2015-073, Forwards Response to Request for Additional Information Regarding Relief Request Number RR 4-22 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination2015-09-17017 September 2015 Forwards Response to Request for Additional Information Regarding Relief Request Number RR 4-22 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination PNP 2015-075, Submittal of Relief Request Number RR 4-23, Proposed Alternative Concerning ASME Code Depth Sizing Requirement2015-09-16016 September 2015 Submittal of Relief Request Number RR 4-23, Proposed Alternative Concerning ASME Code Depth Sizing Requirement 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 PNP 2015-024, Requests Relief of Proposed Alternatives for the Fifth 10-Year Inservice Test Interval2015-05-19019 May 2015 Requests Relief of Proposed Alternatives for the Fifth 10-Year Inservice Test Interval PNP 2015-022, Relief Request Number RR 5-1, Proposed Alternative, Extend the Current ASME Code of Record Into the Fifth 10-year ISI Interval for ISI Related Activities2015-04-29029 April 2015 Relief Request Number RR 5-1, Proposed Alternative, Extend the Current ASME Code of Record Into the Fifth 10-year ISI Interval for ISI Related Activities ML14199A5572014-08-13013 August 2014 Relief Request Number RR-4-19, Proposed Alternative to the Requirements of ASME Code Case N-638-4 ML12258A3522012-09-26026 September 2012 Relief from Certain Requirements of the ASME Code Case N-77-1 for the Fourth 10-Year 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 ML0824801002008-09-19019 September 2008 Acceptance of Requested Licensing Action Relief Request and Supporting Amendment to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examination ML0726304272007-09-21021 September 2007 Relief, Request Relief No. 1 - from Requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Requirements for Repair of Pressurizer Nozzle Penetrations ML0719002512007-09-12012 September 2007 Relief Request 1 for the Repair of Reactor Vessel Closure Head Penetrations ML0716201362007-09-12012 September 2007 Relief Request 2 for ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations ML0716302482007-05-31031 May 2007 Request for Relief from ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Vent Line Penetration ML0709200292007-04-30030 April 2007 Request for Relief from ASME Code Regarding Weld Reference System, Relief Request No. RR 4-11 ML0617103642006-07-0303 July 2006 Monticello Nuclear Generating Plant, Palisades Nuclear Plant, Point Beach Nuclear Plant Units 1 and 2, Prairie Island Nuclear Generating Plant, Units 1 and 2 - Use of ASME Code Case N-513-2 ML0607902512006-04-0303 April 2006 Request for Relief from ASME Code, Section XI, Requirements for Repair of Pressurizer Nozzle Penetrations ML0607900612006-04-0303 April 2006 Request for Authorization to Use Alternatives to ASME Code, Section XI, IWA-3300, IWBb-3142.4, IWB-3420, and IWB-3613 for Reactor Pressure Vessel Head Penetration Repair ML0608003192006-04-0303 April 2006 Request for Authorization to Use Alternatives to ASME Code, Section XI, IWA-4120 for Reactor Pressure Vessel Head Penetration Repair ML0605800602006-03-21021 March 2006 Request for Authorization of Relief Request Number 1 for Certain Requirements in ASME Code, Section XI, Code Case N-638-1 ML0601201042006-01-27027 January 2006 Request for Authorization to Extend the Third 10-Year ISI Interval for Reactor Vessel Visual Examination, MC6546 ML0532002962005-11-29029 November 2005 Request for Authorization to Extend the Third Inservice Inspection Interval for Reactor Vessel Weld Examination ML0520706392005-08-17017 August 2005 Revised Relief Requests 28, 30, and 31 for 3rd 10-year Pump and Valve Inservice Testing ML0436504802005-01-18018 January 2005 Relief Request to Use Code Case N-661, and Safety Evaluation ML0430901912004-11-0808 November 2004 Relief, ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations ML0430605712004-11-0303 November 2004 Verbal Authorization of Relief from ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations ML0419103642004-09-14014 September 2004 Relief, Third 10-Year Interval Inservice Inspection Program Plan ML0422402492004-08-0909 August 2004 Request for Relief from ASME Section XI Code Requirements for Repair of Pressurizer Nozzle Penetrations ML0401607382004-02-26026 February 2004 Prairie, Units 1 and 2, Kewaunee, Point Beach, Units 1 and 2, Palisades, Re Request for Alternatives to ASME Section XI, Appendix Viii, Supplement 10 ML0311505002003-05-19019 May 2003 Risk-Informed Inservice Inspection Program TAC No. MB4420 ML0306906292003-03-20020 March 2003 3/20/2003, Palisades, Relief, Re Third Inservice Inspection Interval Program ML0207202292002-03-0101 March 2002 Relief Code, Relief Request for Alternate ASME Code, Section XI, Risk-Informed Inservice Inspection Program ML0207201452002-02-27027 February 2002 Code Relief, Request for Relief from ASME Code Requirements for Inservice Inspection Pressure Test Program (Relief Request PR-07) 2021-10-28
[Table view] Category:Letter
MONTHYEARML24022A1172024-01-23023 January 2024 Acceptance of Requested Licensing Action Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML24012A2422024-01-16016 January 2024 Acceptance of Requested Licensing Action License Transfer Request ML23236A0042023-12-27027 December 2023 Issuance of Amendment 274 Re Changes to Perm Defueled Emergency Plan and Perm Defueled Emergency Action Level Scheme ML23355A1242023-12-26026 December 2023 Withdrawal of an Amendment Request Re License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML23192A0772023-12-26026 December 2023 Letter Exemption from the Requirements of 10 CFR 140.11(a)(4) Concerning Offsite Primary and Secondary Liability Insurance ML23191A5222023-12-22022 December 2023 Exemption Letter from the Requirements of 10 CFR 50.54(W)(1) Concerning Onsite Property Damage Insurance (EPID - L-2022-LLE-0032) ML23263A9772023-12-22022 December 2023 Exemption from Certain Emergency Planning Requirements and Related Safety Evaluation ML23354A2602023-12-21021 December 2023 Reference Simulator Inspection Request for Information L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 PNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations PNP 2023-035, Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements2023-12-12012 December 2023 Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements PNP 2023-028, Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments2023-12-0606 December 2023 Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23291A4402023-11-0303 November 2023 Acceptance of Requested Licensing Action Request for Exemption from 10 CFR 50.82(a)(2) to Support Reauthorization of Power Operations IR 05000255/20230032023-10-0404 October 2023 NRC Inspection Report No. 05000255/2023003(DRSS)-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23275A0012023-10-0202 October 2023 Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant PNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023 Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 PNP 2023-026, Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations2023-09-28028 September 2023 Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations PNP 2023-023, Special Report High Range Noble Gas Monitor Inoperable2023-08-0909 August 2023 Special Report High Range Noble Gas Monitor Inoperable ML23215A2302023-08-0303 August 2023 Notice of Organization Change - Chief Nuclear Officer IR 05000255/20230022023-07-19019 July 2023 NRC Inspection Report 05000255/2023002 DRSS-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23087A0362023-05-0202 May 2023 PSDAR Review Letter ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment PNP 2023-018, 2022 Annual Non-Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Non-Radiological Environmental Operating Report L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 PNP 2023-007, and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports2023-04-19019 April 2023 and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports PNP 2023-008, 2022 Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Radiological Environmental Operating Report L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations PNP 2023-002, 6 to Updated Final Safety Analysis Report2023-03-31031 March 2023 6 to Updated Final Safety Analysis Report ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance PNP 2023-006, Report of Changes to Security Plan, Revision 202023-03-29029 March 2023 Report of Changes to Security Plan, Revision 20 PNP 2023-012, Presentation on Regulatory Path to Reauthorize Power Operations2023-03-16016 March 2023 Presentation on Regulatory Path to Reauthorize Power Operations ML23038A0982023-03-15015 March 2023 Request for Withholding Information from Public Disclosure ML23095A0642023-03-14014 March 2023 American Nuclear Insurers, Notice of Cancellation Rescinded PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations PNP 2023-004, Report of Changes to Palisades Nuclear Plant Technical Specification Bases2023-03-0808 March 2023 Report of Changes to Palisades Nuclear Plant Technical Specification Bases PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23052A1092023-02-17017 February 2023 FEMA Letter to NRC, Proposed Commission Paper Language for Palisades Nuclear Plant Emergency Plan Decommissioning Exemption Request ML23032A3992023-02-0101 February 2023 Regulatory Path to Reauthorize Power Operations IR 05000255/20220032022-12-28028 December 2022 NRC Inspection Report No. 05000255/2022003(DRSS); 07200007/2022001 (Drss) Holtec Decommissioning International, LLC, Palisades Nuclear Plant L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 PNP 2022-037, Report of Changes to Security Plan, Revision 192022-12-14014 December 2022 Report of Changes to Security Plan, Revision 19 ML22321A2852022-11-17017 November 2022 LLC Master Decommissioning Trust Agreement for Palisades Nuclear Plant IR 05000255/20224012022-11-0909 November 2022 Decommissioning Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2022401 PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-035, International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations2022-11-0202 November 2022 International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations PNP 2022-024, Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance PNP 2022-026, Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance ML22292A2572022-10-25025 October 2022 Permanently Defueled Emergency Plan License Amendment RAI Letter 2024-01-23
[Table view] Category:Safety Evaluation
MONTHYEARML23263A9772023-12-22022 December 2023 Exemption from Certain Emergency Planning Requirements and Related Safety Evaluation ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML22039A1982022-05-13013 May 2022 Issuance of Amendment No. 272 Permanently Defueled Technical Specifications ML21292A1482021-12-13013 December 2021 Safety Evaluation Related to Request for Direct and Indirect Transfers of Control of Facility Operating License DPR-6 for Big Rock Point and Renewed Facility Operating License DPR-20 for Palisades Nuclear Plant and ISFSI (EPID L-2020-LLM-00 ML21292A1472021-12-13013 December 2021 Draft Conforming License Amendments - Palisades Nuclear Plant Renewed Facility Operating License DPR-20 and ISFSI and Big Rock Point Facility Operating License DPR-6 and ISFSI (EPID L-2020-LLM-0003) (Enclosure 2) ML20365A0012021-01-19019 January 2021 Relief Request 5-8 Related to ASME Code Case N-729-4 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI ML19317D8552019-12-30030 December 2019 Issuance of Amendment No. 271 Regarding Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML19318E3942019-12-0202 December 2019 Reactor Vessel Material 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 ML19198A0802019-08-20020 August 2019 Issuance of Amendments No. 269 Regarding Changes to NFPA 805 Modifications and Change to Full Compliance Implementation Date for the Fire Protection Program (Epids L-2018-LLA-0296 and L-2019-LLA-0049) ML19135A0502019-05-21021 May 2019 Correction to Safety Evaluation for Amendment No.268 Regarding Revision to Diesel Generator Undervoltage Start Surveillance Requirement ML19107A0532019-05-13013 May 2019 Issuance of Amendment No. 268 Regarding Revision to Diesel Generator Undervoltage Start Surveillance Requirement ML19112A3172019-04-26026 April 2019 Approval of Alternative for Repair of Reactor Pressure Vessel Head Penetrations ML18170A2192018-09-24024 September 2018 Issuance of Amendment Changes to the Emergency Plan for Permanently Defueled Condition (CAC No. MG0198; EPID L-2017-LLA-0305) 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 ML18114A4102018-06-0404 June 2018 Issuance of Amendment Regarding Administrative Controls for Permanently Defueled Condition (CAC No. MG0021; EPID L-2017-LLA-0266) ML18135A2632018-05-21021 May 2018 Relief Request No. RR 5-6 Alternate to the Reexamination Frequency for a Relevant Condition ML18039A2442018-02-27027 February 2018 Issuance of Amendment License Amendment Request to Change the Full Compliance Implementation Date for the Fire Protection Program Transition License Condition for Required Modifications ML17328B0332017-12-15015 December 2017 Issuance of Amendment Cyber Security Plan Implementation Schedule (CAC No. MF9523; EPID L-2017-LLA-0199) ML21067A4982017-09-0707 September 2017 Relief Request No. RR 5-4 Proposed Alternative, Weld Reference System ML17151A3502017-08-21021 August 2017 Approval of Certified Fuel Handler Training and Retraining Program ML17194A8072017-08-14014 August 2017 Relief Request No. RR 4-25 Limited Coverage Examinations During the Fourth 10-Year Inservice Inspection Interval ML17137A0282017-06-29029 June 2017 Relief Request Number RR 5; 5 Proposed Alternative, Under-Vessel Leakage Examination ML17121A5102017-06-0808 June 2017 Issuance of Amendment License Amendment Request for Editorial and Administrative Changes to Technical Specifications ML17082A4652017-05-30030 May 2017 Issuance of Amendment Application to Revise Technical Specifications to Adopt TSTF 545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ML16300A0302016-12-19019 December 2016 Issuance of Amendment Revision to the Requirements for Steam Generator Tube Inspections and Repair Criteria in the Cold Leg Tube Sheet Region ML16281A4982016-10-28028 October 2016 Issuance of Amendment No. 260, Revise License Condition 2.C.(4) and Technical Specifications Related to Control Rod Drive Exercise Surveillance ML16251A6202016-09-13013 September 2016 Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) ML16014A3182016-08-22022 August 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 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 ML16078A0682016-05-0202 May 2016 Issuance of Amendment Cyber Security Plan Implementation Schedule ML16043A4852016-03-14014 March 2016 Relief Request Number RR 4-24 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination ML16022A1072016-02-0101 February 2016 Relief Request Number RR 4-23- Proposed Alternative Concerning ASME Code Depth Sizing Requirement ML15334A3072015-12-22022 December 2015 Relief Request Numbers RR 5-2 and 5-3, Proposed Alternative to the Requirements of the ASME OM Code for the Fifth 10-Year Inservice Test Interval ML15320A2442015-11-25025 November 2015 Relief Request Number 5-1, Proposed Alternative, Extend the Current ASME Code of Record Into the Fifth 10-Year ISI Interval for ISI Related Activities ML15103A0592015-05-18018 May 2015 Issuance of Amendment Adoption of TSTF-426, Revision 5, Revise or Add Actions to Preclude Entry Into Limiting Condition for Operation 3.0.3 - RITSTF Initiatives 6B and 6C. ML15055A1062015-04-22022 April 2015 Issuance of Amendment License Amendment Request to Revise Emergency Response Organization Staff Augmentation Response Times ML15007A1912015-02-27027 February 2015 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) ML14237A1442014-12-0808 December 2014 Issuance of Amendment Cyber Security Plan Implementation Schedule ML14283A2872014-10-22022 October 2014 Issuance of Amendment Application for Technical Specification Change (TSTF-427) to Add Limiting Condition for Operation 3.0.9 Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process ML14223B2262014-09-0404 September 2014 Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination ML14199A5572014-08-13013 August 2014 Relief Request Number RR-4-19, Proposed Alternative to the Requirements of ASME Code Case N-638-4 ML14210A2662014-08-0808 August 2014 Arkansas, Units 1 & 2, Big Rock Point, James A. Fitzpatrick, Grand Gulf, Unit 1, Indian Point, Units 1, 2 & 3, Palisades, Pilgrim, River Bend, Unit 1, Vermont Yankee, Waterford, Safety Evaluation Quality Assurance Program Manual, Rev. 24 & ML13312A4232013-11-26026 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13129A2192013-05-29029 May 2013 Staff Assessment in Response to Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13025A3062013-03-14014 March 2013 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Correction to Amendments Issued on 12/28/12, Revise QA Program Manual and Staff Qualification Technical Specifications ML13056A5142013-02-28028 February 2013 Non-Proprietary Issuance of Amendment Regarding Replacement of Spent Fuel Pool Region 1 Storage Racks 2023-05-01
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Vice President, Operations Entergy Nuclear Operations, Inc. Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Ml 49043-9530 August 13, 2014
SUBJECT:
PALISADES NUCLEAR PLANT-RELIEF REQUEST NUMBER RR-4-19, PROPOSED ALTERNATIVE TO THE REQUIREMENTS OF ASME CODE CASE N-638-4 (TAC NO. MF3517)
Dear Sir:
By letter dated February 26, 2014 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML 14057A766),
as supplemented by letter dated March 5, 2014 (ADAMS Accession No. ML 14064A475),
Entergy Nuclear Operations, Inc. (the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the use of alternatives to certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV Code) requirements at Palisades Nuclear Plant (PNP). Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR) 50.55a(a)(3)(ii),
the licensee requested relief from article IWA-4000 of Section XI of the ASME Code to permit the use of modified ASME Code Case N-638-4 to repair the dissimilar metal butt weld of pressurizer safety relief valve, RV-1 041, on the basis that complying with the specified requirement would result in hardship or unusual difficulty.
On March 6, 2014, the NRC staff verbally authorized the use of Relief Request Number 4-19 at PNP (ADAMS Accession No. ML 14066A 130) for the fourth 1 0-year inservice inspection (lSI) interval which ends on December 12, 2015. This safety evaluation (SE) provides the technical basis for the verbal authorization.
The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed SE, that Entergy Nuclear Operations, Inc. has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(ii) and is in compliance with the requirements of the ASME Code,Section XI for which relief was not requested.
Therefore, the NRC staff authorizes the use of Relief Request RR 4-19 at the PNP for the fourth 10-year lSI interval which ends on December 12, 2015. All other requirements of the ASME Code,Section XI, for which relief has not been specifically requested and authorized by NRC staff remain applicable, including a third party review by the Authorized Nuclear lnservice Inspector. If you have any questions, please contact the Project Manager, Jennivine Rankin at 301-415-1530 or via e-mail at Jennivine.Rankin@nrc.gov.
Docket No. 50-255
Enclosure:
Safety Evaluation cc w/encl: Distribution via ListServ David Pelton, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST NUMBER RR 4-19 ALTERNATIVE REPAIR OF WELD AT PRESSURIZER SAFETY RELIEF VALVE NOZZLE PALISADES NUCLEAR PLANT ENTERGY NUCLEAR OPERATIONS, INC. DOCKET NO. 50-255
1.0 INTRODUCTION
By letter dated February 26, 2014 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML 14057A766),
and supplement dated March 5, 2014 (ADAMS Accession No. ML 14064A475),
Entergy Nuclear Operations, Inc. (the licensee) requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, IWA-4000, at Palisades Nuclear Plant (PNP). The proposed alternative is documented in Relief Request RR 4-19 for the repair of degraded weld PCS-6-PRS-1 C 1-1 of pressurizer safety relief valve, RV-1 041, for the fourth 1 0-year inservice inspection (lSI) interval.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR) 50.55a(a)(3)(ii),
the licensee requested relief from article IWA-4000 of Section XI of the ASME Code to permit the use of modified ASME Code Case N-638-4 to repair the dissimilar metal butt weld of pressurizer safety relief valve, RV-1 041, on the basis that complying with the specified ASME Code requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. On March 6, 2014, the NRC staff verbally authorized the use of Relief Request Number RR 4-19 at PNP (ADAMS Accession No. ML 14066A130) for the fourth 10-year lSI interval which ends on December 12, 2015. This safety evaluation documents the NRC staff's detailed technical basis for the verbal authorization.
Enclosure 2.0 REGULATORY EVALUATION In Relief Request RR 4-19, the licensee requests authorization of an alternative to the requirements of article IWA-4000 of Section XI of the ASME Code pursuant to Title 10, Code of Federal Regulations, Part 50 (1 0 CFR 50), paragraph 55a(a)(3)(ii).
Adherence to article IWA-4000 of Section XI of the ASME Code is mandated by 10 CFR 50.55a(g)(4),
which states, in part, that ASME Code Class 1, 2, and 3 components (including supports) will meet the requirements, except the design and access provisions and the pre-service examination requirements set forth in the ASME Code,Section XI. 10 CFR 50.55a(a)(3) states, in part, that alternatives to the requirements of paragraph (g) of 10 CFR 50.55a may be used, when authorized by the NRC, if the licensee demonstrates that: (i) the proposed alternative provides 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 the above, and subject to the following technical evaluation, the NRC staff concludes that regulatory authority exists for the licensee to request the use of an alternative and for the NRC to authorize the proposed alternative.
3.0 TECHNICAL EVALUATION 3.1 Relief Request RR 4-19 3.1.1 Description The affected component is the dissimilar metal weld, number PCS-6-PRS-1 C1-1, of the pressurizer safety relief valve, RV-1 041. During the current 1 R23 refueling outage, the licensee detected two axial indications in the root area of weld PCS-6-PRS-1C1-1 which is located between the pressurizer shell nozzle and the flange for the safety relief valve. The licensee reported that these two indications did not meet applicable acceptance criteria under the ASME Code,Section XI, Table IWB-3410, "Acceptance Standards,"
and require a repair/replacement activity to return the weld to an acceptable condition
.. By letter dated February 26, 2014, the licensee describes the existing design of the affected components:
In the existing design, the pressurizer safety relief valve nozzle configuration contains
[Alloy 600/82/182]
materials that are susceptible to primary water stress corrosion cracking (PWSCC).
First, the safety relief valve weld neck flange was manufactured from SB-166, UNS N06600 (Alloy 600) nickel alloy while the DMW [dissimilar metal weld] attaching the flange to the vessel nozzle was fabricated from Alloy 82/182 filler metal. The nozzle was manufactured from low alloy steel A-508, Class 2 material, and the pressurizer upper head is low alloy steel A-533, Grade B Class 1. 3.1.2 Licensee's Proposed Alternative and Bases for Use The code of record is ASME,Section XI, 2001 Edition through 2003 Addenda as amended by 10 CFR 50.55a. As stated in the licensee's supplemental information dated March 5, 2014: ASME Section XI, IWA-4411 requires that welding and installation activities be performed in accordance with the original Construction Code of the component or item. IWA-4411 also includes the following alternatives:
- As an alternative to the original Construction Code, IWA-4411 (a) allows use of later Editions/Addenda of the Construction Code. However, if welding is performed in accordance with the Construction Code regardless of which Edition or Addenda is used, conventional PWHT [post-weld heat treatment]
would be required.
- IWA-4411 (e) also allows use of the temper bead welding requirements of IWA-4600 as an alternative to the PWHT requirements of the Construction Code. However, in this case, the IWA-4600 temper bead rules require application of an elevated preheat temperature and a post weld soak. As an alternative to the welding provisions of IWA-4411, to repair the subject weld, the licensee requests to use ASME Code Case N-638-4, "Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW Temper Bead Technique,Section XI, Division 1 ," modified so that it can be used for a through-wall butt weld. As stated in Relief Request RR 4-19 dated February, 26, 2014: Code Case N-638-4 allows for ambient temperature temper bead welding of ferritic materials without the requirement for elevated preheat or post weld heat treatment.
In addition, Code Case N-638-4, paragraph 1 (b), requires that "the depth of the weld shall not be greater than one-half of the ferritic base metal thickness".
The NRC approved Code Case N-638-4 in Regulatory Guide (RG) 1.147, "lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1 ," (Reference
- 5) with the following conditions:
( 1) Demonstration for ultrasonic examination of the repaired volume is required using representative samples which contain construction type flaws. (2) The provisions of 3(e)(2) or 3(e)(3) [of the code case] may only be used when it is impractical to use the interpass temperature measurement methods described in 3(e)(1 ), such as in situations where the weldment area is inaccessible (e.g., internal bore welding) or when there are extenuating radiological conditions. The RG 1.147 conditions do not apply to the planned repair/replacement activity at Palisades as discussed in Sections 3 and 4 below. Condition
( 1) [of R G 1. 14 7] does not apply because radiography will be used for the required volumetric examination per the Construction Code (Reference 7). The use of radiography as a volumetric examination method complies with paragraph 4(a) of N-638-4.
Condition (2) [of RG 1.147] does not apply because interpass temperature measurement will be performed by direct measurement using the provision of 3(e)(1) [of the code case] and will not be performed using the provisions of either 3(e)(2) or 3(e)(3).
The licensee will completely remove the original Alloy 82/182 DMW, install a new Alloy 52M DMW, and examine it in accordance with the 1992 Edition of ASME Section Ill, Subsection NB. However, in lieu of the preheat and post-weld heat treatment requirements of the Construction Code, the licensee plans to install the Alloy 52M weld buttering across the face and full circumference of the weld end preparation of the A-508, Class 2 nozzle using the ambient temperature temper bead provisions of Code Case N-638-4.
By letter dated February 26, 2014, the licensee proposed the following alternative:
Pursuant to 10 CFR 50.55a(a)(3)(ii),
ENO proposes an alternative to the provision in paragraph 1 (b) of N-638-4 that limits the depth of the weld to half the ferritic base metal thickness."
More specifically, ENO proposes to use the new alternative provision in paragraph 1 (b)(1) of N-638-5 which states: (1) Through-wall circumferential welds are permitted if the following restrictions are met: (a) For repair/replacement activities associated with existing welds, the existing weld (including any associated buttering) shall be removed in its entirety.
(b) Temper bead buttering shall be applied across the entire face of the weld preparation area on the base materials requiring tempering, and shall extend around the full circumference of the joint. ENO will replace the existing nozzle/flange assembly with a modified design. The modification will replace the existing SB-166, Alloy 600 weld neck flange with an SA-182 F316 austenitic stainless steel flange, which is less susceptible to PWSCC. Alloy 82/182 weld material will be removed and the nozzle cut back slightly to assure that all of the original weld metal is removed.
The new DMW between the stainless steel weld neck flange and low alloy steel nozzle will be made with ERNiCrFe-7A (Alloy 52M) weld metal [which is less susceptible to PWSCC than Alloy 82/182 weld metal]. The weld neck flange will be slightly longer to make up for the removal of the original weld metal, but the overall length from the vessel to the safety valve bolted flanged joint will remain the same. The change is essentially like-for-like in its geometry, with only the materials being changed. The welding operation for the DMW, as shown in Figure 2, includes the following basic steps: 1. Install Alloy 52M weld buttering across the entire face and circumference of the weld end preparation of the A-508, Class 2 nozzle. 2. Install ER308L buffer layer and Alloy 52M buttering across the entire face circumference of the weld end preparation of the SA-182, F316 stainless steel flange. 3. Complete the Alloy 52M groove weld. Code Case N-638-4 and [N-638-]5 specify requirements for performing ambient temperature temper bead welding using the machine gas Tungsten Arc Welding (GTAW) process.
Research by the Electric Power Research Institute (EPRI) and other organizations on the use of an ambient temperature temper bead welding operation using the machine GTAW process is documented in EPRI Report GC-111050, "Ambient Temperature Preheat for Machine GTAW Temper Bead Applications."
According to the EPRI report, repair welds performed with an ambient temperature temper bead procedure utilizing the machine GTAW welding process exhibit mechanical properties equivalent or better than those of the surrounding base material.
Laboratory
- testing, analysis, successful procedure qualifications, and successful repairs have all demonstrated the effectiveness of this process.
EPRI Report GC-111050, Section 6.0 concluded the following:
"Repair of RPV components utilizing machine GTAW temper bead welding at ambient temperature produces mechanical properties that are commonly superior to those the service-exposed substrate.
The risk of hydrogen delayed cracking is minimal using the GTAW process.
Cold stress cracking is resisted by the excellent toughness and ductility developed in the weld HAZ (heat affected zone). Process design and geometry largely control restraint considerations, and these factors are demonstrated during weld procedure qualification."
ENO plans to deposit the Alloy 52M butter layers to the weld end preparation of the low alloy steel A-508, Class 2 nozzle using Code Case N-638-4.
- However, paragraph 1 (b) of N-638-4 limits the depth of the weld to one-half the ferritic base material thickness.
The incorporation of this weld depth limitation is likely the result of concerns related to the high restraint that a repaired weld would experience if a localized or partial-depth weld repair was performed.
As stresses build under a high degree of restraint, cracking may occur at defect locations.
It should be noted that paragraph 1 (b) of N-638-5 also limits the depth of weld repairs to one-half the thickness of the ferritic base material.
While paragraph 1 (b)(1) does allow through-wall circumferential welds to be made, the following two requirements must be met: a) The existing weld (including any associated buttering) shall be removed in its entirety. b) Temper bead buttering shall be applied across the entire face of the weld preparation area on the base materials requiring tempering, and shall extend around the full circumference of the joint. The restrictions in paragraphs 1 (b)(1) of N-638-5 preclude the high restraint associated with localized and partial-depth weld repairs.
Regarding the PNP pressurizer nozzle DMW, only the weld butter will be deposited with the ambient temperature temper bead rules of [Code Case] N-638-4 [since only the weld with the ferritic nozzle requires post weld heat treatment by the ASME Code]. Upon completion of all welding, the DMW will be nondestructively examined in accordance with paragraph 4(a) of Code Case N-638-4.
These nondestructive examinations will be performed at least 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after completing the third temper bead layer and will include liquid penetrant and radiographic examinations.
The provisions of Code Case N-638, and its revisions, ensure that the impact properties of the ferritic heat affected zone (HAZ) are not adversely affected when using the ambient temperature temper bead welding process.
That said, utilization of paragraph 1 (b)(1) of Code Case N-638-5 has no effect on the impact properties established during welding procedure qualification or create any adverse metallurgical conditions in the ferritic HAZ. Rather, as noted above, utilization of machine GTAW temper bead welding at ambient temperature produces mechanical properties that are commonly superior to those of the service-exposed substrate.
In addition, by letter dated March 5, 2014, the licensee stated that prior to welding the flange to the temper bead buttering, both a visual examination and a liquid penetrant examination will be conducted after the temper bead butter is installed.
Also, pre-service ultrasonic examination, as required by IWA-4530, will be performed in accordance with ASME Section XI, Appendix VIII. The proposed alternative applies to the remainder of the fourth lSI interval for PNP, scheduled to end on December 12, 2015. 3.1.3 Hardship By letter dated February 26, 2014, the licensee stated the following when describing the hardship of performing the repair replacement:
If this repair/replacement activity was exclusively performed in accordance with the Construction Code [ASME Code, Section Ill], then conventional post-weld heat treatment, as prescribed in the Construction Code for this repair/replacement
- activity, would have to be performed in the field, and would result in unnecessary radiological exposure to maintenance personnel.
This process would result in approximately 1 Rem [roentgen equivalent man] of added dose as compared to the [proposed]
alternative. 3.2 NRC Staff Evaluation The licensee proposed using Code Case N-638-4 as an alternative to the ASME Code, Section Ill post weld heat treatment requirements of the carbon steel pressurizer nozzle for repair of the axial indications in the subject weld. The licensee requested relief from the weld depth limitation of paragraph 1 (b) in the Code Case and proposed completely removing the degraded Alloy 82/182 weld, replacing the stainless steel valve flange, and installing a new weld using Alloy 52M filler metal. The new weld will be installed following the requirements of the ASME Code, Section Ill and the modified ASME Code Case N-638-4.
The NRC staff noted that the weld depth limitations imposed by Code Case N-638-4 are meant to alleviate concerns related to the high restraint that a repaired weld would experience if a localized or partial-depth weld repair was performed.
Stresses from the welding process may lead to cracking under a high degree of restraint.
- However, the licensee has proposed to remove the Alloy 82/182 weld entirely and perform the Alloy 52M buttering using the machine GTAW temper bead process around the full circumference of the joint, reducing the concerns of high restraint in the weld. Furthermore, replacement of all of the Alloy 82/182 material with Alloy 52M weld metal will produce a joint that is less susceptible to PWSCC. The staff further notes that the buttering will be examined both visually and by liquid penetrant examination prior to welding the flange to the temper bead buttering.
The completed butt weld will be radiographic and liquid penetrant examined per NB-5222 of the ASME Code, Section Ill, and a pre-service ultrasonic examination will be performed in accordance with Appendix VIII of the ASME Code,Section XI. Therefore, the NRC staff determines that the proposed repair will provide reasonable assurance of the structural integrity and leak tightness of the new weld at the pressurizer safety relief valve nozzle. Furthermore, the NRC staff concludes that complying with the specified ASME Code, Section Ill requirement for post weld heat treatment of the dissimilar metal nozzle weld would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety due to the added radiological dose associated with the post weld heat treatment.
4.0 CONCLUSION
As set forth above, the NRC staff concludes that the proposed alternative provides reasonable assurance of structural integrity of the subject weld. The staff concludes that complying with the specified ASME Code requirements 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 is in compliance with the requirements of the ASME Code,Section XI for which relief was not requested.
Therefore, the NRC staff authorizes the use of Relief Request RR 4-19 at the PNP for the fourth 10-year lSI interval which ends on December 12, 2015. Once the proposed alternative is installed during the fourth 1 0-year lSI interval, the installed alternative may remain in place for the life of the plant. Should the licensee desire to install the alternative during a subsequent 1 0-year lSI interval, the licensee must seek authorization from the NRC staff for that interval. All other requirements of the ASME Code,Section XI, for which relief has not been specifically requested and authorized by NRC staff remain applicable, including a third party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor:
Joshua Kusnick Date: August 13, 2014 If you have any questions, please contact the Project Manager, Jennivine Rankin at 301-415-1530 or via e-mail at Jennivine.Rankin@nrc.gov.
Docket No. 50-255
Enclosure:
Safety Evaluation cc w/encl: Distribution via ListServ DISTRIBUTION:
PUBLIC LPL3-1 r/f RidsNrrDoriDpr Resource RidsNrrDorllpl3-1 Resource RidsEpnb Resource RidsAcrsAcnw
_MaiiCTR Resource RidsNrrLAMHenderson Resource RidsN rrPM Palisades Resource RidsRgn3Mai1Center Resource ADAMS Accession No* ML14199A557
.. Sincerely, IRA/ David Pelton, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- via memorandum OFFICE NRR/DORLILPL3-1
/PM NRR/DORLILPL3-1
/LA NRR/DE/EPNB/BC*
NRR/DORL/LPL3-1
/BC NAME JRankin MHenderson Tlupold (JTsao for) DPelton DATE 07/31/2014 08/4/2014 06/25/2014 08/13/2014 OFFICIAL RECORD COPY