ML15099A018
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| ML15099A018 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/07/2015 |
| From: | David Pelton Plant Licensing Branch III |
| To: | McCartney E A Point Beach |
| Chawla M L | |
| References | |
| TAC MF4142, TAC MF4143 | |
| Download: ML15099A018 (10) | |
Similar Documents at Point Beach | |
|---|---|
Category:Code Relief or Alternative
MONTHYEARML24068A2492024-04-22022 April 2024
[Table view]– Authorization and Safety Evaluation for Alternative Request No. I6-RR-01 ML24071A0912024-04-22022 April 2024 Issuance of Relief Request I6-RR-03 - Extension of the Unit 2 Steam Generator Primary Nozzle Dissimilar Metal Welds Sixth 10-Year Inservice Inspection Program Interval ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval ML20036F2612020-03-0404 March 2020 Approval of Relief Request 1-RR-13 and 2-RR-13 Regarding Extension of Inspection Interval for Point Beach Unit 1 and Unit 2 Reactor Pressure Vessel Welds from 10 to 20 Years ML19339H7472019-12-13013 December 2019 Approval of Relief Request 2-RR-17 Regarding Steam Generator Primary Nozzle Dissimilar Metal Welds Inspection Interval ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques L-2017-121, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-07-24024 July 2017 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML16063A0582016-03-22022 March 2016 Approval of Relief Request 2-RR-11; Steam Generator Nozzle to Safe-End Dissimilar Metal (DM) Weld Inspection ML15246A3052015-09-16016 September 2015 Evaluation of Relief Request RR-10 - Examination of Feedwater Nozzle Extension to Nozzle Weld Fifth 10-Year Inservice Program Interval ML15127A2912015-05-20020 May 2015 Relief Request RR-8, Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Examination of Buried Components NRC 2015-0025, Requests Relief from Performing Inservice Testing (ISI) of Relief Valve 1CC-00763B2015-05-14014 May 2015 Requests Relief from Performing Inservice Testing (ISI) of Relief Valve 1CC-00763B ML15099A0182015-05-0707 May 2015 Relief Request RR-9, Proposed Alternative from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for System Leakage Test ML14343A0512014-12-10010 December 2014 Relief from the Requirements of the ASME Code for Re-Examination of the Reactor Pressure Vessel a Inlet Nozzle Weld for the Fifth Ten-Year Inservice Inspection Program Interval ML13329A0312013-12-20020 December 2013 Relief from the Requirements of ASME B&PV Code, Section XI, for the Fourth 10-Year ISI Interval (RR-4L1) ML13079A1412013-03-19019 March 2013 CFR 50.55a Request, Relief Request RR-4L3 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspection Program Interval NRC 2013-0020, CFR 50.55a Request, Relief Request RR-4L3 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspection Program Interval2013-03-19019 March 2013 CFR 50.55a Request, Relief Request RR-4L3 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspection Program Interval ML13064A4252013-03-18018 March 2013 Relief Request 1-RR-4 Re-Examination of the Unit 1 RPV Indication on the a Inlet Nozzle Weld ML12286A1042012-11-15015 November 2012 Evaluation of Relief Requests RR-2 & RR-3 (ME7974 & ME7975) 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 ML0527001972006-01-18018 January 2006 Relief Request - Reactor Vessel Closure Head Penetration Flaw Characterization Relief Request MR 02-018-2, Revision 2 ML0526503122005-09-27027 September 2005 Relief Requests - the Previsions of ASME Section XI, IWA-5244, Buried Components, RR-1-26 and RR-2-34 NRC 2005-0084, Reactor Vessel Closure Head Penetration Flaw Characterization Relief Request MR 02-018-2, Revision 22005-07-0101 July 2005 Reactor Vessel Closure Head Penetration Flaw Characterization Relief Request MR 02-018-2, Revision 2 NRC 2005-0016, Relief Request from the Provisions of ASME Section Xl, IWA-4422.2.2, Defect Removal Followed by Welding or Brazing, Relief Request 162005-02-0404 February 2005 Relief Request from the Provisions of ASME Section Xl, IWA-4422.2.2, Defect Removal Followed by Welding or Brazing, Relief Request 16 NRC 2005-0015, Relief Request from the Provisions of ASME Section XI, IWA-5244, Buried Components, Relief Request 152005-01-21021 January 2005 Relief Request from the Provisions of ASME Section XI, IWA-5244, Buried Components, Relief Request 15 ML0408601612004-04-0101 April 2004 Request for Relief VRR 03-01 on a One Time Basis for Performing Inservice Testing of Relief Valve 1RH-861C 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 ML0323104022003-09-10010 September 2003 Relief, MR 02 018-2 Pertaining to Reactor Vessel Closure Head Penetration Repair ML0306203282003-03-21021 March 2003 Relief, Use of Code Case N-600 for the Fourth 10-Year Interval, MB5403 and MB5404 ML0225401092003-03-21021 March 2003 Relief Request No 8 - Requirement for Scheduling of Components for Examination ML0302101262003-02-27027 February 2003 Relief, Alternative to Examine All Three Vessels of the Regenerative Heat Exchanger, MB5401 & MB5402 ML0225300232002-10-0808 October 2002 Relief, Granted for ASME Code Section XI, Relief Request 6 Regarding Evaluation of Leakage with Bolting In-Place ML0225300062002-10-0808 October 2002 Code Relief, ASME Code Section XI, Relief Request 5 Regarding Visual Examination of Insulted Bolting on Borated Systems NRC 2002-0073, Reactor Vessel Closure Head Penetration Repair Relief Requests MR 02-018-1 and MR 02-018-22002-08-28028 August 2002 Reactor Vessel Closure Head Penetration Repair Relief Requests MR 02-018-1 and MR 02-018-2 2024-04-22 Category:Letter MONTHYEARIR 05000266/20240032024-11-0505 November 2024
[Table view]Integrated Inspection Report 05000266/2024003 and 05000301/2024003 ML24295A1142024-10-31031 October 2024 Suppl Env Audit Summary Letter W/Enclosure 1 L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums ML24295A0862024-10-21021 October 2024 Notification of NRC Baseline Inspection and Request for Information Inspection Report 0500026/2025002 L-2024-160, Core Operating Limits Report (COLR) Unit 2 Reload Cycle 41 (U2C41)2024-10-21021 October 2024 Core Operating Limits Report (COLR) Unit 2 Reload Cycle 41 (U2C41) L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-120, LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization2024-10-0808 October 2024 LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20240112024-09-18018 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000266/2024011 and 05000301/2024011 L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-145, Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency2024-09-0909 September 2024 Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency ML24207A0202024-08-28028 August 2024 Response to Request for Re-Engagement Regarding the Subsequent License Renewal Environmental Review for Point Beach Nuclear Plant, Units 1 and 2 (Docket Numbers: 50-0266 and 50-0301) IR 05000266/20240052024-08-21021 August 2024 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2024005 and 05000301/2024005) IR 05000266/20240022024-08-13013 August 2024 Integrated Inspection Report 05000266/2024002 and 05000301/2024002 L-2024-131, Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-08-0909 August 2024 Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review ML24214A3092024-08-0202 August 2024 Confirmation of Initial License Examination L-2024-113, License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections2024-07-24024 July 2024 License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections ML24194A1802024-07-24024 July 2024 – Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20244012024-07-23023 July 2024 Public - Point Beach Nuclear Plant Cyber Security Inspection Report 05000266/2024401 and 05000301/2024401 ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-116, Preparation and Scheduling of Operator Licensing Examinations2024-07-11011 July 2024 Preparation and Scheduling of Operator Licensing Examinations L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal IR 05000266/20240102024-07-10010 July 2024 Age-Related Degradation Inspection Report 05000266/2024010 and 05000301/2024010 L-2024-105, License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-06-26026 June 2024 License Amendment Request 300, Modify Containment Average Air Temperature Requirements L-2024-107, Schedule for Subsequent License Renewal Environmental Review2024-06-25025 June 2024 Schedule for Subsequent License Renewal Environmental Review ML24176A2242024-06-24024 June 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-093, Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision2024-06-10010 June 2024 Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision IR 05000266/20244202024-06-0505 June 2024 Security Baseline Inspection Report 05000266/2024420 and 05000301/2024420 ML24149A1922024-05-28028 May 2024 Notification of NRC Baseline Inspection and Request for Information ML24141A1382024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection.Docx ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000266/2024301; 05000301/2024301 L-2024-067, Annual Monitoring Report2024-04-26026 April 2024 Annual Monitoring Report ML24116A0402024-04-23023 April 2024 Periodic Update of the Updated Final Safety Analysis Report ML24071A0912024-04-22022 April 2024 Issuance of Relief Request I6-RR-03 - Extension of the Unit 2 Steam Generator Primary Nozzle Dissimilar Metal Welds Sixth 10-Year Inservice Inspection Program Interval IR 05000266/20240012024-04-11011 April 2024 Integrated Inspection Report 05000266/2024001 and 05000301/2024001 L-2024-030, Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-03-27027 March 2024 Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-043, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-03-25025 March 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules L-2024-011, And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications IR 05000266/20230062024-02-28028 February 2024 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2023006 and 05000301/2023006) ML24053A3732024-02-22022 February 2024 Operator Licensing Examination Approval Point Beach, March 2024 L-2024-020, Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections2024-02-22022 February 2024 Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections ML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 2024-09-09 Category:Safety Evaluation MONTHYEARML24194A1802024-07-24024 July 2024
[Table view]– Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML24200A1612024-07-19019 July 2024 Alternative CISI-03-01 ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter ML24068A2492024-04-22022 April 2024 – Authorization and Safety Evaluation for Alternative Request No. I6-RR-01 ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22193A1142022-09-12012 September 2022 Issuance of Amendment Nos. 270 and 272 Elimination of the Requirements to Maintain the Post-Accident Sampling System ML22140A1272022-05-25025 May 2022 Subsequent License Renewal Application Safety Evaluation Revision 1 Public ML22041A3342022-02-23023 February 2022 Transmittal Letter for Point Beach Final SE for SLRA Review to AA La 2-9 (3) ML22054A1082022-02-23023 February 2022 Subsequent License Renewal Application Safety Evaluation Public ML21148A2552021-07-21021 July 2021 Issuance of Amendment Nos. 269 and 271 Technical Specification Changes to Implement New Surveillance Methods for Transient Heat Flux Hot Channel Factor ML20363A1762021-02-23023 February 2021 Issuance of Amendment Nos. 268 and 270 Regarding Tornado Missile Protection Licensing Basis ML20241A0582020-09-25025 September 2020 Issuance of Amendment No. 267 for One-Time Extension of License Condition 4.I, Containment Building Construction Truss (EPID L-2020-LLA-0180 (COVID-19)) ML20036F2612020-03-0404 March 2020 Approval of Relief Request 1-RR-13 and 2-RR-13 Regarding Extension of Inspection Interval for Point Beach Unit 1 and Unit 2 Reactor Pressure Vessel Welds from 10 to 20 Years ML19357A1952020-02-10010 February 2020 Unit No.1; & Turkey Point Nuclear Generating Unit Nos. 3 & 4 - Issuance of Amendments Nos. 265, 268, 164, 290, and 284 Revise Technical Specifications to Adopt TSTF-563 ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19339H7472019-12-13013 December 2019 Approval of Relief Request 2-RR-17 Regarding Steam Generator Primary Nozzle Dissimilar Metal Welds Inspection Interval ML19064A9042019-04-25025 April 2019 Issuance of Amendments to Extend Containment Leakage Rate Test Frequency ML19052A5442019-03-27027 March 2019 Issuance of Amendments 264 and 267 to Adopt TSTF-547, Clarification of Rod Position Requirements ML18289A3782018-11-26026 November 2018 Issuance of Amendments to Adopt Title 10 of Code of Federal Regulations 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML18079A0452018-06-13013 June 2018 Issuance of Amendments Revision to the Point Beach Nuclear Plant Emergency Action Level Scheme (CAC Nos. MF9859 and MF9860 EPID L-2017-LLS-0278) ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML17159A7782017-07-27027 July 2017 Issuance of Amendment to Approve H*: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17039A3002017-02-22022 February 2017 Issuance of Amendments -Removal of Completed License Conditions and Changes to the Ventilation Filter Testing Program ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML16241A0002016-09-23023 September 2016 Mitigating Strategies and Spent Fuel Pool Instrumentation Safety Evaluation ML16196A0932016-09-0808 September 2016 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48 (C) ML16118A1542016-06-17017 June 2016 Issuance of Amendments ML16063A0582016-03-22022 March 2016 Approval of Relief Request 2-RR-11; Steam Generator Nozzle to Safe-End Dissimilar Metal (DM) Weld Inspection ML16035A5092016-03-0909 March 2016 Correction of Typographical Error in Safety Evaluation Associated with License Amendment Nos. 238 and 242 ML15293A4572015-11-25025 November 2015 Issuance of Amendments for the Steam Generator Technical Specifications, to Reflect Adoption of TSTF-510 ML15246A3052015-09-16016 September 2015 Evaluation of Relief Request RR-10 - Examination of Feedwater Nozzle Extension to Nozzle Weld Fifth 10-Year Inservice Program Interval ML15195A2012015-07-28028 July 2015 Issuance of Amendments Regarding Relocation of Surveillance Frequencies to Licensee Control ML15155A5392015-07-14014 July 2015 Issuance of Amendments Concerning Extension of Cyber Security Plan Milestone 8 ML15161A5352015-06-24024 June 2015 Relief Request VR-01; Alternatives to Certain Inservice Testing Requirements of the American Society of Mechanical Engineers (ASME) Code of Operation and Maintenance of Nuclear Power Plants ML15127A2912015-05-20020 May 2015 Relief Request RR-8, Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Examination of Buried Components ML15099A0182015-05-0707 May 2015 Relief Request RR-9, Proposed Alternative from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for System Leakage Test ML15014A2492015-01-27027 January 2015 Issuance of Amendments to Revise Technical Specifications to Adopt Technical Specifications Task Force - 523, Generic Letter 2008-01, Managing Gas Accumulation (Tac Nos. MF4353 and MF4354) ML14343A0512014-12-10010 December 2014 Relief from the Requirements of the ASME Code for Re-Examination of the Reactor Pressure Vessel a Inlet Nozzle Weld for the Fifth Ten-Year Inservice Inspection Program Interval ML14293A0022014-10-21021 October 2014 Issuance of Safety Evaluation Regarding Relief Request RR-5 ML14126A3782014-06-30030 June 2014 Issuance of License Amendment Nos. 250 and 254 Regarding Change to Technical Specification 5.6.5, Reactor Coolant System Pressure and Temperature Limits Report ML14058B0292014-05-0909 May 2014 Issuance of Amendment Nos. 249 and 253 Regarding Use of Optimized Zirlo Fuel Cladding Material ML14014A2052014-01-30030 January 2014 Issuance of Relief Request Regarding Risk-Informed Inservice Inspection Program for the Fifth 10-Year Inservice Inspection Interval ML13329A0422013-12-20020 December 2013 Relief from the Requirements of ASME Code, Section XI, for the Fourth 10-Year Inservice Inspection Interval (RR-4L3) ML13329A0312013-12-20020 December 2013 Relief from the Requirements of ASME B&PV Code, Section XI, for the Fourth 10-Year ISI Interval (RR-4L1) ML13346A0402013-12-18018 December 2013 Relief from the Requirements of ASME Code, Section XI, for the Fourth 10-Year Inservice Inspection Interval (RR-4L2) 2024-07-24 |
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