ML16180A289
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| ML16180A289 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/29/2016 |
| From: | Anderson S M Plant Licensing Branch IV |
| To: | Entergy Nuclear Operations |
| Huffman W C, NRR/DORL/LPL1-1, 415-2046 | |
| References | |
| CAC MF8013 | |
| Download: ML16180A289 (13) | |
Similar Documents at FitzPatrick | |
|---|---|
Category:Code Relief or Alternative
MONTHYEARML23278A1292023-12-14014 December 2023
[Table view]Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML21299A0032021-10-28028 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 ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20099D9552020-04-17017 April 2020 Request to Use Provisions in the 2013 Edition of the ASME Boiler and Pressure Vessel Code for Performing Non-Destructive Examinations ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19135A4442019-06-21021 June 2019 Issuance of Relief Request I4R-22 Relief from the Requirements of the ASME Code ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins JAFP-19-0023, Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds2019-02-15015 February 2019 Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds JAFP-18-0076, End of Interval Relief Request Associated with the Fourth Ten-Year Lnservice Inspection (ISI) Interval2018-07-26026 July 2018 End of Interval Relief Request Associated with the Fourth Ten-Year Lnservice Inspection (ISI) Interval JAFP-18-0053, Proposed Alternative to Utilize Code Cases N-878 and N-8802018-05-30030 May 2018 Proposed Alternative to Utilize Code Cases N-878 and N-880 ML18039A8542018-05-30030 May 2018 Relief Requests I5R-02, I5R-03, I5R-04 from ASME Code Requirements for Reactor Vessel Internals, Ferretic Piping Repair/Replacement, and RPV Flange Welds, 5th 10-Year Inservice Inspection Interval (MG0116-MG0118; L-2017-LLR-0083 to 0085) JAFP-18-0052, Proposed Alternative to Utilize Code Case N-8792018-05-30030 May 2018 Proposed Alternative to Utilize Code Case N-879 ML18044A9932018-04-13013 April 2018 Request for Alternatives PRR-01, PRR-02, PRR-04, VRR-02, VRR-03, and VRR-04 from ASME OM Code Requirements for Various Pumps and Valves, Fifth 10-Year Inservice Testing Interval (CAC MG0052-MG0061; EPID L-2017-LLR-0067 to L-2017-LLR-0074) ML17289A0752017-12-12012 December 2017 Issuance of Relief Request for Proposed Alternative to Use ASME Code Case N-789-1 (CAC No. MF9692; EPID L-2017-LLR-0027) Note Correction Safety Evaluation See ML18003B382 ML17219A4282017-12-11011 December 2017 Issuance of Relief Request-Alternative to Certain Requirements of the ASME Code Regarding Use of ASME Code Case N-513-4 (CAC No. MF9641; EPID L-2017-LLR-0023) ML17223A2802017-08-10010 August 2017 Submittal of Relief Requests Associated with the Fifth Lnservice Inspection (ISI) Interval ML17090A1682017-04-12012 April 2017 Alternative to ASME Code Requirements for Weld Overlay Repair ML16355A4292017-01-0606 January 2017 Relief Request for Proposed Alternative for the Implementation of BWRVIP-05 ML16334A4402016-12-0606 December 2016 Relief from the Requirements of the ASME Code Case N-702 and BWRVIP-241 for Plant Nozzle-to-Vessel Welds and Nozzle Inner Radii ML16270A0462016-10-0303 October 2016 Acceptance of Requested Licensing Action Relief Request for Proposed Alternative for the Implementation of BWRVIP-05 ML16253A3412016-09-14014 September 2016 Acceptance of Requested Licensing Action Relief Request for Plant Nozzle-to-Vessel Welds and Nozzle Inner Radii Using ASME Code Case N-702 and BWRVIP-241 ML16180A2892016-06-29029 June 2016 Inservice Inspection Program Alternative for Safety Relief Valves 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 ML16077A3522016-03-22022 March 2016 Withdrawal of Relief Request No. 19 from the Fourth Inservice Inspection Interval JAFP-15-0122, Withdrawal of Application for Alternative Examination Requirements for James A. FitzPatrick Nuclear Power Plant Nozzle-to-Vessel Welds and Nozzle Inner Radii Using ASME Code Case N-702 and BWRVIP-2412015-11-20020 November 2015 Withdrawal of Application for Alternative Examination Requirements for James A. FitzPatrick Nuclear Power Plant Nozzle-to-Vessel Welds and Nozzle Inner Radii Using ASME Code Case N-702 and BWRVIP-241 ML15230A3502015-08-18018 August 2015 J.A Fitzpatrick Nuclear Power Plant - Requests Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1), Implementation of BWRVIP-05 (GL 98-05) 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 ML12279A2482012-10-17017 October 2012 Issuance of Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code JAFP-11-0112, Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP2011-10-0303 October 2011 Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP ML0803902232008-03-13013 March 2008 Relief Request No. 5, Use of Performance Demonstration Initiative in Lieu of ASME Code Section XI, Appendix Viii, Supplement 11 Requirement ML0803003072008-02-28028 February 2008 Relief Request No. RR-6, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals Components Inspection ML0803700802008-02-25025 February 2008 Relief Request No. 2 (RR-2) from the Requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Appendix Viii, Supplement 10 ML0804204272008-02-22022 February 2008 Relief Request No. 3 (RR-3) Risk-Informed Inservice Inservice Inspection Program ML0520700472005-08-0909 August 2005 Relief Request for Temporary Non-Code Repair of a Shutdown Cooling Pipe JAFP-05-0105, Request for Approval of Relief Request No. RR-38, Proposed Alternative to Perform a Temporary Non-Code Repair in Accordance with 10 CFR 50.55a(a)(3)(ii)2005-07-0909 July 2005 Request for Approval of Relief Request No. RR-38, Proposed Alternative to Perform a Temporary Non-Code Repair in Accordance with 10 CFR 50.55a(a)(3)(ii) ML0427406642004-10-14014 October 2004 Relief Request Nos. R-33, R-71, R 3-40(A) and R-41, James A. FitzPatrick Nuclear Power Plant, Indian Point Nuclear Generating Unit Nos. 2 and No. 3 and Pilgrim Nuclear Power Station ML0420301572004-07-20020 July 2004 Relief, Relief Request No. 30 for Third 10-Year Inservice Inspection (ISI) Program Interval ML0410700882004-07-0606 July 2004 Relief Request to Use American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Case N-600 ML0417401842004-07-0606 July 2004 Relief Request, Nos. RR-34 and PRR for the Third 10-Year Inservice Inspection (ISI) Interval, MC1999 and MC2006 ML0405406932004-04-12012 April 2004 Relief Request Review, Relief Request VRR-08 Related to the Third 10-Year Inservice Testing (IST) Ubtervak JPN-03-020, Indian Point Nuclear Generating Station, Units 2 & 3, Pilgrim Nuclear Power Station, Vermont Yankee Nuclear Power Station, Relief, Relief Request to Use ASME Code Case N-6002003-08-11011 August 2003 Indian Point Nuclear Generating Station, Units 2 & 3, Pilgrim Nuclear Power Station, Vermont Yankee Nuclear Power Station, Relief, Relief Request to Use ASME Code Case N-600 JAFP-03-0111, Proposed Alternatives in Accordance with 10CFR50.55a(g)(6)(ii)(A)(5) and Relief from ASME Section XI Code Regarding Inspection of RPV Vertical Shell Welds Pursuant to 10 CFR 50.55a (g)(6)(i)2003-08-0404 August 2003 Proposed Alternatives in Accordance with 10CFR50.55a(g)(6)(ii)(A)(5) and Relief from ASME Section XI Code Regarding Inspection of RPV Vertical Shell Welds Pursuant to 10 CFR 50.55a (g)(6)(i) ML0306502552003-04-0101 April 2003 Relief Request Review, Third 10-Year Pump and Valve Inservice Testing Program, Revision of Relief Request VRR-04 ML0231804962002-11-14014 November 2002 Relief, Request for Relief No. RR-28 for the Third 10-Year Inservice Inspection Interval Program Plan for the FitzPatrick Power Plant JAFP-02-0194, Proposed Revision of Relief Request VRR-06 for In-Service Testing Program2002-09-30030 September 2002 Proposed Revision of Relief Request VRR-06 for In-Service Testing Program JPN-02-011, Request for Relief RR-29, Third 10-Year Inservice Inspection Interval Program Plan2002-05-0808 May 2002 Request for Relief RR-29, Third 10-Year Inservice Inspection Interval Program Plan JPN-02-010, Relief Request RR-28, Revision 1 for the Third 10-Year Inservice Inspection Interval Program Plan2002-05-0808 May 2002 Relief Request RR-28, Revision 1 for the Third 10-Year Inservice Inspection Interval Program Plan 2023-12-14 Category:Letter MONTHYEARIR 05000333/20240902024-10-29029 October 2024
[Table view]Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000333/2024090 IR 05000333/20244022024-10-28028 October 2024 Material Control and Accounting Program Inspection Report 05000333/2024402 (Cover Letter Only) ML24276A1332024-10-17017 October 2024 Issuance of Amendment No. 357 Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision-4, and Administrative Changes ML24282B0302024-10-11011 October 2024 Project Manager Assignment RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24207A0192024-10-0909 October 2024 SE Addendum Related to the License Amendment No. 338 for Implementation of the Alternative Source Term (DPO-2021-001) ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing JAFP-24-0051, Reply to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000333/2024011; EA-24-0882024-10-0303 October 2024 Reply to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000333/2024011; EA-24-088 ML24270A0742024-09-30030 September 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0134) - LTR ML24270A1452024-09-26026 September 2024 Notice of Enforcement Discretion for James A. Fitzpatrick Nuclear Power Plant JAFP-24-0046, Request for Enforcement Discretion for Technical Specification (TS) 3.3.2.1 Control Rod Block Instrumentation2024-09-25025 September 2024 Request for Enforcement Discretion for Technical Specification (TS) 3.3.2.1 Control Rod Block Instrumentation JAFP-24-0047, License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software2024-09-25025 September 2024 License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software JAFP-24-0045, Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2024-09-20020 September 2024 Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications IR 05000333/20240112024-09-19019 September 2024 Follow-up to Inspection Procedure 71153 Report 05000333/2024011 and Preliminary White Finding and Apparent Violation JAFP-24-0044, Core Operating Limits Report Cycle 272024-09-16016 September 2024 Core Operating Limits Report Cycle 27 JAFP-24-0043, Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2024-09-12012 September 2024 Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues 05000333/LER-2024-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2024-09-0404 September 2024 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation ML24165A0382024-09-0404 September 2024 Issuance of Amendment No. 356 Update Fuel Handling Accident Analysis IR 05000333/20240052024-08-29029 August 2024 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2024005) 05000333/LER-2024-001-01, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-08-21021 August 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000333/20240022024-08-0707 August 2024 Integrated Inspection Report 05000333/2024002 JAFP-24-0034, 10 CFR 50.46 Annual Report2024-07-31031 July 2024 10 CFR 50.46 Annual Report ML24208A0492024-07-30030 July 2024 Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Proposed No Significant Hazards Consideration Determination (Letter) JAFP-24-0036, Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-07-29029 July 2024 Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0033, Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test2024-07-23023 July 2024 Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test IR 05000333/20244032024-07-18018 July 2024 Biennial Problem Identification and Resolution Inspection Report 05000333/2024403 (Cover Letter Only) IR 05000333/20244012024-07-15015 July 2024 Security Baseline Inspection 05000333/2024401 RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions ML24190A1932024-07-0909 July 2024 Correction Letter of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance IR 05000333/20240102024-07-0808 July 2024 Commercial Grade Dedication Inspection Report 05000333/2024010 ML24184A1662024-07-0303 July 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24136A1162024-06-26026 June 2024 Issuance of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance 05000333/LER-2024-001, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket ML24176A2412024-06-24024 June 2024 Licensed Operator Positive Fitness-for-Duty Test JAFP-24-0027, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations JAFP-24-0026, Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance2024-06-12012 June 2024 Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 IR 05000333/20240012024-05-0909 May 2024 Integrated Inspection Report 05000333/2024001 JAFP-24-0023, 2023 Annual Radiological Environmental Operating Report2024-05-0909 May 2024 2023 Annual Radiological Environmental Operating Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests JAFP-24-0020, 2023 Annual Radioactive Effluent Release Report2024-04-25025 April 2024 2023 Annual Radioactive Effluent Release Report JAFP-24-0019, 2023 REIRS Transmittal of NRC Form 52024-04-18018 April 2024 2023 REIRS Transmittal of NRC Form 5 ML24106A0152024-04-15015 April 2024 Request for Withholding Information from Public Disclosure Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling ML24107A6972024-04-12012 April 2024 Engine Systems, Inc Part 21 Report Re EMD Cylinder Liner Water Leak ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24068A0532024-03-28028 March 2024 Issuance of Amendment No. 354 Revise Technical Specifications Section 3.3.1.2, Source Range Monitors Instrumentation JAFP-24-0014, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-03-25025 March 2024 Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis 2024-09-04 Category:Safety Evaluation MONTHYEARML24276A1332024-10-17017 October 2024
[Table view]Issuance of Amendment No. 357 Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision-4, and Administrative Changes ML24207A0192024-10-0909 October 2024 SE Addendum Related to the License Amendment No. 338 for Implementation of the Alternative Source Term (DPO-2021-001) ML24165A0382024-09-0404 September 2024 Issuance of Amendment No. 356 Update Fuel Handling Accident Analysis ML24136A1162024-06-26026 June 2024 Issuance of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance ML24068A0532024-03-28028 March 2024 Issuance of Amendment No. 354 Revise Technical Specifications Section 3.3.1.2, Source Range Monitors Instrumentation ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML22223A1412022-09-0101 September 2022 Issuance of Amendment No. 353 Adoption of TSTF - 505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML22196A0612022-08-23023 August 2022 Issuance of Amendment No. 352 Adoption of 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22166A4302022-07-15015 July 2022 Issuance of Amendment No. 351 Removal of Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation ML22126A1962022-05-27027 May 2022 Issuance of Amendment No. 350 Adoption of TSTF-264, Revision 0 ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22094A0012022-04-15015 April 2022 Constellation Energy Generation, LLC - Proposed Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles (Epids L-2021-LLR-0057 and L-2021-LLR-0058) ML21364A0432022-02-28028 February 2022 Issuance of Amendment No. 348 Revising Surveillance Requirement 3.5.1.6 Involving Recirculation Pump Discharge Valves ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21300A3552021-11-16016 November 2021 Issuance of Amendment No. 345 Adoption of TSTF-582 ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21131A1272021-08-0909 August 2021 Issuance of Amendment No. 343 Modifications to Technical Specification 3.6.1.3, Primary Containment Isolation Valves (Pcivs) ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21166A1682021-06-25025 June 2021 ML21162A0422021-06-14014 June 2021 Issuance of Amendment No. 342, One Time Extension of Completion Times to Support Residual Heat Removal Pump Motor Replacement (Emergency Circumstances) ML21049A3552021-04-28028 April 2021 Issuance of Amendment No. 341 Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20169A5102020-08-20020 August 2020 Issuance of Amendment No. 339 Changes to Technical Specifications Related to Primary Containment Hydrodynamic Loads ML20140A0702020-07-21021 July 2020 Issuance of Amendment No. 338 Application of Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20094G9032020-06-0202 June 2020 Issuance of Amendment No. 335 Adoption of TSTF-372, Addition of LCO 3.0.8, 'Inoperability of Snubbers' ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20024C6612020-03-0202 March 2020 Issuance of Amendment No. 332 Adopt TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, Using the Consolidated Line Item Improvement Process ML19295G7832019-12-19019 December 2019 Issuance of Amendment No. 331 Regarding Change to Technical Specifications to Remove Ultimate Heat Sink Bar Rack Heaters ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques 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 ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR ML19189A0842019-08-19019 August 2019 Issuance of Amendment No. 326 Adoption of TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19157A2032019-07-11011 July 2019 Issuance of Amendment No. 325 Reactivity Anomalies Surveillance ML19135A4442019-06-21021 June 2019 Issuance of Relief Request I4R-22 Relief from the Requirements of the ASME Code ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins ML18360A6352019-02-25025 February 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC No. MF4464; EPID No. L-2014-JLD-0049) ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18289A4322018-11-28028 November 2018 Issuance of Amendment No. 323 Revision to the Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 ML18214A7062018-09-19019 September 2018 Issuance of Amendment No. 322, Revise Technical Specification 2.1.1, Reactor Core Sls, to Change Cycle 24 Safety Limit Minimum Critical Power Ratio Numeric Values ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18180A3722018-07-19019 July 2018 Issuance of Amendment No. 319, Revise Technical Specification Surveillance Requirement 3.6.4.1.3 to Allow Opening of Inner and Outer Secondary Containment Access Openings (CAC MG0239; EPID L-2017-LLA-0298) ML18039A8542018-05-30030 May 2018 Relief Requests I5R-02, I5R-03, I5R-04 from ASME Code Requirements for Reactor Vessel Internals, Ferretic Piping Repair/Replacement, and RPV Flange Welds, 5th 10-Year Inservice Inspection Interval (MG0116-MG0118; L-2017-LLR-0083 to 0085) 2024-09-04 |
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