SR-2D3.6.1.3
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creation date: 2025-12-09T04:00:52-05:00
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IR 05000259/2015007
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GO2-17-124, Final Technical Specification Markup and Clean Pages for Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3
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CNL-16-165, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specification Change
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NRC-16-0036, License Amendment Request 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, Using the Consolidated Line Item Improvement Pro
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NMP2L2616, Supplemental Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual
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NMP2L2611, Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual
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GO2-15-173, Supplement to Response to Second Request for Additional Information on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 3
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JAFP-15-0098, License Amendment Request to Revise Technical Specifications Section 5.5.6 for Extension of Type a and Type C Leak Rate Test Frequencies
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NMP2L2576, License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual
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CNL-14-106, Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs - TS-485
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RS-14-006, Updated Safety Analysis Report, Revision 16, CPS Operational Requirements Manual
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L-MT-13-041, License Amendment Request: Revision of Technical Specification 5.5.11 for Drywell Personnel Airlock Leakage Rate Testing
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RS-13-009, Operational Requirements Manual (Orm) 2013
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NL-18-0206, Supplement to Application to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
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RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases
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NLS2010029, Technical Specifications Bases Changes
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RS-08-132, LaSalle County Station, Units 1 and 2 - Transmittal Letter of Additional Information Regarding Request for License Amendment Regarding Application of Alternative Source Term. Attachments 1 - 5
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PLA-6437, 10 CFR 50.59 Summary Report and Changes to Regulatory Commitments for 10/01/2004 to 08/31/2006
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GO2-08-122, Supplement to Adoption of Approved Generic Technical Specification Changes Associated with Containment Isolation Valves
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RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 6.0 - Engineered Safety Features
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RS-18-103, Response to Request for Additional Information Concerning License Amendment Request to Revise Alternate Source Term Dose Calculation
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TSTF-06-11, Response to NRC Request for Additional Information Regarding TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities, Dated April 7, 2006
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TSTF-05-15, TSTF-454, Revision 1, Extend PCIV Completion Times (NEDC-33046)
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NLS2007036, Technical Specification Bases Changes
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NL-07-0277, Technical Specifications Bases Changes for 2006
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RS-06-141, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
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NL-06-1637, Request to Implement an Alternative Source Term
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NG-06-0516, Response to Request for Additional Information Related to Proposed Amendment to Revise Limiting Condition for Operation 3.10.1
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L-MT-06-054, Supplemental Submittal Regarding Full Scope Application of an Alternative Source Term (AST)
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U-603781, Transmittal of Revision 10 to the Clinton Power Station Technical Specifications Bases
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GO2-06-061, Request for Amendment to Technical Specifications Surveillance Requirements for the Suppression Chamber-to-Drywell Vacuum Breakers and the Drywell-to-Suppression Chamber Bypass Leakage Test
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NLS2005102, License Amendment Request to Establish a Combined Main Steam Line Leakage Rate Technical Specification
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RBG-46183, License Amendment Request Deletion of Technical Specification 3.6.4.4 Shield Building Annulus Mixing System; and Revision of Main Steam Isolation Value(Msiv) Surveillance Requirement SR 3.6.1.3.10
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RS-19-076, Supplement to License Amendment Request to Increase Technical Specifications Allowable MSIV Leakage Rates
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IR 05000387/2019003
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NRC-05-0045, Proposed License Amendment Request to Revise the Combined Secondary Containment Bypass Leakage Rate and the Combined MSIV Leakage Rate Limits in Technical Specification 3.6.1.3
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NL-05-0813, Response to Request for Additional Information on a Technical Specifications Revision Request on Surveillance Requirements for Leak Testing on Containment Purge Valves
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RBG-46419, Revisions to the Technical Requirements Manual and the Technical Specifications Bases
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JAFP-19-0077, License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences
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RS-04-125, Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program
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NRC-04-0075, Revision to the Proposed License Amendment for the Implementation of Alternative Radiological Source Term Methodology for LOCA
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PLA-5728, Proposed License Amendment Numbers 262 for Unit 1 and 227 for Unit 2 Containment Purge Valve Leak Rate Test Frequency PLA-5728
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RBG-46303, Supplement to Amendment Request, Deletion of Technical Specification 3.6.4.4 Shield Building Annulus Mixing System and Revision of Main Steam Isolation Valve (MSIV) Surveillance Requirement SR 3.6.1.3.10
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NL-04-1001, Edwin 1. Hatch Nuclear Plant Unit 1 and 2 - Technical Specifications Amendment Request Appendix J Leakage Rate Test for Containment Purge Valves
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NL-04-0981, Transmittal of Quarterly Update for Hatch, Units 1 and 2 Technical Specifications Bases
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NRC-03-0095, Response to NRC Request for Additional Information Regarding the Implementation of Alternative Source Term
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U-603640, Transmittal of Revision 8 to the Technical Specification Bases
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RBG-46179, Revisions to the Technical Requirements Manual and the Technical Specification Bases
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RS-03-106, Supplement to Request for Amendment to TS Surveillance Requirement 3.6.1.3.8
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RS-03-031, Request for Amendment to Technical Specifications Surveillance Requirement 3.6.1.3.8
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RS-03-036, Request for TS Surveillance Requirement 3.6.1.3.8 Change Related to Excess Flow Check Valve Testing
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NRC-03-0007, Proposed License Amendment for Implementation of Alternative Radiological Source Term Methodology
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RBG-46052, License Amendment Request, Revised Full Scope Application of NUREG-1465 Alternative Source Term Insights
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U-603588, Transmittal of Revision 7 to Clinton Power Station Technical Specification Bases
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NL-02-130, Response to Request for Additional Information Regarding Section 3.6 (Containment Systems) of the Improved Technical Specifications (ITS)
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JAFP-02-0138, Updated Markup and Retyped Technical Specification Pages for Proposed Change to the Technical Specifications Regarding Allowable MSIV Leakage
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RS-02-076, Request for Amendment to Technical Specifications, Excess Flow Check Valve Testing Surveillance Requirement 3.6.1.3.8 & Relief Request RV-12
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GO2-02-050, Technical Specification Amendment Request to Technical Specification Surveillance Requirement 3.6.1.3.6
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RS-20-046, Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.3
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RA-20-0165, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
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ML20196A202
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ML20265A240
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ML20198F430
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ML20198A705
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ML20206A311
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ML20205D310
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ML20203F771
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ML20203F676
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ML20202H921
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ML20202F511
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ML20206M112
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NRC-99-0045, Forwards Rev 5a to Fermi 980403 Submittal,Converting TS to Its.Encl Rev Provides Remaining Responses to NRC RAIs Re ITS Section 3.6 Contained in NRC 990211 Rai.Brief Abstract of Changes & Responses to Rai,Encl
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ML20209B314
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ML20302A197
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IR 05000458/1998015
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ML20237C575
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RA-20-0361, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, Dated September 24, 2020, ADAMS Accession Number ML20272A091
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ML20323A254
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ML20304A416
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ML20248M147
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ML20248F188
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ML20248E844
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ML20248A121
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ML20358A155
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ML20217C796
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ML20216G532
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ML20216G523
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NRC-99-0077, Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS
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ML20342A347
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IR 05000440/2021012
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JAFP-21-0028, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
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NLS2021018, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
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NMP1L3402, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0
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NG-99-1358, Forwards DAEC plant-specific Response to 990927 RAI Re TS Change Request on Excess Flow Check Valve Surveillance requirements.TSTF-334,included
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IR 05000277/2021003
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ML21181A057
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NRC-99-0044, Forwards Rev 5 to ITS to Provide Responses to RAI Re ITS Section 3.6 (Except ITS Section 3.6.1.3) Contained in & Update in ITS Submittal to Reflect Responses
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U-603032, Application for Amend to License NPF-62,adding TS LCO 3.6.1.9, FW LCS (FWLCS) for Implementation of FWLCS Mode of RHR Sys
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RBG-43358, Application for Amend to License NPF-47,permitting Increase in Allowable Leak Rate for MSIVs & Deleting Penetration Valve Leakage Control Sys & Main steam-positive Leakage Control Sys Requirements
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ML21361A217
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ML21307A207
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ML22136A158
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U-602628, Forwards Response to Each of Questions Contained in NRC 960808 Request for Addl Info Re 960628 Application for Amend to License NPF-62 for Removal of Inclined Fuel Transfer Sys & Primary Containment Isolation Valves
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ML22192A117
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U-602565, Application for Amend to License NPF-62,implementing 10CFR50,App J-Option B
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NG-95-2985, Application for Amend to License DPR-49,revising TS Section 3.7, Plant Containment Sys
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HL-5051, Application for Amends to Licenses DPR-57 & NPF-5,revising TS to Reflect Implementation of 10CFR50,App J,Option B
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HL-4832, Requests Exemption from Testing Criteria of 10CFR50,App J
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ENS 56434
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ML23122A233
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PY-CEI-NRR-1999, Application for Amend to License NPF-58,revising Improved Tech Specs.Changes Either Administrative in Nature or Reflect Minor Technical Errors Discovered During Implementation Process
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ML20056H516
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ML20056F490
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IR 05000263/2023003
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ENS 45676
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ENS 53646
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ENS 56455
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RBG-46842, Unit 1, Revisions to the Technical Requirements Manual and the Technical Specification Bases
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ML18192A903
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RS-05-111, Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term
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ML20071E907
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NL-06-0756, E. I. Hatch Operating License Revision to Support Use of Potassium Iodide for an Interim Period, Supplemental Information
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ML24142A429
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ML081970461
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ML080360497
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ML072470723
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PLA-8112, Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-8112
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ML040300619
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ML071200070
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NL-16-0091, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application
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ML021970092
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ML031150536
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ML061240255
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ML031190342
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ML20216G560
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NRC-19-0054, DTE Energy Company - License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle
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ML20169A614
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ML20160A378
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ML15343A043
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PY-CEI-NRR-2352, Suppl to 980909 LAR to License NPF-58,improving Licensing & Design Basis for Isolation of Feedwater Penetrations, Including Sensitivity Study Performed to Examine Radiological Significance of Leakage Through FW Sys Cvs
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page: https://kanterella.com/PY-2DCEI-2DNRR-2D2352-2C_Suppl_to_980909_LAR_to_License_NPF-2D58-2Cimproving_Licensing_-26_Design_Basis_for_Isolation_of_Feedwater_Penetrations-2C_Including_Sensitivity_Study_Pe…
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wiki page sort key: PY-CEI-NRR-2352, Suppl to 980909 LAR to License NPF-58,improving Licensing & Design Basis for Isolation of Feedwater Penetrations, Including Sensitivity Study Performed to Examine Radiological Significance of Leakage Through FW Sys Cvs

PY-CEI-NRR-2165, Application for Amend to License NPF-58,revising Tech Specs Surveillance Requirement for MSIV Leakage Rate Acceptance Criteria
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ML062780135
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RS-03-060, Request for License Amendment Related to Application of Alternative Source Term
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ML060690169
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ML17250A871
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ML20141L011
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ML032680861
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ML20154G655
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IR 05000387/2023004
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ML24274A237
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ML24207A019
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05000387/LER-2024-001, Main Steam Isolation Valve Leakage
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ML24299A264
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05000388/LER-2023-001, Secondary Containment Bypass Leakage Limit Exceeded Due Inadequate Procedure Guidance Resulting in Failure of the Inboard Containment Isolation Valve to Close and Pressurize
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05000263/LER-2023-001, Main Steam Isolation Valve Leakage Exceeds Technical Specification Requirements Due to Stem Scoring
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05000440/LER-2023-002, Main Steam Line Leakage Exceeded Technical Specification Limit
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NL-16-165, Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificat
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ML040020328
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ML021980125
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ML20205E059
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05000458/LER-1997-009-01, :on 971016,inadequate Pressure Test Performance Was Noted.Caused by Inappropriate Testing Lineups.Llrt Valves,Were Retested Utilizing Revised Test Configurations
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ML20217J823
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ML18039A315
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LER-1997-003-02, :on 970328,excessive Leakage Identified on Secondary Bypass Valves Was Caused by Undersized Valve Operators & Inappropriate Valve & Operator Orientation. Re-routed Piping Containing Valves
type: Subject
label: 05000366/LER-1997-003-02, :on 970328,excessive Leakage Identified on Secondary Bypass Valves Was Caused by Undersized Valve Operators & Inappropriate Valve & Operator Orientation. Re-routed Piping Containing Valves
page: https://kanterella.com/05000366/LER-2D1997-2D003-2D02-2C_-3Aon_970328-2Cexcessive_Leakage_Identified_on_Secondary_Bypass_Valves_Was_Caused_by_Undersized_Valve_Operators_-26_Inappropriate_Valve_-26_Ope…
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New Valve & Restored Other to Zero Leakage
type: Subject
label: 05000366/LER-1995-004-03, :on 951009,excessive Leakage Was Identified on Secondary Containment Bypass Valves.Caused by Degradation of Valves.Replaced One Valve W/New Valve & Restored Other to Zero Leakage
page: https://kanterella.com/05000366/LER-2D1995-2D004-2D03-2C_-3Aon_951009-2Cexcessive_Leakage_Was_Identified_on_Secondary_Containment_Bypass_Valves.Caused_by_Degradation_of_Valves.Replaced_One_Valve_W/New…
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ML19007A090
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ML20196C536
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ML20106H672
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ML20198H547
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ML20058M436
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NRC-22-0023, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
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page: https://kanterella.com/NRC-2D22-2D0023-2C_Application_to_Revise_Technical_Specifications_to_Adopt_TSTF-2D582-2C_Reactor_Pressure_Vessel_Water_Inventory_Control_-28RPV_WIC-29_Enhancements
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RS-08-045, LaSalle, Units 1 and 2, Technical Requirements Manual
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ML071200046
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RS-02-174, Co., Llc. (EGC) Application for Amendment to Licenses DPR-19, DPR-25, DPR-29 & DPR-30, Related to Application of Alternative Source Term, Attachments a - E-1
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ML030760746
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ML032671359
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ML032671360
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ML061030029
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ML20128G922
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ML20113C104
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ML20128G917
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ML20117N964
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ML20058M464
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JAFP-16-0129, License Amendment Request to Revise Technical Specifications Section 5.5.6 for Extension of Type a and Type C Leak Rate Test Frequencies
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ML20095J991
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ML20100Q438
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ML20206Q357
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ML19294A304
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ML22297A146
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PY-CEI-NRR-2299, Supplemental Application for Amend to License NPF-58, Revising MSL Leakage Requirements & Eliminating Msli Valve Leakage Control Sys.Proprietary & non-proprietary Rev 1 to Calculation Psat 08401T.03,encl.Proprietary Info Withheld
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page: https://kanterella.com/PY-2DCEI-2DNRR-2D2299-2C_Supplemental_Application_for_Amend_to_License_NPF-2D58-2C_Revising_MSL_Leakage_Requirements_-26_Eliminating_Msli_Valve_Leakage_Control_Sys.Proprietary_-…
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05000388/LER-2019-001-01, Main Steam Isolation Valve Leakage
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TSTF-19-08, Draft of Traveler TSTF-582, Revision 0, RPV WIC Enhancements
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ML18304A392
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ML18066A384
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GO2-96-172, Submits Comments on Draft SE of Proposed Improved Tech Specs
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LER-1997-006, :on 970527,non-performance of Surveillance Requirement 3.6.1.3.2 for Blind Fanges,Was Noted.Caused Because Misunderstanding of Intent of Specs.Added Five Structural Assemblies for Sp
type: Subject
label: 05000397/LER-1997-006, :on 970527,non-performance of Surveillance Requirement 3.6.1.3.2 for Blind Fanges,Was Noted.Caused Because Misunderstanding of Intent of Specs.Added Five Structural Assemblies for Sp
page: https://kanterella.com/05000397/LER-2D1997-2D006-2C_-3Aon_970527-2Cnon-2Dperformance_of_Surveillance_Requirement_3.6.1.3.2_for_Blind_Fanges-2CWas_Noted.Caused_Because_Misunderstanding_of_Intent_of_Spe…
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05000461/LER-1917-004, For Clinton Power Station, Unit 1 Main Steam Isolation Valve Local Leak Rate Test Limit Exceeded During Refueling Outage
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page: https://kanterella.com/05000461/LER-2D1917-2D004-2C_For_Clinton_Power_Station-2C_Unit_1_Main_Steam_Isolation_Valve_Local_Leak_Rate_Test_Limit_Exceeded_During_Refueling_Outage
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05000263/LER-1917-003, Regarding Main Steam Isolation Valve Leakage Exceeds Technical Specification Limits
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IR 05000387/1999006
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LD-99-002, Part 21 Rept Re Incorrect Modeling of BWR Lower Plenum Vol in Bison.Defect Applies Only to Reload Fuel Assemblies Currently in Operation at WNP-2.BISON Code Model for WNP-2 Has Been Revised to Correct Error
type: Subject
page: https://kanterella.com/LD-2D99-2D002-2C_Part_21_Rept_Re_Incorrect_Modeling_of_BWR_Lower_Plenum_Vol_in_Bison.Defect_Applies_Only_to_Reload_Fuel_Assemblies_Currently_in_Operation_at_WNP-2D2.BISON_Code_M…
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CNL-16-155, Application to Revise Technical Specifications to Adopt TSTF-545, Rev. 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, to Request Alternative to the ASME Code, and to
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NLS2016046, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify Surveillance Requirement Usage Rule Application to Section 5.5 Testing
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05000254/LER-2015-003, Regarding Main Steam Isolation Valve Local Leak Rates Exceed Technical Specifications Limits
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05000458/LER-2015-001, Regarding Operations Prohibited by Technical Specifications Due to Deficient Local Leak Rate Test Procedures Containing Erroneous Valve Alignments
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05000259/LER-2014-004, Regarding Main Steam Isolation Valves Leaking in Excess of Technical Specification Requirements
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NRC-15-0010, Response to NRC Request for Additional Information for the Review of License Renewal Application - Set 16
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IR 05000387/2018004
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RS-17-086, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
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05000387/LER-2012-003, Regarding Unit 1 Secondary Containment Bypass Leakage Exceeded
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TSTF-12-01, Transmittal of TSTF-454, Revision 2, Extend PCIV Completion Times (NEDC-33046)
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IR 05000387/2012003
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05000461/LER-2008-003, For Clinton Power Station Unit 1, Regarding Excessive Leakage Through Feedwater Isolation Valve 1B21F032A
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IR 05000461/2010004
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05000321/FIN-2010004-04
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05000341/LER-2007-001, Regarding Excessive Feedwater Check Valve Leakage at Containment Penetration
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RS-07-118, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
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RS-07-074, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
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TSTF-05-07, Submittal and Request for Fee Waiver for Review of TSTF-343, Revision 1, Containment Structural Integrity
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05000237/LER-2003-005, Regarding Main Steam Isolation Valve Leakage Exceeding Technical Specification Limit
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HL-6208, Response to Requests for Additional Information on Technical Specification Change Request: Excess Flow Check Valve Surveillance Requirements (EFCV)
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RA08-089, Regulatory Commitment Change Summary Report
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NUREG-1433, Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases
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IR 05000387/2013002
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RS-18-005, License Amendment Request to Incorporate Revised Alternative Source Term Dose Calculation
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CNL-21-008, Application to Revise Technical Specifications to Adopt TSTF-582, RPV WIC Enhancements (BFN TS-532)
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L-MT-20-036, Response to Request for Additional Information Related to License Amendment Request to Implement Technical Specification Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times
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LR-N25-0015, License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 2
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ML022030467
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NL-21-0722, Units 1 and 2, License Amendment Request: Revise Technical Specifications to Adopt TSTF-207-A, Completion Time for Restoration of Various Excessive Leakage Rates
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05000387/LER-2022-001-01, From Susquehanna Steam Electric Station Unit 1 - Main Steam Line Isolation Valve Leakage Due to Seating Surfaces Wear and Material Deposits
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NMP2L2894, Exemption Request from Certain Requirements of 10 CR 50, Appendix J
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PLA-8164, Modification to Technical Specification 2.6.1.3 Main Steam Line Isolation System Leakage Rate Surveillance Requirements
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ML25134A031
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05000254/LER-2025-003, Main Steam Isolation Valves Local Leak Rate Test Exceed Technical Specification Limits
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ML20245E192
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NL-20-0785, Southern Nuclear Operating Co - Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
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ML20217N930
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BSEP-97-0443, Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Converting Current TS to Improved Ts,As Contained in Rev 1 of NUREG-1433.Rev a to Improved TS & Revised Responses to 970808 & 970911 RAIs Also Encl
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ML071090068
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ML20212C695
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ML20205P803
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GO2-96-132, Requests Amend to Ts,Revising Rev a, Including Changes in Vol 7.Proposed Rev Does Not Change Conclusion of Nhsc or Environ Assessment Provided in Rev a
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ML18039A887
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ML052570461
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ML062070290
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ML103230145
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IR 05000440/2023002
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ML20141L008
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IR 05000387/2023001
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ML021970084
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ML062260141
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L-09-218, Submittal of Technical Specification Bases, Revision 7
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L-14-245, Response to Request for Additional Information Regarding Request for Licensing Action on Alternative Accident Source Term Radiological Dose Calculations
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05000265/LER-2016-001, Regarding Main Steam Isolation Valve Local Leak Rate Tests Exceed Technical Specification Limits
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page: https://kanterella.com/05000265/LER-2D2016-2D001-2C_Regarding_Main_Steam_Isolation_Valve_Local_Leak_Rate_Tests_Exceed_Technical_Specification_Limits
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ML17128A316
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NMP2L2905, Response to Request for Additional Information for License Amendment Request to Revise Surveillance Requirement (SR) 3.6.1.3.12 to a Reduced Test Pressure and Corresponding Leakage Rate for Main Steam Isolation Valves
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page: https://kanterella.com/NMP2L2905-2C_Response_to_Request_for_Additional_Information_for_License_Amendment_Request_to_Revise_Surveillance_Requirement_-28SR-29_3.6.1.3.12_to_a_Reduced_Test_Pressure_and_C…
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IR 05000254/2025002
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ML25224A046
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SR
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