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| Issue date | Title | Topic | |
|---|---|---|---|
| ML23010A088 | 15 January 2023 | Summary of Regulatory Audit in Support of License Amendment Request to Revise Control Rod Technical Specifications | Shutdown Margin |
| PLA-8026, Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026) | 19 October 2022 | Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026) | Turbine Missile Grace period Affidavit |
| PLA-7998, Submittal of Unit 1 Cycle 23 Core Operating Limits Report and Reload Safety Analysis Report | 29 March 2022 | Submittal of Unit 1 Cycle 23 Core Operating Limits Report and Reload Safety Analysis Report | |
| PLA-7984, Supplement to License Amendment Requesting Adoption of TSTF-505, Revision 2 | 8 March 2022 | Supplement to License Amendment Requesting Adoption of TSTF-505, Revision 2 | Safe Shutdown High winds Reactor Vessel Water Level Ultimate heat sink Mission time Internal Flooding Probabilistic Risk Assessment FLEX Thermoset Surveillance Frequency Control Program Open Phase Condition Scram Discharge Volume Feedwater Controller Failure Large early release frequency Time Critical Operator Action Earthquake Maintenance Rule Program Offsite Circuit Continuous fire watch Fire Protection Program |
| PLA-7959, Owner'S Activity Report PLA-7959 | 15 July 2021 | Owner'S Activity Report PLA-7959 | Through Wall Leak |
| PLA-7910, Submittal of Unit 2 Cycle 21 Fuel Rod Design Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies PLA-7910 | 10 December 2020 | Submittal of Unit 2 Cycle 21 Fuel Rod Design Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies PLA-7910 | Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence |
| PLA-7757, Final Integrated Plan to Comply with June 06, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (NRC-Order EA-13-109), Revision 1 | 27 November 2018 | Final Integrated Plan to Comply with June 06, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (NRC-Order EA-13-109), Revision 1 | High winds Ultimate heat sink FLEX Design basis earthquake Severe Accident Management Guideline Hardened vent |
| ML18024A114 | 24 January 2018 | a Reaction to Cracking of Austenitic Stainless Steel Piping in Boiling Water Reactors (Includes Susquehanna Ses Design Modifications) | |
| ML17093A668 | 27 March 2017 | Technical Requirements Manual Unit 2, Revision 93 with Revision 13 to Table of Contents | |
| PLA-7559, Flooding Mitigating Strategies Assessment (MSA) Report | 19 December 2016 | Flooding Mitigating Strategies Assessment (MSA) Report | Hydrostatic FLEX Fukushima Dai-Ichi |
| ML16231A509 | 25 August 2016 | Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents)(Cac Nos. MF4364 and MF4365) | High winds Ultimate heat sink FLEX Fukushima Dai-Ichi Severe Accident Management Guideline Containment Hardened Vent Earthquake |
| PLA-7491, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insight from the Dai-Ichi Accident | 30 June 2016 | Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insight from the Dai-Ichi Accident | Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi |
| ML16054A243 | 9 February 2016 | NPDES Permit No. PA 0047325 Renewal Application | |
| ML15356A247 | 20 January 2016 | Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulation Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force | Safe Shutdown Earthquake Fukushima Dai-Ichi Earthquake |
| PLA-7414, Redacted - Susquehanna, Units 1 and 2 - Submittal of 10 CFR 71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 9168 | 19 November 2015 | Redacted - Susquehanna, Units 1 and 2 - Submittal of 10 CFR 71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 9168 | |
| PLA-7374, Submittal of 10 CFR71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 9168 | 20 August 2015 | Submittal of 10 CFR71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 9168 | |
| PLA-7311, Negative Blind Specimen Report, PLA-7311 | 9 April 2015 | Negative Blind Specimen Report, PLA-7311 | |
| ML15090A300 | 1 April 2015 | Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) (TAC Nos. MF4364 & MF4365) | High winds FLEX Tornado Generated Missile Fukushima Dai-Ichi Design basis earthquake Containment Hardened Vent Earthquake Scaffolding |
| PLA-7287, Flood Hazards Reevaluation Report PLA-7287 | 3 March 2015 | Flood Hazards Reevaluation Report PLA-7287 | Ultimate heat sink Internal Flooding Hydrostatic Incorporated by reference Fukushima Dai-Ichi |
| ML14176A961 | 24 June 2014 | Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 | Fire Barrier Coatings Foreign Material Exclusion |
| PLA-7175, (SSES)- 10 CFR 50.46 - Annual Report | 20 June 2014 | (SSES)- 10 CFR 50.46 - Annual Report | |
| ML14156A234 | 16 June 2014 | Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (MF0288 and MF0289) | Unanalyzed Condition Ultimate heat sink Internal Flooding Hydrostatic Operator Manual Action Fukushima Dai-Ichi Earthquake |
| ML14056A449 | 6 May 2014 | Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (Tacs MF0183, MF0184) | Unanalyzed Condition Safe Shutdown Earthquake Fukushima Dai-Ichi Earthquake |
| ML14113A555 | 23 April 2014 | Draft Staff Assessment of Seismic Walkdown Report Near-term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident; PPL Susquehanna, LLC; Susquehanna Steam Electric Station, Unit 1. Docket No. 50-387 | Unanalyzed Condition Safe Shutdown Earthquake Fukushima Dai-Ichi Earthquake |
| ML14085A398 | 26 March 2014 | Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(F) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident PLA-7145 | Safe Shutdown Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi Design basis earthquake Earthquake Seismic Walkdown Report |
| ML14085A426 | 26 March 2014 | Apendix B IPEEE Adequacy Review | Safe Shutdown Mission time Safe Shutdown Earthquake Fukushima Dai-Ichi Seismically rugged Earthquake |
| ML14010A371 | 15 January 2014 | Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Susquehanna Steam Electric Station, Units 1 and 2, TAC Nos.: MF0888 and MF0889 | Safe Shutdown High winds Reactor Vessel Water Level Ultimate heat sink Time to boil Safe Shutdown Earthquake Internal Flooding Emergency Lighting FLEX Tornado Generated Missile Fukushima Dai-Ichi Frazil ice Earthquake |
| PLA-6938, Response to Request for Information Pursuant to 10 CFR 50.54 (F) Regarding Results of the SSES Flooding Walkdown (References 1 and 2) PLA-6938 | 21 November 2012 | Response to Request for Information Pursuant to 10 CFR 50.54 (F) Regarding Results of the SSES Flooding Walkdown (References 1 and 2) PLA-6938 | Unanalyzed Condition Fire Barrier Safe Shutdown Earthquake Internal Flooding Hydrostatic Fukushima Dai-Ichi |
| PLA-6809, Proposed Amendment No. 309 to License NPF-14 & Proposed Amendment No. 280 to License NPF-22: Change to Technical Specification Surveillance Requirement (SR) 3.8.1.19 to Increase Diesel Generator E Minimum Steady. | 18 September 2012 | Proposed Amendment No. 309 to License NPF-14 & Proposed Amendment No. 280 to License NPF-22: Change to Technical Specification Surveillance Requirement (SR) 3.8.1.19 to Increase Diesel Generator E Minimum Steady. | Safe Shutdown Anticipated operational occurrence Offsite Circuit |
| ML13168A428 | 29 March 2012 | NRC 2012 Susquehanna Steam Electric Station Unit 2 - TN1179 | |
| ML13168A421 | 29 March 2012 | NRC 2012 Susquehanna Steam Electric Station Unit 1 - TN1178 | |
| ML12068A195 | 23 February 2012 | Technical Requirements Manual Unit 2 | Shutdown Margin Ultimate heat sink Post Accident Monitoring |
| ML11348A110 | 1 December 2011 | TRM1, Technical Requirements Manual, Unit 1 | Safe Shutdown Shutdown Margin High Radiation Area Ultimate heat sink Post Accident Monitoring Fire Protection Program |
| ML13046A137 | 30 November 2011 | Enclosure 8 | |
| ML112700069 | 26 September 2011 | Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants | Shutdown Margin Anticipated operational occurrence Safe Shutdown Earthquake Probabilistic Risk Assessment Operating Basis Earthquake Channel-control blade interference Scram Discharge Volume Earthquake |
| ML110871250 | 24 March 2011 | BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages | Weld Overlay VT-2 Earthquake EVT-1 Dissimilar Metal Weld DM weld |
| ML110250471 | 14 January 2011 | Technical Requirements Manual | Shutdown Margin Reactor Vessel Water Level Ultimate heat sink Post Accident Monitoring Scram Discharge Volume |
| PLA-6657, 10 CFR 50.59 Summary Report and Changes to Regulatory Commitments | 7 October 2010 | 10 CFR 50.59 Summary Report and Changes to Regulatory Commitments | Reactor Vessel Water Level Power Uprate |
| ML102040144 | 12 May 2010 | Replacement Steam Dryer Report, Unit 1, Start-Up, 107% Power Test Plateau 05/11/10 | |
| ML101270439 | 5 May 2010 | Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants | |
| ML100480185 | 31 December 2009 | BWRVIP-117NP-A: BWR Vessel and Internals Project - RAMA Fluence Methodology Plant Application-Susquehanna Unit 2 Surveillance Capsule Fluence Evaluation for Cycles 1-5, Final Report | |
| PLA-6568, Submittal of 10CFR26.719(c)(1) Report for Drug and Alcohol Testing Errors PLA-6568 | 5 October 2009 | Submittal of 10CFR26.719(c)(1) Report for Drug and Alcohol Testing Errors PLA-6568 | Fitness for Duty |
| ML092170333 | 31 July 2009 | Enclosure 2 to PLA-6542 - SSES Replacement Steam Dryer and Flow Induced Vibration Report Unit 2 Start-Up 107.0% Power Test Plateau. (Non-Proprietary) | Flow Induced Vibration |
| PLA-6523, Fourteen Refueling Outage Owner'S Activity Report PLA-6523 | 31 July 2009 | Fourteen Refueling Outage Owner'S Activity Report PLA-6523 | |
| ML091800460 | 23 June 2009 | Submittal of Work Environment Improvement Plan, PLA-6528 | |
| PLA-6510, Engineering Report 0000-0101-0766-NP-R0, Main Steam Line Limit Curve Adjustment During Power Ascension. | 30 April 2009 | Engineering Report 0000-0101-0766-NP-R0, Main Steam Line Limit Curve Adjustment During Power Ascension. | |
| ML090770447 | 28 February 2009 | Enclosure 5 to PLA-6484, Susquehanna Replacement Steam Dryer Updated Stress Analysis at Extended Power Uprate Conditions, Non-Proprietary Version Engineering Report 0000-0095-2113-NP-R0 | Finite Element Analysis Flow Induced Vibration |
| ML090770448 | 27 February 2009 | Enclosures 6, 7, 8 and 9 to PLA-6484, Revised Susquehanna Replacement Steam Dryer Limit Curves - Main Steam Line Mounted Instrumentation, Non-Proprietary Version Engineering Report 0000-0096-5766-NP-R1 | |
| PLA-6438, Proposed Amendment No. 274 to Unit 2: MCPR Safety Limits, Including Enclosure 2 to PLA-6438, PPL Evaluation of the Proposed Changes Unit 2 Minimum Critical Power Ratio Safety Limits, Non-Proprietary Version | 30 October 2008 | Proposed Amendment No. 274 to Unit 2: MCPR Safety Limits, Including Enclosure 2 to PLA-6438, PPL Evaluation of the Proposed Changes Unit 2 Minimum Critical Power Ratio Safety Limits, Non-Proprietary Version | Reactor Vessel Water Level Anticipated operational occurrence |
| ML082880420 | 14 October 2008 | River Drainage Yoy Smallmouth Bass Disease Investigations 2005 and 2007 |