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 Issue dateTitle
ML23345A08428 November 2023Technical Requirements Manual
ML23345A08828 November 2023Technical Requirements Manual
ML19290H0345 December 2019Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-Ichi Accident
ML19161A13715 May 2019Technical Specification Bases Manual
ML19163A18815 May 2019Unit, Technical Specification Bases Manual
ML17223A19821 July 2017Part 21 Notification - Eaton/Cutler Hammer A200 Series Starter
ML16334A26417 November 2016Technical Specification Bases Manual
ML16334A26517 November 2016Technical Specification Bases Manual
ML15317A0095 November 2015Technical Specifications Bases Manual
ML15317A0105 November 2015Technical Specifications Bases Manual
ML15296A05916 October 2015Enclosure 1, Response to NRC Request for Additional Information Regarding License Amendment Request to Adopt Nuclear Energy Institute 99-0 1, Revision 6 and Enclosure 2, Mark-up of the Changes Made to the SSES EAL Basis..
ML15296A06016 October 2015Enclosure 3, Revised (Clean) Copy of the SSES EAL Basis Document Which Includes the Changes Made in Enclosure 2
ML15296A05215 October 2015Attachments 1 Through 9 - EP-RM-004 to Enclosure 3 to PLA-7399 Mark-up of Proposed Additional Changes Made to the SSES EAL Basis Document
ML15296A05315 October 2015Enclosure 4 to PLA-7399 Revised (Clean) Copy of the SSES EAL Basis Document
PLA-7285, Revision (X) to EP-RM-004, EAL Classification Bases19 March 2015Revision (X) to EP-RM-004, EAL Classification Bases
ML14156A23416 June 2014Staff 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)
ML14056A4496 May 2014Staff 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)
ML14113A55523 April 2014Draft 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
ML13228A2831 August 2013Susquehanna - Handouts to Applicants (Folder 3)
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-693821 November 2012Response to Request for Information Pursuant to 10 CFR 50.54 (F) Regarding Results of the SSES Flooding Walkdown (References 1 and 2) PLA-6938
IR 05000387/201200310 August 2012IR 05000387-12-003, 05000388-12-003, 04/01/2012 - 06/30/2012; Susquehanna Steam Electric Station, Units 1 and 2; Maintenance Effectiveness, Operability Evaluations
ML12053A34012 March 2012Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident
ML12056A04912 March 2012Enclosure 3 - Recommendation 2.3: Seismic
ML12056A05012 March 2012Enclosure 4 - Recommendation 2.3: Flooding
ML10236034726 February 2010E-Mail from Thomas to Rosebrook Et Al., Subject: Ioeb Screening Summary for Friday, February 26, 2010
ML0913906297 May 2009Revisions to Technical Specifications Bases, Manual
ML08127018124 April 2008Revisions to Technical Specification Bases Unit 1 Manual
ML06142052811 May 2006Technical Specifications Bases Unit 1 Manual, Rev. 74
ML06142052511 May 2006Technical Specifications Bases Unit 2 Manual, TSB2, Revision 72
ML06123067524 April 2006Technical Specification Bases Unit 1 Manual, Revision 72
ML06124010424 April 2006Technical Specification Bases Unit 2 Manual
PLA-5933, Proposed Amendment No. 280 to Unit 1, and Proposed Amendment No. 249 to Unit 2, Revise Technical Specification 3.4.10, RCS Pressure and Temperature (P/T) Limits.5 October 2005Proposed Amendment No. 280 to Unit 1, and Proposed Amendment No. 249 to Unit 2, Revise Technical Specification 3.4.10, RCS Pressure and Temperature (P/T) Limits.
PLA-5632, Letter Transmitting for NRC Review and Approval, Revisions to Susquehanna Ses Emergency Action Levels27 October 2003Letter Transmitting for NRC Review and Approval, Revisions to Susquehanna Ses Emergency Action Levels
ML0231805007 November 2002Approved Amendment to Technical Specifications Bases Manual, Revision 33
ML0231900647 November 2002Revision to Improved Technical Specifications Manual Bases Unit 1
ML18017A2936 January 1998Provides Responses to Improved TS Section 3.8 Per 970324 NRC Rai.Schedule 980628 for Improved TS Implementation. Submittal of Revised Specifications Is Planned for Jan 1998
Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures9 July 1997Inadequate or Inappropriate Interim Fire Protection Compensatory Measures
ML18017A28913 February 1997Responds to RAI Re Adequacy & Availability of Design Bases Info
ML18017A2832 October 1995Responds to NRC Staff Questions on Rev of Emergency Plan That Implemented NUMARC NESP-007
ML18030A38913 December 1994Informs of Completion of Review of Ref Draft Final SE Re Spent Fuel Pool Cooling for Factual Accuracy
ML07104001728 April 199459 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations
ML20058M03010 September 1993Forwards Listed Info,In Response to Asking NRC to Address Issues Raised in Ltr from Constituent Me Lampert Re Problems at Pilgrim,W/Exception of Issue of Loss of Power & Fpc.Issue of Loss of off-site Power & FPC Related to SSES
ML18026A24827 November 1992Part 21 Rept Re Substantial Safety Hazard in Design of Facility for Loss of Normal Spent Fuel Pool Cooling
ML17157C14221 October 1992Engineering Assessment of Fuel Pool Cooling Piping EDR-G20020.
ML17157C14031 August 1992Review of Fuel Pool Cooling During Postulated Off-Normal & Accident Events SSES Units 1 & 2.
ML17157C13827 July 1992Safety Consequences of Boiling Spent Fuel Pool at Susquehanna Steam Electric Station.
NRC Generic Letter 1992-026 March 1992NRC Generic Letter 1992-002: Resolution of Generic Issue 79, Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown.
ML0311405497 November 1991Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability
Information Notice 1991-38, Thermal Stratification in Feedwater System Piping13 June 1991Thermal Stratification in Feedwater System Piping
ML18030A07522 October 1990Discusses Util Current Approach Re Reportability of Design Issues & Regulatory Analysis
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