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List of results

• AECM-84-0324, Updated Special Rept 84-021/1:on 840408,Fire Door 1A320 to Main Steam Tunnel Blocked Open to Support Planned Maint Activities.Initially Reported on 840515.Maint Outage Continues.Fire Watch to Be Kept Until Door Restored  + (Updated Special Rept 84-021/1:on 840408,Fire Door 1A320 to Main Steam Tunnel Blocked Open to Support Planned Maint Activities.Initially Reported on 840515.Maint Outage Continues.Fire Watch to Be Kept Until Door Restored)
• AECM-84-0387, Updated Special Rept 84-022/1:on 840429,auxiliary Main Steam Tunnel Temps Exceeded 125 F Limit of Tech Spec 3.7.8. Task Cards Will Be Issued to Track New Qualified Life of Each Affected Component  + (Updated Special Rept 84-022/1:on 840429,auxiliary Main Steam Tunnel Temps Exceeded 125 F Limit of Tech Spec 3.7.8. Task Cards Will Be Issued to Track New Qualified Life of Each Affected Component)
• AECM-84-0186, Updated Special Rept 84-110/1:on 831213,Fire Door 1A320 Blocked Open to Support Planned Maint & Testing Activities. Fire Watches Established Until Door Restored on 840306  + (Updated Special Rept 84-110/1:on 831213,Fire Door 1A320 Blocked Open to Support Planned Maint & Testing Activities. Fire Watches Established Until Door Restored on 840306)
• AECM-84-0185, Updated Special Rept 84-111/1:on 830328,fire Penetration CE-519D in Computer Room Opened Under Maint Work Order (Mwo) to Install Conduits.Caused by Design Closure Detail Being Omitted from Mwo.Programmatic Control Implemented  + (Updated Special Rept 84-111/1:on 830328,fire Penetration CE-519D in Computer Room Opened Under Maint Work Order (Mwo) to Install Conduits.Caused by Design Closure Detail Being Omitted from Mwo.Programmatic Control Implemented)
• ML20108E558  + (Updated Special Rept 84-37/1:on 841129,loose Parts Detection Sys Declared Inoperable for 30 Days,Reaching Limiting Condition for Operation Time Limit of Tech Spec 3.3.7.10, Causing Alarm to Seal In.Alarm Response Instruction Revised)
• ML20033E263  + (Updated Special Rept Containing Revised Dates for Fire Damper Operability.Fire Damper 97,located in Electrical Switchgear Room B,Will Be Restored to Operability by 900316 & Damper 93 Will Be Restored by 900416)
• JAFP-93-0011, Updated Special Rept Documenting Inability to Restore Fire Door to Functional Status within Required Time Frame.On 921201,door Determined to Be Nonfunctional & Not Restored Until 921211.As of 930104,two Doors Remain Nonfunctional  + (Updated Special Rept Documenting Inability to Restore Fire Door to Functional Status within Required Time Frame.On 921201,door Determined to Be Nonfunctional & Not Restored Until 921211.As of 930104,two Doors Remain Nonfunctional)
• ML20113J115  + (Updated Special Rept MP-91-1080:on 910816,passive Triaxial (Recording) Peak Accelerograph Removed from Svc Due to Inconsistency of Magnetic Trace Data.Amended Surveillance Program Assures Exisitng Accelerographs Meet Design Intent)
• ML20137V742  + (Updated Special Rept Re Continuing Investigation & Addl Corrective Actions for Inoperable Radiation Monitoring Instrumentation,Per Tech Spec Section 6.9.3.f.Monitor R-1258B Not Returned to Svc by 851101)
• ML20107D515  + (Updated Special Rept Re Diesel Generator Failures. Reevaluation Reduced Failures of Diesel Generator 1A to One Common Failure,Decreasing Total to Two Failures Out of 58 Valid Tests)
• ML17328A651  + (Updated Special Rept on 891113 Re Fire Door 387,Unit 1 Reactor Cable Tunnel Quadrant No 2 Door Declared Inoperable. Caused by Failure of Latching Mechanism.Design Change Provided Adequate Repair to Door)
• BECO-84-108, Updated Special Rept:On 820118,carbon Dioxide Fire Suppression Sys in Cable Spreading Room Determined Inoperable.Carbon Dioxide Sys Main Shutoff Valve Closed & Tagged,Allowing Either Automatic or Manual Operation  + (Updated Special Rept:On 820118,carbon Dioxide Fire Suppression Sys in Cable Spreading Room Determined Inoperable.Carbon Dioxide Sys Main Shutoff Valve Closed & Tagged,Allowing Either Automatic or Manual Operation)
• ML20087A376  + (Updated Special Rept:On 910816,triaxial Peak Accelerograph Inoperable for More than 30 Days & Vendor Stated Tolerance Could Not Be Verified.Accelerograph Will Be Replaced W/Model Which Complies W/Reg Guide 1.12)
• ML20128E806  + (Updated Special Rept:On 920204,loose Parts Monitoring Sys Declared Inoperable Due to Receipt of Low Level Alarms on All Channels.On 920902,Channel 12 Went Into Alarm Due to Spurious Low Level Vibration Alarms.Channel to Be Restored)
• ML24281A203  + (Updated Species List: Tennessee Ecological Services Field Office Clinch River Exemption Request Review)
• TMI-23-005, Updated Spent Fuel Management Plan  + (Updated Spent Fuel Management Plan)
• ML18157A014  + (Updated Staff Assessment of National SAFER Response Centers Established in Response to Order EA-12-049)
• ML22061A199  + (Updated Staff Response to ACRS on RG 1.9 Rev 5)
• ML19347F500  + (Updated Statement of Matl Facts as to Which No Genuine Issue Exists to Be Heard Re Intervenor,Ba Bursey,Contention A10. Proposed Evidentiary Support for Intervenor Bursey Indicates That Low Level Radiation Causes Cancer & Genetic Damage)
• LIC-15-0100, Updated Status of Generic Letter (GL) 2004-02 and Generic Safety Issue (GSI) 191, Pressurized Water Reactor Sump Performance  + (Updated Status of Generic Letter (GL) 2004-02 and Generic Safety Issue (GSI) 191, Pressurized Water Reactor Sump Performance)
• NL-14-0672, Updated Status/Analysis of Core Shroud  + (Updated Status/Analysis of Core Shroud)
• ML14162A011  + (Updated Status/Analysis of Core Shroud Acknowledgment Letter)
• ML18102B278  + (Updated Std Format for Reporting Number of Personnel & Person-Mrem by Work & Job Function for 960101-1231)
• L-16-241, Updated Steam Generator Inspection Report - Fall 2015 Refueling Outage  + (Updated Steam Generator Inspection Report - Fall 2015 Refueling Outage)
• NL-22-0147, Updated Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements  + (Updated Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements)
• LR-N21-0075, Updated Steam Generator Tube Inspection Report - March 2020 to Reflect TSTF-577 Reporting Requirements  + (Updated Steam Generator Tube Inspection Report - March 2020 to Reflect TSTF-577 Reporting Requirements)

• ML23305A041  + (Updated Steam Generator Tube Inspection Report)
• ML23305A042  + (Updated Steam Generator Tube Inspection Report)

• LR-N21-0076, Updated Steam Generator Tube Inspection Report - Twenty-second Refueling Outage (2R22) to Reflect TSTF-577 Reporting Requirements  + (Updated Steam Generator Tube Inspection Report - Twenty-second Refueling Outage (2R22) to Reflect TSTF-577 Reporting Requirements)
• ML19351F074  + (Updated Stipulations Re Intervenors Pl Hourihan,K Dahl & C Shuey Contentions.Parties Agreed to Language in Accepted Contentions 1,5,7 & 8 & Disputed Contentions 6A,6B,14,17,18, 23A,23B & 28)
• L-13-312, Updated Submittal of FENOC Response to NRC Request for Information Pursuant to 10CFR50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident  + (Updated Submittal of FENOC Response to NRC Request for Information Pursuant to 10CFR50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident)
• JAFP-04-0173, Updated Submittal of Security Plan  + (Updated Submittal of Security Plan)
• JAFP-04-0168, Updated Submittal of Security Plan  + (Updated Submittal of Security Plan)
• BVY 04-104, Updated Submittal of Security Plan  + (Updated Submittal of Security Plan)
• PLA-5815, Updated Submittal of the PPL Susquehanna, LLC Physical Security Plan Revision 0, PLA-5815  + (Updated Submittal of the PPL Susquehanna, LLC Physical Security Plan Revision 0, PLA-5815)
• PLA-5798, Updated Submittal of the Plant Physical Security Plan Revision 0 PLA-5798  + (Updated Submittal of the Plant Physical Security Plan Revision 0 PLA-5798)
• GNRO-2004/00055, Updated Submittal to Security Plan, T&Q Plan and Safeguards Contingency Plan Incorporating RAI Responses  + (Updated Submittal to Security Plan, T&Q Plan and Safeguards Contingency Plan Incorporating RAI Responses)
• ML20213D531  + (Updated Summary of Clinical Evaluation Study)
• ML20003H778  + (Updated Summary of Intervenor B Bursey Standing Contentions)
• ML21089A218  + (Updated Supplemental Guidance Regarding IMC 2515 Appendix E Application to Radiation Safety Inspections)
• NL-09-138, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.  + (Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.)
• L-2008-160, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.  + (Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.)
• ML090641038  + (Updated Supplemental Response to NRC Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
• ML090641018  + (Updated Supplemental Response to NRC Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
• ML111180686  + (Updated Supplemental Response to NRC Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
• L-2009-179, Updated Supplemental Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors  + (Updated Supplemental Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
• ML092170370  + (Updated Supplemental Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
• LR-N09-0072, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors  + (Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
• ML091000557  + (Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
• ML093290316  + (Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
• ML082380244  + (Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
• RS-14-133, Updated Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident  + (Updated Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident)