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Category:Letter
MONTHYEARIR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 PLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8077, Emergency Plan Revision 67 (PLA-8077)2023-12-27027 December 2023 Emergency Plan Revision 67 (PLA-8077) IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 PLA-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan PLA-8084, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22023-11-29029 November 2023 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 ML23345A0682023-11-28028 November 2023 Technical Specification Bases, Manual PLA-8091, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091)2023-11-0808 November 2023 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091) IR 05000387/20230032023-11-0303 November 2023 Integrated Inspection Report 05000387/2023003 and 05000388/2023003 PLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML23291A1132023-10-12012 October 2023 Submittal of Revision 71 to Updated Final Safety Analysis Report and Revision 25 to Fire Protection Review Report ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0412023-10-0505 October 2023 Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information IR 05000387/20233012023-09-20020 September 2023 Initial Operator Licensing Examination Report 05000387/2023301 and 05000388/2023301 ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) IR 05000387/20230052023-08-31031 August 2023 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2023005 and 05000388/2023005) ML23228A1952023-08-21021 August 2023 Summary of August 10, 2023, Public Observation Meeting Re. Proposed Alternative PLA-8080, Proposed Relief for Valve 251130 (PLA-8080)2023-08-14014 August 2023 Proposed Relief for Valve 251130 (PLA-8080) PLA-8074, Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2023-08-0303 August 2023 Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval IR 05000387/20230022023-08-0101 August 2023 Integrated Inspection Report 05000387/2023002 and 05000388/2023002 ML23195A1852023-07-27027 July 2023 Correction to Technical Specifications Page 3.3-73 in Amendment No. 265 PLA-8076, Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076)2023-07-20020 July 2023 Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076) ML23201A0152023-07-20020 July 2023 Operator Licensing Examination Approval ML23200A1012023-07-19019 July 2023 Notification of Conduct of a Fire Protection Team Inspection ML23193A0062023-07-12012 July 2023 Requalification Program Inspection PLA-8078, Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-80782023-07-0505 July 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-8078 ML23163A1012023-06-12012 June 2023 10 CFR 50.46 Annual Report (Pla 8065) PLA-8054, Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence2023-06-0808 June 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence IR 05000387/20234012023-06-0707 June 2023 Security Baseline Inspection Report 05000387/2023401 and 05000388/2023401 PLA-8073, Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval2023-06-0101 June 2023 Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval PLA-8064, Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064)2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064) ML23132A3212023-05-17017 May 2023 Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 285 and 269 Related to Order Approving Transfer of Licenses PLA-8067, Notification of Completion of Emergence from Bankruptcy (PLA-8067)2023-05-17017 May 2023 Notification of Completion of Emergence from Bankruptcy (PLA-8067) IR 05000387/20230012023-05-12012 May 2023 Integrated Inspection Report 05000387/2023001 and 05000388/2023001 PLA-8066, Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-80662023-05-0808 May 2023 Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-8066 PLA-8053, Radiation Exposure Information and Reporting System2023-04-27027 April 2023 Radiation Exposure Information and Reporting System PLA-8058, Annual Radiological Environmental Operating Report (PLA-8058)2023-04-26026 April 2023 Annual Radiological Environmental Operating Report (PLA-8058) PLA-8041, Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041)2023-04-25025 April 2023 Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041) PLA-8047, 2022 Annual Environmental Operating Report (Nonradiological), PLA-80472023-04-19019 April 2023 2022 Annual Environmental Operating Report (Nonradiological), PLA-8047 PLA-8062, Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-80622023-04-11011 April 2023 Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-8062 PLA-8061, Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-80612023-04-10010 April 2023 Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-8061 ML23090A2302023-03-31031 March 2023 NRC Decommissioning Funding Status Report PLA-8049 PLA-8060, Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060)2023-03-30030 March 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060) ML23095A0572023-03-29029 March 2023 NRC Decommissioning Funding Status Report December 31, 2022 PLA-8057, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-80572023-03-15015 March 2023 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-8057 ML23065A1962023-03-0202 March 2023 EN 56387 Paragon - Part 21 Report Re Defect Identified in Automatic Transfer Switch Pn: NLI-ATS480A400X1 IR 05000387/20220062023-03-0101 March 2023 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2022006 and 05000388/2022006) PLA-8052, (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums2023-02-13013 February 2023 (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums IR 05000387/20220042023-02-0808 February 2023 Integrated Inspection Report 05000387/2022004 and 05000388/2022004 ML23010A0882023-01-15015 January 2023 Summary of Regulatory Audit in Support of License Amendment Request to Revise Control Rod Technical Specifications 2024-02-07
[Table view] Category:Report
MONTHYEARML23010A0882023-01-15015 January 2023 Summary of Regulatory Audit in Support of License Amendment Request to Revise Control Rod Technical Specifications PLA-8026, Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026)2022-10-19019 October 2022 Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026) PLA-7998, Submittal of Unit 1 Cycle 23 Core Operating Limits Report and Reload Safety Analysis Report2022-03-29029 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 22022-03-0808 March 2022 Supplement to License Amendment Requesting Adoption of TSTF-505, Revision 2 PLA-7959, Owner'S Activity Report PLA-79592021-07-15015 July 2021 Owner'S Activity Report PLA-7959 PLA-7910, Submittal of Unit 2 Cycle 21 Fuel Rod Design Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies PLA-79102020-12-10010 December 2020 Submittal of Unit 2 Cycle 21 Fuel Rod Design Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies PLA-7910 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 12018-11-27027 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 ML18024A1142018-01-24024 January 2018 a Reaction to Cracking of Austenitic Stainless Steel Piping in Boiling Water Reactors (Includes Susquehanna Ses Design Modifications) ML17093A6682017-03-27027 March 2017 Technical Requirements Manual Unit 2, Revision 93 with Revision 13 to Table of Contents PLA-7559, Flooding Mitigating Strategies Assessment (MSA) Report2016-12-19019 December 2016 Flooding Mitigating Strategies Assessment (MSA) Report ML16231A5092016-08-25025 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) 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 Accident2016-06-30030 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 ML16054A2432016-02-0909 February 2016 NPDES Permit No. PA 0047325 Renewal Application ML15356A2472016-01-20020 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 PLA-7414, Redacted - Susquehanna, Units 1 and 2 - Submittal of 10 CFR 71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 91682015-11-19019 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 91682015-08-20020 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-73112015-04-0909 April 2015 Negative Blind Specimen Report, PLA-7311 ML15090A3002015-04-0101 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) PLA-7287, Flood Hazards Reevaluation Report PLA-72872015-03-0303 March 2015 Flood Hazards Reevaluation Report PLA-7287 ML14176A9612014-06-24024 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 PLA-7175, (SSES)- 10 CFR 50.46 - Annual Report2014-06-20020 June 2014 (SSES)- 10 CFR 50.46 - Annual Report ML14156A2342014-06-16016 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) ML14056A4492014-05-0606 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) ML14113A5552014-04-23023 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 ML14085A3982014-03-26026 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 ML14085A4262014-03-26026 March 2014 Apendix B IPEEE Adequacy Review ML14010A3712014-01-15015 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 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-69382012-11-21021 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 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.2012-09-18018 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. ML13168A4282012-03-29029 March 2012 NRC 2012 Susquehanna Steam Electric Station Unit 2 - TN1179 ML13168A4212012-03-29029 March 2012 NRC 2012 Susquehanna Steam Electric Station Unit 1 - TN1178 ML12068A1952012-02-23023 February 2012 Technical Requirements Manual Unit 2 ML11348A1102011-12-0101 December 2011 TRM1, Technical Requirements Manual, Unit 1 ML13046A1372011-11-30030 November 2011 Enclosure 8 ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML1108712502011-03-24024 March 2011 BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages ML1102504712011-01-14014 January 2011 Technical Requirements Manual PLA-6657, 10 CFR 50.59 Summary Report and Changes to Regulatory Commitments2010-10-0707 October 2010 10 CFR 50.59 Summary Report and Changes to Regulatory Commitments ML1020401442010-05-12012 May 2010 Replacement Steam Dryer Report, Unit 1, Start-Up, 107% Power Test Plateau 05/11/10 ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1004801852009-12-31031 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-65682009-10-0505 October 2009 Submittal of 10CFR26.719(c)(1) Report for Drug and Alcohol Testing Errors PLA-6568 ML0921703332009-07-31031 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) PLA-6523, Fourteen Refueling Outage Owner'S Activity Report PLA-65232009-07-31031 July 2009 Fourteen Refueling Outage Owner'S Activity Report PLA-6523 ML0918004602009-06-23023 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.2009-04-30030 April 2009 Engineering Report 0000-0101-0766-NP-R0, Main Steam Line Limit Curve Adjustment During Power Ascension. ML0907704472009-02-28028 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 ML0907704482009-02-27027 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 Version2008-10-30030 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 ML0828804202008-10-14014 October 2008 River Drainage Yoy Smallmouth Bass Disease Investigations 2005 and 2007 2023-01-15
[Table view] Category:Technical
MONTHYEARPLA-8026, Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026)2022-10-19019 October 2022 Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026) PLA-7998, Submittal of Unit 1 Cycle 23 Core Operating Limits Report and Reload Safety Analysis Report2022-03-29029 March 2022 Submittal of Unit 1 Cycle 23 Core Operating Limits Report and Reload Safety Analysis Report PLA-7910, Submittal of Unit 2 Cycle 21 Fuel Rod Design Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies PLA-79102020-12-10010 December 2020 Submittal of Unit 2 Cycle 21 Fuel Rod Design Report to Support License Amendment Requesting Application of Advanced Framatome Methodologies PLA-7910 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 12018-11-27027 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 ML18024A1142018-01-24024 January 2018 a Reaction to Cracking of Austenitic Stainless Steel Piping in Boiling Water Reactors (Includes Susquehanna Ses Design Modifications) ML17093A6682017-03-27027 March 2017 Technical Requirements Manual Unit 2, Revision 93 with Revision 13 to Table of Contents 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 Accident2016-06-30030 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 ML16054A2432016-02-0909 February 2016 NPDES Permit No. PA 0047325 Renewal Application PLA-7287, Flood Hazards Reevaluation Report PLA-72872015-03-0303 March 2015 Flood Hazards Reevaluation Report PLA-7287 ML14176A9612014-06-24024 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 ML14010A3712014-01-15015 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 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-69382012-11-21021 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 ML13168A4282012-03-29029 March 2012 NRC 2012 Susquehanna Steam Electric Station Unit 2 - TN1179 ML13168A4212012-03-29029 March 2012 NRC 2012 Susquehanna Steam Electric Station Unit 1 - TN1178 ML11348A1102011-12-0101 December 2011 TRM1, Technical Requirements Manual, Unit 1 ML1102504712011-01-14014 January 2011 Technical Requirements Manual ML1004801852009-12-31031 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 ML0921703332009-07-31031 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) PLA-6510, Engineering Report 0000-0101-0766-NP-R0, Main Steam Line Limit Curve Adjustment During Power Ascension.2009-04-30030 April 2009 Engineering Report 0000-0101-0766-NP-R0, Main Steam Line Limit Curve Adjustment During Power Ascension. ML0907704472009-02-28028 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 ML0907704482009-02-27027 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 Version2008-10-30030 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 ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0828300742008-07-31031 July 2008 GE-NE 0000-0085-2413 NP-R0, Susquehanna Unit 1, Replacement Steam Dryer Vibration Instrumentation Program NRC Summary Test Report ML0810105462008-04-0101 April 2008 Attachment 2 to PLA-6346, Non-Proprietary Version of Unit 1 Main Steam Line Limit Curves ML0806602552008-02-22022 February 2008 GE-NE-000-0080-2994-NP-R2, Revision 2, Susquehanna Replacement Steam Dryer Instrumentation Acceptance Criteria - Dryer Mounted Instrumentation. ML0803800892008-01-31031 January 2008 Engineering Report, GE-NE-0000-0079-2250-NP-R0, Susquehanna Replacement Steam Dryer Stress Analysis at Extended Power Uprate Conditions ML0728501222007-10-10010 October 2007 BWRVIP-145NP, BWR Vessel and Internals Project, Evaluation of Susquehanna Unit 2 Top Guide and Core Shroud Material Samples Using RAMA Fluence Methodology ML0720103642007-06-30030 June 2007 GE-Hitachi Nuclear Energy Americas LLC Report GE-NE-0000-0061-0595-NP-R1, Susquehanna Replacement Steam Dryer Fatigue Analysis. ML0700403832006-12-31031 December 2006 GE-NE-OOOO-0061-0595-NP-RO, Engineering Report: Susquehanna Replacement Steam Dryer Fatigue Analysis. PLA-6136, Proposed License Amendment, Arts/Mella Implementation Response to Request for Additional Information PLA-61362006-11-29029 November 2006 Proposed License Amendment, Arts/Mella Implementation Response to Request for Additional Information PLA-6136 PLA-5995, Proposed Amendment No. 269 to Unit 1 & Amendment No. 236 to Unit 2: DC Electrical Power Systems Technical Specifications Rewrite - Response to Request for Additional Information (RAI)2005-12-15015 December 2005 Proposed Amendment No. 269 to Unit 1 & Amendment No. 236 to Unit 2: DC Electrical Power Systems Technical Specifications Rewrite - Response to Request for Additional Information (RAI) PLA-5983, Proposed License Amendment Numbers 272 for Unit 1 Operating License No. NPF-014 and 241 for Unit 2 Operating License No. NPF-022, Power Range Neutron Monitor Digital Upgrade Supplemental Information2005-12-0101 December 2005 Proposed License Amendment Numbers 272 for Unit 1 Operating License No. NPF-014 and 241 for Unit 2 Operating License No. NPF-022, Power Range Neutron Monitor Digital Upgrade Supplemental Information PLA-6130, Rev. 0 to 0000-0039-3825 Susq A-M T506-RBM-Calc-2005, Instrument Limits Calculation, PPL Susquehanna, LLC, Susquehanna Steam Electric Station Units 1 & 2, Rod Block Monitor (Numac ARTS-MELLA).2005-10-31031 October 2005 Rev. 0 to 0000-0039-3825 Susq A-M T506-RBM-Calc-2005, Instrument Limits Calculation, PPL Susquehanna, LLC, Susquehanna Steam Electric Station Units 1 & 2, Rod Block Monitor (Numac ARTS-MELLA). ML0601203532005-10-13013 October 2005 Proposed Amendment No. 281 and Proposed Amendment No. 251: Application for License Amendment and Related Technical Specification Changes to Implement Full-Scope Alternative Source Term in Accordance with 10 CFR 50.67 ML0507504332005-03-11011 March 2005 PROJ0704 - BWRVIP-1 17NP: BWR Vessel and Internals Project, RAMA Fluence Methodology Plant Application - Susquehanna Unit 2 Surveillance Capsule Fluence Evaluation for Cycles 1-5 ML0710400422003-08-0101 August 2003 Environmental Studies in the Vicinity of the Susquehanna Steam Electric Station 2002 Water Quality and Fishes. PLA-5616, Annual Personnel Exposure Report PLA-56162003-04-28028 April 2003 Annual Personnel Exposure Report PLA-5616 ML18024A0561978-09-15015 September 1978 Letter Supplementing PP&L Letters Dated April 17, 1978 and July 14, 1978 and Attaching a Final Report of a Deficiency in Seismic Qualification of Medium Voltage, Metal Clad, Safeguards Switchgear ML18026A2181978-04-14014 April 1978 SSES Design Assessment Report, Revision 1 ML18025A6661978-02-28028 February 1978 Structural Integrity Test Report Containment Structure Unit 1 ML18025A6671977-12-30030 December 1977 Final Report on Shear Studs ML18025A1901977-06-22022 June 1977 Letter Enclosing an Interim Report of Reportable Deficiency Regarding Unsatisfied Field Welding and Inspection of Shear Studs ML18026A1191977-03-22022 March 1977 Results of Non-Nuclear Hot Test with the Relief System in the Philippsburg Nuclear Power Plant ML18025A0911976-05-31031 May 1976 Ecological Studies of the North Branch Susquehanna River in the Vicinity of the Susquehanna Steam Electric Station - Progress Report for the Period January-December 1974 ML18023A8811975-08-29029 August 1975 Letter Transmitting Report on Deficiency in Box Column Supports for the Susquehanna Nuclear Plant. ML18025A2011975-08-29029 August 1975 Definitive Report of Deficiencies in Fabricated Structural Steel Members (Box Column Supports) ML18023A8841975-07-25025 July 1975 Letter Regarding an Interim Report of Reportable Deficiency ML18023A8871975-04-0404 April 1975 Letter Attaching an Interim Report on a Potential Deficiency Which Was Discussed on March 6, 1975 ML18026A1181972-12-31031 December 1972 Formation and Oscillations of a Spherical Gas Bubble Under Water 2022-03-29
[Table view] |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (BIDS >
DISTRIBUTION FOR INCOMING MATERIAL 50-387 REC: GRIER 8 H ORG: CURTIS N W DOCDATE: 09/15/78 NRC PA PNR 5 LIGI-lT DATE RCVD: 09/22/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL FURNISHING SUPPLEMENT TO APPLICANT"S LTRS OF 04/17/73 AND 07/14/78 CONTAINING FINAL CONSTRUCTION DEFICIENCY REPT CONCERNING DEFICIENCY IN EISMIC QUALIFICATION OF MEDIUM VOLTAGE M.TAL CLAD SAFEGUARDS WITCHGEAR.
PLANT NAME: SUSQUEHANNA " <<UNIT 1 REVIEWER INITIAL: X JM DISTRIBUT0B INITIAL~
u v%%%%%%%%%%%%%%% DISTRIBUTION OF THIS MATERIAL IG AS FOLLOWS %%<%%%%%%%%%%%%%%%
NOTES:
SEND IS(E 3CYS FSAR 8( ALL AMDTG CONSTRUCTION DEFICIENCY REPORT <10CFR50. 55E)
(DISTRIBUTION CODE 8019>
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$ITJNE: (215) 821-5151 g~XKD NORMAN W, CURTIS Vice President Engineering 8 Construction 821-5381 CJ Pl o>
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Mr. Boyce H. Grier n rn C)
Director, Region I Cll U. S. Nuclear Regulatory Cczanission 631 Park Avenue King of Prussia, Pennsylvania 17406 SUSQUEEQKA STEAM ELECTRIC STATION F3'EPORT OF A DEFICIENT',CY IN SEISMIC QUAIZFICATION OF I%DEN VOLTAGE, M'TAL CLAD, SM."%GUARDS SWITCHGFAR DOCKET NO.: 50-387 LICENSE NO: CPPR-101 ER 100450 FILE 840-4
' I PLA 289 ~ = I ~ 4 \
Dear Mr. Grier:
This supplements PPSZ letters PLA-246, dated April 17, 1978 and PLA-271, dated July 14, 1978, and provides a final report of the subject deficiency as recpuzed by 10CFR50.55 (e) .
Please advise should you recure additional information.
Very truly yours, N. W. Curtis Vice President-Engineering 6 Construction Attachment ARS:mcb cc: Mr. J. G. Davis (15)
Acting Director-Office of Inspection 6 Enforcement U. S. Nuclear ReyQatory Ccmiission--
Washington, D.C. 20555 Mr. G. MDonald, Director (1)
Office of Managanent,,Information 6
'U. S. Nuclear Regulatory Ccmtission
~am Contxol Washington, D.C. 20555 t78p86p147 PENNSYLVANIA POWER 8, LIGHT COMPANY 9'e~t
Mr. B. H. Grier Sept.anber 15, 1978 cc: Mr. Robert M. Gallo U. S. Nuclear Regulatory Gmxnission P.O. Box 52 Shickshinny, Pennsylvania 18655
OF A DEFICIENCY IN SEISMIC QUALIFICATION OF MEDIUM VOLTAGE, MEAL CLAD, SAFEGUABDS SWHCHG1RR FOR THE SUSQUEHANNA STEAM 1KZCTRIC STATICN D. P. Parsons SSES Electrical Group Supvr.
Approved By: .. ~~~
A. M. e 9 r~ pg.
Supervising Engineer-Design-Suscpehanna Reviewed:
A. R. Scil Manager-Nuclear Quality Assurance PENNSYLVANIA HMK 6 LIGHT CCMPANY AL'EZKTQWN, PENNSYLVANIA S1M.'EMBER 15, 1978
TABLE OF CONTENTS Introduction Pg. l Description of Deficiency Pgs, lg 2g 3 Analysis of Safety Implications Pg. 3 Corrective Action Pgs. 4, 5 Conclusion Pg. 5
INTRODUCZION This report is prepared in accordance with the requirements described in Title 10, Code of Federal Regulations, Part 50, Section 50.55(e) .
PPK was advised, through its A/E (Bechtel) organization, t1wt Westinghouse supplied, medium voltage, metal clad switchgear was not capable of withstanding the postulated seismic event for Susquehanna Plant. Bechtel was requested to review the situation and advise PPsZ of its findings. On Parch 31, 1978 the NRC was informed that a deficiency, potentially reportable under 10CFR50.55(e),
was being evaluated, and on April 17, 1978, following an engineering review, PAL issued its Interim Report of the deficiency.
The deficiency was determined to be reportable under 10CFR50.55(e) for the following reasons:
- 1. The deficiency, were it to remain uncorrected, could have resulted in a safety hazard to the operation of the plant.
- 2. The deficiency represented a deficiency in final design as approved and released for fabrication and installation.
- 3. Eight safety-related switchgear units had, been shipped and accepted for installation before the deficiency was discovered.
DJHCRIPTION OF DEFICIENCY The Susquehanna Plant was supplied eight deficient safety related medium voltage switchgear units by Westinghouse. Four of these switchgear units supply power directly to 4kv safety related equipnent, pump rmtors and load centers, >Rich are used to mitigate the effects of an accident in Unit l.
Likewise, four switchgear units are used as the supply for 4kv safety related loads on Unit 2.
Each switchgear unit, contains three potential transformer circuits, one of the circuits consists of ~ potential transformers connected in an open delta. The other two circuits each contain one potential transformer used to sense single phase potential. The potential transformers are used to obtain 120 volt, potential irr3ication for use with relays on the switchgear units'he IIedium Voltage Ywtal Clad Switchgear (Safeguards) Specif ication (8856-E-109) requires the equipment to meet seismic recpdxements of Project Specification 8856-6-10, IEEE Standard M. 344, and to reaein functional, koth, during and after an OBE or DBE.
Westinghouse advised Bechtel on January 24, 1978 that the potential transformer secondary disconnecting contact assanblies on equignent similar to that supplied for Susquehanna had failed to withstand recent seismic tests.
Westinghouse further stated that, under seismic conditions, it is possible that the slip-fit secondary contacts could be dislodged fran their normal positions resulting in open or. short circuiting of the secondary circuits.
Westinghouse requested that Bechtel evaluate the condition to detaanine if it auld constitute a safety hazard.
.Westinghouse confirmed that there were no failures of potential transformer circuits during the original seismic qualification tests. However, these circuits were subsequent1y redesigned and the new design was analytically qualified. Situal seismic tests on switchgear units incorporating the new design resulted in the potential transformer circuit failures >M.ch are the subject of this report.
Westinghouse also confirmed that the seianic qualification of all other canponents in these assemblies remain valid.
MALYSIS OF SMOKY IMPLICATIONS The engineering evaluation determined that the open or short circuiting of any of the seco~ contacts could result. in incorrect operation of a switchgear unit. It was concluded that the worst condition results fran the loss of all three potential transformer circuits on each switchgear bus.
Under this condition, the tm inccming bus feeders frcm the safeguard transformers (one from each offsite source) would be automatically disconnected frcm each switchgear bus and the diesel generator power source connected restoring power to the bus.
A LOCA occuring during or after the postulated, seismic event would initiate a closing signal to the motor feeder breakers of the shutdown loads, i.e.
RHR and Core Spray Hotors. These feeder breakers would close and ismMiately trip due to the false undervoltage indication as sensed by the undervoltage relay. The circuit breakers would be unable to close again because of the permanent undervoltage trip signal imposed on them. The above analysis assumes'hat, the failures concurrently occur on all redundant m~tchgear huses.
Based upon the evaluation of Bechtel Engineering~it is concluded that this condition of not being able to supply power to the shutdown loads under a DXK condition constitutes a safety hazard to the operation of the plant and represents a deficiency in final design.
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CORRECTIVE 'ACTION Action Taken to Contxol 'Deficient.'Items The actions taken by Bechtel prior to the suhnittal of the interim report of the deficiency by PP&L are domunented in PZA-246 dated April 17, 1978.
In addition to the measures previously identified, and in the interest of obtaining documented evidence of Bechtel Pxoject Engineering's evaluation of the condition's cause, corrective action required, and reportability under 10CFR50.55(e), Bechtel QA generated Ihnagerrent Corrective Action Request No.
1-22 dated March 28, 1978.
Corrective Action to 'Control 'Resolution 'of 'the Def iciencies Westinghouse has supplied modification kits which provide for eliminating the stationaxy, secondary disconnecting contact assemblies from the potential transformer circuits. Twenty-four (24) (three kits for each of the eight safety-related switchgear units) potential transfoxmer secondary fieM rmdification kits (Westinghouse Style No. 628F14G01) have been provided.
These rrodification kits have been installed by Bechtel field electricians per the instructions on Westinghouse drawing 628F146. These changes were made under the supervision of the Westinghouse Engineering Service Personnel.
The modification consists of hard wiring the secondary arable contact to a texminal block via a wiring harness. The PT secondary circuits are then connected to the field side of the terminal block. The secondary stationary contacts are removed entirely, thus eliminating the source of the seismic failure.
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Westinghouse has seianically qualified the potential transformers with the
@edified secondary contact arrangement. Donznented evidence of this qualification has been provided to Bechtel through a revision to the original qualification report.
COVZIJSXONS l4xlifications have been made to aU. the Westinghouse safety-related, median voltage switchgear units containing potential transformers and purchased under P.O. 8856-E-109AC for Susquehanna Steam Electric Station. The Bechtel generated hMnconfoxmance Report (NCR hM. 2514) will not be closed out until Bechtel Quality Contxol has performed the attendant inspections and has verified that the mxlification kits rare installed according to design requirements-The andified switchgear units are qualified to meet the postulated seismic event. for Susquehanna and documentation of this seismic qualification has been received and will be reviewed by Bechtel Engineering. Bechtel's acceptance of this documentation will result in an acceptably documented revision to the Westinghouse Seianic Qualification Report.
The switchgear units~as presently modified, are compatible with purchase order, PSAR and FSAR requiranents.