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Category:Letter type:PLA
MONTHYEARPLA-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) 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 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) 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 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 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) 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 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 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-8067, Notification of Completion of Emergence from Bankruptcy (PLA-8067)2023-05-17017 May 2023 Notification of Completion of Emergence from Bankruptcy (PLA-8067) 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) 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 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) 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 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 PLA-8048, Response to Request for Additional Information Regarding License Amendment Requesting Temporary Addition of Analyzed Rod Position Sequence2023-01-14014 January 2023 Response to Request for Additional Information Regarding License Amendment Requesting Temporary Addition of Analyzed Rod Position Sequence PLA-8042, Proposed Emergency Amendment to License NPF-22: Temporary Addition of Analyzed Rod Position Sequence2023-01-10010 January 2023 Proposed Emergency Amendment to License NPF-22: Temporary Addition of Analyzed Rod Position Sequence PLA-8039, Application for Order Approving Indirect Transfer of Control of License Amendments - Supplemental Information2022-12-22022 December 2022 Application for Order Approving Indirect Transfer of Control of License Amendments - Supplemental Information PLA-8038, Notification of Petition for Bankruptcy (PLA-8038)2022-12-14014 December 2022 Notification of Petition for Bankruptcy (PLA-8038) PLA-8036, Registration for the Use of Spent Fuel Storage Casks 203, 202, and 204, PLA-80362022-11-30030 November 2022 Registration for the Use of Spent Fuel Storage Casks 203, 202, and 204, PLA-8036 PLA-8035, Registration for the Use of Spent Fuel Storage Casks 205, 200, and 201, PLA-80352022-11-0808 November 2022 Registration for the Use of Spent Fuel Storage Casks 205, 200, and 201, PLA-8035 PLA-8031, Emergency Plan Revision 66 (PLA-8031)2022-11-0707 November 2022 Emergency Plan Revision 66 (PLA-8031) PLA-8032, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments - Supplemental Information (PLA-8032)2022-10-28028 October 2022 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments - Supplemental Information (PLA-8032) 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-8015, Application for Order Approving Indirect Transfer of Control of Licenses2022-09-29029 September 2022 Application for Order Approving Indirect Transfer of Control of Licenses PLA-8030, Evacuation Time Estimate Report PLA-80302022-09-15015 September 2022 Evacuation Time Estimate Report PLA-8030 PLA-8025, Supplement to License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value2022-08-10010 August 2022 Supplement to License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value PLA-8019, Nd Refueling Outage Owner'S Activity Report, PLA-80192022-07-13013 July 2022 Nd Refueling Outage Owner'S Activity Report, PLA-8019 PLA-8013, Response to Request for Additional Information Regarding License Amendment Requesting Adoption of TSTF-505, Revision 2 PLA-80132022-06-27027 June 2022 Response to Request for Additional Information Regarding License Amendment Requesting Adoption of TSTF-505, Revision 2 PLA-8013 PLA-8012, 10 CFR 50.46 Annual Report2022-06-10010 June 2022 10 CFR 50.46 Annual Report PLA-8005, Response to Request for Additional Information Regarding License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value (PLA-8005)2022-05-23023 May 2022 Response to Request for Additional Information Regarding License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value (PLA-8005) PLA-8001, Radiation Exposure Information and Reporting System - PLA-80012022-04-28028 April 2022 Radiation Exposure Information and Reporting System - PLA-8001 PLA-7987, Radioactive Effluent Release Report and Offsite Dose Calculation Manual - (PLA-7987)2022-04-26026 April 2022 Radioactive Effluent Release Report and Offsite Dose Calculation Manual - (PLA-7987) PLA-7986, 2021 Annual Environmental Operating Report (Nonradiological) Docket No. 50-387, PLA-79862022-04-26026 April 2022 2021 Annual Environmental Operating Report (Nonradiological) Docket No. 50-387, PLA-7986 PLA-7985, Annual Radiological Environmental Operating Report2022-04-22022 April 2022 Annual Radiological Environmental Operating Report PLA-7883, Proposed Amendment to Licenses NPF-14 and NPF-22: Relocate Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program (PLA-7883)2022-03-31031 March 2022 Proposed Amendment to Licenses NPF-14 and NPF-22: Relocate Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program (PLA-7883) PLA-7995, Property Insurance Program (PLA-7995)2022-03-30030 March 2022 Property Insurance Program (PLA-7995) 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-7991, Proof of Financial Protection and Guarantee of Payment of Deferred Premium2022-03-24024 March 2022 Proof of Financial Protection and Guarantee of Payment of Deferred Premium 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-7962, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR PLA-79622022-01-0505 January 2022 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR PLA-7962 2024-01-04
[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:Miscellaneous
MONTHYEARML23010A0882023-01-15015 January 2023 Summary of Regulatory Audit in Support of License Amendment Request to Revise Control Rod Technical Specifications 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-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) 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-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 ML14085A4262014-03-26026 March 2014 Apendix B IPEEE Adequacy Review 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 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. ML12068A1952012-02-23023 February 2012 Technical Requirements Manual Unit 2 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 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 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 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 ML0828804202008-10-14014 October 2008 River Drainage Yoy Smallmouth Bass Disease Investigations 2005 and 2007 PLA-6437, 10 CFR 50.59 Summary Report and Changes to Regulatory Commitments for 10/01/2004 to 08/31/20062008-10-0909 October 2008 10 CFR 50.59 Summary Report and Changes to Regulatory Commitments for 10/01/2004 to 08/31/2006 PLA-6408, EPU Start-Up Main Steam Line Strain Gage and Piping Vibration Summary Test Report, Enclosure 22008-08-31031 August 2008 EPU Start-Up Main Steam Line Strain Gage and Piping Vibration Summary Test Report, Enclosure 2 ML0821206262008-07-30030 July 2008 Day Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 PLA-6388, Fifteenth Refueling Outage Owner'S Activity Report, PLA-63882008-07-0707 July 2008 Fifteenth Refueling Outage Owner'S Activity Report, PLA-6388 PLA-6358, License Condition 2.C. (36) (a) 32008-05-15015 May 2008 License Condition 2.C. (36) (a) 3 PLA-6280, License Renewal Application Evaluation of Errors in the Severe Accident Mitigation Alternatives Analysis2007-10-0202 October 2007 License Renewal Application Evaluation of Errors in the Severe Accident Mitigation Alternatives Analysis ML0707406842007-04-16016 April 2007 Issuance of Environmental Scoping Summary Report Associated with the NRC Staff'S Review of the Application by PPL Susquehanna, Lcc, for Renewal of the Operating Licenses for Susquehanna Steam Electric Station, Units 1 and 2 (TAC No. MD3021 ML0708004142007-03-20020 March 2007 High Conservation Priority - Big River Species ML0708004392007-03-20020 March 2007 Pennsylvania Fishes: Suckers ML0708004432007-03-20020 March 2007 Pennsylvania Fishes: Sunfishes ML0707204572007-03-0707 March 2007 Adw Pandion Haliaetus Information ML0707204522007-03-0707 March 2007 Adw Cryptobranchus Alleganiensis Information ML0707204752007-03-0707 March 2007 Butterflies and Moths of North America, Aphrodite Fritillary Species Detail ML0707204772007-03-0707 March 2007 Butterflies and Moths of North America, Baltimore Species Detail ML0707204822007-03-0707 March 2007 Butterflies and Moths of North America, Mulberry Wing Species Detail ML0707204872007-03-0707 March 2007 Butterflies and Moths of North America, Northern Pearly Eye Species Detail ML0707204912007-03-0707 March 2007 Butterflies and Moths of North America, Pine-Devil Moth Species Detail ML0707204542007-03-0707 March 2007 Adw Ardea Alba Information ML0707206152007-03-0707 March 2007 Wetplants and Shrubs ML0707206192007-03-0707 March 2007 Adw Myotis Sodalis Information ML0707206582007-03-0707 March 2007 Wrcf - Northeastern Bulrush ML0707206792007-03-0707 March 2007 Pennsylvania Natural Heritage Program, Natural Community Types, Updated January 2007 2023-01-15
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Britt T. McKinney PPL Susquehanna, LLC Sr. Vice President & Chief Nuclear Officer 769 Salem Boulevard , '
- ~Berwick, PA 18603 a Na Tel. 570.542.3149 Fax 570.542.15043 se '
btmckinney@pplweb.com * :6 .
MAYý 1 5 2008 ppI, Net.
TM U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop OP1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION UNIT 1 OPERATING LICENSE NO. NPF-14 LICENSE CONDITION 2.C. (36) (a) 3 Docket Nos. 50-387 PLA-6358 and 50-388 The purpose of this letter is to docket the attached evaluation of steam dryer performance based on the data collected at the 3.5% power ascension step that was provided via electronic submission to the NRC on May 1, 2008 as required by the License Condition.
License Condition 2.C. (36) (a) 3 requires:
"PPL shall hold the facility at each 3.5% ascension step to collect data from License Condition 2.C. (36) (a) and conduct plant inspections and walk-downs, and evaluate steam dryer performance based on the data; shall provide the evaluation to the NRC Staff by facsimile or electronic transmission to the NRC project manager upon completion of the evaluation; and shall not increase power above each hold point until 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after the NRC project manager confirms receipt of the transmission."
Enclosure 1 contains the proprietary version of "SSES Replacement Dryer Test Condition '1 1.' Results." The information in Enclosure 1 contains proprietary information as defined by 10CFR2.390. GEH and PPL, as the owners of the proprietary information, have executed the enclosed affidavits, which identify that the enclosed proprietary information has been handled and classified as proprietary, is customarily held in confidence, and has been withheld from public disclosure. The proprietary information was provided to PPL in a GEH transmittal that is referenced by the affidavit.
The proprietary information has been faithfully reproduced in the enclosed information such that the affidavit remains applicable. GEH and PPL hereby request that the enclosed proprietary information be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390 and 9.17.
-2 - Document Control Desk PLA-6358 The header of each page in this enclosure carries the notation "GEH Proprietary Information" or "GEH and PPL Proprietary Information." GEH proprietary information is identified by a dotted underline inside double square brackets. ((This..s.e.tent..c.e.is .a~n example..)) In each case, the superscript notation 3 refers to Paragraph (3) of the GEH affidavit, which provides the basis for the proprietary determination. Specific information that is not so marked is not GEH proprietary. PPL proprietary information is identified inside triple brackets. (({This sentence is an exainple.{2k} In each case, the superscript notation{21 refers to Paragraph (2) of the PPL affidavit, which provides the basis for the proprietary determination. Specific information that is not so marked is not PPL proprietary.
The following is in response to a question from the NRC on the references provided in :
Reference 3:
GE-NE-0000-0080-2994-R2, which provided the designed Dryer Instrumentation Acceptance Criteria, was transmitted to the NRC in PLA-6332 on February 22, 2008.
During the installation of the instrumentation, one of the instruments was not installed in the exact location assumed in GE-NE-0000-0080-2994-R2. Therefore, a new set of acceptance criteria was developed for that one instrument. The revised acceptance criteria was transmitted to the NRC in PLA-6349 dated April 11, 2008. PLA-6332 and PLA-6349 contain the same acceptance criteria that are in GE-NE-0000-0080-2994-R4 (Reference 3).
Reference 4:
This reference was transmitted to the NRC in PLA-6323 dated January 25, 2008.
1 contains the non-proprietary version of "SSES Replacement Dryer Test Condition '1.1' Results." Enclosure 3 contains the signed affidavits. Enclosure 4 contains the steam dryer data log sheet.
If you have any questions or require additional information, please contact Mr. Michael H. Crowthers at (610) 774-7766.
Document Control Desk PLA-6358 I declare under penalty of perjury that the foregoing is true and correct.
Executed on:
B. T. McKinney - SSES Replacement Dryer Test Condition "1 .I" Results - PPL and GEH Proprietary Information - SSES Replacement Dryer Test Condition "1 .I" Results - Non-Proprietary Information - Affidavits - Steam Dryer Data Log Sheets Copy: NRC Region I Mr. R. R. Janati, DEP/BRP Mr. F. W. Jaxheimer, NRC Sr. Resident Inspector Mr. B. K. Vaidya, NRC Project Manager
Enclosure 2 to PLA-6358 Non-Proprietary Version of SSES Replacement Dryer Test Condition "l.1" Results
ENCLOSURE 2 102992-PPL-38159 1-C-001 SSES Replacement Dryer Test Condition "1.1" Results Non-Proprietary Information This is a non-proprietary version of the Enclosure 1 of 102992-PPL-381591-C-001, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here (( I].
102992-PPL-381591 -C-00 1 Non-Proprietary Version Page 1 of 25 This enclosure provides a summary of the SSES Unit 1 replacement steam dryer instrumentation measurements at Test Condition "l.1". Test Condition "l.r"was performed at a power level of 3612 MWth (91.4% of the licensed EPU power level). The dryer instrumentation locations are documented in Appendix A of this enclosure. Table 1 shows the maximum strain and acceleration amplitudes as a percent of the acceptance limits provided in Reference 3. All values of strain and acceleration are below the Level 2 acceptance limits for Test Condition "l.I".
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Figures 1 through 10 ((
102992-PPL-381591-C-001 Non-Proprietary Version Page 2 of 25 Figures 11 through 20 provide ((
102992-PPL-381591-C-001 Non-Proprietary Version Page 3 of 25
102992-PPL-381591-C-001 Non-Proprietary Version Page 4 of 25
102992-PPL-381591 -C-001 Non-Proprietary Version Page 5 of 25
References:
- 1. Steam Dryer Instrumentation for PPL-Susquehanna Unit 1 Contract # 381591-C
- 2. PPL Susquehanna LLC, Susquehanna Steam Electric Station Units 1 and 2, Extended Power Uprate Phase I1,GE Proposal No. 1208- 1JMZL -KRO, Revision 1, submitted March 29, 2005.
- 3. GE-NE-0000-0080-2994-R4, "Susquehanna Replacement Steam Dryer Instrumentation Acceptance Criteria - Dryer Mounted Instrumentation" April 2008.
- 4. GE-NE-0000-0079-2250-P-RO, "Susquehanna Replacement Steam Dryer Stress Analysis at Extended Power Uprate Conditions," January 2008.
102992-PPL-38159 1-C-001 Non Proprietary Version Page 6 of 25
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102992-PPL-38159 l-C-001 Non-Proprietary Version Appendix A Page 1 of 6 ENCLOSURE 2 102992-PPL-381591-C-001 Appendix A: SSES Replacement Dryer Instrumentation Locations
102992-PPL-381591 -C-00 1 Non-Proprietary Version Appendix A Page 2 of 6 Table A-i: Description of (( 1].
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102992-PPL-38159 1-C-001 Non-Proprietary Version Appendix A Page 3 of 6
[I Figure A-1 Dryer Top View
102992-PPL-381591-C-001 Non-Proprietary Version Appendix A Page 4 of 6
[1 Figure A-2 Elevation Ninety Degree View
- Dimension measured along circumference.
- This (( )) is vertical, all others horizontal
102992-PPL-38159 l-C-001 Non-Proprietary Version Appendix A Page 5 of 6 Figure A-3 Elevation Zero Degree View
** Dimension measured along circumference.
102992-PPL-381591-C-001 Non-Proprietary Version Appendix A Page 6 of 6
((
Figure A-4 Elevation 270 Degree View to PLA-6358 Affidavits
GE-Hitachi Nuclear Energy Americas LLC AFFIDAVIT I, Richard E. Kingston, state as follows:
(1) I am Vice President, Methods Licensing, Regulatory Affairs, GE-Hitachi Nuclear Energy-Americas LLC ("GEH"). I have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in GEH letter, 102992-PPL-381591-C-001, dated May 1, 2008. GEH proprietary information is identified by a dotted underline inside double square brackets ((.Th-..ia m../*.[.e... 3))). In each case, the superscript notation {3} refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.
(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GEH relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for "trade secrets" (Exemption 4). The material for which exemption from disclosure is here sought also qualify under the narrower definition of "trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975F2d871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704F2d1280 (DC Cir. 1983).
(4) Some examples of categories of information which fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GEH's competitors without license from GEH constitutes a competitive economic advantage over other companies;
- b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;
- c. Information which reveals aspects of past, present, or future GEH customer-funded development plans and programs, resulting in potential products to GEH;
- d. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. above.
Af 102992-PPL-381591-C-OO1 .doc Affidavit Page I of 3
(5) To address 10 CFR 2.390(b)(4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GEH, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GEH, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties, including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7) following.
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or subject to the terms under which it was licensed to GEH. Access to such documents within GEH is limited on a "need to know" basis.
(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist, or other equivalent authority for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GEH are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.
(8) The information identified in paragraph (2) above is classified as proprietary because it contains results and details of structural analysis methods and techniques developed by GEH for evaluations of a BWR Steam Dryer and of other reactor internals, including separators. Development of these methods, techniques, and information and their application for the design, modification, and analyses methodologies and processes for the Steam Dryer Program and to the design and manufacturing of other BWR internal hardware was achieved at a significant cost to GEH, on the order of approximately several million dollars.
The development of the evaluation process along with the interpretation and application of the analytical results is derived from the extensive experience database that constitutes a major GEH asset.
(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GEH's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GEH's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost.
The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
Af 102992-PPL-381591-C-OO1.doc Affidavit Page 2 of 3
The research, development, engineering, analytical and NRC review costs comprise a substantial investment of time and money by GEH.
The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.
GEH's competitive advantage will be lost if its competitors are able to use the results of the GEH experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to GEH would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GEH of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.
I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to the best of my knowledge, information, and belief.
Executed on this 3 0 th day of April 2008.
9YýJ E,-ký'
Richard E. Kingston GE-Hitachi Nuclear Energy Americas LLC Af 102992-PPL-381591-C-OO1.doc Affidavit Page 3 of 3
.CONFIDENTIAL INFORMATION SUBMITTED UNDER 10 C.F.R. §2.390 AFFIDAVIT OF RICHARD D. PAGODIN I, Richard D. Pagodin General Manager-Nuclear Engineering PPL Susquehanna, LLC, do hereby affirm and state:
- 1. I am authorized to execute this affidavit on behalf of PPL Susque-hanna, LLC (hereinafter referred to as "PPL").
- 2. PPL requests that the information attached and identified inside triple brackets (({This sentence is an example.}}} be withheld from public disclosure under the provisions of 10 C.F.R. 2.390(a)(4).
- 3. The PPL Documents contain confidential commercial information, the disclosure of which would adversely affect PPL.
- 4. This information has been held in confidence by PPL. To the extent that PPL has shared this information with others, it has done so on a confidential basis.
- 5. PPL customarily keeps such information in confidence and there is a rational basis for holding such information in confidence. The information is not available from public sources and could not be gathered readily from other publicly available information.
- 6. Public disclosure of this information would cause substantial harm to the competitive position of PPL, because such information has significant commercial value to PPL.
- 7. The information identified in paragraph (2) above is classified as proprietary because it details the results of test data derived from test instrumentation installed specifically to collect this data. This instrumentation was installed at a significant cost to PPL.
The data and the conditions under which it was collected constitute a major PPL asset.
- 8. Public disclosure of the information sought to be withheld is likely to cause substantial harm to PPL by foreclosing or reducing the availability of profit-making opportunities. The information is of value to other BWR Licensee's and would support evaluations and analyses associated with extended power uprate license amendment submittals. Making this information available to other BWR Licensee's would represent a windfall and deprive PPL the opportunity to recover a portion of its large investment in the test instrumentation from which this data is derived.
PPL SUSQUEHANNA, LLC Richard D. Pagodin
/
Subscribed and sworn before me, a Notary Public in and for the Commonwealth of Pennsylvania This !*day of I('\ .. 2008 COMMONWEALTH OF PENNSYLVANIA Notarial Seal Laurie M.Minto, Notary Public Salem Twp., Luzeme County My Commission Expires July 24, 2010 Member, P~nnsy!vIr, A.sociation of Notaries
Enclosure 4 to PLA-6358 Steam Dryer Data Log Sheets
Steam Dryer Data Log Sheets S. iI ' " '...,.
Start Dat~fýime 410/2008 11:37
- Computer ID ::Value *UnIts Thermal: Power (Instantaneous) uO:.nba0l 360694 MWth J:
Thermal Power (15 m n Ave.) *, * :u.nbaIl01 3611.20: MWth Electrical Power U01.tra178 1209.28 Mwe Total Core Flow " U01.tra026 100.16 M:.Ibm/hr.::.
Recirc Lobp Flow A :U01.tra028 50.20 M lbm/hr Recird Looo Flow B u0l.tra29: 49.51 : M lbm/lhr Recirc LOOp A:Suctlon Temperature U0l.nrt01 526.71 : °F Recirc Loop B:zSuctlon Temperature : u01.nrt02 527.33 F Core PlateDIP !uOl.tra*27 15.98 .:PSlI Indlcated Steam Flow L.ine A uO.talS::3 3.78 -M Ibm/hr indlIcated team Flow Line B u:I.tra14 3.097: MIbrn/lhr::
Indlcated.SteamrFlow Line C :U1OtAaI55 3.97: M lI*bm/hr IndicatedSteam Flow Line D u01.3tra156 3.83 M ibm/h Indicated.:Total:Steam Flow ii.tr*097 15.42 M.:
MIbm/hr:.
Indicated FeeAdwater Flow U1.trao98. 15.A15 M Ibm/ihr:
FeedWater .Temperature Line A u01tra102 ;396.3 7F:
Feedwater Temperature Line B u:.u tral3: 394F.51 ____. :..
FeedWater Temperature LlneC U00.tal04 395.84.: F "
Rx Dome Pressure Narrow Range uOl.trUa28 1019.51 .PSIG::
RxDonmePressure Wide Range u01.tra209 1020.86: PSIG-:
Steam Dome Temperature :Iu01.nfa05 548.92:::
Reclriculation Pump A Speed vm.1p401 all ajrpjtac 1463.00 RPM:
Recirculatlon Pump B Speed vm,1p401b/lbjrrp tac 1467.00 RPM Reclrculatlon Pump A Power :::U.nrJ5 3.92. ..
1: M aWe Recirculaton Pump B, Power -01.nrj52 3.94 :: MWe CRD Cooling Header Flow u0i.nef03 63.39 GPM:::q CRDSystem Flow d:0.nef0I 62.52,: :GPM CRD.SystemTemperature ul0.ndt05 122.52:::
Bottom:Head:Drain.Temp u~l).tra2O6 533.71,., O ReactoriWaterL'eLvel.:NarrOw Range uO1.tra142. -34.03:: Inches1-120:
Reactor0Water:Level, Narrow Range .. - u fi02. "35.0 ::1Idhes:H20, Reactor WaterLevel Narrow Range :UO0.nfIO3: 33.80 hIc,,esH20 Reactor Water Level[Wde Range. ... t.....r:::::::r0ai43:: 34.86 Inches:1120ý RecirculitioniPuwnp A Vaine Passsing Freq. n/a 121.92: Hz Reclrculation:Pump BVaiie Passing:Fre. - /a :::122.25- Hz-Recirculation PUmp AM otor Frequency, n/a 49.26'.. Hz Reclrculation.~ump.BMotor Frequiency n/a 49.39.: ýHz Enhanced Steam Flow Calculations Feed Flow'Lne A.(LEFM) u:0.nff77 4.98 M IbmI/hr;.
Feed FIow ULIn B (LEFM) ,uOl nff78 5.06 :.::, M Ibm/hr-Feed Flow. Line C (LEFM) . u01.nff79 4.92 : M Ibmlhr CRD Flow uol.ndf0i:.: 0.03 ::...:WM Ibm/lhr.
Total Feedwater Flow n/........ 14.99 M MIbm/r SteiamrFlow Line.A n/a 3.65 M ibm/hr Steam Flow Line B n/a 3.82: MIbm/hr Steam Flow Line C n/a 3.83,:::. ::M' Ibmlhr:.
Steam: Flow Line D na-3.169 '.:!M lbm/hr,:
Total Steam L.n/a Flow .14.:9 M Ibm/hr
3ý' ~'.
Steam Dryer Data Log Sheets-* .11 Finish Dae/F m 4130/2008 11:42 (Finish)
Computer. ID :Vali3b i Units:
Thermai Power (Instantaneous) uOl.nba0i 3608.21 MWth ThermailPower (15 min Ave.) uOl.nbal0l 3610.55 MWth Electrical Power.. . . uOl.tralT78 1203.45 Mwe Total Core Flow. uOl.tra026 .:100;54 Mibm/hr Redlrc Loop,:Flow,,A uOl'traO28 50.44 MIbmn/hr Reclrc iaoopFowB :uO*tra029 L 49.61 M Ib:mnhr Recirc:Lboop A Suction Temperature u:0.nrt02i : 526.56 T Reclrc Loop :B Suction Temperature, uOl .nrt02,271 CoreýPlate D/P .uOi.traO27 16.03 PSI' SteamnFlowbLne A uol.tralS3 'q 3.77 -M Ibm/hlr SteamF!ow Line B :U0.tra14 .3.95 M Ibm/hr SteamFlow. Line C u:0.tra155 : .. 3.98 M Ibm/hr.
SteamoFIow Line.D .Ol~tra556 3.83 M Ibm/hr TbtalSteai Flow u01.:trao97"./ . 15.42 M: Ibm/hr :.
Feedwater Flow. uol.trao98 .... 15.18 M ibm/Ir.hr Feedater.Temperature Line A u01.tralO2 396.41 1V Feedwater Temperature Line B .8, uOltra103 .. 394.58 TF Feedwater Temperature Une:C . .uOl.tralO4::: .395.86 ...... F° F& Dorme Pressure Narow :Range uOl.tra208 i*1019.51 RX Dome Pressure Wide Range PSIG
. uOl.tra2O9 1020.13 1 PSIG Steam Dome Temperature uOl.nfa05 548.92 ..... .F..
RecirculationrPumipA:Speed vm. Ip4la/lal...rptac, 1462.00: RPM.
Recirculation PumpB:Speed .. i..lp4O1blbrrp tac 1467.00-:, RPM Recirculation Pump A Power :o1nr5 , : .3194'. - MWe Recirculation Pump B Power ulu.nr52 .:3.96 MWe CRD0Co"1ing Header Flow uOl.nefO3>
CRD Sysftem Flow 63.40 GPM
,: uOl.nefOl 62.53: GPMV B ttom rH,..e Dra.n.Tep ,Had, ... uOl.tra2O6 533.92 . ...
Reactor Water Level:NarrowRange uOl.tral42 34.83 Inches H20 Rea*ctor Water:Level:Narrow.Range uOl.nfIO2 35.15 inches H20 Reactor Water Level Narrow :Range... uOl.nflO3 34.77 Inches H20 Reactor Waterr Level Wide:Range : uOl.tral43 Recirculation Pump A Vane Passing Freq. 35.80 Inches H20
, n/a 121.83 Hz Reclrculation Pump B Vane Passing Freq. nla 122.25 Hz Reclrrculation Purnp A Motor Frequency n/a' 49.23 Hz lRecirculation PurnO BrMotor Frequency n/a 49.39 Hz Enhanced' Steam Flow CalculationsA*____
Feed Flow Line A (LEFM) FuOl.nff7T. :5.00 M Ibm/~hr:.
Feed Flow Line B (LEFM) uOl.nff78: 506 MIbm/lhr Fie~d Flow Line C(LEFM) .uOI.nff79,ý.:.:,,.::.::..
4.921- - MlIbm/hr::'
CR0 Flow u0.dO Total Fee-dwater Flow .03:1 Mibm/ryr.
n/a .. :150 .. Mib/h Steam Flow Line A n/a .':3.65: M bmn/hr Steam, .Flow Une B n/a :3.82: M WIb/hr:
SteamnFlow Line C , .n/a 3.85._ M.Ibi/hr Steam FlowrLine D n/a 3.76 M: Ibm/hr Total Steamn Flow n/a 15.01o M Ibmn/hr}}