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).ML063460054 |
Person / Time |
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Site: |
Susquehanna ![Talen Energy icon.png](/w/images/c/c7/Talen_Energy_icon.png) |
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Issue date: |
10/31/2005 |
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From: |
General Electric Co, Susquehanna |
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To: |
Office of Nuclear Reactor Regulation |
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References |
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PLA-6130 DRF 0000-0044-6732, Rev 1, GE 0000-0039-3825, Susq A-M-T506-RBM-Calc-2005, Rev 0 |
Download: ML063460054 (16) |
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Category:Calculation
MONTHYEARPLA-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) ML16181A4172016-06-29029 June 2016 Projected Income Statement and Calculation of Six-Month Fixed Costs (Redacted) PLA-7455, Radioactive Effluent Release Report and Offsite Dose Calculation Manual2016-05-0202 May 2016 Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-7322, Offsite Dose Calculation Manual, 2014 Annual Report2015-04-28028 April 2015 Offsite Dose Calculation Manual, 2014 Annual Report PLA-7163, Attachment 2 to PLA-7163: Offsite Dose Calculation Manual2014-04-23023 April 2014 Attachment 2 to PLA-7163: Offsite Dose Calculation Manual PLA-7131, Calculation Number EC-RADN-1129, Revision 4, DBA-LOCA Total Control Room Dose.2014-01-10010 January 2014 Calculation Number EC-RADN-1129, Revision 4, DBA-LOCA Total Control Room Dose. ML14042A1452014-01-10010 January 2014 Calculation Number EC-RADN-1125, Revision 5, Crhe and Off Site Post LOCA Doses. PLA-6998, Response to Request for Additional Information Regarding Changes to Technical Specification (TS) Surveillance Requirement (SR) 3.8.1.19 to Increase Diesel Generator E Minimum Steady State Frequency PLA-69982013-05-10010 May 2013 Response to Request for Additional Information Regarding Changes to Technical Specification (TS) Surveillance Requirement (SR) 3.8.1.19 to Increase Diesel Generator E Minimum Steady State Frequency PLA-6998 PLA-6997, Response to Request for Additional Information Regarding Changes to Technical Specification Surveillance Requirements to Increase Diesel Generator Minimum Steady State Voltage2013-05-10010 May 2013 Response to Request for Additional Information Regarding Changes to Technical Specification Surveillance Requirements to Increase Diesel Generator Minimum Steady State Voltage PLA-6994, Annual Radioactive Effluent Release Report, Appendix a Through End2013-04-10010 April 2013 Annual Radioactive Effluent Release Report, Appendix a Through End PLA-6561, Amendment Request No. 296 to Unit 1 and Amendment Request No. 266 to Unit 2 Re Emergency Core Cooling System Instrumentation - Technical Specification (TS) Table 3.3.5.1-1 and Editorial Change to TS 3.10.8.F, Response to RAI2009-09-11011 September 2009 Amendment Request No. 296 to Unit 1 and Amendment Request No. 266 to Unit 2 Re Emergency Core Cooling System Instrumentation - Technical Specification (TS) Table 3.3.5.1-1 and Editorial Change to TS 3.10.8.F, Response to RAI ML0912006162008-11-25025 November 2008 Attachment 1 to PLA-6501, Calculation EC-037-001 ML0824211382008-07-0707 July 2008 Nuclear Engineering Calculation EC-RADN-1129, Revision 2, DBA-LOCA Total Control Room Dose ML0824211392008-06-30030 June 2008 Nuclear Engineering Calculation EC-RADN-1125, Revision 3, Crhe and Off Site Post LOCA Doses - AST ML0706702672006-12-0101 December 2006 Appendix to Attachment to PLA-6130 Arts/Mellla RBM Calculation ML0633104572006-11-10010 November 2006 Calculation EC-ENVR-1058, Rev 1, Crhe Accident Dispersion Factors (X/Q). ML0633104502006-11-10010 November 2006 Calculation EC-RADN-1128, Rev 1, Steam Line Break Accident Crhe & Off-Site Doses - Ast. ML0630601222006-03-13013 March 2006 Nuclear Engineering Calculation EC-059-1041, Rev. 02, Suppression Pool Ph Post Loca. ML0716203342006-01-24024 January 2006 GE Ne 0000-0038-8052 Susq-EPU-T506-MSLHiFlo-Calc-2006, Revision 0, Instrument Limits Calculation, PPL Susquehanna, LLC Susquehanna Steam Electric Station Units 1 and 2, Main Steam Line High Flow MSIV Isolation. ML0615204602005-12-0505 December 2005 Revised Calculation EC-RADN-1126, Revision 1 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). ML0601204882005-09-30030 September 2005 Calculation EC-RADN-1134, Impact of AST on Current NUREG-0737 Radiological Evaluations That Use TID-14844 DBA-LOCA Releases. ML0601204182005-09-21021 September 2005 Calculation NEPM-QA-0221-1, Assessment of Sblc System for Suppression Pool Ph Control. ML0601204212005-09-20020 September 2005 Calculation EC-059-1041, Suppression Pool Ph Post Loca. ML0601204292005-09-0606 September 2005 Calculation EC-RADN-1129, DBA-LOCA Total Control Room Dose. PLA-5963, Calculation EC-RADN-1135, Justification of AST 60 Isotope Radtrad Source Term for Direct Shine.2005-09-0101 September 2005 Calculation EC-RADN-1135, Justification of AST 60 Isotope Radtrad Source Term for Direct Shine. ML0601204832005-08-23023 August 2005 Calculation EC-RADN-1125, Crhe and Off Site Post LOCA Doses - Ast. ML0601204872005-08-19019 August 2005 Calculation EC-RADN-1127, Control Rod Drop Accident Crhe and Off Site Doses - Ast. ML0601204852005-08-19019 August 2005 Calculation, EC-RADM-1126, Crhe and Off Site Fha/Eha Doses - Ast. ML0601203642005-08-19019 August 2005 Calculation EC-RADN-1128, Steam Line Break Accident Crhe and Off Site Doses -AST. ML0601204792005-07-19019 July 2005 Calculation EC-ENVR-1059, Crhe Accident Dispersion Factors (X/Q) RB U2 Intake. ML0601204782005-07-19019 July 2005 Calculation EC-ENVR-1058, Crhe Accident Dispersion Factors (X/Q). ML0601203562005-04-18018 April 2005 Calculation EC-ENVR-1057, Offsite X/Q Values for the SSES Base on 1999-2003 Meteorological Data. ML0718001572004-10-0808 October 2004 Calculation EC-041-0508, Rev. 4, Cooling Tower Evaporation and Blowdown Rates for Power. 2023-04-25
[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
Appendix to Attachment to PLA-6130 ARTS/MELLLA RBM Calculation
GE Number: 0000-0039-3825 Susq A-M-T506-RBM-Calc-2005 Revision Number: 0 DRF Folder: 0000-0044-6732 Rev. I DRF Number: 0000-0039-3825 October 2005 Instrument Limits Calculation PPL Susquehanna, LLC Susquehanna Steam Electric Station Units 1 &.2 Rod Block Monitor (NUMAC ARTS-MELLLA)
Preparer: October 10, 2005 Andrew Poulos /Date Verifier: October 10, 2005 Robert Copp /Date Approved: October 10, 2005 Bradley Erbes /Date
0000-0039-3825 Susq A-M-T506-RBM-Caic-2005, Rev. 0 IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT Please Read Carefully The only undertakings of the General Electric company (GE) respecting information in this document are contained in the contract between PPL Susquehanna, LLC (PPL) and GE, ARTS/MELLLA for Susquehanna SES units 1 and 2 contract 280220-C, accepted July 22, 2004, as amended to the date of transmittal of this document, and nothing contained in this document shall be construed as changing the contract. The use of this information by anyone other than PPL, or for any purpose other than that for which it is intended is not authorized; and with respect to any unauthorized use, GE makes no representation or warranty, express or implied, and assumes no liability as to the completeness, accuracy or usefulness of the information contained in this document, or that its use may not infringe privately owned rights.
file: 05Sus Rbm Numac AMcalc OutDoc_RO.doc .2
0000-0039-3825 Susq A-M-T506-RBM-Caic-2005, Rev. 0 Contents:
This document is a supplement analysis data sheet to Reference 1. Included in this document in sequential order are:
- the setpoint functions for the system,
- the setpoint function analyses inputs and the source reference of the inputs,
- the devices in the setpoint function instrument loop,
- the component analysis inputs and input sources,
- input comments and result recommendations,
System: Rod Block Monitor (RBM)
The following setpoint functions are included in this document:
- Low Power Trip Setpoint (LTSP)
- Intermediate Power Trip Setpoint (ITSP)
- High Power Trip Setpoint (HTSP)
- Low Power Setpoint (LPSP)
- Intermediate Power Setpoint (IPSP)
- High Power Setpoint (HPSP) file: 05Sus Rbm Numac AMcalc OutDoc_R0.doc 3
0000-0039-3825 Susq A-M-T506-RBM-Calc-2005, Rev. 0
- 1. Function: RBM Rod Withdrawal Blocks Setpoint Characteristics: I Definition Reference(s)
Event Protection: Limiting event for the setpoint: Ref. 2, Ref. 3.1 Intro.
The RBM is designed to prevent fuel damage System Purpose, Ref.
. 3.2 Intro. System during a Rod Withdrawal Error (RWE) event Purpose, Ref. 4 Bases during high power operation. Section B 3.3.2.1 Function After Earthquake L Required 19 Not Required Ref. 4 Bases Section 3.3.2.1, Comment 9 Setpoint Direction: Ref. 4 Bases Section
" Low Power Trip Setpoint [K Increasing El Decreasing 3.3.2.1 (LTSP) Rod Block
" Intermediate Power Trip E Increasing El Decreasing Setpoint (ITSP)
" High Power Trip Setpoint E Increasing El Decreasing (HTSP)
" Low Power Setpoint (LPSP) E Increasing El Decreasing
" Intermediate Power Setpoint [D Increasing El Decreasing (IPSP)
" High Power Setpoint (HPSP) ED Increasing El Decreasing Single or Multiple Channel E Single El Multiple Ref. 4 Bases Section 3.3.2.1, Ref. 6.2 Section 4.1.6 LER Calculation Basis if Multiple Standard (Conservative) LER Calculation ED, or Ref. 1, Ref. 2 Channel Configuration Specific LER Calculation E]
Trip Logic for Configuration n/a Specific LER Calculation Plant Data: Value Sigma if not 2 Reference(s)
LPRM Detector (APRM PEA)
(% power)
APEAAccuracy +/- 1%; bias 0.49% Ref. 7.2 Section 2.1.1 APEApowerSupplyEffect negligible Ref. 2, Comment 6 DPEA
- Trip Setpoints negligible Ref. 7.2 Sec. 2.1.2
- Power Setpoints +/- 0.2% / 7 days); bias Ref. 7.2 Section 2.1.1 0.33% / 7 days file: 05Sus Rbm Numac AMcalc OutDoc RO.doc 4
0000-0039-3825 Susq A-M-T506-RBM-Calc-2005, Rev. 0
- 1. Function: RBM Rod Withdrawal Blocks (cont'd)
Plant Data: Value Sigma if not 2 Reference(s)
LPRM Detector (APRM PMA)
(% power)
" Tracking - Trip Setpoints 1% 3 Ref. 7.2 Sec. 1.1.2
" Tracking - Power Setpoints +/- 1.11% Ref. 7.4 Sec. 1 b),
Ref. 7.2 Sec. 1.1.1
" Noise - Trip Setpoints +/- 2% Ref. 7.4 Sec. 2, Ref.
7.2 Sec. 1.1.1
- Noise - Power Setpoints n/a Ref. 7.4 Sec. 1 b)
Components (or Devices) in Setpoint Function Instrument Loop:
" NUMAC Chassis:
- Instrument Loop Power Electronics (LPRM, APRM, RBM, Trip Circuit) file: 05Sus Rbm Numac AMcalc OutDoc_RO.doc 5
0000-0039-3825 Susq A-M-T506-RBM-CaIc-2005, Rev. 0 1.1 RBM Low Power Trip Setpoint (LTSP) Rod Block Current Function Value/Equation Reference(s)
Limits:
Present Susql & ARTS-MELLLA Ref. 6.2 Sec.
Susq2 Calculation Condition 4.8.2.4
(% RTP) (% RBM Ave. Flux)
Analytical Limit n/a 118% for TLO/SLO Ref. 3.1, Ref. Ref. 5.3 3.2 Tech Spec Allowable n/a Ref. 3.1, Ref. 3.2 Value Nominal Trip Setpoint n/a Ref. 3.1, Ref. 3.2 Operational Limit n/a n/a Ref. 3. 1, Ref. Ref. 1, Ref. 2, 3.2 Comment 3 1.2 RBM Intermediate Power Trip Setpoint (ITSP) Rod Block Current Function Value/Equation Reference(s)
Limits:
Present Susql & ARTS-MELLLA Ref. 6.2 Sec.
Susq2 Calculation Condition 4.8.2.4
(% RTP) (% RBM Ave. Flux)
Analytical Limit n/a 113% for TLO/SLO Ref. 3.1, Ref. Ref. 5.3 3.2 Tech Spec Allowable n/a / Ref. 3.1, Ref. 3.2 Value Nominal Trip Setpoint n/a yy Ref. 3.1, Ref. 3.2 Operational Limit n/a n/a Ref. 3.1, Ref. Ref. 1, Ref. 2, 3.2 Comment 3 1.3 RBM High Power Trip Setpoint (HTSP) Rod Block and Clamp Current Function Value/Equation Reference(s)
Limits:
Present Susql & ARTS-MELLLA Ref. 6.2 Sec.
Susq2 Calculation Condition 4.8.2.4
(% RTP) (% RBM Ave. Flux)
Analytical Limit TLO 0.58Wd + 58% 1.08% for TLO/SLO Ref. 3.1, Ref. Ref. 5.3 Clamp: n/a Clamp: n/a 3.2 SLO 0.58Wd + 53%
Tech Spec Allowable 0.66Wd + 55% - .! Ref. 3.1, Ref. 3.2, Ref. 4 Section Value TLO 3.3.2.1 SLO 0.58Wd + 50% ,
Nominal Trip Setpoint 0.58Wd + 52% .... Ref. 3.1, Ref. 3.2 TLO SLO 0.58Wd + 47% /
Operational Limit n/a n/a Ref. 3.1, Ref. Ref. 1, Ref. 2, 3.2 Comment 3 file: 05Sus Rbm Numac AMcalc OutDoc RO.doc 6
0000-0039-3825 Susq A-M-T506-RBM-Caic-2005, Rev. 0 1.4 RBM Low Power Setpoint (LPSP)
Current Function Value/Equation Reference(s)
Limits: I Present Susql & ARTS-MELLLA Susq2 Calculation Condition
(% RTP) (% RTP)
Analytical Limit - 30% 30% for TLO/SLO Ref. 4 Section Ref. 7.1, Ref.
3.3.2.1 5.3 Tech Spec Allowable n/a Ref. 3.1, Ref. 3.2 Value *k, Nominal Trip Setpoint n/a Ref. 3.1, Ref. 3.2 Operational Limit n/a n/a Ref. 3.1, Ref. Ref. 1, Ref. 2, 3.2 Comment 3 1.5 RBM Intermediate Power Setpoint (IPSP)
Current Function Value/Equation Reference(s)
Limits:
Present Susql & ARTS-MELLLA Susq2 Calculation Condition
(% RTP) (% RTP)
Analytical Limit n/a 65% for TLO/SLO Ref. 3.1, Ref. Ref. 5.3 3.2 1 Tech Spec Allowable n/a Ref. 3.1, Ref. 3.2 Value Nominal Trip Setpoint n/a Ref. 3.1, Ref. 3.2 Operational Limit n/a n/a Ref. 3.1, Ref. Ref. 1, Ref. 2, 3.2 Comment 3 1.6 RBM High Power Setpoint (HPSP)
Current Function Value/Equation Reference(s)
Limits:
Present Susql & ARTS-MELLLA Susq2 Calculation Condition
(% RTP) (% RTP)
Analytical Limit n/a 85% for TLO/SLO Ref. 3. 1, Ref. Ref. 5.3 3.2 Tech Spec Allowable n/a Ref. 3.1, Ref. 3.2 Value Nominal Trip Setpoint n/a Ref. 3.1, Ref. 3.2 Operational Limit n/a n/a Ref. 3.1, Ref. Ref. 1, Ref. 2; 3.2 Comment 3 file: 05Sus Rbm Numac AMcalc OutDoc_RO.doc 7
0000-0039-3825 Susq A-M-T506-RBM-Calic-2005, Rev. 0
- 2. Components:
2.1 Power Electronics (LPRM, APRM, RBM, Trip Circuit)
Component Information: Value/Equation Reference(s)
Plant Instrument ID No. Not provided Comment 2 Instrument vendor GE / Reuter-Stokes Ref. 5.3 Model ID No. (including LPRMs: NA300 Ref. 5.3 Range Code)
Plant Location(s) Control Structure - Lower Relay Room Ref. 5.1, Ref. 5.2, Ref. 5.3 Process Element Neutron detector Ref. 6.2 Sections 1.5 & 3.2, Ref. 7.3 Inputs:
Vendor Specifications Value / Equation Sigma if not 2 Reference s)
Top of Scale FS = 125%
- Ref. 6.2 Sections 4.3.2 & 4.7.2 Bottom of Scale 0% Ref. 6.2 Sections 4.3.2 & 4.7.2 Upper Range Limit n/a Ref. 6.2 Sections
>~4.3.2 & 4.7.2 Accuracy ALPRM Detector -
" LPRM Detector See APRM PEA (Section 1) APRM PEA per Ref. 1 & Ref. 2
" LPRM Electronics +/- 0.943% (% local power) Ref. 7.3 Section 5.1.1.1.1 Temperature Effect included in accuracy Ref. 7.3 Section 5.1.1.1.1 Seismic Effect negligible Ref. 6.7 Section 4.1.1, Comment4 Radiation Effect negligible Ref. 7.3 Section 5.1.1.1.1 Humidity Effect included in accuracy Ref. 7.3 Section 5.1.1.1.1 Power Supply Effect See APRM PEA (Detector)
RFI/EMI Effect negligible Comment 4 Insulation Resistance Effect negligible Comment 4 Over-pressure Effect n/a Comment 5 Static Pressure Effect n/a Comment 5 file: 05Sus Rbm Numac AMcalc OutDoc_RO.doc 8
0000-0039-3825 Susq A-M-T506-RBM-Caic-2005, Rev. 0 2.1 Power Electronics (LPRM, APRM, RBM, Trip Circuit) (cont'd)
Plant Data: Value Calib Temperature Range 60 to 80 degF Normal Temperature Range 60 to 80 degF Trip Temperature range 60 to 80 degF Plant seismic value 1.95g Plant Radiation value 1.8 x 102 RAD TID Plant Humidity value 10 to 60% RH Power Supply Variation value Not provided RFI/EMI value Not provided Over-pressure value n/a Static Pressure value n/a Drift: Value ia if not 2 Reference(s)
Current Calib. Interval 7 days --lncludes 25% extra Ref. 4 Table Desired Calib. Interval 7 days Ellncludes 25% extra *! Ref. 4 Table 3.3.1.1-1 Drift Source [Vendor ECalculated ~Ref. 1, Ref. 2 Trip Setpts Power Setpts Drift Value (Trip Setpoints) + 0.3% FS / 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Ref. 6.2 Section 4.7.2.9, Comment
(% RBM power) 8 Drift Value (Power Setpoints) +/- 0.5% FS/ +/- 0.5% SP / Ref. 6.4 Section
(% power) 7700 hours0.0891 days <br />2.139 hours <br />0.0127 weeks <br />0.00293 months <br /> 8.75 days 4.3.3.3 file: 05Sus Rbm Numac AMcalc OutDocRO.doc 9
0000-0039-3825 Susq A-M-T506-RBM-Caic-2005, Rev. 0 2.1 Power Electronics (LPRM, APRM, RBM, Trip Circuit) (cont'd)
Calibration: Value / equation Si ma if not 3 1 Reference(s)
Included in APRM calibration Ref. 5.3 As Left Tolerance Trip setpoints: 0 Ref. 7.3 Sections 5.1.1.1.1 & 5.2.2.1, Power setpoints: AGAF Comment 7 As Found Tolerance Trip setpoints: = ALT Ref. 5.3, Comment 7
Power setpoints: = ALT Input Calibration Tool: n/a Comment 7 Accuracy Resolution / Readability Minor Division Upper Range Temperature Effect Input Calibration Standard: n/a Comment 7 Accuracy Resolution / Readability Minor Division Upper Range Temperature Effect Output Calibration Tool: n/a _ _ Comment 7 Accuracy Resolution / Readability Minor Division Upper Range Temperature Effect Output Calibration Standard: n/a Comment 7 Cc-Accuracy Resolution / Readability Minor Division Upper Range __ ___
Temperature Effect Application Specific Input: Value Sigma if not 2 Reference(s)
Minimum no. of LPRMs per 4 of 8 Ref. 6.6 Sections RBM Channel (Trip Setpoints) 4.3.3.3 & 4.3.4.5 Minimum no. of LPRMs per Ref. 6.1 Section APRM Channel (Power 20 of 43 4.1.5 Setpoints)
APRM Gain Adjustment Factor + 2% RTP 3 Ref. 4.1 Table (Power Setpoints) 3.3.1.1-1, Ref. 5.3 file: 05Sus Rbm Numac AMcalc OutDoc_RO.doc 10
0000-0039-3825 Susq A-M-T506-RBM-Calc-2005, Rev. 0
- 3. Summary Results:
Calculated Values Y V Y Meets Meets Analytic Limit Allowable Value Nominal Trip LER Spurious Setpoint Function (from Section 1) (% ARTS-MELLLA Setpoint Avoid- Trip Avoid-(% ARTS- ance ance
(% ARTS- RTP)' t MELLLA RTP) MELLLA RTP) 1 Criteria Criteria Low Power Setpoint 30% 28.0% 26.0% Y n/a (LPSP)
Intermediate Power 65% 63.0% 61.0% Y n/a Setpoint (IPSP)
High Power Setpoint 85% 83.0% 81.0% Y n/a (HPSP)
Meets Meets Analytic Limit Allowable Value Nominal Trip LER Spurious Setpoint Function (from Section 1) (% ARTS-MELLLA Setpoint Avoid- Trip Avoid-(%ARTS- RBM Average (%ARTS- ance ance MELLLA RBM Flux)" MELLLA RBM Criteria Criteria Average Flux) Average Flux)'
Low Power Trip 118% 115.6% 115.2% Y n/a Setpoint (LTSP)
Intermediate Power 113% 110.6% 110.2% Y n/a Trip Setpoint (ITSP)
High Power Trip 108% 105.6% 105.2% Y n/a Setpoint (HTSP) t See Comment 12.
Application Specific Setpoint Adjustments Setpoint Function Low Power Setpoint NTSP Deadband Actual Instrument Ref. 6.2 Section (LPSP)- setting 26.0% RTP 1.1% RTP Setting 4.7.9.1.2 and adjustment (from above) 24.9% RTP Section 4.8.2.4, Comment 10 Calculated AL to AV AL to AV (Minimum AL to AL to NTSPI AL to Selected Margin and AL to Required Margin)* Selected AV (Minimum Required NTSP NTSP Margins Margin)*
LPSP 1.939174 2.0 2.358089 4.0 IPSP 1.939174 2.0 2.358089 4.0 HPSP 1.939174 2.0 2.358089 4.0 LTSP 2.313792 2.4 2.339689 2.8 ITSP 2.313792 2.4 2.339689 2.8 HTSP 2.313792 2.4 2.339689 2.8
- Per Reference 1 and Reference 2.
file: 05Sus Rbm Numac AMcalc OutDoc_RO.doc 11
t 0000-0039-3825 Susq A-M-T506-RBM-Caic-2005, Rev. 0
- 4. Comments and Recommendations:
- 1. Unless specifically identified as "bias" errors in this document, all instrument uncertainty errors will be considered to be random in nature, even when the "+/-"symbol is not shown.
- 2. Some plant specific information has not been provided in the current SSES setpoint calculation(s) and is considered unnecessary because the impact of this information is included within the instrument accuracy values.
- 3. STA evaluations are not performed for rod blocks or permissives per GE setpoint methodology (Reference 1 and Reference 2), such as the RBM Rod Blocks. Therefore, the Operational Limits are not applicable.
- 4. Seismic effect, radiation effect, humidity effect, power supply effect, Radio Frequency Interference/ Electromagnetic Interference (RFI/EMI) effect, and insulation resistance effect errors are marked "negligible" or "included in accuracy" and are considered to have negligible impact on the manufacturer's accuracy terms when they are not identified separately.
- 5. Per Reference 1 and Reference 2, overpressure effects are only applicable to pressure measurement devices (e.g., differential pressure transmitters), and static pressure effects are only applicable to differential pressure measurement devices. These effects are marked "n/a" for other devices.
- 6. The variation of the LPRM ion chamber output current with +/- 1 percent change of the ion chamber voltage in the saturated range is negligibly small. (Reference 2 Section 4.5.3)
- 7. The APRM subsystem is calibrated on-line weekly (Reference 4) using the AGAF process, where the gain of the APRMs is adjusted to read the Core Thermal Power (CTP) determined by the Process Computer (P/C), within a specified As Left Tolerance. This is equivalent to a standard calibration of the APRM electronics sub-loop (consisting of the LPRM and APRM signal conditioning electronics), where the P/C is the calibration tool and standard. It is assumed that the P/C and heat balance error is already accounted for in transient analyses.
Thus, the only calibration error to consider for the APRM electronics sub-loop is the As Left Tolerance specified by the AGAF process.
- 8. The Power Electronics Drift for the RBM Trip setpoints uses the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> drift error specification.
The only drift error would be the drift in the several hours after control rod selection and nulling, and before the control rod is motion. This is estimated to be a few hours, so the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> drift interval is used.
- 9. The RBM Rod Blocks limit control rod withdrawal if localized neutron flux exceeds a pre-determined setpoint during control rod manipulations. However, the RBM system is not essential for the safety of the plant. Hence, the RBM rod withdrawal block setpoint does not perform a protective function. (Reference 5.3)
Therefore, the Seismic Effect for the RBM does not need to be considered.
- 10. As described in the Technical Specifications (Reference 4 Section 3.3.2.1), the LPSP is considered as an automatic "enable" feature when above the LPSP, and the AV and NTSP are calculated accordingly. The enable feature occurs as Reactor power increases past the LPSP.
The vendor documents for the RBM equipment (and the Reference 4 Bases) treat the LPSP as an automatic "bypass" feature (Reference 6.2) when below the LPSP. The bypass feature occurs as Reactor Power decreases below the LPSP. These two descriptions are not interchangeable/equivalent; there is a need in the equipment logic for an instrument setting "deadband". Therefore, the equipment instrument setting for the LPSP NTSP must include the 1.1% Rated Thermal power deadband (i.e., hysteresis of 1.0% and an accuracy of 0.1%). The deadband does not apply to the AV.
The equipment instrument setting is equal to the NTSP for the other RBM setpoint functions.
file: 05Sus Rbm Numac AMcalc OutDoc_RO.doc 12
0000-0039-3825 Susq A-M-T506-RBM-Caic-2005, Rev. 0
- 4. Comments and Recommendations (cont'd):
- 11. For the RBM Downscale Trip Setpoint (DTSP), no credit is taken for it in the RWE analyses.
Choice of this setpoint is an operational issue to be decided by the plant. There is no AL for this setpoint. A value of 94 is recommended, but it can be lowered if operational problems are encountered. (Reference 7.1)
- 12. Per Reference 1 and Reference 2, the difference between the AL and AV and the difference between the AL and NTSP are independent of the number for the AL. This applies for all of the Power and Trip setpoint functions.
- 13. Transfer functions used in this calculation:
RBM Power Electronics: Output is proportional to the average of the inputs, and multiplied by a gain to increase the output to match the APRM reference.
APRM Power Electronics: Output is proportional to the average of the inputs.
file: 05Sus Rbm Numac AMcalc OutDoc_RO.doc 13
0000-0039-3825 Susq A-M-T506-RBM-Caic-2005, Rev. 0
- 5.
References:
- 1. NEDC-32889P, Rev. 3, General Electric Methodology for Instrumentation Technical Specification and Setpoint Analysis, November 2002
- 2. NEDC-31336P-A, General Electric Instrument Setpoint Methodology, September 1996
- 3. Current applicable Susquehanna setpoint calculations:
3.1. CALC EC-078-0509, Rev. 4, Unit 1 RBM A and B Flow Biased Setpoint Change, July 21, 1999 3.2. CALC EC-078-0503, Rev. 4, Unit 2 RBM A and B Flow Biased Setpoint Change, July 22, 1999
- 4. Susquehanna Technical Specifications and Bases, as revised through Amendment 219 for Unit 1 and Amendment 190 for Unit 2.
- 5. Current applicable Susquehanna procedures/documents:
5.1. Procedure SI-178-325A, Rev. 2, 24 Month Channel Calibration of Rod Block Monitor (RBM) Channel A, August 7, 2001 5.2. Procedure SI-178-325B, Rev. 2, 24 Month Channel Calibration of Rod Block Monitor (RBM) Channel A, August 7, 2001 5.3. PPL Susquehanna, LLC, Extended Power Uprate Project, ARTS/MELLLA: Completed Design Input Request T0506, EPUL-0188, (Rev. 2), transmittal letter dated July 28, 2005, from Michael S. Gorski (PPL) to Larry W. King (GE)
- 6. Vendor Specifications:
6.1. GE 24A5221WJ, Rev. 0, PRNM Requirements Specification, Data Sheet, Susquehanna 1 &2 6.2. GE 24A5221, Rev. 11, NUMAC Power Range Neutron Monitor (PRNM), Requirements Specification, March 23, 2005 6.3. (not used) 6.4. GE 25A5916, Rev. 5, NUMAC Average Power Range Monitor (APRM), Performance Specification, February 28, 2005 6.5. (not used) 6.6. GE 25A5917, Rev. 3, NUMAC Rod Block Monitor (RBM), Performance Specification, November 14, 2003 6.7. GE 23A5082, Rev. 1, NUMAC Requirements Specification, Design Spec, August 9, 1995
- 7. GE Letters / Reports:
7.1. GE Project Task Report, PPL Susquehanna LLC, Susquehanna Steam Electric Station Units 1&2, ARTS/MELLLA, Task T0500, GE-NE-0000-0026-6330-RO, Rev. 0, Class III, March 2005 file: 05Sus Rbm Numac AMcalc OutDocRO.doc 14
0000-0039-3825 Susq A-M-T506-RBM-Caic-2005, Rev. 0
- 5. References (cont'd):
7.2. Bases for PMA & PEA Values for NMS setpoints, BasesNMSPMAPEA2.doc, DRF 051-00217, Y. Dayal, 3/15/99 [internal GE document; not releasable]
7.3. GE CD-4608 Volume XI DCD; Rev. B, Design Calculation for NUMAC Power Range Neutron Monitoring System (PRNM), DRF C51-00136 (4.42), October 9, 1998 [not releasable]
7.4. GE document, "Closure of CAR 6912 for RBM and APRM Setpoint Calculations, file CAR6912Closure Basis.doc, DRF A74-00011-00, 3/19/2002 [internal GE document; not releasable]
file: 05Sus Rbm Numac AMcalc OutDoc_RO.doc 15