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| {{#Wiki_filter:Brad Berryman Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 Brad.Berryman | | {{#Wiki_filter:Brad Berryman Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 TALEN~ |
| @TalenEnergy | | Brad.Berryman @TalenEnergy.com ENERGY U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 10 CFR 50.46 SUSQUEHANNA STEAM ELECTRIC STATION (SSES) 10 CFR 50.46 -ANNUAL REPORT Docket Nos. 50-387 PLA-7606 and 50-388 Reference 1: PLA-7475, J A. Franke (Susquehanna Nuclear, LLC) to Document Control Desk (USNRC), "Susquehanna Steam Electric Station, 10 CFR 50.46 -Annual Report," |
| .com U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION (SSES) 10 CFR 50.46 -ANNUAL REPORT PLA-7606 ENERGY 10 CFR 50.46 Docket Nos. 50-387 and 50-388 Reference 1: PLA-7475, J A. Franke (Susquehanna Nuclear, LLC) to Document Control Desk (USNRC), "Susquehanna Steam Electric Station, 10 CFR 50.46 -Annual Report," dated June 7, 2016. Reference 2: AREVA Record FS1-0031872 , Revision 1.0 , "10 CFR 50.46 PCT Error Reporting for the Susquehanna Units, "dated April 26, 2017. Pursuant to the reporting requirements of 10 CFR 50.46(a)(3)(ii) | | dated June 7, 2016. |
| Susquehanna Steam Electric Station (SSES) is submitting the Emergency Core Cooling System (ECCS) evaluation model annual repmt for SSES Units 1 and 2. Attachment 1 to this letter summarizes the nature of and estimated effect of any changes or errors in the ECCS models for SSES Units 1 and 2 for the repmting period of April28, 2016 through April 26, 2017. There are no new regulatory commitments contained in this submittal. | | Reference 2: AREVA Record FS1-0031872, Revision 1.0, "10 CFR 50.46 PCT Error Reporting for the Susquehanna Units, "dated April 26, 2017. |
| If you have any questions regarding this letter, please contact Mr. Jason R. Jennings, Nuclear Regulatory Affairs, at (570) 542-3155. | | Pursuant to the reporting requirements of 10 CFR 50.46(a)(3)(ii) Susquehanna Steam Electric Station (SSES) is submitting the Emergency Core Cooling System (ECCS) evaluation model annual repmt for SSES Units 1 and 2. to this letter summarizes the nature of and estimated effect of any changes or errors in the ECCS models for SSES Units 1 and 2 for the repmting period of April28, 2016 through April 26, 2017. |
| Attachment 1-SSES Units 1 & 2-10 CFR 50.46 ECCS Evaluation Model Annual Report Copy: NRC Region I Ms. T. E. Hood, NRC Project Manager Ms. L. Micewski, NRC Sr. Resident Inspector Mr. M. Shields, PA DEP/BRP Attachment 1 to PLA-7606 SSES Units 1 & 2 -10 CFR 50.46 ECCS Evaluation Model Annual Report BACKGROUND Attachment 1 to PLA-7606 Page 1 of 1 In accordance with 10 CFR 50.46(a)(3)(ii), this annual repmt summarizes the nature of and estimated effect of any changes or enors in the Emergency Core Cooling System (ECCS) model for the period April28, 2016 through April26, 2017 for Susquehanna Steam Electric Station (SSES) Units 1 and 2. DISCUSSION The ECCS performance evaluation method applicable to both SSES Unit 1 and Unit 2 is the AREV A NP EXEM BWR-2000 LOCA Methodology.
| | There are no new regulatory commitments contained in this submittal. |
| For the repmting period of April28 , 2016 to April26 , 2017, there have been two repmtable changes for 10 CFR 50.46 as stated in Reference 2: 1) Previous analyses have been perfmmed on a DEC ALPHA computer platfmm. New analyses have been qualified on a LINUX based computer platfmm. The impact of the change in platfmms was estimated to have an insignificant impact on Peak Clad Temperature (PCT). Therefore, the 10 CFR 50.46 repmtable impact is estimated as 0°F. 2) Previous versions of the heatup code HUXY allowed a limited number of different rod types to be modeled. The method grouped rods that had similar local peaking histories. HUXY has been revised to no longer have a limited number of rod groupings. | | If you have any questions regarding this letter, please contact Mr. Jason R. Jennings, Manager-Nuclear Regulatory Affairs, at (570) 542-3155. - SSES Units 1 & 2- 10 CFR 50.46 ECCS Evaluation Model Annual Report Copy: NRC Region I Ms. T. E. Hood, NRC Project Manager Ms. L. Micewski, NRC Sr. Resident Inspector Mr. M. Shields, PA DEP/BRP |
| This change in rod grouping resulted in a 1 °F decrease in PCT. Therefore , the 10 CFR 50.46 repmtable impact is estimated as -1 °F. The total change listed in the last column of Table 1 does not meet the significance threshold for change (50°F) identified in 10 CFR 50.46(a)(3)(i) for which a 30-day report is required. | | |
| IMPACT Table 1 Non-Zero Changes and/or Errors in Calculated ECCS Perfmmance Evaluation Model: AREV A NP EXEM BWR-2000 Methodology Estimated Description of Change/Error t.PCT (°F) HUXY capability enhancement to model each fuel rod individually | | Attachment 1 to PLA- 7606 SSES Units 1 & 2 - |
| -1 I Total -1 CONCLUSION Absolute Value of t.PCT (°F) 1 1 As documented in Table 1 , the SSES Unit 1 and Unit 2 Loss of Coolant Accident analysis Peak Clad Temperature (PCT) remains in compliance with 10 CFR 50.46(b)(l), which requires that the PCT shall not exceed 2200°F.}} | | 10 CFR 50.46 ECCS Evaluation Model Annual Report |
| | |
| | Attachment 1 to PLA-7606 Page 1 of 1 BACKGROUND In accordance with 10 CFR 50.46(a)(3)(ii), this annual repmt summarizes the nature of and estimated effect of any changes or enors in the Emergency Core Cooling System (ECCS) model for the period April28, 2016 through April26, 2017 for Susquehanna Steam Electric Station (SSES) Units 1 and 2. |
| | DISCUSSION The ECCS performance evaluation method applicable to both SSES Unit 1 and Unit 2 is the AREVA NP EXEM BWR-2000 LOCA Methodology. |
| | For the repmting period of April28, 2016 to April26, 2017, there have been two repmtable changes for 10 CFR 50.46 as stated in Reference 2: |
| | : 1) Previous analyses have been perfmmed on a DEC ALPHA computer platfmm. New analyses have been qualified on a LINUX based computer platfmm. The impact of the change in platfmms was estimated to have an insignificant impact on Peak Clad Temperature (PCT). Therefore, the 10 CFR 50.46 repmtable impact is estimated as 0°F. |
| | : 2) Previous versions of the heatup code HUXY allowed a limited number of different rod types to be modeled. The method grouped rods that had similar local peaking histories. |
| | HUXY has been revised to no longer have a limited number of rod groupings. This change in rod grouping resulted in a 1°F decrease in PCT. Therefore, the 10 CFR 50.46 repmtable impact is estimated as -1 °F. |
| | The total change listed in the last column of Table 1 does not meet the significance threshold for change (50°F) identified in 10 CFR 50.46(a)(3)(i) for which a 30-day report is required. |
| | IMPACT Table 1 Non-Zero Changes and/or Errors in Calculated ECCS Perfmmance Evaluation Model: AREV A NP EXEM BWR-2000 Methodology Estimated Absolute Value Description of Change/Error t.PCT (°F) of t.PCT (°F) |
| | HUXY capability enhancement to model each fuel rod individually -1 1 I Total -1 1 CONCLUSION As documented in Table 1, the SSES Unit 1 and Unit 2 Loss of Coolant Accident analysis Peak Clad Temperature (PCT) remains in compliance with 10 CFR 50.46(b)(l), which requires that the PCT shall not exceed 2200°F.}} |
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Category:Annual Operating Report
MONTHYEARML23163A1012023-06-12012 June 2023 10 CFR 50.46 Annual Report (Pla 8065) PLA-8047, 2022 Annual Environmental Operating Report (Nonradiological), PLA-80472023-04-19019 April 2023 2022 Annual Environmental Operating Report (Nonradiological), PLA-8047 PLA-8012, 10 CFR 50.46 Annual Report2022-06-10010 June 2022 10 CFR 50.46 Annual Report PLA-7947, 10 CFR 50.46 Annual Report (PLA-7947)2021-06-10010 June 2021 10 CFR 50.46 Annual Report (PLA-7947) PLA-7870, 10 CFR 50.46 Annual Report (PLA-7870)2020-06-10010 June 2020 10 CFR 50.46 Annual Report (PLA-7870) PLA-7770, CFR 50.46 Annual Report2019-06-10010 June 2019 CFR 50.46 Annual Report PLA-7752, Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments2018-10-18018 October 2018 Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments PLA-7713, Submittal of Emergency Core Cooling System Evaluation Model Annual Report2018-06-14014 June 2018 Submittal of Emergency Core Cooling System Evaluation Model Annual Report PLA-7606, Submittal of 10 CFR 50.46 - Annual Report2017-06-0707 June 2017 Submittal of 10 CFR 50.46 - Annual Report PLA-7475, Submittal of 10 CFR 50.46 - Annual Report2016-06-0707 June 2016 Submittal of 10 CFR 50.46 - Annual Report ML16141A1162016-05-10010 May 2016 Annual Radiological Environmental Operating Report PLA-7464 ML14134A2482014-05-13013 May 2014 Annual Radiological Environmental Operating Report, Attachment 1, Cover - Page 16 PLA-7000, Annual Report on Radiation Exposure Per 10 CFR 20.2206, PLA-70002013-04-28028 April 2013 Annual Report on Radiation Exposure Per 10 CFR 20.2206, PLA-7000 PLA-7001, Annual Environmental Operating Report (Non-Radiological) PLA-70012013-04-24024 April 2013 Annual Environmental Operating Report (Non-Radiological) PLA-7001 ML13220A0442013-04-0202 April 2013 Annual Report 2012 for PPL Susquehanna, LLC PLA-6853, 2011 Annual Radiological Environmental Operating Report2012-05-0808 May 2012 2011 Annual Radiological Environmental Operating Report PLA-6838, Annual Environmental Operating Report (Non-Radiological)2012-04-24024 April 2012 Annual Environmental Operating Report (Non-Radiological) PLA-6729, 10 CFR 50.46 - Annual Report2011-06-22022 June 2011 10 CFR 50.46 - Annual Report PLA-6718, Annual Environmental Operating Report (Non-Radiological) PLA-67182011-04-27027 April 2011 Annual Environmental Operating Report (Non-Radiological) PLA-6718 ML1011703042010-04-30030 April 2010 Radioactive Effluent Release Report for 2009, Cover Through Section 8 PLA-6601, Radioactive Effluent Release Report for 2009, Appendix a Through End2010-04-30030 April 2010 Radioactive Effluent Release Report for 2009, Appendix a Through End PLA-6604, Submittal of Annual Environmental Operating Report2010-04-26026 April 2010 Submittal of Annual Environmental Operating Report PLA-6522, Enclosure 2 - Allegheny Electric Cooperative, Inc., 2008 Annual Report2009-06-29029 June 2009 Enclosure 2 - Allegheny Electric Cooperative, Inc., 2008 Annual Report PLA-6508, Annual Radiological Environmental Operating Report for Calendar Year 20082009-05-12012 May 2009 Annual Radiological Environmental Operating Report for Calendar Year 2008 PLA-6182, Annual Radiological Environmental Operating Report for Calendar Year 2006 in Accordance with Technical Specification 5.6.22007-04-30030 April 2007 Annual Radiological Environmental Operating Report for Calendar Year 2006 in Accordance with Technical Specification 5.6.2 PLA-6185, 2006 Annual Environmental Operating Report (Nonradiological.)2007-04-20020 April 2007 2006 Annual Environmental Operating Report (Nonradiological.) PLA-5929, 10 CFR 50.46 - 30-Day and Annual Reports PLA-59292005-08-0202 August 2005 10 CFR 50.46 - 30-Day and Annual Reports PLA-5929 PLA-5890, 2004 Annual Environmental Operating Report (Non - Radiological)2005-04-28028 April 2005 2004 Annual Environmental Operating Report (Non - Radiological) PLA-5747, Annual Environmental Operating Report (Non-Radiological) PLA-57472004-04-27027 April 2004 Annual Environmental Operating Report (Non-Radiological) PLA-5747 PLA-5687, CFR 50.46 - Annual Report PLA-56872003-10-31031 October 2003 CFR 50.46 - Annual Report PLA-5687 PLA-5623, Annual Radiological Environmental Operating Report, Ambient Radiation Monitoring, Pages 18 - 522003-04-30030 April 2003 Annual Radiological Environmental Operating Report, Ambient Radiation Monitoring, Pages 18 - 52 ML19184A4041978-05-23023 May 1978 Environmental Monitoring Report, Er 100450 2023-06-12
[Table view] 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] |
Text
Brad Berryman Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 TALEN~
Brad.Berryman @TalenEnergy.com ENERGY U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 10 CFR 50.46 SUSQUEHANNA STEAM ELECTRIC STATION (SSES) 10 CFR 50.46 -ANNUAL REPORT Docket Nos. 50-387 PLA-7606 and 50-388 Reference 1: PLA-7475, J A. Franke (Susquehanna Nuclear, LLC) to Document Control Desk (USNRC), "Susquehanna Steam Electric Station, 10 CFR 50.46 -Annual Report,"
dated June 7, 2016.
Reference 2: AREVA Record FS1-0031872, Revision 1.0, "10 CFR 50.46 PCT Error Reporting for the Susquehanna Units, "dated April 26, 2017.
Pursuant to the reporting requirements of 10 CFR 50.46(a)(3)(ii) Susquehanna Steam Electric Station (SSES) is submitting the Emergency Core Cooling System (ECCS) evaluation model annual repmt for SSES Units 1 and 2. to this letter summarizes the nature of and estimated effect of any changes or errors in the ECCS models for SSES Units 1 and 2 for the repmting period of April28, 2016 through April 26, 2017.
There are no new regulatory commitments contained in this submittal.
If you have any questions regarding this letter, please contact Mr. Jason R. Jennings, Manager-Nuclear Regulatory Affairs, at (570) 542-3155. - SSES Units 1 & 2- 10 CFR 50.46 ECCS Evaluation Model Annual Report Copy: NRC Region I Ms. T. E. Hood, NRC Project Manager Ms. L. Micewski, NRC Sr. Resident Inspector Mr. M. Shields, PA DEP/BRP
Attachment 1 to PLA- 7606 SSES Units 1 & 2 -
10 CFR 50.46 ECCS Evaluation Model Annual Report
Attachment 1 to PLA-7606 Page 1 of 1 BACKGROUND In accordance with 10 CFR 50.46(a)(3)(ii), this annual repmt summarizes the nature of and estimated effect of any changes or enors in the Emergency Core Cooling System (ECCS) model for the period April28, 2016 through April26, 2017 for Susquehanna Steam Electric Station (SSES) Units 1 and 2.
DISCUSSION The ECCS performance evaluation method applicable to both SSES Unit 1 and Unit 2 is the AREVA NP EXEM BWR-2000 LOCA Methodology.
For the repmting period of April28, 2016 to April26, 2017, there have been two repmtable changes for 10 CFR 50.46 as stated in Reference 2:
- 1) Previous analyses have been perfmmed on a DEC ALPHA computer platfmm. New analyses have been qualified on a LINUX based computer platfmm. The impact of the change in platfmms was estimated to have an insignificant impact on Peak Clad Temperature (PCT). Therefore, the 10 CFR 50.46 repmtable impact is estimated as 0°F.
- 2) Previous versions of the heatup code HUXY allowed a limited number of different rod types to be modeled. The method grouped rods that had similar local peaking histories.
HUXY has been revised to no longer have a limited number of rod groupings. This change in rod grouping resulted in a 1°F decrease in PCT. Therefore, the 10 CFR 50.46 repmtable impact is estimated as -1 °F.
The total change listed in the last column of Table 1 does not meet the significance threshold for change (50°F) identified in 10 CFR 50.46(a)(3)(i) for which a 30-day report is required.
IMPACT Table 1 Non-Zero Changes and/or Errors in Calculated ECCS Perfmmance Evaluation Model: AREV A NP EXEM BWR-2000 Methodology Estimated Absolute Value Description of Change/Error t.PCT (°F) of t.PCT (°F)
HUXY capability enhancement to model each fuel rod individually -1 1 I Total -1 1 CONCLUSION As documented in Table 1, the SSES Unit 1 and Unit 2 Loss of Coolant Accident analysis Peak Clad Temperature (PCT) remains in compliance with 10 CFR 50.46(b)(l), which requires that the PCT shall not exceed 2200°F.