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| | issue date = 06/18/2015 | | | issue date = 06/18/2015 |
| | title = 10 CFR 50.46 - Annual Report | | | title = 10 CFR 50.46 - Annual Report |
| | author name = Franke J A | | | author name = Franke J |
| | author affiliation = Susquehanna Nuclear, LLC, Talen Energy | | | author affiliation = Susquehanna Nuclear, LLC, Talen Energy |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:Jon A. Franke Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 Jon.Franke@TalenEnergy.com U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 E N ERG Y SUSQUEHANNA STEAM ELECTRIC STATION (SSES) 10 CFR 50.46-ANNUAL REPORT PLA-7339 Docket Nos. 50-387 and 50-388 | | {{#Wiki_filter:Jon A. Franke Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 TALEN ~ |
| | Jon.Franke@TalenEnergy.com ENERGY U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION (SSES) 10 CFR 50.46- ANNUAL REPORT Docket Nos. 50-387 PLA-7339 and 50-388 |
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| ==Reference:== | | ==Reference:== |
| : 1. PLA-7175, J A. Franke (PPL) to Document Control Desk (USNRC), "Susquehanna Steam Electric Station, 10 CFR 50.46-Annual Report, " dated June 20, 2014. This report is being sent in accordance with 10 CFR 50.46(a)(3)(ii). | | : 1. PLA-7175, J A. Franke (PPL) to Document Control Desk (USNRC), |
| | "Susquehanna Steam Electric Station, 10 CFR 50.46- Annual Report, " |
| | dated June 20, 2014. |
| | This report is being sent in accordance with 10 CFR 50.46(a)(3)(ii). |
| 10 CFR 50.46(a)(3)(ii) requires (in part) annual reporting of changes to or errors in evaluation models used for calculating Emergency Core Cooling System (ECCS) performance, and an estimate of their effect on the limiting ECCS analysis. | | 10 CFR 50.46(a)(3)(ii) requires (in part) annual reporting of changes to or errors in evaluation models used for calculating Emergency Core Cooling System (ECCS) performance, and an estimate of their effect on the limiting ECCS analysis. |
| Additionally, a proposed schedule is required for re-analysis or identification of other actions necessary to show compliance with 10 CFR 50.46 requirements. | | Additionally, a proposed schedule is required for re-analysis or identification of other actions necessary to show compliance with 10 CFR 50.46 requirements. |
| The ECCS performance evaluation method applicable to both SSES Unit 1 and Unit 2 is the AREV A NP EXEM BWR--2000 LOCA Methodology. | | The ECCS performance evaluation method applicable to both SSES Unit 1 and Unit 2 is the AREVA NP EXEM BWR--2000 LOCA Methodology. |
| Since May 6, 2014 (as reported by Reference | | Since May 6, 2014 (as reported by Reference 1) until May 6, 2015, there have been no non-zero Peak Cladding Temperature (PCT) changes reported to PPL Susquehanna, LLC for Units 1 and 2. Thus, the current licensing basis PCT remains valid. |
| : 1) until May 6, 2015, there have been no non-zero Peak Cladding Temperature (PCT) changes reported to PPL Susquehanna, LLC for Units 1 and 2. Thus, the current licensing basis PCT remains valid. There is one reportable issue for 10 CFR 50.46 since the last report (Reference 1). In the EXEM BWR-2000 eva luation model, End ofBlowdown is defined as the time when rated flow from the low pressure core spray system (LPCS) is reached. For some plants, including Susquehanna, this time was implemented as the time the pressure reached the pressure corresponding to rated LPCS flow. A review of the limiting break conditions show there is no difference between the times determined by the two methods of implementation.
| | There is one reportable issue for 10 CFR 50.46 since the last report (Reference 1). In the EXEM BWR-2000 evaluation model, End ofBlowdown is defined as the time when rated flow from the low pressure core spray system (LPCS) is reached. For some plants, including Susquehanna, this time was implemented as the time the pressure reached the pressure corresponding to rated LPCS flow. A review of the limiting break conditions show there is no difference between the times determined by the two methods of implementation. Therefore, the 10 CFR 50.46 reportable impact on the Susquehanna analysis of record PCT is 0°F. There have been no other modeling or error corrections to the ECCS evaluation method since the last report (Reference 1). |
| Therefore, the 10 CFR 50.46 reportable impact on the Susquehanna analysis of record PCT is 0°F. There have been no other modeling or error corrections to the ECCS evaluation method since the last report (Reference 1 ). This letter meets the annual reporting requirements. Document Control Desk PLA-7339 Susquehanna Nuclear, LLC will continue to track future changes to the evaluation models used in the applicable loss of coolant accident (LOCA) analysis methods to ensure that the PCT values remain below the 10 CFR 50.46 limit, and to ensure that the 10 CFR 50.46 reporting requirements are met. There are no new regulatory commitments contained in this submittal. | | This letter meets the annual reporting requirements. |
| If you have any questions, please contact Mr. JefferyN. | | |
| Grisewood, Manager-Nuclear Regulatory Affairs at (570) 542-1330 . . Franke Copy: NRC Region I Mr. J. Greives, NRC Sr. Resident Inspector Mr. J. Whited, NRC Project Manager Mr. B. Fuller, PA DEP/BRP}} | | Document Control Desk PLA-7339 Susquehanna Nuclear, LLC will continue to track future changes to the evaluation models used in the applicable loss of coolant accident (LOCA) analysis methods to ensure that the PCT values remain below the 10 CFR 50.46 limit, and to ensure that the 10 CFR 50.46 reporting requirements are met. |
| | There are no new regulatory commitments contained in this submittal. |
| | If you have any questions, please contact Mr. JefferyN. Grisewood, Manager- Nuclear Regulatory Affairs at (570) 542-1330 . |
| | . Franke Copy: NRC Region I Mr. J. Greives, NRC Sr. Resident Inspector Mr. J. Whited, NRC Project Manager Mr. B. Fuller, PA DEP/BRP}} |
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Category:Annual Report
MONTHYEARPLA-7926, 2020 Annual Environmental Operating Report (Nonradiological) PLA-79262021-04-0909 April 2021 2020 Annual Environmental Operating Report (Nonradiological) PLA-7926 PLA-7863, Annual Financial Report Required by 10 CFR 50.71 (PLA-7863)2020-04-29029 April 2020 Annual Financial Report Required by 10 CFR 50.71 (PLA-7863) PLA-7775, Annual Financial Information Required by 10 CFR 50.71 (PLA-7775)2019-04-30030 April 2019 Annual Financial Information Required by 10 CFR 50.71 (PLA-7775) PLA-7698, Submittal of Annual Financial Information Required by 10 CFR 50.712018-06-0404 June 2018 Submittal of Annual Financial Information Required by 10 CFR 50.71 ML17272A7332017-10-0505 October 2017 Report for the Audit of Licensee Responses to Interim Staff Evaluation Open Items Related to NRC Order Ea-13-109 to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operations ML15237A2592015-07-16016 July 2015 2014 Annual Financial Report -PLA-7350 PLA-7339, 10 CFR 50.46 - Annual Report2015-06-18018 June 2015 10 CFR 50.46 - Annual Report PLA-7350, PPL Corporation Annual Report 20142014-12-31031 December 2014 PPL Corporation Annual Report 2014 PLA-7203, 2013 Annual Financial Report, PLA-72032014-07-23023 July 2014 2013 Annual Financial Report, PLA-7203 PLA-7029, (SSES) - 10 CFR 50.46 - Annual Report (PLA-7029)2013-06-20020 June 2013 (SSES) - 10 CFR 50.46 - Annual Report (PLA-7029) PLA-7048, Allegheny Electric Cooperative, Inc. - 2012 Annual Report Table of Contents2012-12-31031 December 2012 Allegheny Electric Cooperative, Inc. - 2012 Annual Report Table of Contents ML12221A3572012-07-27027 July 2012 Allegheny Electric Cooperative Annual Report 2011 - Note 5, Nuclear Decommissioning Trust Through End ML12221A3552012-07-27027 July 2012 PPL Corporation Annual Report 2011 ML12221A3562011-12-31031 December 2011 Allegheny Electric Cooperative Annual Report 2011 - Cover Through Note 4, Investments PLA-6742, Reaching Milestones, 2010 Annual Report2011-07-29029 July 2011 Reaching Milestones, 2010 Annual Report ML11220A3652011-07-29029 July 2011 PPL Corporation Annual Report 2010 PLA-6624, Annual Financial Report2010-07-25025 July 2010 Annual Financial Report ML0919600762009-06-29029 June 2009 Enclosure 1 - PPL Corporation 2008 Annual Report PLA-6402, Annual Financial Report2008-07-22022 July 2008 Annual Financial Report ML0816504352008-07-21021 July 2008 Allegation Program Annual Trends Report Cy 2007 PLA-6246, 2006 Annual Financial Report2007-07-24024 July 2007 2006 Annual Financial Report PLA-6247, CFR 50.46 - Annual Report2007-07-24024 July 2007 CFR 50.46 - Annual Report ML0712901562006-12-31031 December 2006 Appendix a, Radioactive Effluent Release Report, Offsite Dose Calculation Manual/Technical Requirement Manual, 2006 Annual Report PLA-6098, 10 CFR 50.46 - Annual Report, PLA-60982006-07-25025 July 2006 10 CFR 50.46 - Annual Report, PLA-6098 PLA-6079, Transmittal of Susquehanna Annual Financial Reports for 20052006-07-10010 July 2006 Transmittal of Susquehanna Annual Financial Reports for 2005 PLA-6050, Annual Environmental Operating Report (Non-Radiological) PLA-60502006-04-27027 April 2006 Annual Environmental Operating Report (Non-Radiological) PLA-6050 PLA-6041, Appendix a, SSES Odcm/Trm Radioactive Effluent Release Report 2005 Annual Report2005-12-31031 December 2005 Appendix a, SSES Odcm/Trm Radioactive Effluent Release Report 2005 Annual Report ML0512205432004-12-31031 December 2004 Radioactive Effluent Release Report. ML0518903572004-12-31031 December 2004 PPL Corp 2004 Annual Report ML0518903592004-12-31031 December 2004 Continental Cooperative Services 2004 Annual Report ML0512206062004-12-31031 December 2004 Appendix a, Radioactive Effluent Release Report. PLA-5773, Annual Financial Report2004-06-30030 June 2004 Annual Financial Report PLA-5641, Annual Financial Report2003-07-0101 July 2003 Annual Financial Report PLA-5618, Radioactive Effluent Release Report & Offsite Dose Calculation Manual PLA-5618, Bases B 3.11 - B 3.11.4.32003-04-30030 April 2003 Radioactive Effluent Release Report & Offsite Dose Calculation Manual PLA-5618, Bases B 3.11 - B 3.11.4.3 PLA-5491, Annual Financial Report2002-07-16016 July 2002 Annual Financial Report ML18023B2931978-03-0101 March 1978 Annual Report 1977 Pennsylvania Power & Light Company 2021-04-09
[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
Jon A. Franke Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 TALEN ~
Jon.Franke@TalenEnergy.com ENERGY U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION (SSES) 10 CFR 50.46- ANNUAL REPORT Docket Nos. 50-387 PLA-7339 and 50-388
Reference:
- 1. PLA-7175, J A. Franke (PPL) to Document Control Desk (USNRC),
"Susquehanna Steam Electric Station, 10 CFR 50.46- Annual Report, "
dated June 20, 2014.
This report is being sent in accordance with 10 CFR 50.46(a)(3)(ii).
10 CFR 50.46(a)(3)(ii) requires (in part) annual reporting of changes to or errors in evaluation models used for calculating Emergency Core Cooling System (ECCS) performance, and an estimate of their effect on the limiting ECCS analysis.
Additionally, a proposed schedule is required for re-analysis or identification of other actions necessary to show compliance with 10 CFR 50.46 requirements.
The ECCS performance evaluation method applicable to both SSES Unit 1 and Unit 2 is the AREVA NP EXEM BWR--2000 LOCA Methodology.
Since May 6, 2014 (as reported by Reference 1) until May 6, 2015, there have been no non-zero Peak Cladding Temperature (PCT) changes reported to PPL Susquehanna, LLC for Units 1 and 2. Thus, the current licensing basis PCT remains valid.
There is one reportable issue for 10 CFR 50.46 since the last report (Reference 1). In the EXEM BWR-2000 evaluation model, End ofBlowdown is defined as the time when rated flow from the low pressure core spray system (LPCS) is reached. For some plants, including Susquehanna, this time was implemented as the time the pressure reached the pressure corresponding to rated LPCS flow. A review of the limiting break conditions show there is no difference between the times determined by the two methods of implementation. Therefore, the 10 CFR 50.46 reportable impact on the Susquehanna analysis of record PCT is 0°F. There have been no other modeling or error corrections to the ECCS evaluation method since the last report (Reference 1).
This letter meets the annual reporting requirements.
Document Control Desk PLA-7339 Susquehanna Nuclear, LLC will continue to track future changes to the evaluation models used in the applicable loss of coolant accident (LOCA) analysis methods to ensure that the PCT values remain below the 10 CFR 50.46 limit, and to ensure that the 10 CFR 50.46 reporting requirements are met.
There are no new regulatory commitments contained in this submittal.
If you have any questions, please contact Mr. JefferyN. Grisewood, Manager- Nuclear Regulatory Affairs at (570) 542-1330 .
. Franke Copy: NRC Region I Mr. J. Greives, NRC Sr. Resident Inspector Mr. J. Whited, NRC Project Manager Mr. B. Fuller, PA DEP/BRP