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Category:Annual Operating Report
MONTHYEARML24120A2552024-04-29029 April 2024 Annual Radiological Environmental Operating Report ML24065A0042024-03-28028 March 2024 Submittal of 2023 Aircraft Movement Data Annual Report ML23059A4392023-02-28028 February 2023 2022 Aircraft Movement Data Annual Report ML22083A1062022-03-24024 March 2022 2020-2021 Biennial 10 CFR 50.59 and 10 CFR 72.48 Summary Reports and 2021 Commitment Revision Summary Report ML22055A4912022-02-28028 February 2022 Us Dept. of Energy, STI-NLF-RPT-218 Revision 0, 2021 Annual Radiological Environmental Monitoring Program (REMP) Report for the Three Mile Island Unit-2 (TMI-2) Independent Spent Fuel Storage Installation (ISFSI) TMI-21-019, Submittal of 2020 Annual Radiological Environmental Operating Report2021-04-27027 April 2021 Submittal of 2020 Annual Radiological Environmental Operating Report ML20127H6722020-05-0606 May 2020 CFR 50.46 Annual Report TMI-20-015, 2018-2019 Biennial 10 CFR 50.59 Summary Report and 2019 Commitment Revision Summary Report2020-04-30030 April 2020 2018-2019 Biennial 10 CFR 50.59 Summary Report and 2019 Commitment Revision Summary Report ML20114E0142020-04-23023 April 2020 (TMl-2) - Biennial 10 CFR 50.59 and Pdms SAR Report ML20062A1822020-02-27027 February 2020 Submittal of 2019 Annual Report ML19126A1632019-05-0606 May 2019 Submittal of 10 CFR 50.46 Annual Report ML18124A0082018-05-0404 May 2018 Submittal of 10 CFR 50.46 Annual Report TMI-18-024, Biennial 10 CFR 50.59 and Pdms SAR Report2018-04-24024 April 2018 Biennial 10 CFR 50.59 and Pdms SAR Report ML17125A1522017-05-0505 May 2017 10 CFR 50.46 Annual Report ML17052A3952017-02-17017 February 2017 Submittal of 2016 Annual Report ML16130A0652016-05-0606 May 2016 Submittal of 10CFR 50.46 Annual Report ML16125A1932016-04-30030 April 2016 Annual Radiological Environmental Operating Report for the Year 2015 ML16123A1822016-04-29029 April 2016 Transmittal of Biennial 10 CFR 50.59 and Pdms SAR Report ML16110A1652016-04-15015 April 2016 Transmittal of Biennial 10 CFR 50.59 and Commitment Revision Reports for 2014 and 2015 TMI-16-012, Transmittal of 2015 Annual Report2016-02-10010 February 2016 Transmittal of 2015 Annual Report RS-15-104, Annual Property Insurance Status Report2015-04-0101 April 2015 Annual Property Insurance Status Report TMI-14-066, 10 CFR 50.46 Annual Report2014-05-0909 May 2014 10 CFR 50.46 Annual Report TMI-14-049, Combined 2013 Annual Radioactive Effluent Release Report2014-04-25025 April 2014 Combined 2013 Annual Radioactive Effluent Release Report TMI-13-073, CFR 50.46 Annual Report2013-05-10010 May 2013 CFR 50.46 Annual Report ML13121A0782013-04-30030 April 2013 Annual Radiological Environmental Operating Report, 1 January Through 31 December 2012 TMI-13-065, Annual Radiological Groundwater Protection Program Report (Argppr), 1 January Through 31 December 20122013-04-30030 April 2013 Annual Radiological Groundwater Protection Program Report (Argppr), 1 January Through 31 December 2012 TMI-12-079, 10 CFR 50.46 Annual Report2012-05-11011 May 2012 10 CFR 50.46 Annual Report TMI-12-072, (TMI-2) - Biennial 10 CFR 50.59 and Pdms SAR Report2012-04-30030 April 2012 (TMI-2) - Biennial 10 CFR 50.59 and Pdms SAR Report TMI-12-047, (TMI-1), Biennial 10 CFR 50.59 and Commitment Revision Reports for 2010 and 20112012-04-16016 April 2012 (TMI-1), Biennial 10 CFR 50.59 and Commitment Revision Reports for 2010 and 2011 TMI-12-013, Annual Report2012-02-29029 February 2012 Annual Report TMI-11-086, Submittal of 10 CFR 50.46 Annual Report2011-05-13013 May 2011 Submittal of 10 CFR 50.46 Annual Report TMI-10-031, Combined 2009 Annual Radioactive Effluent Release Reports2010-04-28028 April 2010 Combined 2009 Annual Radioactive Effluent Release Reports TMI-10-030, Annual Radiological Environmental Operating Report2010-04-28028 April 2010 Annual Radiological Environmental Operating Report TMI-10-008, Submittal of 2009 Annual Operating Report2010-02-19019 February 2010 Submittal of 2009 Annual Operating Report TMI-09-053, Annual Radiological Environmental Operating Report for 1 January Through 31 December 20082009-04-30030 April 2009 Annual Radiological Environmental Operating Report for 1 January Through 31 December 2008 ML0912606692009-04-30030 April 2009 Annual Radiological Environmental Operating Report for 1 January Through 31 December 2008 ML0912804372009-04-30030 April 2009 Combined 2008 Annual Radioactive Effluent Release Report TMI-09-013, Annual Report2009-02-20020 February 2009 Annual Report ML0828807302008-06-30030 June 2008 SEIS Ch. 8 Energy References, Annual Energy Outlook 2008, with Projections to 2030 ML0806501212008-02-20020 February 2008 2007 Annual Report ML0713603372007-05-16016 May 2007 Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Required by 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-water Nuclear Power Reactors. ML0513706302005-05-16016 May 2005 (TMI Unit 1), Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Required by 10 CFR 50.46 ML0828807262005-01-0101 January 2005 Pennsylvania Bureau of Radiation Protection Environmental Radiation in PA - 2003 and 2004 Annual Reports ML0819806862004-12-31031 December 2004 008-C2-AmerGen 2005 - Three Mile Island 2004 Annual Report, Record of Well Pumpage and Water Levels, Susquehanna River Basin Commission Permit No 1991102 ML0415901802004-06-0101 June 2004 2003 Annual Report ML0819806852003-12-31031 December 2003 007-C2-AmerGen 2004 - Three Mile Island 2003 Annual Report, Record of Well Pumpage and Water Levels, Susquehanna River Basin Commission Permit No. 19961102 ML0217104602002-06-0606 June 2002 10CFR 50.46 Annual Report for Three Mile Island, Unit 1 2024-04-29
[Table view] Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24242A3032024-09-0909 September 2024 Letter - Three Mile Island Station, Unit 2, Issuance of Amendment No. 68, Historic and Cultural Resources IR 05000320/20240012024-08-28028 August 2024 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report Nos. 05000320/2024001 and 05000320/2024002 ML24240A2222024-08-27027 August 2024 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 6 ML24220A2742024-08-15015 August 2024 Request for Additional Information Clarification Call Regarding Three Mile Island Station, Unit 2, Amended Post-Shutdown Decommissioning Activities Report, Rev. 6 ML24135A3292024-08-0909 August 2024 Amendment No 68, Historic and Cultural Resources Cover Letter IR 07200077/20240012024-06-18018 June 2024 Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report No. 07200077/2024001 ML24135A1972024-06-13013 June 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0091 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24157A3672024-06-13013 June 2024 Updated Post-Shutdown Decommissioning Activities Report Request for Additional Information Transmittal Letter ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24120A3242024-05-24024 May 2024 TMI-2 Email to Fws RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24121A2472024-04-29029 April 2024 and Three Mile Island, Unit 2 - 2023 Occupational Radiation Exposure Annual Report ML24120A2552024-04-29029 April 2024 Annual Radiological Environmental Operating Report ML24113A0212024-04-18018 April 2024 (TMI-2), Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24065A0042024-03-28028 March 2024 Submittal of 2023 Aircraft Movement Data Annual Report ML24088A0122024-03-28028 March 2024 Notification of Amended Post-Shutdown Decommissioning Activities Report (PSDAR) in Accordance with 10 CFR 50.82(a)(7), Revision 6 ML24092A0012024-03-28028 March 2024 (TMI-2), Decommissioning Trust Fund Annual Report ML24085A2152024-03-25025 March 2024 (TMI-2) - Annual Notification of Property Insurance Coverage RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. ML24052A0602024-03-20020 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0061 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24074A3922024-03-14014 March 2024 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 ML24075A0062024-03-14014 March 2024 List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project ML24073A2312024-03-13013 March 2024 and Three Mile Island Nuclear Station, Unit 2 - Management Change ML24044A0092024-02-12012 February 2024 License Amendment Request – Three Mile Island, Unit 2, Historic and Cultural Resources Review, Response to Request for Additional Information IR 05000320/20230042024-02-0707 February 2024 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report 05000320/2023004 ML24038A0222024-02-0505 February 2024 Achp Letter on Section 106 Programmatic Agreement Participation IR 05000289/20230062024-01-29029 January 2024 Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report No. 05000289/2023006 ML23342A1242024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan ML23325A1092024-01-0505 January 2024 Review of the Management Plan for Three Mile Island Station, Unit No. 2, Debris Material ML23354A2112023-12-20020 December 2023 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 ML23354A2062023-12-20020 December 2023 (TMI-2), Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000320/20230032023-11-28028 November 2023 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2, NRC Inspection Report No. 05000320/2023003 ML23243A9082023-08-29029 August 2023 Shpo Letter to TMI-2 Regarding Section 106 Activities IR 05000320/20230022023-08-17017 August 2023 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report 05000320/2023002 IR 05000289/20230052023-08-14014 August 2023 Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report 05000289/2023005 ML23216A1772023-08-14014 August 2023 Consultation Letter to Rebecca Countess for TMI-2 ML23216A1782023-08-14014 August 2023 Consultation Letter to Steve Letavic for TMI-2 ML23216A1732023-08-14014 August 2023 Consultation Letter to Christine Turner for TMI-2 ML23216A1752023-08-14014 August 2023 Consultation Letter to Joanna Cain for TMI-2 ML23216A1742023-08-14014 August 2023 Consultation Letter to David Morrison for TMI-2 ML23221A1402023-08-0808 August 2023 (TMI-2), Response to Requests for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 ML23200A1882023-07-31031 July 2023 TMI-2 Correction Letter Amendment 67 ML23209A7632023-07-28028 July 2023 Letter from PA Shpo to TMI-2 Solutions on Cultural and Historic Impacts of Decommissioning ML23192A8272023-07-10010 July 2023 TMI-2 Solutions, LLC - Response to Shpo Request for Additional Information for Er Project 2021PR03278.006, TMI-2 Decommissioning Project ML23167A4642023-07-0505 July 2023 Letter - TMI-2- Exemption 10 CFR Part 20 Append G Issuance ML23167A0312023-06-28028 June 2023 Acceptance Review and Schedule for the Request for Exemption from a Requirement from 10 CFR 20, Appendix G, Section Iii.E, EPID L-2023-LLE-0016 ML23171B0222023-06-19019 June 2023 (TMI-2) - Notification Pursuant to 10 CFR 72.140(d) Regarding Application of Previously Approved TMI-2 Quality Assurance Program to Independent Spent Fuel Storage Installation Activities ML23138A0662023-05-17017 May 2023 TMI-2 NHPA Section 106 Shpo Letter to NRC 5-17-23 2024-09-09
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200 Exelon Way Exelon Generation Kennett Square, PA 19348 www.exeloncorp.com 10 CFR 50.46 TMl-17-050 May 5, 2017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289
Subject:
10 CFR 50.46 Annual Report
Reference:
- 1) Letter from James Barstow (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "1 O CFR 50.46 Annual Report,"
dated May 6, 2016 The purpose of this letter is to submit the 10 CFR 50.46 reporting information for Three Mile Island Nuclear Station (TMI), Unit 1. The most recent annual 50.46 Report for TMI, Unit 1 (Reference 1), provided the cumulative Peak Cladding Temperature (PCT) errors for the most recent fuel designs.
Since the Reference 1 report was issued, no vendor notifications of Emergency Core Cooling System (ECCS) model error/changes applicable to TMI, Unit 1, have been issued.
No other EGGS-related changes or modifications have occurred at TMI, Unit 1 that affect the assumptions of the ECCS system.
Two attachments are included with this letter that provide the current TMI, Unit 1, 1o CFR 50.46 status. Attachment 1 ("Peak Cladding Temperature Rack-Up Sheets")
provides updated information regarding the PCT for the limiting SBLOCA and LBLOCA analyses. Attachment 2 ("Assessment Notes") contains a detailed description for each change or error reported.
U.S. Nuclear Regulatory Commission 10 CFR 50.46 Annual Report May 5, 2017 Page2 No new regulatory commitments are established in this submittal.
If any additional information is needed, please contact Frank Mascitelli at (610) 765-5512.
Respectfully,
~MM:
James Barstow Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC Attachments: 1) Peak Cladding Temperature Rack-Up Sheets
- 2) Assessment Notes cc: USNRC Administrator, Region I USNRC Project Manager, TMI, Unit 1 USNRC Senior Resident Inspector, TMI, Unit 1
ATTACHMENT 1 10 CFR 50.46 Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments Assessments as of May 5, 2017 Peak Cladding Temperature Rack-Up Sheets TMI, Unit 1
Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 5, 2017 Attachment 1 Peak Cladding Temperature Rack-Up Sheet Page 1 of 2 PLANT NAME: Three Mile Island Unit 1 ECCS EVALUATION MODEL: Small Break Loss of Coolant Accident (SBLOCA)
REPORT REVISION DATE: 5/05/2017 CURRENT OPERATING CYCLE: gj_
ANALYSIS OF RECORD (AOR) 1 Evaluation Model: BWNT Calculation: AREVA NP, 86-9111507-000, August 2009 (Mark-B-HTP with Enhanced Once-Through Steam Generators (EOTSGs))
Fuel: Mark-B-HTP Limiting Fuel Type: Mark-B-HTP Limiting Single Failure: Loss of One Train of ECCS Limiting Break Size and Location: 0.07 tt2 Break in Cold Leg Pump Discharge Piping Reference Peak Cladding Temperature (PCT) PCT = 1444.0°F MARGIN ALLOCATION A. PRIOR LOSS OF COOLANT ACCIDENT (LOCA) MODEL ASSESSMENTS Annual 10 CFR 50.46 Report dated May 16, 2007 (See Note 1) aPCT =O °F Annual 10 CFR 50.46 Report dated May 15, 2009 (See Note 3) aPCT = o °F Annual 10 CFR 50.46 Report dated May 14, 2010 (See Note 4) L\PCT = 0 °F 30-Day 10 CFR 50.46 Report dated September 7, 2010 (See Note 5) L\PCT = 225°F Annual 10 CFR 50.46 Report dated May 13, 2011 (See Note 6) aPCT=0°F 30-Day 10 CFR 50.46 Report dated March 21, 2012 (See Note 7) aPCT = o °F Annual 10 CFR 50.46 Report dated May 11, 2012 (See Note 8) aPCT = o °F Annual 10 CFR 50.46 Report dated May 1O, 2013 (See Note 9) aPCT=0°F Annual 10 CFR 50.46 Report dated May 9, 2014 (See Note 1O) aPCT = o °F 30-Day 10 CFR 50.46 Report dated December 22, 2014 (See Note L\PCT = 0°F 11)
Annual 10 CFR 50.46 Report dated May 8, 2015 (See Note 12) L\PCT = 0°F Annual 10 CFR 50.46 Report dated May 6, 2016 (See Note 13) L\PCT = 0°F NET PCT PCT= 1669.0°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 14) L\PCT = 0°F Total PCT change from current assessments r L\PCT = 0°F Cumulative PCT change from current assessments r IL\PCTI = 0°F NET PCT PCT = 1669.0°F 1
The BWNT EM is based on RELAP5/MOD2-B&W.
Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 5, 2017 Attachment 1 Peak Cladding Temperature Rack-Up Sheet Page 2 of 2 PLANT NAME: Three Mile Island Unit 1 ECCS EVALUATION MODEL: Large Break Loss of Coolant Accident (LBLOCA)
REPORT REVISION DATE: 05/05/2017 CURRENT OPERATING CYCLE: 21 ANAL VSIS OF RECORD (AOR)
Evaluation Model: BWNT2 Calculation: AREVA NP, 86-9111507-000, August 2009 (Mark-B-HTP with EOTSGs)
Fuel: Mark-B-HTP Limiting Fuel Type: Mark-B-HTP Limiting Single Failure: Loss of One Train of ECCS Limiting Break Size and Location: Guillotine Break in Cold Leg Pump Discharge Piping Reference Peak Cladding Temperature (PCT) PCT= 1890°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS Annual 10 CFR 50.46 Report dated May 16, 2007 (See Note 1) LiPCT = 0 °F Annual 10 CFR 50.46 Report dated May 15, 2008 (See Note 2) LiPCT = 0 °F Annual 10 CFR 50.46 Report dated May 15, 2009 (See Note 3) LiPCT = 0 °F Annual 10 CFR 50.46 Report dated May 14, 2010 (See Note 4) LiPCT = 0 °F Annual 10 CFR 50.46 Report dated May 13, 2011 (See Note 6) ~PCT= 0 °F 30-Day 10 CFR 50.46 Report dated March 21, 2012 (See Note 7) ~PCT= 0 °F Annual 10 CFR 50.46 Report dated May 11, 2012 (See Note 8) ~PCT=0°F Annual 10 CFR 50.46 Report dated May 10, 2013 (See Note 9) ~PCT= 0 °F Annual 10 CFR 50.46 Report dated May 9, 2014 (See Note 1O) ~PCT= 0 °F 30-Day 10 CFR 50.46 Report dated December 22, 2014 (See Note 11) LiPCT = +18°F Annual 10 CFR 50.46 Report dated May 8, 2015 (See Note 12) LiPCT = 0°F Annual 10 CFR 50.46 Report dated May 6, 2016 (See Note 13) LiPCT = 0°F NET PCT PCT= 1908°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 14) LiPCT = 0°F Total PCT change from current assessments r LiPCT = 0°F Cumulative PCT change from current assessments r ILiPCTI = 0°F NET PCT PCT= 1908°F 2
The BWNT EM is based on RELAP5/MOD2-B&W.
ATTACHMENT2 10 CFR 50.46 Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments Assessments as of May 5, 2017 Peak Cladding Temperature Rack-Up Sheets TMI, Unit 1 Assessment Notes
Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 5, 2017 Attachment 2 Assessment Notes Page 1 of 3
- 1. Prior LOCA Model Assessment The 10 CFR 50.46 report dated May 16, 2007 reported an evaluation for a LOCA model change which resulted in a O °F PCT change. The reported evaluation considered the effect on the containment pressure response for LOCA due to GSl-191 related reactor building sump screen replacement. The evaluation resulted in O °F impact for LBLOCA and SBLOCA PCTs.
- 2. Prior LOCA Model Assessment The 10 CFR 50.46 report dated May 15, 2008 reported an evaluation for LOCA model change which resulted in a O °F PCT change. Reported change included the impact of an energy deposition factor error which resulted in a LBLOCA PCT impact of O °F.
- 3. Prior LOCA Model Assessment The 10 CFR 50.46 report dated May 15, 2009 reported no evaluations or PCT penalties for either SBLOCA or LBLOCA.
- 4. Prior LOCA Model Assessment The 10 CFR 50.46 report dated May 14, 2010 reported a change to the reference PCT value for LBLOCA due to the final discharge of all Mark-89 fuel.
Also identified in this report was a new SBLOCA analysis, implemented beginning with the Cycle 18 operation. This SBLOCA analysis was evaluated with the mixed core of Mark-812 and Mark-8-HTP and a new PCT of 1444°F was calculated for the limiting Mark-8-HTP fuel type, which bounds the Mark-812 fuel type. This analysis also includes consideration of the effect of reduced EDW wetting associated with the Enhanced Once-Through Steam Generators (EOTSGs).
- 5. Prior LOCA Model Assessment The 10 CFR 50.46 report dated September 7, 2010 reported an evaluation for the SBLOCA analysis due to a non-bounding axial power shape from middle-of-cycle to end-of-cycle conditions. This resulted in a PCT increase of 225°F. The large break LOCA is not affected in this report.
- 6. Prior LOCA Model Assessment The 10 CFR 50.46 report dated May 13, 2011 reported no evaluations or PCT penalties for either SBLOCA or LBLOCA.
- 7. Prior LOCA Model Assessment The 10 CFR 50.46 report dated March 21, 2012 reported two changes to the TMI LOCA model.
One consisted of an error in the ECCS Bypass Calculation that affected the LBLOCA analysis.
The second change consisted of correcting the Upper Plenum Column Weldment Model which affected both the SBLOCA and LBLOCA analysis. The results of both of these changes were a 0°F PCT impact for both SBLOCA and LBLOCA.
Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 5, 2017 Attachment 2 Assessment Notes Page 2 of 3
- 8. Prior LOCA Model Assessment With the Cycle 19 reload, all Mark-812 fuel types were discharged from the core. Currently, the limiting fuel type is Mark-8-HTP for both SBLOCA and LBLOCA. The limiting PCT for LBLOCA has been updated to 1890°F in accordance with our referenced calculation (86-9111507-000).
All previous PCT assessments that are not applicable to Mark-B-HTP fuel have been removed.
The 10 CFR 50.46 report dated May 11, 2012 reported no evaluations or PCT penalties for either SBLOCA or LBLOCA.
- 9. Prior LOCA Model Assessment The 10 CFR 50.46 report dated May 10, 2013 reported no evaluations or PCT penalties for either SBLOCA or LBLOCA.
- 10. Prior LOCA Model Assessment The 10 CFR 50.46 report dated May 9, 2014 reported no evaluations or PCT penalties for either SBLOCA or LBLOCA.
- 11. Prior LOCA Model Assessment The 30-day 10 CFR 50.46 report dated December 22, 2014 reported a significant error due to thermal conductivity degradation {TCD) based on insufficient LOCA fuel temperature inputs in TAC0-3/GDTACO computer codes. Correction of the TCD modeling in TAC0-3/GDTACO results in a conservative increase of 393F in peak cladding temperature (PCT) for LBLOCA.
The SBLOCA analyses are not sensitive to initial fuel temperature and therefore have an estimated PCT impact of 0°F.
Additionally, TMI has implemented a 2 kw/ft penalty to LHR limits in Cycle 20 (10/20/14). The penalty has been applied through more restrictive operational imbalance limits and results in a reduction of PCT by 375°F for LBLOCA.
The overall cumulative impact for the error and the design input change is 0°F for SBLOCA and 18°F for LBLOCA.
- 12. Prior LOCA Model Assessment The 10 CFR 50.46 report dated May 8, 2015 reported no evaluations or PCT penalties for either SBLOCA or LBLOCA.
Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 5, 2017 Attachment 2 Assessment Notes Page 3 of 3
- 13. Prior LOCA Model Assessment The 1o CFR 50.46 report dated May 6, 2016 reported the reactor coolant system (RCS) flow rate used in the TMI Unit 1 SBLOCA analysis (106.5% of design flow) is inconsistent with the RCS flow rate used in the departure-from-nucleate (DNB) analysis (104.5% of design flow).
Additionally, a lower RCS flow rate was used in the LBLOCA analysis (102% of design flow) than that in the at-power minimum DNB analysis (104.5% of design flow). LOCA analyses are performed using the AREVA LOCA evaluation model (EM) BAW-10192P-A, which is the applicable LOCA EM for TMI Unit 1, and are required to use the RCS flow rate that is used in the at-power minimum DNB analysis. The SBLOCA and LBLOCA RCS flow rate inconsistency assessments were estimated to be a O °F PCT impact.
- 14. Current LOCA Model Assessment No model changes or errors were identified for this annual report.