|
|
| Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:1 OCFR50.46 May 16,2007 5928-07-20099 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Three Mile Island, Unit 1 (TMI Unit | | {{#Wiki_filter:1OCFR50.46 May 16,2007 5928-07-20099 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Three Mile Island, Unit 1 (TMI Unit 1) |
| : 1) Facility Operating License No. DPR-50 NRC Docket No. 50-289
| | Facility Operating License No. DPR-50 NRC Docket No. 50-289 |
|
| |
|
| ==Subject:== | | ==Subject:== |
| 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" In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," paragraph (a)(3)(ii), AmerGen Energy Company, LLC (AmerGen), is submitting the annual report of the Emergency Core Cooling System (ECCS) Evaluation Model changes and errors for TMI Unit 1. Attachment 1, "Peak Cladding Temperature Rack-Up Sheets," provides updated information regarding the peak cladding temperature (PCT) for the limiting small break and large break loss-of-coolant accident (LOCA) analyses evaluations for TMI Unit 1. Attachment 2, "Assessment Notes," contains a detailed description for each change or error reported. | | 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 In accordance with 10 CFR 50.46, Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors, paragraph (a)(3)(ii), AmerGen Energy Company, LLC (AmerGen), is submitting the annual report of the Emergency Core Cooling System (ECCS) |
| No new regulatory commitments are established in this submittal. | | Evaluation Model changes and errors for TMI Unit 1. , Peak Cladding Temperature Rack-Up Sheets, provides updated information regarding the peak cladding temperature (PCT) for the limiting small break and large break loss-of-coolant accident (LOCA) analyses evaluations for TMI Unit 1. Attachment 2, Assessment Notes, contains a detailed description for each change or error reported. |
| If any additional information is needed, please contact David J. Distel at (610) 765-5517. | | No new regulatory commitments are established in this submittal. If any additional information is needed, please contact David J. Distel at (610) 765-5517. |
| Respectfully, A David P. Helker Manager - Licensing Attachments: | | Respectfully, A |
| : 1) Peak Cladding Temperature Rack-Up Sheets 2) Assessment Notes 5928-07-20099 May 16,2007 Page 2 cc: S. J. Collins, USNRC Administrator, Region I P. Bamford, USNRC Project Manager, TMI Unit 1 D. M. Kern, USNRC Senior Resident Inspector, TMI Unit 1 File No. 00068 Attachment 1 TMI Unit 1 Docket No. 50-289 License No. DPR-50 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 Peak Cladding Temperature Rack-Up Sheets 5928-07-20099 Attachment 1 Page 1 of 2 lOCFR50.46 report dated June 6,2002 (see note | | David P. Helker Manager - Licensing Attachments: 1) Peak Cladding Temperature Rack-Up Sheets |
| : 3) 1 OCFR50.46 report dated June 19,2003 (see note
| | : 2) Assessment Notes |
| : 4) 1 OCFR50.46 report dated June 1, 2004 (see note
| | |
| : 5) 10CFR50.46 report dated May 16, 2005 (see note 6) 10CFR50.46 report dated May 09, 2006 (see note
| | 5928-07-20099 May 16,2007 Page 2 cc: S. J. Collins, USNRC Administrator, Region I P. Bamford, USNRC Project Manager, TMI Unit 1 D. M. Kern, USNRC Senior Resident Inspector, TMI Unit 1 File No. 00068 |
| : 7) Attachment 1 APCT = 0°F APCT = 0°F APCT = 0°F APCT = 0°F APCT = 0°F Three Mile Island Unit I 10CFR50.46 Report Peak Cladding Temperature Rack-up Sheets PLANT NAME: ECCS EVALUATION MODEL: REPORT REVISION DATE: CURRENT OPERATING CYCLE:
| | |
| 16 Three Mile Island Unit 1 Small Break Loss of Coolant Accident (SBLOCA) 031 301 07 ANALYSIS OF RECORD (AOR)
| | Attachment 1 TMI Unit 1 Docket No. 50-289 License No. DPR-50 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 Peak Cladding Temperature Rack-Up Sheets |
| Evaluation Model: BWNT ' Calculation: | | |
| Framatome ANP 86-501 1294-00, March 2001 Fuel: Mark-B9, Mark-B12 Limiting Fuel Type: Mark-B12 Limiting Single Failure: Loss of One Train of ECCS Steam Generator Tube Pluqging (SGTP): 20% Limiting Break Size: | | 5928-07-20099 Page 1 of 2 Attachment 1 Three Mile Island Unit I 10CFR50.46 Report Peak Cladding Temperature Rack-up Sheets PLANT NAME: Three Mile Island Unit 1 ECCS EVALUATION MODEL: Small Break Loss of Coolant Accident (SBLOCA) |
| 0.05 ft Break in Cold Leg Pump Discharge Piping Reference Peak Cladding Temperature (PCT) PCT | | REPORT REVISION DATE: 03130107 CURRENT OPERATING CYCLE: 16 ANALYSIS OF RECORD (AOR) |
| = 1454.0"F MARGIN ALLOCATION A. PRIOR LOSS OF COOLANT ACCIDENT (LOCA) MODEL ASSESSMENTS NET PCT PCT = 1454.0"F B. CURRENT LOCA MODEL ASSESSMENTS I Impact of Heat Sink on Safety Analyses (see note | | Evaluation Model: BWNT ' |
| : 8) I APCT = 0°F NET PCT PCT = 1454.0"F ' The BWNT EM is based on RELAP5/MOD2-B&W.
| | Calculation: Framatome ANP 86-5011294-00, March 2001 Fuel: Mark-B9, Mark-B12 Limiting Fuel Type: Mark-B12 Limiting Single Failure: Loss of One Train of ECCS Steam Generator Tube Pluqging (SGTP): 20% |
| 5928-07-20099 Attachment 1 Page 2 of 2 Fuel Type: Limiting Fuel Type: Reference PCT Attachment 1 Mark-B9 Mark-B12 Mark-B9 Mark-B12 2083°F 1 989°F Three Mile Island Unit 1 10CFR50.46 Report Peak Cladding Temperature Rack-up Sheets 10CFR50.46 report dated June 5,2000 (see note 1) 1 OCFR50.46 report dated June 11,2001 (see note | | Limiting Break Size: 0.05 ft Break in Cold Leg Pump Discharge Piping Reference Peak Cladding Temperature (PCT) PCT = 1454.0"F MARGIN ALLOCATION A. PRIOR LOSS OF COOLANT ACCIDENT (LOCA) MODEL ASSESSMENTS 10CFR50.46 report dated June 6,2002 (see note 3) APCT = 0°F 10CFR50.46 report dated June 19,2003 (see note 4) APCT = 0°F 10CFR50.46 report dated June 1, 2004 (see note 5) APCT = 0°F 10CFR50.46 report dated May 16, 2005 (see note 6) APCT = 0°F 10CFR50.46 report dated May 09, 2006 (see note 7) APCT = 0°F NET PCT PCT = 1454.0"F B. CURRENT LOCA MODEL ASSESSMENTS I Impact of Heat Sink on Safety Analyses (see note 8) I APCT = 0°F NET PCT PCT = 1454.0"F |
| : 2) 1 OCFR50.46 report dated June 6,2002 (see note
| | ' The BWNT EM is based on RELAP5/MOD2-B&W. |
| : 3) 10CFR50.46 report dated June 19,2003 (see note
| | |
| : 4) 1 OCFR50.46 report dated June 1,2004 (see note
| | 5928-07-20099 Page 2 of 2 Attachment 1 Three Mile Island Unit 1 10CFR50.46 Report Peak Cladding Temperature Rack-up Sheets PLANT NAME: Three Mile Island Unit 1 ECCS EVALUATION MODEL: Larae Break Loss of Coolant Accident (LBLOCA) |
| : 5) 10CFR50.46 report dated May 16, 2005 (see note
| | REPORT REVISION DATE: 03/30/07 CURRENT OPERATING CYCLE: 16 Evaluation Model: BWNT2 Calculation: Framatome ANP 86-5002073-02, July 1999 (Mark-B9) |
| : 6) 10CFR50.46 report dated May 09, 2006 (see note
| | Framatome ANP 86-5011294-00, March 2001 (Mark-B12) |
| : 7) PLANT NAME: ECCS EVALUATION MODEL: REPORT REVISION DATE:
| | Limiting Single Failure: Loss of One Train of ECCS Steam Generator Tube Plugging (SGTP): 20% |
| 03/30/07 CURRENT OPERATING CYCLE:
| | Limiting Break Size: Guillotine Break in Cold Leg Pump Discharge Piping Fuel Type: Mark-B9 Mark-B12 Limiting Fuel Type: Mark-B9 Mark-B12 Reference PCT 2083°F 1989°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10CFR50.46 report dated June 5,2000 (see note 1) APCT = 0°F NIA 10CFR50.46 report dated June 11,2001 (see note 2) APCT = 0°F NIA 10CFR50.46 report dated June 6,2002 (see note 3) APCT = 0°F APCT = 0°F 10CFR50.46 report dated June 19,2003 (see note 4) APCT = 0°F APCT = 0°F 10CFR50.46 report dated June 1,2004 (see note 5) APCT = -25°F APCT= -35°F 10CFR50.46 report dated May 16, 2005 (see note 6) APCT = 0°F APCT = 0°F 10CFR50.46 report dated May 09, 2006 (see note 7) APCT = 0°F APCT = 0°F NET PCT PCT = 2058°F 1954°F B. CURRENT LOCA MODEL ASSESSMENTS I Impact of Heat Sink on Safety Analyses (see note 8) 1 APCT = 0°F IAPCT=O"F 1 NET PCT PCT = 2058°F 1954°F |
| 16 Three Mile Island Unit 1 Larae Break Loss of Coolant Accident (LBLOCA)
| |
| APCT = 0°F NIA APCT = 0°F NIA APCT = 0°F APCT = 0°F APCT = -25°F APCT= -35°F APCT = 0°F APCT = 0°F APCT = 0°F APCT = 0°F APCT = 0°F APCT = 0°F Evaluation Model: BWNT2 Calculation: Framatome ANP 86-5002073-02, July 1 999 (Mark-B9)
| |
| Framatome ANP 86-501 1294-00, March 2001 (Mark-B12) Limiting Single Failure: Loss of One Train of ECCS Steam Generator Tube Plugging (SGTP): 20% Limiting Break Size: Guillotine Break in Cold Leg Pump Discharge Piping MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS NET PCT PCT = 2058°F 1954°F B. CURRENT LOCA MODEL ASSESSMENTS I Impact of Heat Sink on Safety Analyses (see note
| |
| : 8) 1 APCT = 0°F IAPCT=O"F 1 NET PCT PCT = 2058°F 1954°F
| |
| * The BWNT EM is based on RELAP5/MOD2-B&W. | | * The BWNT EM is based on RELAP5/MOD2-B&W. |
| Attachment 2 TMI Unit 1 Docket No. 50-289 License No. DPR-50 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 Assessment Notes 5928-07-20099 Attachment 2 Page 1 of 1 Attachment 2 Three Mile Island Unit 1 lOCFR50.46 Report Assessment Notes 1. Prior LOCA Model Assessment The 1 OCFR50.46 report dated June 5,2000 reported new LBLOCA and SBLOCA analyses to support operations at 20% steam generator tube plugging conditions for Mark-B9 fuel. | | |
| : 2. Prior LOCA Model Assessment The lOCFR50.46 report dated June 11, 2001 reported evaluations for LBLOCA and SBLOCA model changes which resulted in 0°F PCT change. | | Attachment 2 TMI Unit 1 Docket No. 50-289 License No. DPR-50 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 Assessment Notes |
| : 3. Prior LOCA Model Assessment The 1 OCFR50.46 report dated June 6,2002 reported new LBLOCA analyses to support operations with Mark-B12 fuel. For SBLOCA, an increase in SBLOCA PCT of 42°F for Mark-B9 fuel was reported due to increase in emergency feedwater temperature. This analysis is applicable to both Mark-B12 fuel and Mark-B9 fuel. 4. Prior LOCA Model Assessment The 1 OCFR50.46 report dated June 19,2003 reported evaluation for LBLOCA model change, which resulted in 0°F PCT change. | | |
| SBLOCA was not impacted. | | 5928-07-20099 Attachment 2 Page 1 of 1 Attachment 2 Three Mile Island Unit 1 10CFR50.46 Report Assessment Notes |
| : 5. Prior LOCA Model Assessment The 1 OCFR50.46 report dated June 1,2004 reported evaluation for LBLOCA and SBLOCA model changes which resulted in 0°F PCT change. An error correction in containment pressure input resulted in a reduction in PCT for the LBLOCA analysis. | | : 1. Prior LOCA Model Assessment The 10CFR50.46 report dated June 5,2000 reported new LBLOCA and SBLOCA analyses to support operations at 20% steam generator tube plugging conditions for Mark-B9 fuel. |
| : 6. Prior LOCA Model Assessment The lOCFR50.46 report dated May 16, 2005 reported evaluations for LBLOCA model changes which resulted in a 0°F PCT change. LOCA oxygen/hydrogen recombination was considered and the PCT effect was determined to be 0°F. SBLOCA was not impacted. | | : 2. Prior LOCA Model Assessment The 10CFR50.46 report dated June 11, 2001 reported evaluations for LBLOCA and SBLOCA model changes which resulted in 0°F PCT change. |
| : 7. Prior LOCA Model Assessment The 10CFR50.46 report dated May 09, 2006 reported evaluations for LOCA model changes which resulted in a 0°F PCT change. Reported changes included operation with no APSR pull and batch 18 fuel design changes. These were applicable for SBLOCA and LBLOCA. 8. Impact of Heat Sink on Safety Analyses The evaluation considered the effect on the containment pressure response for LOCA due to GSI-191 related reactor building sump screen replacement. | | : 3. Prior LOCA Model Assessment The 10CFR50.46 report dated June 6,2002 reported new LBLOCA analyses to support operations with Mark-B12 fuel. For SBLOCA, an increase in SBLOCA PCT of 42°F for Mark-B9 fuel was reported due to increase in emergency feedwater temperature. This analysis is applicable to both Mark-B12 fuel and Mark-B9 fuel. |
| The evaluation resulted in 0°F impact for both LBLOCA and SBLOCA PCTs.}} | | : 4. Prior LOCA Model Assessment The 10CFR50.46 report dated June 19,2003 reported evaluation for LBLOCA model change, which resulted in 0°F PCT change. SBLOCA was not impacted. |
| | : 5. Prior LOCA Model Assessment The 10CFR50.46 report dated June 1,2004 reported evaluation for LBLOCA and SBLOCA model changes which resulted in 0°F PCT change. An error correction in containment pressure input resulted in a reduction in PCT for the LBLOCA analysis. |
| | : 6. Prior LOCA Model Assessment The 10CFR50.46 report dated May 16, 2005 reported evaluations for LBLOCA model changes which resulted in a 0°F PCT change. LOCA oxygen/hydrogen recombination was considered and the PCT effect was determined to be 0°F. SBLOCA was not impacted. |
| | : 7. Prior LOCA Model Assessment The 10CFR50.46 report dated May 09, 2006 reported evaluations for LOCA model changes which resulted in a 0°F PCT change. Reported changes included operation with no APSR pull and batch 18 fuel design changes. These were applicable for SBLOCA and LBLOCA. |
| | : 8. Impact of Heat Sink on Safety Analyses The evaluation considered the effect on the containment pressure response for LOCA due to GSI-191 related reactor building sump screen replacement. The evaluation resulted in 0°F impact for both LBLOCA and SBLOCA PCTs.}} |
|
|---|
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
MONTHYEARML24256A0422024-10-0404 October 2024
Updated Post-Shutdown Decommissioning Activities Report, Rev. 6
ML24240A1692024-09-18018 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
ML24157A3672024-06-13013 June 2024
Updated Post-Shutdown Decommissioning Activities Report Request for Additional Information Transmittal Letter
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))
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
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
ML24065A0042024-03-28028 March 2024
Submittal of 2023 Aircraft Movement Data Annual Report
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))
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
ML24074A3922024-03-14014 March 2024
Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5
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
ML23354A2062023-12-20020 December 2023
(TMI-2), Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23354A2112023-12-20020 December 2023
Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5
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
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
ML23216A1772023-08-14014 August 2023
Consultation Letter to Rebecca Countess for TMI-2
IR 05000289/20230052023-08-14014 August 2023
Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report 05000289/2023005
ML23216A1742023-08-14014 August 2023
Consultation Letter to David Morrison for TMI-2
ML23216A1782023-08-14014 August 2023
Consultation Letter to Steve Letavic 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
2024-09-09
[Table view] |
Text
1OCFR50.46 May 16,2007 5928-07-20099 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Three Mile Island, Unit 1 (TMI Unit 1)
Facility Operating License No. DPR-50 NRC Docket No. 50-289
Subject:
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 In accordance with 10 CFR 50.46, Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors, paragraph (a)(3)(ii), AmerGen Energy Company, LLC (AmerGen), is submitting the annual report of the Emergency Core Cooling System (ECCS)
Evaluation Model changes and errors for TMI Unit 1. , Peak Cladding Temperature Rack-Up Sheets, provides updated information regarding the peak cladding temperature (PCT) for the limiting small break and large break loss-of-coolant accident (LOCA) analyses evaluations for TMI Unit 1. Attachment 2, Assessment Notes, contains a detailed description for each change or error reported.
No new regulatory commitments are established in this submittal. If any additional information is needed, please contact David J. Distel at (610) 765-5517.
Respectfully, A
David P. Helker Manager - Licensing Attachments: 1) Peak Cladding Temperature Rack-Up Sheets
- 2) Assessment Notes
5928-07-20099 May 16,2007 Page 2 cc: S. J. Collins, USNRC Administrator, Region I P. Bamford, USNRC Project Manager, TMI Unit 1 D. M. Kern, USNRC Senior Resident Inspector, TMI Unit 1 File No. 00068
Attachment 1 TMI Unit 1 Docket No. 50-289 License No. DPR-50 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 Peak Cladding Temperature Rack-Up Sheets
5928-07-20099 Page 1 of 2 Attachment 1 Three Mile Island Unit I 10CFR50.46 Report Peak Cladding Temperature Rack-up Sheets PLANT NAME: Three Mile Island Unit 1 ECCS EVALUATION MODEL: Small Break Loss of Coolant Accident (SBLOCA)
REPORT REVISION DATE: 03130107 CURRENT OPERATING CYCLE: 16 ANALYSIS OF RECORD (AOR)
Evaluation Model: BWNT '
Calculation: Framatome ANP 86-5011294-00, March 2001 Fuel: Mark-B9, Mark-B12 Limiting Fuel Type: Mark-B12 Limiting Single Failure: Loss of One Train of ECCS Steam Generator Tube Pluqging (SGTP): 20%
Limiting Break Size: 0.05 ft Break in Cold Leg Pump Discharge Piping Reference Peak Cladding Temperature (PCT) PCT = 1454.0"F MARGIN ALLOCATION A. PRIOR LOSS OF COOLANT ACCIDENT (LOCA) MODEL ASSESSMENTS 10CFR50.46 report dated June 6,2002 (see note 3) APCT = 0°F 10CFR50.46 report dated June 19,2003 (see note 4) APCT = 0°F 10CFR50.46 report dated June 1, 2004 (see note 5) APCT = 0°F 10CFR50.46 report dated May 16, 2005 (see note 6) APCT = 0°F 10CFR50.46 report dated May 09, 2006 (see note 7) APCT = 0°F NET PCT PCT = 1454.0"F B. CURRENT LOCA MODEL ASSESSMENTS I Impact of Heat Sink on Safety Analyses (see note 8) I APCT = 0°F NET PCT PCT = 1454.0"F
' The BWNT EM is based on RELAP5/MOD2-B&W.
5928-07-20099 Page 2 of 2 Attachment 1 Three Mile Island Unit 1 10CFR50.46 Report Peak Cladding Temperature Rack-up Sheets PLANT NAME: Three Mile Island Unit 1 ECCS EVALUATION MODEL: Larae Break Loss of Coolant Accident (LBLOCA)
REPORT REVISION DATE: 03/30/07 CURRENT OPERATING CYCLE: 16 Evaluation Model: BWNT2 Calculation: Framatome ANP 86-5002073-02, July 1999 (Mark-B9)
Framatome ANP 86-5011294-00, March 2001 (Mark-B12)
Limiting Single Failure: Loss of One Train of ECCS Steam Generator Tube Plugging (SGTP): 20%
Limiting Break Size: Guillotine Break in Cold Leg Pump Discharge Piping Fuel Type: Mark-B9 Mark-B12 Limiting Fuel Type: Mark-B9 Mark-B12 Reference PCT 2083°F 1989°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10CFR50.46 report dated June 5,2000 (see note 1) APCT = 0°F NIA 10CFR50.46 report dated June 11,2001 (see note 2) APCT = 0°F NIA 10CFR50.46 report dated June 6,2002 (see note 3) APCT = 0°F APCT = 0°F 10CFR50.46 report dated June 19,2003 (see note 4) APCT = 0°F APCT = 0°F 10CFR50.46 report dated June 1,2004 (see note 5) APCT = -25°F APCT= -35°F 10CFR50.46 report dated May 16, 2005 (see note 6) APCT = 0°F APCT = 0°F 10CFR50.46 report dated May 09, 2006 (see note 7) APCT = 0°F APCT = 0°F NET PCT PCT = 2058°F 1954°F B. CURRENT LOCA MODEL ASSESSMENTS I Impact of Heat Sink on Safety Analyses (see note 8) 1 APCT = 0°F IAPCT=O"F 1 NET PCT PCT = 2058°F 1954°F
- The BWNT EM is based on RELAP5/MOD2-B&W.
Attachment 2 TMI Unit 1 Docket No. 50-289 License No. DPR-50 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 Assessment Notes
5928-07-20099 Attachment 2 Page 1 of 1 Attachment 2 Three Mile Island Unit 1 10CFR50.46 Report Assessment Notes
- 1. Prior LOCA Model Assessment The 10CFR50.46 report dated June 5,2000 reported new LBLOCA and SBLOCA analyses to support operations at 20% steam generator tube plugging conditions for Mark-B9 fuel.
- 2. Prior LOCA Model Assessment The 10CFR50.46 report dated June 11, 2001 reported evaluations for LBLOCA and SBLOCA model changes which resulted in 0°F PCT change.
- 3. Prior LOCA Model Assessment The 10CFR50.46 report dated June 6,2002 reported new LBLOCA analyses to support operations with Mark-B12 fuel. For SBLOCA, an increase in SBLOCA PCT of 42°F for Mark-B9 fuel was reported due to increase in emergency feedwater temperature. This analysis is applicable to both Mark-B12 fuel and Mark-B9 fuel.
- 4. Prior LOCA Model Assessment The 10CFR50.46 report dated June 19,2003 reported evaluation for LBLOCA model change, which resulted in 0°F PCT change. SBLOCA was not impacted.
- 5. Prior LOCA Model Assessment The 10CFR50.46 report dated June 1,2004 reported evaluation for LBLOCA and SBLOCA model changes which resulted in 0°F PCT change. An error correction in containment pressure input resulted in a reduction in PCT for the LBLOCA analysis.
- 6. Prior LOCA Model Assessment The 10CFR50.46 report dated May 16, 2005 reported evaluations for LBLOCA model changes which resulted in a 0°F PCT change. LOCA oxygen/hydrogen recombination was considered and the PCT effect was determined to be 0°F. SBLOCA was not impacted.
- 7. Prior LOCA Model Assessment The 10CFR50.46 report dated May 09, 2006 reported evaluations for LOCA model changes which resulted in a 0°F PCT change. Reported changes included operation with no APSR pull and batch 18 fuel design changes. These were applicable for SBLOCA and LBLOCA.
- 8. Impact of Heat Sink on Safety Analyses The evaluation considered the effect on the containment pressure response for LOCA due to GSI-191 related reactor building sump screen replacement. The evaluation resulted in 0°F impact for both LBLOCA and SBLOCA PCTs.
