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{{Adams
#REDIRECT [[TMI-15-063, 10 CFR 50.46 Annual Report]]
| number = ML15128A230
| issue date = 05/08/2015
| title = 10 CFR 50.46 Annual Report
| author name = Barstow J
| author affiliation = Exelon Generation Co, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000289
| license number = DPR-050
| contact person =
| case reference number = TMI-15-063
| document type = Annual Report, Letter
| page count = 8
}}
 
=Text=
{{#Wiki_filter:Exelon Generation TMl-15-063 May 8, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
 
==Subject:==
Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289 10 CFR 50.46 Annual Report 200 Exelon Way Kennett Square, PA 19348 www.exeloncorp.com 10 CFR 50.46
 
==Reference:==
: 1) Letter from James Barstow (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 Annual Report," dated May 9 , 2014 2) Letter from James Barstow (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 30-Day Report," dated December 22, 2014 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, one vendor notification of Emergency Core Cooling System (ECCS) model error/changes applicable to TMI, Unit 1, was reported in TM l's 30-day 10 CFR 50.46 report (Reference 2). No other ECCS-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, 10 CFR 50.46 status. Attachment 1 ("Peak Cladding Temperature Rack-Up Sheets")
U.S. Nuclear Regulatory Commission 1 O CFR 50.46 Annual Report May 8, 2015 Page 2 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.
No new regulatory commitments are established in this submittal.
If any additional information is needed, please contact Frank Mascitelli at (61 O) 765-5512.
Respectfully, 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 8, 2015 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 8, 2015 Peak Cladding Temperature Rack-Up Sheet PLANT NAME: Three Mile Island, Unit 1 Attachment 1 Page 1 of 2 ECCS EVALUATION MODEL: REPORT REVISION DATE: Small Break Loss of Coolant Accident (SBLOCA) 5/08/2015 CURRENT OPERATING CYCLE: 20 ANALYSIS OF RECORD (AOR) Evaluation Model: BWNT 1 Calculation:
AREVA NP, 86-9111507-000, August 2009 (Mark-8-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 ff 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 1 O CFR 50.46 Report dated May 16, 2007 (See Note 1) LlPCT = 0°F Annual 1 O CFR 50.46 Report dated May 15, 2009 (See Note 3) LlPCT = 0°F Annual 1 O CFR 50.46 Report dated May 14, 201 O (See Note 4) LlPCT = 0°F 30-Day 1 O CFR 50.46 Report dated September 7, 201 O (See Note 5) LlPCT = 225°F Annual 1 O CFR 50.46 Report dated May 13, 2011 (See Note 6) LlPCT = 0°F 30-Day 1 O CFR 50.46 Report dated March 21, 2012 (See Note 7) LlPCT = 0°F Annual 10 CFR 50.46 Report dated May 11, 2012 (See Note 8) LlPCT = 0°F Annual 10 CFR 50.46 Report dated May 10, 2013 (See Note 9) LlPCT = 0°F Annual 1 O CFR 50.46 Report dated May 9, 2014 (See Note 10) LlPCT = 0°F 30-Day 1 O CFR 50.46 Report dated December 22 , 2014 (See Note 11) LlPCT = 0°F NET PCT PCT= 1669.0°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 12) Ll PCT = 0°F Total PCT change from current assessments L LlPCT = 0°F Cumulative PCT change from current assessments L I Ll PCTI = 0°F N E T PCT PCT = 1669.0° F 1 T h e B W NT EM i s b ased o n R ELAP 5/M O D 2-B&W.
Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 8, 2015 Peak Cladding Temperature Rack-Up Sheet PLANT NAME: Three Mile Island! Unit 1 Attachment 1 Page 2 of 2 ECCS EVALUATION MODEL: REPORT REVISION DATE: Large Break Loss of Coolant Accident (LBLOCA) 5/08/2015 CURRENT OPERATING CYCLE: 20 ANALYSIS OF RECORD {AOR) Evaluation Model: BWNT 2 Calculation:
AREVA NP, 86-9111507-000, August 2009 (Mark-8-HTP with EOTSGs) Fuel: Mark-8-HTP Limiting Fuel Type: Mark-8-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 1 O CFR 50.46 Report dated May 16, 2007 (See Note 1) i'.'.\PCT
= 0°F Annual 1 O CFR 50.46 Report dated May 15, 2008 (See Note 2) i'.'.\PCT
= 0°F Annual 1 O CFR 50.46 Report dated May 15, 2009 (See Note 3) i'.'.\PCT
= 0°F Annual 1 O CFR 50.46 Report dated May 14 , 201 O (See Note 4) i'.'.\PCT
= 0°F Annual 1 O CFR 50.46 Report dated Mav 13, 2011 (See Note 6) b.PCT = 0°F 30-Day 1 O CFR 50.46 Report dated March 21, 2012 (See Note 7) b.PCT = 0°F Annual 10 CFR 50.46 Report dated May 11, 2012 (See Note 8) b.PCT = 0°F Annual 1 O CFR 50.46 Report dated May 10, 2013 (See Note 9) b.PCT = 0°F Annual 10 CFR 50.46 Report dated Mav 9, 2014 (See Note 1 O) b.PCT = 0°F 30-Day 10 CFR 50.46 Report dated December 22, 2014 (See Note 11) i'.'.\PCT
= + 18°F NET PCT PCT= 1908°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 12) i'.'.\PCT
= 0°F Total PCT change from current assessments r i'.'.\PCT = 0°F Cumulative PCT change from curren t assessments r li'.'.\PCTI
= 0°F NET PCT PCT= 1908°F 2 T h e B W NT EM i s b ase d o n RE L AP 5/M OD2-B&W.
ATTACHMENT 2 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 8, 2015 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 8, 2015 Assessment Notes 1 . Prior LOCA Model Assessment Attachment 2 Page 1 of 2 The 10 CFR 50.46 report dated May 16, 2007, reported an evaluation for a LOCA model change which resulted in a 0°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 0°F impact for L8LOCA and S8LOCA PCTs. 2. Prior LOCA Model Assessment The 1 O CFR 50.46 report dated May 15, 2008, reported an evaluation for LOCA model change which resulted in a 0°F PCT change. Reported change included the impact of an energy deposition factor error which resulted in a L8LOCA PCT impact of 0°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 L8LOCA. 4. Prior LOCA Model Assessment The 1 O CFR 50.46 report dated May 14, 2010, reported a change to the reference PCT value for L8LOCA due to the final discharge of all Mark-89 fuel. Also identified in this report was a new S8LOCA analysis implemented beginning with the Cycle 18 operation.
This S8LOCA 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 1 O CFR 50.46 report dated May 13, 2011, reported no evaluations or PCT penalties for either SBLOCA or L8LOCA. 7. Prior LOCA Model Assessment The 1 O 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 8, 2015 Assessment Notes 8. Prior LOCA Model Assessment Attachment 2 Page 2 of 2 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 S8LOCA and L8LOCA. The limiting PCT for L8LOCA 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-8-HTP fuel have been removed. The 1 O CFR 50.46 report dated May 11, 2012, reported no evaluations or PCT penalties for either S8LOCA or L8LOCA. 9. Prior LOCA Model Assessment The 1 O CFR 50.46 report dated May 10, 2013, reported no evaluations or PCT penalties for either S8LOCA or L8LOCA. 10. Prior LOCA Model Assessment The 10 CFR 50.46 report dated May 9, 2014, reported no evaluations or PCT penalties for either S8LOCA or L8LOCA. 11 . Prior LOCA Model Assessment The 30-day 1 O 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 393°F in peak cladding temperature (PCT} for L8LOCA. The S8LOCA 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 L8LOCA. The overall cumulative impact for the error and the design input change is 0°F for S8LOCA and 18°F for L8LOCA. 12. Current LOCA Model Assessment No model changes or errors were identified for this annual report.}}

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