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MONTHYEARML15353A0022015-12-17017 December 2015
/12/17 Presentation Slides for Pre-Submittal Teleconference - Proposed LAR for Spent Fuel Pool Heat Load Analysis in Response to Confirmatory Order EA-13-188
Project stage: Meeting
ML16004A4732016-01-0404 January 2016
Teleconference Memo to File: Summary of December 17, 2015 - Pre-submittal Call with the NRC Related to Confirmatory Item IV.5
Project stage: Meeting
2015-12-17
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Category:Meeting Briefing Package/Handouts
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[Table view]
Category:Slides and Viewgraphs
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[Table view] |
Text
Pre-Submittal Teleconference Millstone Power Station Unit 2 License Amendment Request for Spent Fuel Pool Heat Load Analysis in Response to Confirmatory Order EA-13-188 December 17, 2015
Agenda
Purpose of LAR
Compliance Item #5:
By no later than February 15, 2016, DNC will submit a license amendment request seeking NRC approval of the spent fuel pool heat load analysis and any associated technical specification changes. This will be treated as a high priority review by the NRC.
- DNC has determined no change to the TS is required
- Request approval of the SFP heat load analyses, TS Bases Section 3/4.9.3 and FSAR Section 9.5
- LAR meets regulatory criteria and will preserve health and safety of the public Pg. 3
Scope of LAR
- LAR will request NRC review and approval of proposed changes to TS Bases Section 3/4.9.3 to remove spent fuel pool decay heat load
- Proposed bases change is based on the TS prior to the 2009 Bases change made by DNC under 10 CFR 50.59
- Change will remove reference to Spent Fuel Pool Decay Heat Load
- The change is consistent with 10 CFR 50.36 and previous License Amendments 240 (2/10/2000) and 315 (6/4/2013)
Pg. 4
Scope of LAR (Continued)
- LAR will request NRC review and approval of proposed changes to FSAR Section 9.5
- Proposed changes are based on the FSAR prior to the 2010 change made by DNC under 10 CFR 50.59
- Proposed FSAR change reflects revisions to:
- Spent fuel movement decay time
- Cooling water temperatures (RBCCW)
- Spent fuel movement rate Pg. 5
Scope of LAR (Continued)
- LAR will provide a summary of the analysis results supporting fuel movement starting at 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after reactor shutdown at a rate of 6 assemblies per hour.
- LAR will include the proprietary analyses performed by Holtec International submitted under 10 CFR 2.390
- Holtec Report No. HI-971778, Rev. 2 "Heat Load from the Spent Fuel Pool for 3 Core Unload Scenarios
- Holtec Report No. HI-2094491, Rev. 0, "Thermal- Hydraulic Analysis of Millstone Unit 2 Spent Fuel Pool with Increased Fuel Transfer Rate and Reduced In-core Hold Time
- Holtec Report No. HI-981901, Rev. 0 including Addenda A & B, "Spent Fuel Pool Thermal- Hydraulic Analysis for Millstone Unit 2 Pg. 6
Schedule
- DNC will submit the LAR by February 15, 2016
- Request review of this LAR within one year of submittal
- To maintain compliance with the Confirmatory Order, Standing Order 14-21 is in place prohibiting fuel movement prior to 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> after shutdown. This will remain in place until NRC makes a final determination on the LAR.
Pg. 7
QUESTIONS?
Pg. 8
Acronym List
- CFR Code of Federal Regulations
- FSAR Final Safety Analysis Report
- LAR License Amendment Request
- MPS2 Millstone Power Station, Unit 2
- RBCCW Reactor Building Closed Cooling Water system
- TS Technical Specifications Pg. 9
Pre-Submittal Teleconference Millstone Power Station Unit 2 License Amendment Request for Spent Fuel Pool Heat Load Analysis in Response to Confirmatory Order EA-13-188 December 17, 2015
Agenda
Purpose of LAR
Compliance Item #5:
By no later than February 15, 2016, DNC will submit a license amendment request seeking NRC approval of the spent fuel pool heat load analysis and any associated technical specification changes. This will be treated as a high priority review by the NRC.
- DNC has determined no change to the TS is required
- Request approval of the SFP heat load analyses, TS Bases Section 3/4.9.3 and FSAR Section 9.5
- LAR meets regulatory criteria and will preserve health and safety of the public Pg. 3
Scope of LAR
- LAR will request NRC review and approval of proposed changes to TS Bases Section 3/4.9.3 to remove spent fuel pool decay heat load
- Proposed bases change is based on the TS prior to the 2009 Bases change made by DNC under 10 CFR 50.59
- Change will remove reference to Spent Fuel Pool Decay Heat Load
- The change is consistent with 10 CFR 50.36 and previous License Amendments 240 (2/10/2000) and 315 (6/4/2013)
Pg. 4
Scope of LAR (Continued)
- LAR will request NRC review and approval of proposed changes to FSAR Section 9.5
- Proposed changes are based on the FSAR prior to the 2010 change made by DNC under 10 CFR 50.59
- Proposed FSAR change reflects revisions to:
- Spent fuel movement decay time
- Cooling water temperatures (RBCCW)
- Spent fuel movement rate Pg. 5
Scope of LAR (Continued)
- LAR will provide a summary of the analysis results supporting fuel movement starting at 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after reactor shutdown at a rate of 6 assemblies per hour.
- LAR will include the proprietary analyses performed by Holtec International submitted under 10 CFR 2.390
- Holtec Report No. HI-971778, Rev. 2 "Heat Load from the Spent Fuel Pool for 3 Core Unload Scenarios
- Holtec Report No. HI-2094491, Rev. 0, "Thermal- Hydraulic Analysis of Millstone Unit 2 Spent Fuel Pool with Increased Fuel Transfer Rate and Reduced In-core Hold Time
- Holtec Report No. HI-981901, Rev. 0 including Addenda A & B, "Spent Fuel Pool Thermal- Hydraulic Analysis for Millstone Unit 2 Pg. 6
Schedule
- DNC will submit the LAR by February 15, 2016
- Request review of this LAR within one year of submittal
- To maintain compliance with the Confirmatory Order, Standing Order 14-21 is in place prohibiting fuel movement prior to 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> after shutdown. This will remain in place until NRC makes a final determination on the LAR.
Pg. 7
QUESTIONS?
Pg. 8
Acronym List
- CFR Code of Federal Regulations
- FSAR Final Safety Analysis Report
- LAR License Amendment Request
- MPS2 Millstone Power Station, Unit 2
- RBCCW Reactor Building Closed Cooling Water system
- TS Technical Specifications Pg. 9
