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| | number = ML15353A002 | | | number = ML15353A002 |
| | issue date = 12/17/2015 | | | issue date = 12/17/2015 |
| | title = Millstone, Unit 2, 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 | | | title = /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 |
| | author name = Craft W D | | | author name = Craft W |
| | author affiliation = Dominion, Dominion Nuclear Connecticut, Inc | | | author affiliation = Dominion, Dominion Nuclear Connecticut, Inc |
| | addressee name = Guzman R V | | | addressee name = Guzman R |
| | addressee affiliation = NRC/NRR/DORL/LPLI-1 | | | addressee affiliation = NRC/NRR/DORL/LPLI-1 |
| | docket = 05000336 | | | docket = 05000336 |
| | license number = DPR-065 | | | license number = DPR-065 |
| | contact person = Guzman R V | | | contact person = Guzman R |
| | case reference number = EA-13-188, MF7126 | | | case reference number = EA-13-188, MF7126 |
| | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs | | | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs |
| Line 18: |
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| =Text= | | =Text= |
| {{#Wiki_filter:}} | | {{#Wiki_filter: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 |
| | * Scope of LAR |
| | * Schedule Pg. 2 |
| | |
| | Purpose of LAR |
| | * LAR required by Confirmatory Order EA-13-188 (8/26/15) |
| | 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 hours 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 hours 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 |
| | * DNC Dominion Nuclear Connecticut |
| | * 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 |
| | * Scope of LAR |
| | * Schedule Pg. 2 |
| | |
| | Purpose of LAR |
| | * LAR required by Confirmatory Order EA-13-188 (8/26/15) |
| | 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 hours 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 hours 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 |
| | * DNC Dominion Nuclear Connecticut |
| | * 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}} |
Letter Sequence Meeting |
|---|
|
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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
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Teleconference Memo to File: Summary of December 17, 2015 - Pre-submittal Call with the NRC Related to Confirmatory Item IV.5
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2015-12-17
[Table View] |
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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
