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MONTHYEARML0603801992006-02-0909 February 2006 RAI Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors Project stage: RAI ML0729706052007-10-24024 October 2007 Exigent License Amendment Request Re Alternative Containment Analysis Methodology Supporting Information - Gothic Model Input Files Project stage: Other ML0731905532007-11-15015 November 2007 North Anna, Units 1 and 2, and Surry, Units 1& 2, Request for Extension of Completion Dates for Corrective Actions Regarding NRC Generic Letter 2004-02 Project stage: Request ML0734505942007-12-13013 December 2007 Approval of Extension of Completion Dates for Corrective Actions of Generic Letter 2004-02 Project stage: Other ML0806503142008-02-29029 February 2008 Kewaunee, NRC Generic Letter 2004-02 Supplemental Response, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0806505622008-02-29029 February 2008 Supplemental Response to NRC GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0806505632008-02-29029 February 2008 Supplemental Response to NRC GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0814306122008-05-22022 May 2008 Units 1 & 2 - NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors Request for Interim. Project stage: Request ML0814905722008-05-29029 May 2008 Request for Extension of Completion Dates for Generic Letter 2004-02 Corrective Actions Project stage: Other ML0818302472008-07-0101 July 2008 Request for Extension of Completion Dates for Generic Letter 2004-02 Corrective Actions Project stage: Other ML0832304692008-12-17017 December 2008 Request for Additional Information, GL 2004-02 Project stage: RAI ML1000700682010-02-0404 February 2010 Request for Additional Information Regarding Generic Letter 2004-02 Project stage: RAI ML1003314992010-03-0101 March 2010 Notice of Conference Call with Dominion Nuclear Connecticut, Inc., to Discuss Millstone Power Station, Unit Nos. 2 and 3 Generic Letter 2004-02 Supplemental Responses Project stage: Other ML1008204222010-03-26026 March 2010 Notice of Conference Call with Dominion Nuclear Connecticut, Inc. to Discuss Millstone Power Station, Unit Nos 2 and 3 Generic Letter 2004-02 Supplemental Responses Project stage: Other ML1009804152010-04-0808 April 2010 Draft Millstone GL2004-02 Supplemental Responses to Support Public Teleconference on 4/08 Project stage: Request ML1011705752010-05-0505 May 2010 Summary of Teleconference with DNC to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI ML1012506232010-05-24024 May 2010 Summary of Meeting with Dominion Nuclear Connecticut, Inc. (DNC) to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI ML1013700502010-05-25025 May 2010 Forthcoming Conference Call with Dominion Nuclear Connecticut, Inc. to Discuss Millstone Power Station, Unit Nos. 2 and 3 Generic Letter 2004-02 Supplemental Responses Project stage: Other ML1015305562010-06-0202 June 2010 Mps GL-04-002 Draft RAI Responses/Public Telecon Handouts Project stage: Request ML1015906482010-06-30030 June 2010 Summary of Meeting with Dominion Nuclear Connecticut, Inc., (DNC) to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI ML1018005132010-07-0101 July 2010 Notice of Forthcoming Public Meeting with Dominion Nuclear Connecticut, Inc. to Discuss Millstone Power Station, Unit No. 3 Generic Letter 2004-02 Supplemental Response Project stage: Meeting ML1019505052010-07-13013 July 2010 MPS3 RAI 6 Project stage: Request ML1019502842010-07-14014 July 2010 Notice of Forthcoming Public Teleconference with Dominion Nuclear Connecticut, Inc. to Discuss Millstone Power Station, Unit No. 3 Generic Letter 2004-02 Supplemental Response Project stage: Meeting ML1020102612010-07-29029 July 2010 Summary of July 13, 2010, Meeting with DNC to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI ML1022201102010-09-14014 September 2010 July 28, 2010, Summary of Teleconference with DNC to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI ML1026402102010-09-16016 September 2010 Response to Request for Additional Information Regarding Generic Letter 2004-02 Project stage: Request ML1031202422010-11-0808 November 2010 Notice of Teleconference with Dominion Nuclear Connecticut, Inc. to Discuss Millstone Power Station, Unit No. 3 Generic Letter 2004-02 Supplemental Response Project stage: Meeting ML1034706502010-12-13013 December 2010 Millstone 3 Draft Response to GL2004-02 RAI No. 6 Project stage: Request ML1034807622011-01-12012 January 2011 November 8, 2010 Summary of Teleconference W/ DNC to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI 2010-03-26
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Category:Slides and Viewgraphs
MONTHYEARML24135A0812024-05-14014 May 2024 5/16/2024, Annual Assessment Meeting for Millstone Power Station - NRC Presentation Slides ML23254A0562023-09-13013 September 2023 Presentation Material for 9/13/23 Pre-Submittal Meeting License Amendment Request to Support Cycle Reloads Using Framatome Gaia Fuel ML23073A0042023-03-14014 March 2023 Annual Assessment Meeting for Millstone Power Station - NRC Presentation Slides ML22277A8412022-10-18018 October 2022 Presentation Material for 10/18/22 Pre-Submittal Meeting Licensing Requests to Implement Framatome Gaia Fuel ML22243A0322022-09-0707 September 2022 Presentation Material for 9/7/22 Pre-Submittal Meeting Supplement to the Spent Fuel Pool Criticality Safety Analysis ML22236A0602022-08-29029 August 2022 Presentation Material for 8/29/22 Pre-Submittal Meeting Reactor Pressure Vessel Head Peening Follow-Up Exam Deferral ML22215A2872022-08-0909 August 2022 Presentation Material for 8/9/22 Pre-Submittal Meeting Containment Recirc Spray System Flow Test Alternative Request ML22082A1482022-03-23023 March 2022 Annual Assessment Meeting for Millstone Power Station - Webinar Presentation (NRC) ML21076A3322021-03-18018 March 2021 3/18/21 - Annual Assessment Meeting for Millstone Power Station - Presentation Slides ML20226A4112020-08-19019 August 2020 Presentation Material for 8/19/20 Pre-Submittal Meeting Biennial Emergency Preparedness Exercise Date Change Exemption Request ML20176A2762020-06-29029 June 2020 Presentation Material for 6/29/20 Pre-Submittal Meeting Proposed License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML20143A0772020-05-26026 May 2020 Presentation Material for 5/26/20 Pre-Submittal Meeting Steam Generator Examination Frequency Alternative Request ML19143A4722019-06-0303 June 2019 Presentation Material for 6/03/19 Pre-Submittal Meeting Integrated Leak Rate Test Extension License Amendment Request ML19128A4072019-05-0909 May 2019 Presentation Material for 5/09/19 Pre-Submittal Meeting TS Coolant Activity Changes, License Amendment Request ML19022A2432019-01-22022 January 2019 Presentation Material for 1/22/19 Pre-Submittal Meeting Fillet Weld Preheat Alternative Request ML18108A2072018-04-10010 April 2018 04/10/2018 Public Teleconference Meeting Slides MPS3 C Charging Pump ML18086A7742018-02-21021 February 2018 LOR Program Biennial Inspection 71111.11B Exam Overlap Issues ML17230A1282017-08-31031 August 2017 Connecticut, Inc. Presentation Slides for Pre-submittal Meeting on August 31, 2017 ML17200C9572017-07-18018 July 2017 Connecticut, Inc. Presentation Slides for Pre-submittal Meeting on July 18, 2017 ML16272A3472016-08-10010 August 2016 08/10/2016 - NEI Supplemental Material 1 (BADGER Measurement of Carborundum B-10 Areal Density) ML16272A3462016-08-10010 August 2016 08/10/2016 - NEI Supplemental Material 2 (Estimate of BADGER System Uncertainty Using Millstone Unit 1 2013) ML16125A0092016-05-0303 May 2016 2016/05/03 Presentation Slides for Pre-Submittal Teleconference for Realistic Large Break LOCA License Amendment Request ML15353A0022015-12-17017 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 ML15344A2942015-12-10010 December 2015 /12/10 Presentation Slides for Pre-Submittal Teleconference - Proposed LAR for Charging System in Response to Confirmatory Order EA-13-188 ML15314A1022015-10-20020 October 2015 2015/10/20 Pre-Submittal Teleconference Meeting Slides: Proposed License Amendment Request for EAL Changes, RCS Sampling Methodology Revision ML15198A3432015-06-22022 June 2015 2015/06/22 Pre-Submittal Teleconference Meeting Slides: LOCA Analyses Supporting MPS2 Upgrade to Areva Standard CE14 Htp Fuel Assembly ML15155B3692015-05-21021 May 2015 Connecticut, Inc. Presentation Slides for Pre-submittal Meeting on May 21, 2015 ML14176A0922014-06-25025 June 2014 6/25/2014, Dominion Public Meeting Presentation for Surry GMRS Profile ML13305A1442013-10-31031 October 2013 Rlbloca, Revision 3 - Post-Submittal Meeting, Areva, Oct. 31, 2013S, Lides IR 05000336/20110102011-08-0808 August 2011 EA-11-047, Millstone - Final Significance Determination for White Finding, W/Assessment Follow-up;Notice of Violation and Results of Regulatory Conference (NRC Special Inspection Report No. 05000336/2011010) ML1120005362011-07-19019 July 2011 EA-11-047, Millstone Regulatory Conference-July 19, 2011-Dominion Slides ML1120005282011-07-19019 July 2011 EA-11-047, Millstone Regulatory Conference-July 19, 2011 NRC Slides ML1118800642011-07-0707 July 2011 NRC Slides - Millstone/Neac Public Meeting on May 25, 2011 ML1118800332011-07-0707 July 2011 NRC Slides - Millstone 2011 Annual Assesssment Meeting ML1019505052010-07-13013 July 2010 MPS3 RAI 6 ML1014101592010-05-21021 May 2010 April 22, 2010 Summary of Meeting with Connecticut Nuclear Energy Advisory Council ML1005009822010-02-17017 February 2010 Spent Fuel Pool Criticality Presentation for Feb 17 Public Meeting ML0910506232009-04-23023 April 2009 NRC & Neac Meeting Concerning Millstone Annual Assessment, 2008 Reactor Oversight Process, Slides ML0909800642009-04-0808 April 2009 Slides for Millstone Annual Assessment Meeting, 2008 Reactor Oversight Process ML0911200622009-03-31031 March 2009 Post Exam Comment Miscellaneous References (Folder 1) ML0808801002008-04-0202 April 2008 Slides - NRC Annual Performance Assessment of Millstone, 2007 Reactor Oversight Process ML0808800832008-03-28028 March 2008 Slides - NRC & Neac Meeting Concerning Millstone Station Performance, 2007 Reactor Oversight Program ML0734708412007-12-11011 December 2007 Drop-In Visit from Dominion (Millstone) ML0730400332007-11-0101 November 2007 Public Meeting Slides for Meeting with Dominion Nuclear ML0729806642007-10-24024 October 2007 Meeting Presentation on Update on Generic Safety Issue 191 Plant Audits ML0707907302007-03-20020 March 2007 2006 NRC and Neac Public Meeting Slides to Discuss Millstone Station Annual Assessment Performance EOC 2006-07 ML0707907132007-03-20020 March 2007 2006 Millstone Annual Assessment Meeting Slides 2006-07 EOC ML0615106012006-05-23023 May 2006 EPRI HRA Users Group Review of Draft NUREG-1842 ML0608300792006-03-24024 March 2006 NRC Slides for Public Meeting with Nuclear Energy Advisory Council (Neac) to Discuss Cy 2005 Annual Assessment of Millstone Station ML0608202022006-03-23023 March 2006 NRC Slides for Public Meeting with Dominion Nuclear (Millstone) to Discuss CY2005 Performance 2024-05-14
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I Millstone Unit 3 , I NRC GL POTENTIAL IMPACT OF DEBRIS BLOCKAGE EMERGENCY RECIRCULATION DURING BASIS ACCIDENTS AT PRESSURIZEDJuly 13, 2010 1 MPS3 RAI NRC Staff Concern: The impact of the chemical precipitates could be significantly higher than was deduced from the Rig-89 test results. This is because Rig-89 head loss results were an order of magnitude lower than Rig-33 results}
which .the NRC staff considers to be more representative of the plant condition from the perspective of bed formation.
Filtration of chemicals on a less porous bed generally leads to significantly higher head losses. As a result}
NRC staff does not consider it appropriate to add Rig-89 chemical effects differential head I loss to the Rig-33 nonchemical head loss result. Nor does the lNRC staff accept the licensee's arguments regarding why Rig-33 result is not representative of the plant. 2 Dominion Rig 89 head loss is design basis head loss for MPS3 and is conservative. Rig 33 is not prototypical of the MPS3 containment. Head loss with chemical precipitants will not challenge the significant existing NPSH margins. I Significant Margins assure that strainer will provide long-term recirculation even if prototypical Rig 33 results are considered.
3 Rig Conservative debris preparation and addition methodology identical to that used for Rig 33. No continuous stirrer to artificially keep debris in *suspension. Submergence of test header section was prototypical of MPS3 containment. Minimal surfaces other than strainer for debris settling ensured a conservatively high amount of debris attached to the strainer. Chemical additions of both calcium and aluminum were a conservative simulation of MPS3 containment.
4 Rig Non-prototypical for MPS3 Containment -Low submergence (6 inches) in test rig versus 5 ft submergence in containment-increasing the susceptibility to air evolution in the debris bed. -Continuous stirring in test rig versus no significant turbulence near strainer (located in containment annulus) as shown by CFD analysis. -River water used in test rig versus deionized water in containment which may have increased head loss somewhat by adding some bacteria or suspended solids. 5 Related Conservatisms
- Debris Bed -10% margin on coatings particulate (2.1 ft 3 margin) -Unqualified coating makes up 1/3 of total particulate load. -Fibrous debris prepared as "single-fine".
-Debris transport assumes all debris arrives at strainer including chemical precipitants.
- Strainer Area -Installed strainer area (5200 ft 2) exceeds tested area (4290 ft-), 6 MPS3 Containment Velocity [ft's] Velocity[ftls] 0.28+ 0.36 0.26 0.32 0.24 0.2 8 0.22 0.24 0.20 0.20 0.18 0.16 0.16 0.12 0.14 0.08 0.11 0.04 0.10 0.00 0.08 0.06 0.04 0.02 0.00 a) Color Range 0.0 100.40 ftls b) Color Range 0
.0 100.28 ftls i !-* " i I Vdodty eo.tlHIn Iftlsl 3 1.1les A....n c..t**mt'" J1IIlor Lenl_ori.N, -lW, .. 4_. North p..w.
Scale: 01 N.T.S. WiU.. _J Proj"" OO3oU23A Do'e:
- 12. 2007 7 Factors for MPS3 Plant
- Strainer Size is 20% larger than tested size. Large Refueling Water Storage Tank (RWST): 1.2 million gallons. : Modification implemented in 2007 to delay I pump start to provide additional I
- Strainer submergence is 4.9 ft at 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Required NPSH for RSS pumps is 4 ft. Lowest available NPSH for RSS pumps is 22.9 8 Margins include Rig 33 non-chemical head loss (5.1 psi at 104°F) which bounds Rig 33 and Rig 89 chemical effects head loss test results after 30 days. NPSH margin (4 ft NPSH required)
- 30 days: 27 -Strainer Flashing
- 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />s: 4 ft
- 30 days: 14 -Suction Line Flashing
- 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />s: 10 ft
- Calcium concentration in the MPS3 containment is negligible. Without calcium, one of the two major components for chemical precipitant head loss is not present. 10 Rig 33 Chemical Test Head 150 .-135 I e 120 s-* i .Q u.. i I e s Millstone 3 Rig 33 Chemical Effects Test iii , , -PDT 105 90 75 60 1 45 I I 1.. 1. 1 .. I iii i I __ L __ I I I :I*:I I: '0 I I I I 1 I I I I I 1 I -FIowrate -K:P ReBUts -CalcUatedCa Concemtion, ii 10 I I 9 1 I 8 I 7 6 ,!
- 5 I I 'a 4 I I:z: 3 2 06I04I08 16104108 26104108 01105108 06J05I08 11105108 16.<l5J08 0:00 0:00 0:00 0:00 0:00 0:00 0:00 0:00 0:00 Time (standard)
Figure 26 Head Loss and Ca Concentration for the Whole Test 11 Rig 33 Chemical Head Loss One test was run in Rig 33 with chemicals (in Apr-May 2008) Identical debris addition methodology to Rig 33 and Rig 89.
Non-chemical head loss was 5.3 psi as compared to 5.1 psi for strainer sizing test. Deionized water was used instead of river water. One aluminum addition was made prior to any calcium additions-no noticeable effect on head Immediate head loss peaks occurred during fiber additions and calcium Overall, head loss changed from a steady value of 5.3 psi prior to any chemical additions to value of 5.5 psi after 10 calcium additions and 1 aluminum addition. The head loss drifted down to 3.8 psi before the test was stopped ( > 30 Head loss from the first to the last calcium addition decreased-possibly due to migration air out of the debris bed offsetting any rise due to chemical Debris bed was intact at end of test (no bore holes or End of Rig 89 head loss was 2 psia and end of Rig 33 chemical test head loss was 3.8 only a factor of 2 12 Rig 89 submergence is prototypical of MPS3 containment.
Rig 33 submergence is too low and adversely affected head loss results. Head loss with chemical precipitants is conservatively bounded by Rig 89 results which showed a maximum of 2.2 psid at 104°F. Significant margins assure that strainer will provide long-term recirculation even if prototypical Rig 33 results are considered.
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