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MONTHYEARML16266A5462016-12-21021 December 2016 Summary of Results of Flooding Hazard Reevaluation Report for Millstone Power Station Units 2 and 3 Project stage: Request ML16308A2262016-12-21021 December 2016 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(F) Information Request - Flood-Causing Mechanism Reevaluation Project stage: Other ML17187A1692017-06-28028 June 2017 Mitigating Strategies Assessment (MSA) Report) Project stage: Other 2016-12-21
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Category:- No Document Type Applies
MONTHYEARML21077A1362021-03-18018 March 2021 Temporary Instruction 2515/194 Inspection Documentation Request ML19011A1712019-01-0404 January 2019 Enclosures 1 to 3 - EAL Scheme Revisions Enclosure Summary, Discussion of Change and Mps EAL Scheme Revisions-Supporting Documents ML16266A5462016-12-21021 December 2016 Summary of Results of Flooding Hazard Reevaluation Report for Millstone Power Station Units 2 and 3 ML15231A3642015-05-27027 May 2015 FOIA/PA-2014-0204 - Resp 1 - Final, Group a ML15065A2382015-02-0606 February 2015 Acord Certificate of Liability Insurance ML14358A3182014-12-22022 December 2014 FOIA/PA-2014-0508 - Resp 1 - Partial. Group a (Records Being Released in Their Entirety) ML14128A0412014-04-30030 April 2014 Attachment 2 - 2013 Radioactive Effluent Release Report - Volume 2 ML14041A1782014-02-0606 February 2014 Attachment 1 - Response to Request for Additional Information for Alternative Request IR-3-17, for ASME Section XI for Repair/Replacement of Class 3 Service Water System Valves ML14041A1792014-02-0606 February 2014 Attachment 3 - Examination of Millstone Unit 3 Service Water Valves for Dealloying ML13364A2832013-12-30030 December 2013 Announcement of 2014 Generic Fundamentals Examination Administration Dates-Letter Dated Dec 30, 2013 ML12093A0832012-04-0202 April 2012 Notice of Public Meeting - April 19, 2012 ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML12032A2252012-01-25025 January 2012 Attachments 4-6 to 11-687, Regarding License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3 ML1123405052011-08-21021 August 2011 Verbal Authorization, Relief Request RR-04-12, of Millstone 2 Temporary Non-Code Compliant Condition of Emergency Diesel Generator Supply Piping in the Service Water System ML1123404642011-08-20020 August 2011 MPS2 RR RAI Response ML1117502192011-06-22022 June 2011 NRC Inspection Findings Related to Closed Cooling Water Systems (1/1/2004 to 6/22/2011) ML1034706502010-12-13013 December 2010 Millstone 3 Draft Response to GL2004-02 RAI No. 6 ML1015305562010-06-0202 June 2010 Mps GL-04-002 Draft RAI Responses/Public Telecon Handouts ML1011904172010-04-22022 April 2010 Westinghouse Electric Co., LLC, LTR-SGMP-10-50 NP-Attachment Assessment of the Effect of the Location of the Bottom of the Expansion Transition on H. ML1009804152010-04-0808 April 2010 Draft Millstone GL2004-02 Supplemental Responses to Support Public Teleconference on 4/08 ML1019304602010-03-25025 March 2010 List of Historical Leaks and Spills at Us Commercial Nuclear Power Plants ML0933507512010-01-14014 January 2010 Temporary Instruction 2515/180, Managing Fatigue ML0813006902008-04-17017 April 2008 Meeting with Neac to Discuss Millstone, Attendance List ML0813006872008-04-17017 April 2008 Annual Assessment Meeting Attendance List ML0732400242007-10-25025 October 2007 Examples of Max Thermal Power License Conditions ML0729502402007-10-10010 October 2007 Siren Milestones ML0730400302007-10-0101 October 2007 Sign-In Roster for Public Meeting with Dominion Nuclear ML0726301142007-09-14014 September 2007 / P. Paquin Ltr Amendment to Certificate of Compliance No. 9208 for the Model No. 10-142B Package (TAC L24117)/S121170 ML0726303192007-09-14014 September 2007 P. Paquin Ltr Amendment to Certificate of Compliance No. 6574 for the Model No. 3-82B Package (TAC L24116)/ Register User List ML0713102392007-04-12012 April 2007 Enclosure 6: List of Proposed Generic Level 1 Milestones ML0634705992006-12-14014 December 2006 Plant Service List ML0701805992006-07-26026 July 2006 Report of Investigation, Case 1-2006-004, Millstone Nuclear Power Plant, Units 2 and 3: Discrimination Against a Senior ECP Investigator for Having Engaged in Protected Activities ML0610704982006-04-17017 April 2006 PI&R Team Inspection Required Documents ML0622700642006-03-29029 March 2006 Statement of Attorney General Richard Blumenthal of Connecticut Regarding the NRC Annual Safety Assessment Public Meeting at Millstone Nuclear Power Station March 29, 2006 ML0614301522006-03-29029 March 2006 Sign-in Sheet for Public Meeting Between NRC and Connecticut Nuclear Energy Advisory Council (Neac) to Discuss Millstone Station'S Annual Assessment for CY2005 ML0527000442005-09-21021 September 2005 Attachment 10, FAQ Log 9/21/05 ML0514602372005-05-20020 May 2005 Event Response Roster ML0514505132005-05-20020 May 2005 Branch 6, Management Directive 8.3 Check Sheet for 3/6/04 Millstone Unit 2 Turbine Trip ML0514505172005-05-20020 May 2005 Branch 6, Management Directive 8.3 Check Sheet for 3/15/04 Millstone Unit 2 Turbine Trip ML0514602232005-05-20020 May 2005 Region I Event Chronology ML0514602362005-05-20020 May 2005 Region I Event Chronology ML0514602602005-05-20020 May 2005 Handwritten Notes - 7 ML0516000592005-05-18018 May 2005 Attendance Sign in Sheet for Public Meeting Between NRC and Nuclear Energy Advisory Council (Neac) Ref: April 17, 2005 Event ML0513005592005-05-0505 May 2005 Enclosure 5, Response to Requests for Additional Information Replacement Discussion of Changes ML0513005562005-05-0505 May 2005 Enclosure 4, Response to Requests for Additional Information Marked Up Discussion of Changes ML0513005442005-05-0505 May 2005 Attachment 2, Response to Requests for Additional Information Re Proposed Technical Specifications Changes Associated with Nuclear Facility Quality Assurance Program Description ML0513005392005-05-0505 May 2005 Attachment 1, Response to Requests for Additional Information on Nuclear Facility Quality Assurance Program Description ML0514602222005-04-19019 April 2005 Forced Outage Schedule, Cold Shutdown ML0514602682005-04-17017 April 2005 Notes from 04/17/2005 Millstone 3 Alert ML0514602742005-04-17017 April 2005 Unit 3 Control Room OPS 2021-03-18
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Millstone Power Station, Unit 2 Table 1. Current Design Basis Flood Hazards for Use in the MSA Mechanism Stillwater Waves/ Design Basis Reference Elevation Runup Hazard Elevation Local Intense Precipitation 14.5 ft Minimal 14.5 ft FHRR Table 1.2-1 NGVD29 NGVD29 Streams and Rivers No Impact No Impact No Impact FHRR Table 1.2-1 on the Site on the Site on the Site Identified Identified Identified Failure of Dams and Onsite Water Control/Storage Structures Not included Not included Not included FHRR Sections 2.3.3 & 3.3 in DB in DB in DB Storm Surge Storm Surge (standing wave) 26.5 ft Not 26.5 ft FHRR Sections 1.5 and 3.4 within the Intake Structure for NGVD29 applicable NGVD29 Unit 2 Storm Surge at the Powerblock 18.1 ft 7.0 ft 25.1 ft FHRR Section 3.9 and FHRR Table NGVD29 NGVD29 3.0-1 FHRR Table 1.2-1 Seiche No Impact No Impact No Impact FHRR Table 1.2-1 on the Site on the Site on the Site Identified Identified Identified Tsunami Not included Not included Not included FHRR Table 1.2-1 in DB in DB in DB Ice-Induced Flooding No Impact No Impact No Impact FHRR Table 1.2-1 on the Site on the Site on the Site Identified Identified Identified
Millstone Power Station, Unit 2 Table 1. Current Design Basis Flood Hazards for Use in the MSA Mechanism Stillwater Waves/ Design Basis Reference Elevation Runup Hazard Elevation Channel Migrations/Diversions No Impact No Impact No Impact FHRR Table 1.2-1 on the SIte on the Site on the Site Identified Identified Identified Note 1: Reported values are rounded to the nearest one-tenth of a foot.
Millstone Power Station, Unit 2 Table 2. Reevaluated Flood Hazards for Flood-Causing Mechanisms for Use in the MSA Mechanism Stillwater Waves/ Reevaluated Reference Elevation Runup Hazard Elevation Local Intense Precipitation 17.5 ft Minimal 17.5 ft FHRR Section 3.1 NGVD29 NGVD29 Streams and Rivers 11.2 ft Not 11.2 ft FHRR Section 2.2 NGVD29 applicable NGVD29 Storm Surge Under Under Under Review Review Review Tsunami 14.7 ft Not 14.7 ft FHRR Section 2.6 NGVD29 applicable NGVD29 Note 1: The licensee is expected to develop flood event duration parameters and applicable flood associated effects to conduct the MSA. The staff will evaluate the flood event duration parameters (including warning time and period of inundation) and flood associated effects during its review of the MSA.
Note 2: Reevaluated hazard mechanisms bounded by the current design basis (see Table 1) are not included in this table.
Note 3: Reported values are rounded to the nearest one-tenth of a foot.
Millstone Power Station, Unit 3 Table 1. Current Design Basis Flood Hazards for Use in the MSA Mechanism Stillwater Waves/ Design Basis Reference Elevation Runup Hazard Elevation Local Intense Precipitation RWST/SIL Valve Enclosure 24.9 ft Minimal 24.9 ft FHRR Table 1.2-3 and Table 3.0-3 NGVD29 NGVD29 Demineralized Water Storage 24.9 ft Minimal 24.9 ft FHRR Table 1.2-3 Tank Block House NGVD29 NGVD29 Fuel Building 24.9 ft Minimal 24.9 ft FHRR Table 1.2-3 NGVD29 NGVD29 Auxiliary Building Door A-24-6 24.9 ft Minimal 24.9 ft FHRR Table 3.0-3 NGVD29 NGVD29 Engineered Safety Features 24.9 ft Minimal 24.9 ft FHRR Table 1.2-3 Building NGVD29 NGVD29 Hydrogen Recombiner Building 24.9 ft Minimal 24.9 ft FHRR Table 1.2-3 NGVD29 NGVD29 Main Steam Valve Building 24.9 ft Minimal 24.9 ft FHRR Table 1.2-3 NGVD29 NGVD29 Emergency Generator Enclosure 24.3 ft Minimal 24.3 ft FHRR Table 1.2-3 NGVD29 NGVD29 Auxiliary Building Door A-24-1 24.9 ft Minimal 24.9 ft FHRR Table 3.0-3 NGVD29 NGVD29 Control Building 24.3 ft Minimal 24.3 ft FHRR Table 1.2-3 NGVD29 NGVD29 Streams and Rivers No Impact No Impact No Impact FHRR Table 1.2-2 on the Site on the Site on the Site Identified Identified Identified
Millstone Power Station, Unit 3 Table 1. Current Design Basis Flood Hazards for Use in the MSA Mechanism Stillwater Waves/ Design Basis Reference Elevation Runup Hazard Elevation Failure of Dams and Onsite Water Control/Storage Structures Not included Not included Not included FHRR Sections 2.3.3 & 3.3 in DB in DB in DB Storm Surge Storm Surge at Seaward Wall of 19.7 ft 21.5 ft 41.2 ft FHRR Section 3.9 Intake Structure for Unit 3 NGVD29 NGVD29 Storm Surge at Powerblock 19.7 ft 4.1 ft 23.8 ft FHRR Section 1.5 NGVD29 NGVD29 FHRR Table 1.2-2 Seiche No Impact No Impact No Impact FHRR Table 1.2-2 on the Site on the Site on the Site Identified Identified Identified Tsunami Not included Not included Not included FHRR Table 1.2-2 in DB in DB in DB Ice-Induced Flooding No Impact No Impact No Impact FHRR Table 1.2-2 on the Site on the Site on the Site Identified Identified Identified Channel Migrations/Diversions No Impact No Impact No Impact FHRR Table 1.2-2 on the SIte on the Site on the Site Identified Identified Identified Note 1: Reported values are rounded to the nearest one-tenth of a foot.
Millstone Power Station, Unit 3 Table 2. Reevaluated Flood Hazards for Flood-Causing Mechanisms for Use in the MSA Mechanism Stillwater Waves/ Reevaluated Reference Elevation Runup Hazard Elevation Streams and Rivers 11.2 ft Not 11.2 ft FHRR Section 2.2 NGVD29 applicable NGVD29 Storm Surge Under Under Under Review Review Review Tsunami 14.7 ft Not 14.7 ft FHRR Section 2.6 NGVD29 applicable NGVD29 Note 1: The licensee is expected to develop flood event duration parameters and applicable flood associated effects to conduct the MSA. The staff will evaluate the flood event duration parameters (including warning time and period of inundation) and flood associated effects during its review of the MSA.
Note 2: Reevaluated hazard mechanisms bounded by the current design basis (see Table 1) are not included in this table.
Note 3: Reported values are rounded to the nearest one-tenth of a foot.