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Category:Letter
MONTHYEARBVY 24-005, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-01-30030 January 2024
Report of Investigation Pursuant to 10 CFR 20, Appendix G
BVY 24-004, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-01-23023 January 2024
Report of Investigation Pursuant to 10 CFR 20, Appendix G
BVY 24-003, Nuclear Onsite Property Damage Insurance2024-01-0404 January 2024
Nuclear Onsite Property Damage Insurance
BVY 24-001, Pre-Notice of Disbursement from Decommissioning Trust2024-01-0202 January 2024
Pre-Notice of Disbursement from Decommissioning Trust
BVY 23-030, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-12-20020 December 2023
Report of Investigation Pursuant to 10 CFR 20, Appendix G
BVY 23-029, Proof of Financial Protection2023-12-12012 December 2023
Proof of Financial Protection
BVY 23-028, Pre-Notice of Disbursement from Decommissioning Trust2023-11-28028 November 2023
Pre-Notice of Disbursement from Decommissioning Trust
BVY 23-027, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-11-21021 November 2023
Report of Investigation Pursuant to 10 CFR 20, Appendix G
BVY 23-026, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-11-13013 November 2023
Report of Investigation Pursuant to 10 CFR 20, Appendix G
BVY 23-025, Pre-Notice of Disbursement from Decommissioning Trust2023-11-0202 November 2023
Pre-Notice of Disbursement from Decommissioning Trust
BVY 23-023, License Amendment Request Addition of License Condition 3.K, License Termination Plan; Proposed Change No. 3172023-10-10010 October 2023
License Amendment Request Addition of License Condition 3.K, License Termination Plan; Proposed Change No. 317
IR 07200059/20234012023-10-0505 October 2023
Independent Spent Fuel Storage Installation Security Inspection Report 07200059/2023401
BVY 23-022, Pre-Notice of Disbursement from Decommissioning Trust2023-08-23023 August 2023
Pre-Notice of Disbursement from Decommissioning Trust
IR 05000271/20230012023-08-15015 August 2023
Northstar Nuclear Decommissioning Company, Llc., Vermont Yankee Nuclear Power Station, - NRC Inspection Report 05000271/2023001
BVY 23-021, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-08-0202 August 2023
Report of Investigation Pursuant to 10 CFR 20, Appendix G
BVY 23-020, Pre-Notice of Disbursement from Decommissioning Trust2023-08-0202 August 2023
Pre-Notice of Disbursement from Decommissioning Trust
BVY 23-019, Update to 2022 Radiological Effluent Release Report2023-07-24024 July 2023
Update to 2022 Radiological Effluent Release Report
BVY 23-018, Update to Nuclear Onsite Property Damage Insurance2023-07-12012 July 2023
Update to Nuclear Onsite Property Damage Insurance
BVY 23-017, Pre-Notice of Disbursement from Decommissioning Trust2023-06-29029 June 2023
Pre-Notice of Disbursement from Decommissioning Trust
BVY 23-015, Report of Investigation Pursuant to 1O CFR 20, Appendix G2023-06-0505 June 2023
Report of Investigation Pursuant to 1O CFR 20, Appendix G
BVY 23-016, 10 CFR 72.48 Report2023-06-0505 June 2023
10 CFR 72.48 Report
BVY 23-014, Pre-Notice of Disbursement from Decommissioning Trust2023-05-31031 May 2023
Pre-Notice of Disbursement from Decommissioning Trust
BVY 23-013, 2022 Radiological Environmental Operating Report2023-05-10010 May 2023
2022 Radiological Environmental Operating Report
BVY 23-011, 2022 Radiological Effluent Release Report2023-05-10010 May 2023
2022 Radiological Effluent Release Report
BVY 23-012, Pre-Notice of Disbursement from Decommissioning Trust2023-05-0202 May 2023
Pre-Notice of Disbursement from Decommissioning Trust
ML23117A2172023-05-0101 May 2023
Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment
BVY 23-009, 2022 Individual Monitoring NRC Form 5 Report2023-04-24024 April 2023
2022 Individual Monitoring NRC Form 5 Report
BVY 23-008, Pre-Notice of Disbursement from Decommissioning Trust2023-04-0606 April 2023
Pre-Notice of Disbursement from Decommissioning Trust
BVY 23-007, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-03-29029 March 2023
Report of Investigation Pursuant to 10 CFR 20, Appendix G
BVY 23-006, Status of Decommissioning and Spent Fuel Management Fund for Year Ending 20222023-03-29029 March 2023
Status of Decommissioning and Spent Fuel Management Fund for Year Ending 2022
BVY 23-005, Nuclear Onsite Property Damage Insurance2023-03-13013 March 2023
Nuclear Onsite Property Damage Insurance
BVY 23-004, Pre-Notice of Disbursement from Decommissioning Trust2023-03-0202 March 2023
Pre-Notice of Disbursement from Decommissioning Trust
ML22361A1022023-02-24024 February 2023
Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities
IR 05000271/20220022023-02-22022 February 2023
Northstar Nuclear Decommissioning Company, LLC, Vermont Yankee Nuclear Power Station - NRC Inspection Report No. 05000271/2022002
BVY 23-003, Pre-Notice of Disbursement from Decommissioning Trust2023-01-31031 January 2023
Pre-Notice of Disbursement from Decommissioning Trust
BVY 22-030, Documentary Evidence of Performance Bond2022-12-30030 December 2022
Documentary Evidence of Performance Bond
ML22347A2792022-12-21021 December 2022
Independent Spent Fuel Storage Installation Security Inspection Plan Dated December 21, 2022
IR 05000271/20224012022-12-15015 December 2022
NRC Inspection Report No. 05000271/2022401, Northstar Nuclear Decommissioning Company, LLC, Vermont Yankee Nuclear Power Station, Vernon, Vermont (Letter Only)
BVY 22-028, Re Proof of Financial Protection2022-11-28028 November 2022
Re Proof of Financial Protection
BVY 22-027, Bvy 22-027; Pre-Notice of Disbursement from Decommissioning Trust for Vermont Yankee Nuclear Power Station2022-11-11011 November 2022
Bvy 22-027; Pre-Notice of Disbursement from Decommissioning Trust for Vermont Yankee Nuclear Power Station
BVY 22-026, Pre-Notice of Disbursement from Decommissioning Trust2022-10-31031 October 2022
Pre-Notice of Disbursement from Decommissioning Trust
ML22273A1492022-10-0404 October 2022
Review of Decommissioning Funding Status 2022
BVY 22-025, Pre-Notice of Disbursement from Decommissioning Trust2022-10-0404 October 2022
Pre-Notice of Disbursement from Decommissioning Trust
BVY 22-023, Pre-Notice of Disbursement from Decommissioning Trust2022-09-0101 September 2022
Pre-Notice of Disbursement from Decommissioning Trust
BVY 22-022, Report of Investigation Pursuant to 10 CFR 20, Appendix G2022-08-22022 August 2022
Report of Investigation Pursuant to 10 CFR 20, Appendix G
BVY 22-021, Report of Investigation Pursuant to 10 CFR 20, Appendix G2022-08-16016 August 2022
Report of Investigation Pursuant to 10 CFR 20, Appendix G
BVY 22-020, Pre-Notice of Disbursement from Decommissioning Trust2022-08-0101 August 2022
Pre-Notice of Disbursement from Decommissioning Trust
IR 05000271/20220012022-08-0101 August 2022
NRC Inspection Report No. 05000271/2022001, Northstar Nuclear Decommissioning Company, LLC, Vermont Yankee Nuclear Power Station, Vernon, Vermont
BVY 22-019, Pre-Notice of Disbursement from Decommissioning Trust2022-07-0606 July 2022
Pre-Notice of Disbursement from Decommissioning Trust
BVY 22-013, Notification of Revised Decommissioning Cost Estimate2022-06-17017 June 2022
Notification of Revised Decommissioning Cost Estimate
2024-01-04
[Table view]
Category:Report
MONTHYEARML21075A1772021-03-15015 March 2021
Response to Vermont Yankee on the State of Vermont Comments on the Review of the Draft Final SER and EA for 20.2002 Alternate Disposal Request
BVY 20-026, Defueled Safety Analysis Report, Revision 22020-09-23023 September 2020
Defueled Safety Analysis Report, Revision 2
BVY 19-020, 72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 20192019-06-20020 June 2019
72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 2019
ML19198A2522019-06-20020 June 2019
Alternate Disposal Request - Rail Shipments (License DPR-28, Docket No. 50-271)
ML16176A3392016-10-28028 October 2016
Decommissioning Lessons Learned Report and Transmittal Memorandum
ML15266A4302015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 24, Flow Diagram Instrument Air System. Sheet 2
BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191595, Control Room Bldg. Ext. Wall Elevs.-M.2015-09-0101 September 2015
Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191595, Control Room Bldg. Ext. Wall Elevs.-M.
ML15266A4452015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191163, Rev. 51, Flow Diagram Fire Protection System Inner Loop. Sheet 2
ML15266A4442015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191163, Rev. 51, Flow Diagram Fire Protection System Inner Loop. Sheet 1
ML15266A4402015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 8
ML15266A4362015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 7
ML15266A4352015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 6
ML15266A4342015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 5
ML15266A4332015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 4
ML15266A4322015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 31, Flow Diagram Instrument Air System. Sheet 3
BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 39, 480V Aux. One Line Diagram MCC-9B, 9D, 89A. Sheet 22015-09-0101 September 2015
Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 39, 480V Aux. One Line Diagram MCC-9B, 9D, 89A. Sheet 2
ML15266A4292015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 37, Flow Diagram Instrument Air System. Sheet 1
ML15266A4282015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191159, Rev. 100, Flow Diagram Service Water System. Sheet 2
ML15266A4272015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191159, Rev. 92, Flow Diagram Service Water System. Sheet 1
ML15266A4262015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191152, Rev. 14, General Arrangement Radwaste Building Section.
ML15266A4252015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191151, Rev 19, General Arrangement Radwaste Building Plans.
ML15266A4242015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191150, Rev. 20, General Arrangement Reactor Building Section.
ML15266A4232015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191149, Rev. 27, General Arrangement Reactor Building Plans Sheet 2.
ML15266A4222015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191148, Rev. 23, General Arrangement Reactor Building Plans Sheet 1.
ML15266A2722015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report - List of Effective Pages
BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 24V DC Neutron Monitoring & 120V AC RPS One Line Diagram, Sheet 52015-09-0101 September 2015
Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 24V DC Neutron Monitoring & 120V AC RPS One Line Diagram, Sheet 5
ML15266A2832015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, DSAR Drawing List
BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191529, Reactor Building Reactor Vessel Pedestal Mat - M&R.2015-09-0101 September 2015
Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191529, Reactor Building Reactor Vessel Pedestal Mat - M&R.
ML15266A2712015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, DSAR Changes
ML15266A2732015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, UFSAR to DSAR Conversion Matrix
ML15267A6092015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 125V DC One Line Diagram, Sheet 3
BVY 15-046, Rev. 0 to Defueled Safety Analysis Report, Drawing G-200347, Circulating Water System Aerating Structure-MAS & Reinf.2015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-200347, Circulating Water System Aerating Structure-MAS & Reinf.
ML15267A6612015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191595, Control Room Bldg. Ext. Wall Elevs.-M.
ML15267A6592015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191592, Control Room Building Fl Plan El 248.50 & Fdn Plan-R, Sheet 1
ML15267A6562015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191529, Reactor Building Reactor Vessel Pedestal Mat - M&R.
ML15267A6542015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191483, Reactor Building Foundation Mat Plan - M&R.
ML15267A6512015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191463, Circulating Water System Discharge Structure Reinf, Sheet 2
ML15267A6492015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191461, Circulating Water System Discharge Structure - Sections, Sheet 1
ML15267A6472015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191453, Circulating Water System Intake Structure-M, Sheet 3
ML15267A6452015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191452, Circulating Water System Intake Structure-V, Sheet 2
ML15267A6412015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191451, Circulating Water System Intake Structure-M, Sheet 1
ML15267A6112015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 24V DC Neutron Monitoring & 120V AC RPS One Line Diagram, Sheet 5
ML15267A6102015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 120/240V Vital AC and Instrument AC One Line Diagram, Sheet 4
BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, Rev. 72, 125VDC One Line Wiring Diagram. Sheet 12015-09-0101 September 2015
Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, Rev. 72, 125VDC One Line Wiring Diagram. Sheet 1
ML15267A6082015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 125V DC One Line Diagram, Sheet 2
ML15267A6072015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, Rev. 72, 125VDC One Line Wiring Diagram. Sheet 1
ML15267A6062015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 39, 480V Aux. One Line Diagram MCC-9B, 9D, 89A. Sheet 2
ML15267A6052015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 30, 480V Aux. One Line Diagram Swgr BUS-9, MCC-9A, 9C. Sheet 1
BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191461, Circulating Water System Discharge Structure - Sections, Sheet 12015-09-0101 September 2015
Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191461, Circulating Water System Discharge Structure - Sections, Sheet 1
BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191483, Reactor Building Foundation Mat Plan - M&R.2015-09-0101 September 2015
Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191483, Reactor Building Foundation Mat Plan - M&R.
2021-03-15
[Table view]
Category:Miscellaneous
MONTHYEARML21075A1772021-03-15015 March 2021
Response to Vermont Yankee on the State of Vermont Comments on the Review of the Draft Final SER and EA for 20.2002 Alternate Disposal Request
BVY 19-020, 72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 20192019-06-20020 June 2019
72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 2019
ML16176A3392016-10-28028 October 2016
Decommissioning Lessons Learned Report and Transmittal Memorandum
BVY 15-049, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask2015-08-19019 August 2015
Submittal of 10 CFR 71.95 Report Involving 8-120B Cask
BVY 15-018, Transmittal of Biennial 10 CFR 50.59 Report2015-03-0202 March 2015
Transmittal of Biennial 10 CFR 50.59 Report
BVY 14-085, Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb)2014-12-19019 December 2014
Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb)
BVY 14-011, Revision to Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima ...2014-02-25025 February 2014
Revision to Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima ...
BVY 13-090, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask2013-10-0202 October 2013
Submittal of 10 CFR 71.95 Report Involving 8-120B Cask
BVY 12-081, Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-21021 November 2012
Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident
ML12160A3732012-06-11011 June 2012
Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to the Fukushima Daichii Nuclear Plant Accident TAC No. ME8747)
ML1127000692011-09-26026 September 2011
Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants
ML1108712502011-03-24024 March 2011
BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages
ML1012704392010-05-0505 May 2010
Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants
BVY 07-079, Update of Aging Management Program Audit Q&A Database2007-11-14014 November 2007
Update of Aging Management Program Audit Q&A Database
BVY 07-004, Emergency Response Data System (ERDS) Data Point Library Update2007-06-21021 June 2007
Emergency Response Data System (ERDS) Data Point Library Update
ENOC-07-00002, Units 1, 2 & 3; Pilgrim and Vermont - Fitness-for-Duty Program Performance Report for the Period July 2006 - December 20062007-02-28028 February 2007
Units 1, 2 & 3; Pilgrim and Vermont - Fitness-for-Duty Program Performance Report for the Period July 2006 - December 2006
L-87-005, Various CRS 08/09/2005 to 02/08/20072007-02-0808 February 2007
Various CRS 08/09/2005 to 02/08/2007
ML0706703802007-02-0101 February 2007
NDE Reports 07-001 Thru 07-008
ML0701705912007-01-0909 January 2007
VYNPS - SEIS Web Reference - Us Census Glossary
ML0701701982006-12-15015 December 2006
VYNPS - SEIS Web Reference - Connecticut River Migratory Fish Counts 1967-2005
ML0629204232006-10-0303 October 2006
(E-Mail) Cooling Tower Report for VY
ML0629203422006-09-18018 September 2006
(E-Mail) Air Emissions Inventory Report for 2005 and MSDS for Nalco H-550
ENOC-06-00018, Stations - Fitness-for-Duty Program Performance Report for the Period January 2006 - June 20062006-08-29029 August 2006
Stations - Fitness-for-Duty Program Performance Report for the Period January 2006 - June 2006
BVY 06-068, Cycle 25 Startup Test Report Following Power Ascension and Testing2006-08-0101 August 2006
Cycle 25 Startup Test Report Following Power Ascension and Testing
CNRO-2006-00034, Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee2006-07-13013 July 2006
Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee
ML0618803852006-05-22022 May 2006
Windham Regional Plan Draft, May 22, 2006
ML0704404852006-05-12012 May 2006
AMRM-16, Revision 0, Aging Management Review of the Instrument Air System.
ML0704404832006-05-12012 May 2006
AMRM-15, Revision 0, Aging Management Review of the Fuel Oil System.
ML0704404782006-05-12012 May 2006
AMRM-15, Aging Management Review of the Fuel Oil System
ML0704404742006-05-12012 May 2006
AMRM-12, Aging Management Review of the Reactor Building Closed Cooling Water System
ML0704404862006-05-11011 May 2006
AMRM-30, Rev. 01, Aging Management Review of Ns Systems Affecting Safety Systems
BVY 06-033, Cycle 24 10 CFR 50.59 Report2006-04-24024 April 2006
Cycle 24 10 CFR 50.59 Report
BVY 06-031, Revision 1 to Steam Dryer Monitoring Plan2006-03-26026 March 2006
Revision 1 to Steam Dryer Monitoring Plan
ML0609503562006-03-22022 March 2006
GALL AMP: XI.M13, Thermal Aging and Neutron Irradiation Embrittlement of Cast Austenitic Stainless Steel (CASS) (Audit Worksheet GALL Report AMP)
ML0609503642006-03-22022 March 2006
GALL AMP: XI.M14, Loose Part Monitoring (Audit Worksheet GALL Report AMP)
ML0609502712006-03-22022 March 2006
GALL AMP: XI.M1, ASME Section XI Inservice Inspection, Subsections Iwb, Iwc, and Iwd (Audit Worksheet, GALL Report AMP)
ML0609505492006-03-22022 March 2006
GALL AMP: XI.M19, Steam Generator Tube Integrity (Audit Worksheet GALL Report AMP)
ML0609502772006-03-22022 March 2006
GALL AMP: XI.M2, Water Chemistry (Audit Worksheet, GALL Report AMP)
ML0609502152006-03-22022 March 2006
GALL AMP: X.E1. Environmental Qualification (EQ) of Electric Components (Audit Worksheet GALL Report AMP)
ML0609505702006-03-22022 March 2006
GALL AMP: XI.M22, Boraflex Monitoring (Audit Worksheet GALL Report AMP)
ML0609502202006-03-22022 March 2006
GALL AMP: X.S1, Concrete Containment Tendon Prestress (Audit Worksheet GALL Report AMP)
ML0609502502006-03-22022 March 2006
GALL AMP: XI.E3, Inaccessible Medium-Voltage Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet GALL Report AMP)
ML0609502582006-03-22022 March 2006
GALL AMP: XI.E4, Metal Enclosed Bus (Audit Worksheet GALL Report AMP)
ML0609502622006-03-22022 March 2006
GALL AMP: XI.E5, Fuse Holder (Audit Worksheet GALL Report AMP)
ML0609503472006-03-22022 March 2006
GALL AMP: XI.M11A, Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of Pressurized Water Reactors
ML0609506062006-03-22022 March 2006
GALL AMP: XI.M28, Buried Piping and Tanks Surveillance (Audit Worksheet GALL Report AMP)
ML0609506242006-03-22022 March 2006
GALL AMP: XI.M32, One-Time Inspection (Audit Worksheet GALL Report AMP)
ML0609502902006-03-22022 March 2006
GALL AMP: XI.M5, BWR Feedwater Nozzle (Audit Worksheet, GALL Report AMP)
ML0610000902006-03-22022 March 2006
GALL AMP: XI.M39, Lubricating Oil Analysis Program (Audit Worksheet GALL Report AMP)
ML0609503312006-03-22022 March 2006
GALL AMP: XI.M10, Boric Acid Corrosion (Audit Worksheet GALL Report AMP)
2021-03-15
[Table view] |
Text
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.Vermont Yankee 322 Governor Hunt Rd.Vernon, VT 05354 Tel 802-257-7711 26 Janiiary 2006 Mr. Daniel Riley, Environmental Engineer Vermont Agency of Natural Resources Department of Environmental Conservation Air Pollution Control Division Building 3 South 103 South Main Street Waterbury, VT 05671-0402
Subject:
2005 Air Pollutant Emissions Inventory Report for Entergy Nuclear Vermont Yankee, LLC. Facility ID WM 2335.
Dear Mr. Riley:
Enclosed is Entergy Nuclear Vermont Yankee's air emissions inventory report for 2005.Total air emissions from significant activities, which includes the house heating boilers and the waste oil burners, was 9.07 tons for the year. Vermont Yankee does not include emissions from the emergency diesel generators (A and B), the John Deere diesel, or the emergency diesel fire pump toward the total tonnage in this inventory report as these emergency generators, each of which operate less than one hundred hours per year, are considered
'insignificant activities under the State regulations.
The cooling tower particulate emissions calculations for the mechanical draft cooling towers are based on the drift and drift rate, and as in 2004, remain conservatively high.The cooling towers operated for 2,149 hours0.00172 days <br />0.0414 hours <br />2.463624e-4 weeks <br />5.66945e-5 months <br /> during 2005. The operating hours were utilized in calculating the 2005 PM emissions.
PM Emissions (TPY) = Drift gpm x 8.33 lbs/gal x TDS x 60 min/hr x hrs/yr of operation x 1 ton/2000 lbs= 72.0 gpm x 8.33 lbs/gal x (62 lbs/1000000.lbs) x 60 min/hr x 2149 x 1 tonr2000 lbs The calculations for the 2005 emission data for cooling tower hazardous air contaminants (HAC) consider the miscibility of the product constituent and the water circulated through the cooling towers versus percentage of water loss through evaporation when the towers are running. The circulating water flow through the cooling towers is approximately 360,000 gallons per minute (gpm), and based on the Final Environmental Statement Related to the Operation of Vermont Yankee Nuclear Power Corporation 1
published by the Nuclear Regulatory Commission, 5,000 gpm is lost through cooling tower evaporation.
The HAC emissions from the cooling towers are insignificant and do not exceed any action levels outlined in Appendix C of the Vermont Air Pollution Control Regulations.
Cooling Towers Pollutant Tons lbs/8 hours Action level (bs/8hrs)Particulate Matter 2.4 Dodecylguanidine Hydrochloride 0.001 0.002 0.025 Ethyl Alcohol 0.0004 0.001 2,330 Glutaraldehyde 0.008 0.015 340 Isopropyl Alcohol 0.0005 0.001 63 Total 2.41 This submittal does not include additional hazardous air contaminant (HAC) emissions inventory, as those would be associated with routine maintenance activities, such as painting and cleaning, and are therefore not subject to any State reporting requirements.
Please do not hesitate to call if you have questions or concerns with the enclosed information.
- Sincerely, Entergy Nuclear Vermont Yankee, LLC Lynn DeWald Environmental Specialist 802-258-5526 Samuel A. Wender IV Chemistry Superintendent 802-258-5650 2
Supporting Calculations A.B.SPECTRUS NX-1104 Isopropy1 Alcohol I (400 gals/yr) x (8.24 lbs/gal) x (2.4%) x (1 ton/2,000 Ibs) x (5,000 gpm/360,000 gpm) =0.0005 tons/yr Ethyl Alcohol (400 gals/yr) x (8.24 lbs/gal) x (1.8%) x (1 ton/2,000 lbs) x (5,000 gpm/360,000 gpm) = 0.0004 tons/yr Dodecylauanidine Hydrochloride (400 gals/yr) x (8.24 lbs/gal) x (5%) x (1 ton/2,000 Ibs) x (5,000 gpmn/360,000 gpm) = 0.001 tons/yr NALCO H-550 Glutaraldehvde (50% Solution)(250 gals/yr) x (9.4 lbs/gal) x (50%) x (1 ton/2,000 lbs) x (5,000 gpm/360,000 gpm) = 0.008 tons/yr 3 CERTIFICATION OF DATA ACCURACY For Purposes of Emission Calculations This form Inust be signed by an individual responsible for ihe completion and certification of the data contained in the forms attached which are intended to meet both the requirements of State Statute {10 V.S.A. 555 (c) and 3 v.S.A. 2822 (j)(1)(B)}
and the requirements for "Emission Statements" contained in the Federal Clean Air Act as amended in 1990. Certification indicates that the signatory takes legal responsibility for the accuracy of the information on the form.The data presented herein represents the best available information and is true, accurate, and complete to the'best of my knowledge.
Print Full Name SiTlhtureN Telephone Number Print Full Title Dt of2Signa1tu(o Date of Signature Received JAN 4 2006.~,'. .4 r*.N?
Vermont Agency of Natural Resources 2005 Air Pollutant Emissions Inventory Combustion Source For Criteria Pollutants The information displayed on this form is that which Is currently on file for your.facility.
It is based on inventory forms completed for calendar year 2004 or the most recent year available.
The information must be updated to calendar year 2005 .Please revied the information contained in the boxes. If there is no value in a box, write in the correct 2005 value. If there Is a value, but it Is incorrect for 2005, cross out the value and in its place write the correct value.If you have questions, or desire assistance with completing the inventory, please call Dan Riley at (802)-241-3858.
Facility Name: ENTERGY NUCLEAR VERMONT YANKEE Person Completing Inventory Form [b4.1 n~ rb A I d.Facility ID WM2335 Source
Description:
house heating boilers (2)Stack Number: Source Number: Segment Number: 1 1 1 Source Classification Code: 1-03-005-01 Operational Data: Hours Per Day: Days Per Week: Weeks Per Year: Hours Per Year: 0-.Winter Throughput
(%)Spring Throughput
(%): 30J Summer Throughput
(%): 0 Autumn Throughput
(%) 31 (Over)
Combustion Source (continued)
FuelType:
FUEL OIL (#2)2005 Fuel Consumption (supply units) : o,'q', 14 Av. Sulfr Content of Fuel(%): -Ash Content of Fuel (%):jj. J (Please supply a current estimate of mid-range sulfur content)Maximum Heat Input (million BTU/hr): Burner Rating: Boiler Rating: /4,5. LLZ *Maximum Actual Firing Rate (million BTIJ/hr):
IiIi Percent Space Heat: I0Jj .Percent Process Heat: 0II Stack Parameters:
Stack Number: l Stack/Duct Discharge Height (feet) : 87.9 Stack/Duct Inner Diameter at Exit (inches) 27.6 Exit Gas Temperature (deg. F) : 151 J Flow Rate at Exit (actual FT3/min) :119,915 I I If an air pollution control, device for the source exists inspect the following information and correct if necessary.:
TSP Control Device: none Theoretical Efficiency:
F 7"0]S02 Control Device: none NOx Control Device:I none ITheoretical Efficiency:
j__...] Theoretical Efficiency:
_VOC Control Devicej none .Theoretical Efficiency:
CO Control Device: .none Theoretical Efficiency:.
If an estimated emission rate exists, please supply the information below .0 LZ~Estimated Emission Rate*Basis of Estimate : [If test data 4 years old or less is available.
zJ Vermont Agency of Natural Resources 2005 Air Pollutant Emissions Inventory Combustion Source For Criteria Pollutants The Information displayed on this form is that which is currently on file for your facility.
It is based on inventory forms completed for calendar' year 2004 or the most recent year available.
The Information must be updated to calendar year 2005. Please review the information contained in the boxes. If there is no value in a box, write in the correct 2005 value. If there is a value, but it is incorrect for 2005, cross out'the value and in Its place write the correct value.If you have questions, or desire assistance with completing the inventory, please call Dan Riley at (802)-241-3858.
Facility Name.: ENTERGY NUCLEAR VERMONT YANKEE Person Completing Inventory Form Facility.ID-WM2335 Source
Description:
ywae oil furnace (2)UL-Lr\ V1L i'(2)de(I)
I Cd I.Stack Number: Source Number: Seement Number: 2 2 1 Source Classlflcation Code: 1-02-004-01 Operational Data: Hours Per Day: 0 Days Per Week: 0 j Weeks Per Year: 0 Hours Per Year: 1-7L-0-0-7 Winter Throughput
(%) 50 Spring Throughput
(%): L0il " Summer Throughput
(%): 0 Autumn Throughput
(%) :1 50" (Over)
Combustion Source (continued)
Fuel Type:- FUEL OIL (#6)2005 Fuel Consumption: (supply units): [ S * ( .* .c.Av. Sulfpr Content of Fuel (%): '/,5 Ash Content of Fuel (%): (Please supply a curreunt estimate of mid-range sulfur content)Maximum Heat Input (million BTU/hr): Burner Rating: Boiler Rating: Maximum Actual Firing Rate (million BTU/hr): Percent Space Heat: 1 O0 Percent Process Heat: 0 Stack Parameters:
Stack Number: 2 Stack/Duct Discharge Height (feet): 21.0 6 Stack/Duct Ifiner Diameter at Exit (inches) :7.9 Exit Gas Temperature (deg. F): .250*Flow.Rate at Exit (actual FT3/min):
1,992 If an air pollution control device for the source exists inspect the following information and correct if necessary:
TSP Control Device: none Theoretical Effciency:
S02 Control Device: I.none
f 0]NOx Control Device: I none Theoretical Efficiency:
VOC Control Devicef none .* Theoretical Efficiencyi*EZ I CO Control Device: Fnone -Theoretical Efficiency:.j
]If an estimated emission rate exists, please supply the information below: Estimated Emission Raie*. :1 Basis of Estimate:* If test data 4 years old or less is available.
Vermont Agency of Natural Resources 2005 Air Pollutant Emissions Inventory Process Source For Criteria Pollutants The information displayed on this form is that which is currently on file for your facility.
It is based on inventory forms completed for calendar year 2004 or the most recent year available.
The information must be updated to calendar year 2005. Please review the information contained in the boxes. If there is no value in a box, write in the correct 2005 value. If there Is a value, but it Is incorrect for 2005, cross out the value and in its place write the correct value.If you have *questions, or desire assistance with completing the inventory, please call Dan Riley at (802)-241-3858.
Facility Name: ENTERGY NUCLEAR VERMONT YANKEE Person Completing Inventory Form: 1 I Facility ID : WM2335 Source
Description:
Particulate Emissions from Cooling Tower Stack Number: Source Number: Segment Number: 5 5 1 Source Classification Code: 3-85-001-01 Operational Data: LHoursPerDay
- i DaysPerWeek:
WeeksPerYear:
Ii HoursPerYear:
F T, I'~F?Winter Throughput
(%): 0 j Spring Throughput
(%): I zf o S Summer Throughput
(%): CO." to Autumn Throughput
(%): [I 1o o.4 ;oi5'(Over)
Process Source (continued)
Raw Materials Input*:-Aol-ype q,!uanuty Product Materials Output*.: Type Quantity I I I:*Information in this section only necessary if accurate figures for stack flow rate and hours of operation cannot be supplied.Stack Parameters:
Stack Number: 5 Stack/Duct Discharge Height (Feet) : Stack/Duct Inner Diameter at Exit (Inches):
I I0.0 Exit Gas Temperature (Deg Y) : I i70i I Flow Rate at Exit (Actual FT3/Min) : I0 If there is an airpollution control device on this source inspect the following information and correct if necessary:
PM Control Device: Fnone Theoretical Efficiency
(%): [j 01 If available, supply theoretical efficiencies for: PMIO Efficiency
(%).: PM.Efiiec(%/):[Z I (NOTE: This Information will not affect the Air Registration Feý Estimate).
If an estimated emission rate exists for PM, supply the information below .Estimated Emission Rate* [Basis of Estimate:#.If test data 4 years old or less Is available.
Vermont Agency of Natural Resources 2005 Air Pollutant Emissions Inventory Combustion Source For Criteria Pollutants The information displayed on this form Is that which is currently on file for your facility.
It is based on inventory forms completed for calendar year 2004 or.the most recent year available.
The information must be updated to calendar year 2005. Please revieiv the information contained In the boxes. If there is no value in a box, write in the correct 2005 value. If there is a value, but it is incorrect for 2005, cross out the value and in its place write the correct value.If you have questions, or desire assistance with completing the inventory, please call Dan Riley at (802)-241-3858.
Facility Name: ENTERGY NUCLEAR VERMONT YANKEE Person Completing Inventory Formýj )_ f% bewcz H_Facility ID WM2335 Source
Description:
Emergency Diesels (2) -1675 hp Stack Number: Source Number: Seement Number: 3 3 1 Source Classification Code: 2-02-004-01 Operational Data: Hours Per Day: Z 0I J Days Per Week: 0 Weeks Per Year: EI 0i I Hours Per Year: '59::;* L-7", VCe Winter Throughput
(%)Spring Throughput
(%): L1325.Summer Throughput
(%): .251 J Autumn Throughput
(%): 2.(Over)15>
Combustion Source (continued)
Fuel Type: FUEL OIL (#2)2005 Fuel Consumption: (supply units): , 0/5 Av. Sulfur Content of Fuel (%): [OYZ- Ash Content of Fuel (%): 0.005 (Please supply a current estimate of mid-range sulfur content)Maximum Heat Input (million BTU/hr): BumerRating:
Boller Rating: Jj2"4IJ Maximum Actual Firing Rate (million BTU/hr): *I O Percent Space Heat: W Percent Process Heat: Stack Parameters:
Stack Number: 3.Stack/Duct Discharge Height (feet): [29.8 Stack/Duct Inner Diameter at Exit (inches):
27.6*Exit Gas Temperature (deg. F): "180.Flow Rate at Exit (actual FT3/min) :63,983 If an air pollution control device for the source exists inspect the following information and correct if necessary:
TSP Control Device: none Theoretical Efficiency:
[-I S02 Control Device: none NOx Conirol Device: none VOC Control Devicei none 1 Theoretical Efficiency:-Theoretical Efficiency:
.i Theoretical Efficiency:
i 0 i* CO Control Device: none Theoretical Efficiency:
L If an estimated emission rate exists, please supply-the information below: Estimated Emisslon Rate*Basis of Estimate:* If test data 4 years old or less is available.
'In Vermont Agency of Natural Resources Combustion Source 2005 Air Pollutant Emissions Inventory For Criteria Pollutants The information displayed on this form is that which is currently on file for your facility.
It is based on inventory forms completed for calendar year 2004 or the most recent year available.'The Information must be updated to calendar year 2005. Please revied the information contained in the boxes. If there is no value In a box, write in the correct 2005 value. If there is a value, but It is incorrect for 2005, cross out the value and.in its place write the correct value.If you have questions, or desire assistance with completing the inventory, please call Dan Riley at (802)-241-3858.
Facility Name : ENTERGY NUCLEAR VERMONT YANKEE.Person Completing Inventory Form I+~YeAAdJ.
IzIIzzii Facility ID WM2335 Source
Description:
235 hp John Deere Diesel Stack Number:'Source Number: Seament Number: 4 4.I1.Source Classification Code: 2-01-001-02 Operational Data: Hours Per Day: 0 Days Per Week: [Z 0 Weeks Per Year: [Z .0 Hours Per Year: Winter Throughput
(%)* Spring Throughput
(%): 251 25 Summer Throughput
(%): 5 Autumn Throughput
(%) :1 25.(Over)
Combustion Source (continued)
Fuel Type: FUEL OIL (#2)2005 Fuel Consumption
- (supply units): Li" ILl s Av. Sulfur Content of Fuel (%): j,-- Ash Content of Fuel(%): 0.005 (Please sapply a current estimate of mid-range sulfur content)Maximum Heat Input (million BTU/hr): Burner Rating: ojIjBoiler Rating: I i Maximum Actual Firing Rate (million BTU/hr): jj 0"[Percent Space Heat: Percent Process Heat: Stack Parameters:
Stack Number: 4 Stack/Duct Discharge Height (feet) " 12.5I II Stack/Duct Inner Diameter atExit (inches).:3.9 Exit Gas Temperature (deg. F): 180 Flow Rate at Exit (actuil FT3/min) :4,301 If an air pollution control device for the source exists inspect the following information and correct if necessary:
TSP Control Device: none Theoretical Efficiency:
F W I S02 Control Device: none*" Theoretical Efficiency:
NOx Control Device:1 none Theoretical Efficiency:
VOC Control Devicei none -Theoretical Efficiency:
CO Control Device:- none Theoretical Efficiency:
If an estimated emission rate exists, please supply the information below: Estimated Emission Rate*: I01 I o Basis oof stlmate: .* If test data"4 years old or less is available.
