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Category:Letter type:BVY
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
BVY 23-022, Pre-Notice of Disbursement from Decommissioning Trust2023-08-23023 August 2023
Pre-Notice of Disbursement from Decommissioning Trust
BVY 23-020, Pre-Notice of Disbursement from Decommissioning Trust2023-08-0202 August 2023
Pre-Notice of Disbursement from Decommissioning Trust
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 23-019, 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 23-016, 10 CFR 72.48 Report2023-06-0505 June 2023
10 CFR 72.48 Report
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 23-014, 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
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 23-006, 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 23-007, 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 23-005, 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
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
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
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
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
BVY 22-018, Pre-Notice of Disbursement from Decommissioning Trust2022-06-0808 June 2022
Pre-Notice of Disbursement from Decommissioning Trust
BVY 22-015, 2021 Radiological Environmental Operating Report2022-05-0505 May 2022
2021 Radiological Environmental Operating Report
BVY 22-017, Pre-Notice of Disbursement from Decommissioning Trust2022-05-0505 May 2022
Pre-Notice of Disbursement from Decommissioning Trust
BVY 22-014, 2021 Radiological Effluent Release Report2022-04-28028 April 2022
2021 Radiological Effluent Release Report
BVY 22-012, Biennial Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d)2022-04-12012 April 2022
Biennial Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d)
BVY 22-011, Pre-Notice of Disbursement from Decommissioning Trust2022-04-0404 April 2022
Pre-Notice of Disbursement from Decommissioning Trust
BVY 22-009, Status of Decommissioning and Spent Fuel Management Fund for the Year Ending 20212022-03-23023 March 2022
Status of Decommissioning and Spent Fuel Management Fund for the Year Ending 2021
BVY 22-008, Pre-Notice of Disbursement from Decommissioning Trust2022-02-24024 February 2022
Pre-Notice of Disbursement from Decommissioning Trust
BVY 22-005, ISFSI Decommissioning Funding Plan2022-02-24024 February 2022
ISFSI Decommissioning Funding Plan
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 Operations, Inc.
Vermont Yankee
-Entergy P.O. Box 0500 185 Old Ferry Road Brattleboro, VT 05302-0500 Tel 802 257 5271 August 1, 2006 BVY 06-068 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)
Vermont Yankee Cycle 25 Startup Test Report Following Power Ascension and Testing The purpose of this letter is to submit the Vermont Yankee (VY) Cycle 25 Startup Test Report in accordance with the VY Technical Requirements Manual (TRM). TRM Section 6.7.A.1 requires a summary report of plant startup and power escalation testing be submitted following an amendment to the license involving a planned increase in power level. On May 5, 2006, VY obtained the new authorized power level of 1912 MWT.
There are no new regulatory commitments contained in this submittal.
We trust that the information provided is adequate; however, should you have questions, please contact James M. DeVincentis at (802) 258-4236.
Sincerely, Site Vice President Vermont Yankee Nuclear Power Station Attachment (8 pages) 0?,'-?
BVY 06-068 Page 2 of 2 cc: Mr. Samuel J. Collins Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. James J. Shea, Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8C2A Washington, DC 20555 USNRC Resident Inspector Entergy Nuclear Vermont Yankee, LLC P.O. Box 157 Vernon, Vermont 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, Vermont 05620-2601
STARTUP TEST REPORT - VERMONT YANKEE CYCLE 25 In accordance with Vermont Yankee Technical Requirements Manual Section 6.7.A.1, this Startup Test Report is being submitted to the NRC since a 20 % Extended Power Uprate (EPU) was implemented. This Startup Test Report contains Cycle 25 startup data (November 2005) and an EPU summary (March 2006 to May 2006).
In accordance with USFAR Section 13.5.5, the following information is being provided in this Startup Test Report.
Overview:
Vermont Yankee Cycle 25 initial startup commenced on November 10, 2005, following a 19-day outage for refueling and maintenance activities. Steady state, full power conditions were reached on November 14,2005.
The core loading for Cycle 25 consists of the following:
Quantity Fuel Description Cycle Type loaded 92 GE- 14 GEl 4-PIODNAB394-7G5.0/6G4.0-100T-150-T6-2566 23 16 GE-14 GE14-P1ODNAB394-8G5.0/6G4.0-1OOT- 150-T6-2595 23 20 GE-14 GE14-PIODNAB394-12G5.0-100T-150-T6-2596 23 32 GE-14 GE14-P1ODNAB426-16G6.0-100T-150-T6-2682 24 44 GE-14 GE14-PIODNAB390-14GZ-100T- 150-T6-2683 24 40 GE-14 GE14-P1ODNAB388-17GZ-100T-150-T6-2684 24 48 GE-14 GE14-P1ODNAB422-16GZ- 100T- 150-T6-2862 25 32 GE-14 GE14-PIODNAB383-14G6.0-100T- 150-T6-2864 25 28 GE-14 GE14-P1ODNAB383-13G6.0-100T-150-T6-2863 25 16 GE-14 GE14-P1ODNAB383-17G6.0-100T-150-T6-2865 25 For Cycle 25, VY replaced 104 GE13 and 20 GE9B fuel bundles with 124 new GE14 fuel bundles.
Core Verification:
An as-loaded Cycle 25 core map is included as Figure 1. Details of the Cycle 25 core loading are contained in the Global Nuclear Fuels (GNF) document 0000-0045-9096-CMR, Rev. 0, "Cycle Management Report for Vermont Yankee Nuclear Power Station Cycle 25 (at Current Licensed Power Level of 1593 MWt)," October 2005 (PROPRIETARY).
Vermont Yankee personnel verified the final as-loaded core loading in accordance with Vermont Yankee procedure OP-141 1, "Core Verification." Three separate criteria were checked:
- 1. Proper bundle seating was checked.
- 2. Proper bundle orientation, channel fastener integrity and upper tie plate cleanliness were checked and verified.
- 3. Proper core loading was verified by checking the serial number of each bundle against the final approved core-loading map.
This verification was performed independently by two separate teams.
Process Computer Data Checks:
Process computer data evaluation checks were completed in accordance with ENN-DC-503 "3D Monicore New Cycle Update and Databank Maintenance." These checks included various manual and computer checks of the new databank, including updating and checking the new databank for EPU conditions.
Control Rod Drive System Testing:
No control blades and six control rod drive mechanisms were replaced during RF025. Control rod coupling and withdrawal speed verification were completed satisfactorily for all 89 control rods per OP-41 11, "Control Rod Drive System Surveillance."
Single rod scram timing was performed in accordance with OP4424, "Control Rod Scram Testing and Data Reduction." Testing of all 89 control rods was completed in conjunction with OP-4101 "RPV Operational System Leakage Test" and in accordance with Vermont Yankee Technical Specification Section 4.3.C.1. All insertion times were within the limits defined in the Vermont Yankee Technical Specification Section 3.3.C.1. In accordance with Vermont Yankee Technical Specification Section 4.3.C.2, the results of the testing are included in Table 1.
Shutdown Margin Testing:
The cold shutdown margin calculation was performed using data collected during the in-sequence critical and information provided in Global Nuclear Fuels (GNF) document 0000-0045-9096-CMR, Rev. 0, "Cycle Management Report for Vermont Yankee Nuclear Power Station Cycle 25 (at Current Licensed Power Level of 1593 MWt)," October 2005 (PROPRIETARY).
In accordance with Vermont Yankee Technical Specification Section 3.3.A.1, the minimum shutdown margin required is 0.38% Ak/k. The actual demonstrated shutdown margin was 1.129%
Ak/k as determined in accordance with OP-4430 "Reactivity Anomalies/Shutdown Margin Check."
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In-Sequence Critical Eigenvalue:
The in-sequence critical test was performed as part of the reactor startup. Control rod sequence 25-A2-(1) was used to perform the in-sequence critical test. Criticality was achieved on the 9h rod in group 2 (18-3 1) at notch position 26. The moderator temperature was 195 'F as recorded by Emergency Response Facility Information System Emergency (ERFIS) point ID B023.
The actual critical rod pattern and the prediction agreed within +/- 1% Ak per OP-4430 "Reactivity Anomalies/Shutdown Margin Check."
LPRM Operability Check:
No local power range monitors (LPRM) were replaced during RF025.
LPRM connection verification and hi and low trip alarm set points were performed satisfactorily in accordance with OP 4406, "LPRM Calibration and Functional Check".
The local power range monitors were calibrated at approximately 100% Core Thermal Power (CTP) in accordance with OP 2425, "Core Power Distribution Calculation Utilizing the Traversing In-Core (TIP) System" and OP 4406, "LPRM Calibration and Functional Check."
APRM Calibration:
In accordance with Vermont Yankee Technical Specification Section 2.1.A, APRM gain adjustments were performed as required in accordance with OP 4400 "Calibration of the Average Power Range Monitoring System to Core Thermal Power." In addition, APRM gain adjustments were performed throughout the reactor startup.
Core Performance Evaluations:
In accordance with Vermont Yankee Technical Specification Section 3.11, the Average Planer Linear Heat Generation Rate (APLHGR), Linear Heat Generation Rate (LHGR) and Minimum Critical Power Ratio (MCPR) were all checked within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of reaching 25% CTP in accordance with OP 4401, "Core Thermal Hydraulic Limits Evaluation." The limits were all less than 1.0 as specified in the Vermont Yankee Technical Specifications.
At approximately 50, 75 and 100 percent power level, a heat balance calculation was performed using three separate computer calculations in accordance with OP 2409 "Operating Data Collection and Evaluation" and OP 2410 "Reactor Core Thermal Power Evaluation." The calculated core thermal power from each method was found to be in agreement (within 5 Megawatts thermal).
Core flow calibration was completed in accordance with OP 2429 "Recirculation Flow System Baseline Data Collection and Instrument Calibration" and OP 2440 "Reactor Core Flow 0 Page 3 of 8
Determination" to ensure that the core flow calculation by the process computer is accurate over the entire operating range.
Process Computer Power Distribution:
The plant process computer power distribution was updated at approximately 73% CTP using the TIP system during the ascent to full power. A few days later, the plant process computer power distribution was updated at approximately 100% CTP (1593 MWT) using the TIP system.
The process computer power distribution update performed after reaching steady state conditions was used as a basis for comparison with an off-line calculation performed using SIMULATE-3.
The axial and radial power distribution comparison between 3D Monicore (on-line code) and Simulate-3 (off-line code) is documented in Table 2 and Table 3. The result of the comparison is acceptable.
In addition, the plant process computer power distribution was updated for EPU conditions at approximately 100% CTP (1912 MWT) using the TIP system.
TIP Uncertainty:
Total TIP uncertainty was calculated in accordance with OP 4455, "TIP Uncertainty." The resulting total TIP uncertainty for this case of 1.22% is less than the 6% licensing acceptance criteria.
EPU:
On March 4, 2006, following receipt of License Amendment No. 229 to increase maximum authorized reactor power level, Vermont Yankee started a controlled and deliberate power ascension program including the following activities:
" APRM setpoint change and calibration to new 100% licensed power level.
" Individual power increase limits of 1% per hour.
" At each 5% power level increment, testing of the feedwater level control response and turbine pressure control systems was performed.
" In accordance with the steam dryer monitoring plan and license condition requirements, steam dryer monitoring system data was obtained and analyzed hourly during power ascension. In addition, at each 5% increment, data was supplied to the NRC and a minimum 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> hold period was implemented.
" At each 5% increment, plant piping walkdown and monitoring data were obtained and provided to the NRC for review. System walkdown information was also obtained and evaluated at each hold point.
On May 5, 2006 Vermont Yankee achieved the new 100% authorized reactor power level of 1912 MWT.
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On May 8,2006, a Condensate Pump Trip Test at Full EPU Power, ERSTI-04-VTYI-1409-000 8 was implemented successfully per VY's EPU license condition: "Prior to exceeding 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> of plant operation at the nominal full power EPU reactor power level, with feedwater and condensate flow rates stabilized at approximately the EPU full power level, confirm through performance of transient testing that the loss of one condensate pump will not result in a complete loss of reactor feedwater."
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TABLE I CONTROL ROD SCRAM TESTING RESULTS VERMONT YANKEE BEGINNING OF CYCLE 25 Scram Number: 218 Single Rod Scram testing performed on November 8, 2005 Reactor Pressure: 1020 Psia Reactor Power: 0%
Full Core Average - Number of Rods Averaged: 89 Dropout Position Avg. Scram Time Admin. Limit Pass/Fail 46 0.290 0.347 PASS Dropout from Average Scram Tech. Spec. Pass/Fail Tech. Spec. Pass/Fail Notch Position Insertion Time Criteria Criteria 3.3.C. 1.1 3.3.C. 1.2 PASS 46 0.290 0.358 PASS 0.358 PASS 36 0.800 0.912 PASS 1.096 PASS 26 1.327 1.468 PASS 1.860 PASS 06 2.436 2.686 3.419 PASS Slowest 2X2 Average Summary for Each % Insertion
- Admin. Limit Pass/Fail Position 46 0.290 0.368 PASS Dropout from 2 X 2 Average
- Tech. Spec. Pass/Fail Tech. Spec. IPass/Fail Notch Position Insertion Time Criteria Criteria 3.3.C.1.1 3.3.C. 1.2 PASS 46 0.290 0.379 PASS 0.379 PASS 36 0.813 0.967 PASS 1.164 PASS 26 1.343 1.556 PASS 1.971 PASS 06 2.474 2.848 PASS 3.624
- The 2X2 Averages consist of the slowest arithmetic average of the three fastest rods in a 2X2 array.
Slowest Single Rod Dropout Position Rod Id. Scram Time Tech. Spec. Criteria 3.3.C.2. Pass/Fail 06 22-03 2.710 7.000 PASS 0 Page 6 of 8
TABLE 2 CORE AVERAGE AXIAL POWER DISTRIBUTION COMPARISON BETWEEN PROCESS COMPUTER (3D MONICORE) AND SIMULATE-3 VERMONT YANKEE BEGINNING OF CYCLE 25 Node 3DM Simulate-3 25 0.115 0.105 24 0.295 0.317 23 0.452 0.432 22 0.578 0.552 21 0.670 0.638 20 0.751 0.718 19 0.808 0.774 18 0.837 0.805 17 0.849 0.797 16 0.850 0.793 15 0.908 0.856 14 1.101 1.016 13 1.171 1.105 12 1.269 1.217 11 1.347 1.293 10 1.375 1.343 9 1.402 1.406 8 1.45 1.464 7 1.475 1.508 6 1.506 1.592 5 1.542 1.643 4 1.506 1.626 3 1.352 1.493 2 1.030 1.169 1 0.361 0.337 TABLE 3 RELATIVE RADIAL POWER DISTRIBUTION COMPARISON BETWEEN PROCESS COMPUTER (3D MONICORE) AND SIMULATE-3 VERMONT YANKEE BEGINNING OF CYCLE 25 Ring 3DM Simulate-3 1 0.823 0.802 2 1.193 1.205 3 1.112 1.107 4 1.175 1.179 5 1.135 1.139 6 0.702 0.696 S Page 7 of 8
FIGURE 1 Vermont Yankee Core Map
, North Cvcle 25 44 42 40 38 I 1 I I 7 9 11 13 15 177I I 19 I 21 23 25 27 I 29
--- C-23: GZ14-P1ODNAB3 4--7GS.0/ 6 92 Core Loading Reference Document:DRl0000-OO3S-6409 C-23: GE14-P10DtaAB394-SG5.0/06 16 Reference Loading Pattern (RLP) Databank
--- C-23: GE14-P10DUAB394-12G5.U 20 Edit
--- C-24: GE14-PIODNA.B426-16G6.0 32
--- C-24: GE14-PIODNAB390-14GZ 44, Form Completed by: (Originalsignedby Je..*'r L. Dean) (*A04/2005
--- C-24: GE14-PIODNAB388-17GZ 40
--- C-25: G~E14-PIODUAB422-16GZ 48,
--- C-25: GE14-PIODNAfl383-14G6.0 32 Verified by: (0,igmaI i~g-dby. Robel A Vita) OMi4=5~f
--- C-25: GE14-PIODNAB383-13G6.0 28:
--- C-25: GE14-PI0DNAB3!33-17G6.0 16 36a Core Weight: 72.867 ST VYOPF 1410 03 0P1410 PageRev. 26 1 of 1 0 Page 8 of 8
