Letter Sequence Other |
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TAC:MF3068, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) |
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MONTHYEARBVY 13-097, Proposed Change 306, Areva Document No. 32-9145461-001, Vynpp - Re-analysis of Ast/Fha Radiological Consequences with Open Containment2013-11-14014 November 2013 Proposed Change 306, Areva Document No. 32-9145461-001, Vynpp - Re-analysis of Ast/Fha Radiological Consequences with Open Containment Project stage: Request ML14140A2982014-05-19019 May 2014 NRR E-mail Capture - Vermont Yankee RAI for LAR on Eliminate Certain ESF Requirements During Movement of Irradiated Fuel Project stage: RAI BVY 14-036, Response to Request for Additional Information on Technical Specifications Proposed Change No. 306, Eliminate Certain ESF Requirements During Movement of Irradiated Fuel - Supplement 12014-06-0909 June 2014 Response to Request for Additional Information on Technical Specifications Proposed Change No. 306, Eliminate Certain ESF Requirements During Movement of Irradiated Fuel - Supplement 1 Project stage: Supplement ML14210A1592014-07-29029 July 2014 NRR E-mail Capture - RAI - Eliminate Certain ESF Eequirements During Fuel Movement Project stage: RAI BVY 14-059, Response to Request for Additional Information on Technical Specifications Proposed Change No. 306 Eliminate Certain ESF Requirements During Movement of Irradiated Fuel - Supplement 22014-08-0606 August 2014 Response to Request for Additional Information on Technical Specifications Proposed Change No. 306 Eliminate Certain ESF Requirements During Movement of Irradiated Fuel - Supplement 2 Project stage: Supplement ML14265A0002014-09-17017 September 2014 NRR E-mail Capture - 2nd RAI from Radiation Protection Branch - Eliminate Certain ESF Eequirements During Fuel Movement Project stage: RAI ML14295A3502015-02-0404 February 2015 Request for Withholding Information from Public Disclosure - 8/7/14 Areva, Inc. Submittal with Affidavit Executed by Gayle F. Elliott Related to Areva Document No. 32-9053350-000, Dated August 2008 Project stage: Withholding Request Acceptance ML14304A5882015-02-12012 February 2015 Issuance of Amendment No. 261, Revise Technical Specifications to Eliminate Certain Requirements During Movement of Irradiated Fuel and Core Alterations Consistent with TSTF-51 Project stage: Approval BVY 15-024, Revision of Technical Specifications Bases Pages2015-03-25025 March 2015 Revision of Technical Specifications Bases Pages Project stage: Other 2014-08-06
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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:Technical Specification
MONTHYEARBVY 15-055, Revision of Technical Specifications Bases Pages2015-11-16016 November 2015 Revision of Technical Specifications Bases Pages BVY 15-024, Revision of Technical Specifications Bases Pages2015-03-25025 March 2015 Revision of Technical Specifications Bases Pages ML14231A0172014-08-13013 August 2014 Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 4 ML14202A2062014-07-16016 July 2014 Technical Specifications Proposed Change No. 307, Revision to Technical Specification Administrative Controls for Permanently Defueled Condition - Supplement 2 BVY 14-049, Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 32014-06-11011 June 2014 Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 3 ML13323A5182013-11-14014 November 2013 Technical Specifications Proposed Change No. 306 Eliminate Certain ESF Requirements During Movement of Irradiated Fuel BVY 13-084, Revision of Technical Specification Bases Page2013-09-0909 September 2013 Revision of Technical Specification Bases Page BVY 13-053, Revision of Technical Specifications Bases Pages2013-07-24024 July 2013 Revision of Technical Specifications Bases Pages BVY 13-062, Revised of Technical Specification Bases Pages2013-06-26026 June 2013 Revised of Technical Specification Bases Pages BVY 13-043, Technical Specifications Proposed Change No. 304, Revision to Low Pressure Safety Limit2013-05-14014 May 2013 Technical Specifications Proposed Change No. 304, Revision to Low Pressure Safety Limit BVY 13-023, License Amendment Request; Changes to 10 CFR 50.63 Licensing Basis, Supplement 22013-04-29029 April 2013 License Amendment Request; Changes to 10 CFR 50.63 Licensing Basis, Supplement 2 BVY 13-022, Revision of Technical Specification Bases Pages2013-03-26026 March 2013 Revision of Technical Specification Bases Pages BVY 12-078, Technical Specifications Proposed Change 297, Supplement 2 Response to Request for Additional Information2012-11-20020 November 2012 Technical Specifications Proposed Change 297, Supplement 2 Response to Request for Additional Information BVY 12-055, Technical Specifications Proposed Change 297, Supplement 1, Response to Request for Additional Information2012-08-0707 August 2012 Technical Specifications Proposed Change 297, Supplement 1, Response to Request for Additional Information BVY 12-018, Technical Specifications Proposed Change No. 299 Recirculation System Discharge Bypass Valve Change2012-04-17017 April 2012 Technical Specifications Proposed Change No. 299 Recirculation System Discharge Bypass Valve Change BVY 12-006, Technical Specifications Proposed Change No. 298, Rod Worth Minimizer Bypass Allowance2012-02-0101 February 2012 Technical Specifications Proposed Change No. 298, Rod Worth Minimizer Bypass Allowance BVY 12-005, Technical Specifications Proposed Change No. 297, Suppression Chamber-Drywell Leak Rate Test Surveillance Frequency Change2012-02-0101 February 2012 Technical Specifications Proposed Change No. 297, Suppression Chamber-Drywell Leak Rate Test Surveillance Frequency Change BVY 11-068, Revision of Technical Specification Bases Pages Due to License Amendment 2482011-09-30030 September 2011 Revision of Technical Specification Bases Pages Due to License Amendment 248 BVY 11-042, Technical Specifications Proposed Change No. 293, Supplement 1 Revised Reactor Vessel Pressure-Temperature Limitation Curves2011-05-16016 May 2011 Technical Specifications Proposed Change No. 293, Supplement 1 Revised Reactor Vessel Pressure-Temperature Limitation Curves BVY 11-037, Revision of Technical Specification Bases Pages Due to License Amendment 2462011-04-21021 April 2011 Revision of Technical Specification Bases Pages Due to License Amendment 246 BVY 10-059, Technical Specifications Proposed Change No. 294, Elimination of Provisions Allowing HPCI and RCIC Suctions to Be Aligned to the Suppression Pool2010-11-0808 November 2010 Technical Specifications Proposed Change No. 294, Elimination of Provisions Allowing HPCI and RCIC Suctions to Be Aligned to the Suppression Pool BVY 10-056, Submittal of Revision of Technical Specification Bases Pages2010-10-0606 October 2010 Submittal of Revision of Technical Specification Bases Pages BVY 10-047, Revision of Technical Specifications Bases Page2010-08-18018 August 2010 Revision of Technical Specifications Bases Page BVY 10-027, Revision of Technical Specification Bases Pages2010-05-21021 May 2010 Revision of Technical Specification Bases Pages BVY 10-017, Technical Specifications Proposed Change No. 290 Administrative Changes2010-04-13013 April 2010 Technical Specifications Proposed Change No. 290 Administrative Changes BVY 10-021, Revision of Technical Specification Bases Pages2010-03-31031 March 2010 Revision of Technical Specification Bases Pages BVY 09-074, Revision of Technical Specifications Bases Pages2009-12-0909 December 2009 Revision of Technical Specifications Bases Pages BVY 09-072, Technical Specification Bases Pages Associated with License Amendment 2362009-12-0909 December 2009 Technical Specification Bases Pages Associated with License Amendment 236 BVY 09-068, Technical Specifications Proposed Change No. 288 Scram Discharge Volume Vent and Drain Valves2009-12-0303 December 2009 Technical Specifications Proposed Change No. 288 Scram Discharge Volume Vent and Drain Valves BVY 09-055, Revision of Technical Specifications Bases Page2009-09-28028 September 2009 Revision of Technical Specifications Bases Page BVY 09-052, Technical Specifications Proposed Change No. 284 Change to Requirements for Inoperable Containment Isolation Valves2009-09-16016 September 2009 Technical Specifications Proposed Change No. 284 Change to Requirements for Inoperable Containment Isolation Valves BVY 09-051, Technical Specifications Proposed Change No. 285 Revision of High Radiation Area Controls2009-08-26026 August 2009 Technical Specifications Proposed Change No. 285 Revision of High Radiation Area Controls BVY 09-044, Revision of Technical Specifications Bases Pages2009-07-28028 July 2009 Revision of Technical Specifications Bases Pages BVY 09-029, Technical Specifications Proposed Change No. 283 Change to Requirements for Performing 10 CFR 50, Appendix J, Type a Test2009-05-0505 May 2009 Technical Specifications Proposed Change No. 283 Change to Requirements for Performing 10 CFR 50, Appendix J, Type a Test BVY 09-021, Submittal of Revision of Technical Specification Bases Pages2009-03-31031 March 2009 Submittal of Revision of Technical Specification Bases Pages BVY 09-014, Submittal of Revised Technical Specification Bases Pages2009-02-24024 February 2009 Submittal of Revised Technical Specification Bases Pages BVY 09-012, Submittal of Proposed License Amendment for Technical Specifications No. 282, Revision of Drywell Vacuum Breaker Surveillance Requirements2009-02-24024 February 2009 Submittal of Proposed License Amendment for Technical Specifications No. 282, Revision of Drywell Vacuum Breaker Surveillance Requirements ML0836500072008-12-18018 December 2008 Vermont Yankee Nuclear Power Station, Response to Request for Additional Information on Technical Specifications Proposed Change No. 273, Supplement 6 BVY 08-087, Vermont Yankee Nuclear Power Station, Response to Request for Additional Information on Technical Specifications Proposed Change No. 273, Supplement 62008-12-18018 December 2008 Vermont Yankee Nuclear Power Station, Response to Request for Additional Information on Technical Specifications Proposed Change No. 273, Supplement 6 BVY 08-087, Attachment 2, Technical Specification Proposed Change No. 273, Supplement 6, Sample Set-Point Calculations2008-12-18018 December 2008 Attachment 2, Technical Specification Proposed Change No. 273, Supplement 6, Sample Set-Point Calculations BVY 08-081, Submittal of Revision of Technical Specification Bases Page 292008-11-17017 November 2008 Submittal of Revision of Technical Specification Bases Page 29 BVY 08-076, Revision of Technical Specification Bases Pages2008-10-14014 October 2008 Revision of Technical Specification Bases Pages BVY 08-052, Technical Specifications Proposed Change No. 278, Changes to Main Steam Isolation Valve Surveillance Requirements2008-09-22022 September 2008 Technical Specifications Proposed Change No. 278, Changes to Main Steam Isolation Valve Surveillance Requirements BVY 08-059, Technical Specifications Proposed Change No. 280 Relocation of Reactor Building Crane Technical Specifications2008-09-22022 September 2008 Technical Specifications Proposed Change No. 280 Relocation of Reactor Building Crane Technical Specifications BVY 08-069, Transmittal of Technical Specifications Proposed Change No. 281, Revision to Battery Systems2008-09-22022 September 2008 Transmittal of Technical Specifications Proposed Change No. 281, Revision to Battery Systems BVY 08-066, Submittal of Corrected Technical Specification Page2008-08-26026 August 2008 Submittal of Corrected Technical Specification Page BVY 08-060, Submittal of Revision of Technical Specification Bases Page 2202008-08-25025 August 2008 Submittal of Revision of Technical Specification Bases Page 220 BVY 08-046, Revision of Technical Specification Bases Page 972008-07-28028 July 2008 Revision of Technical Specification Bases Page 97 BVY 08-031, Revision of Technical Specification Bases Page2008-05-29029 May 2008 Revision of Technical Specification Bases Page BVY 08-001, Technical Specifications Proposed Change No. 273 Instrumentation Technical Specifications2008-02-12012 February 2008 Technical Specifications Proposed Change No. 273 Instrumentation Technical Specifications 2015-03-25
[Table view] Category:Bases Change
MONTHYEARBVY 15-055, Revision of Technical Specifications Bases Pages2015-11-16016 November 2015 Revision of Technical Specifications Bases Pages BVY 15-024, Revision of Technical Specifications Bases Pages2015-03-25025 March 2015 Revision of Technical Specifications Bases Pages ML14231A0172014-08-13013 August 2014 Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 4 ML14202A2062014-07-16016 July 2014 Technical Specifications Proposed Change No. 307, Revision to Technical Specification Administrative Controls for Permanently Defueled Condition - Supplement 2 ML13323A5182013-11-14014 November 2013 Technical Specifications Proposed Change No. 306 Eliminate Certain ESF Requirements During Movement of Irradiated Fuel BVY 13-084, Revision of Technical Specification Bases Page2013-09-0909 September 2013 Revision of Technical Specification Bases Page BVY 13-053, Revision of Technical Specifications Bases Pages2013-07-24024 July 2013 Revision of Technical Specifications Bases Pages BVY 13-062, Revised of Technical Specification Bases Pages2013-06-26026 June 2013 Revised of Technical Specification Bases Pages BVY 13-043, Technical Specifications Proposed Change No. 304, Revision to Low Pressure Safety Limit2013-05-14014 May 2013 Technical Specifications Proposed Change No. 304, Revision to Low Pressure Safety Limit BVY 13-023, License Amendment Request; Changes to 10 CFR 50.63 Licensing Basis, Supplement 22013-04-29029 April 2013 License Amendment Request; Changes to 10 CFR 50.63 Licensing Basis, Supplement 2 BVY 13-022, Revision of Technical Specification Bases Pages2013-03-26026 March 2013 Revision of Technical Specification Bases Pages BVY 12-078, Technical Specifications Proposed Change 297, Supplement 2 Response to Request for Additional Information2012-11-20020 November 2012 Technical Specifications Proposed Change 297, Supplement 2 Response to Request for Additional Information BVY 12-055, Technical Specifications Proposed Change 297, Supplement 1, Response to Request for Additional Information2012-08-0707 August 2012 Technical Specifications Proposed Change 297, Supplement 1, Response to Request for Additional Information BVY 12-018, Technical Specifications Proposed Change No. 299 Recirculation System Discharge Bypass Valve Change2012-04-17017 April 2012 Technical Specifications Proposed Change No. 299 Recirculation System Discharge Bypass Valve Change BVY 12-006, Technical Specifications Proposed Change No. 298, Rod Worth Minimizer Bypass Allowance2012-02-0101 February 2012 Technical Specifications Proposed Change No. 298, Rod Worth Minimizer Bypass Allowance BVY 12-005, Technical Specifications Proposed Change No. 297, Suppression Chamber-Drywell Leak Rate Test Surveillance Frequency Change2012-02-0101 February 2012 Technical Specifications Proposed Change No. 297, Suppression Chamber-Drywell Leak Rate Test Surveillance Frequency Change BVY 11-068, Revision of Technical Specification Bases Pages Due to License Amendment 2482011-09-30030 September 2011 Revision of Technical Specification Bases Pages Due to License Amendment 248 BVY 11-042, Technical Specifications Proposed Change No. 293, Supplement 1 Revised Reactor Vessel Pressure-Temperature Limitation Curves2011-05-16016 May 2011 Technical Specifications Proposed Change No. 293, Supplement 1 Revised Reactor Vessel Pressure-Temperature Limitation Curves BVY 11-037, Revision of Technical Specification Bases Pages Due to License Amendment 2462011-04-21021 April 2011 Revision of Technical Specification Bases Pages Due to License Amendment 246 BVY 10-056, Submittal of Revision of Technical Specification Bases Pages2010-10-0606 October 2010 Submittal of Revision of Technical Specification Bases Pages BVY 10-047, Revision of Technical Specifications Bases Page2010-08-18018 August 2010 Revision of Technical Specifications Bases Page BVY 10-027, Revision of Technical Specification Bases Pages2010-05-21021 May 2010 Revision of Technical Specification Bases Pages BVY 10-017, Technical Specifications Proposed Change No. 290 Administrative Changes2010-04-13013 April 2010 Technical Specifications Proposed Change No. 290 Administrative Changes BVY 10-021, Revision of Technical Specification Bases Pages2010-03-31031 March 2010 Revision of Technical Specification Bases Pages BVY 09-072, Technical Specification Bases Pages Associated with License Amendment 2362009-12-0909 December 2009 Technical Specification Bases Pages Associated with License Amendment 236 BVY 09-074, Revision of Technical Specifications Bases Pages2009-12-0909 December 2009 Revision of Technical Specifications Bases Pages BVY 09-068, Technical Specifications Proposed Change No. 288 Scram Discharge Volume Vent and Drain Valves2009-12-0303 December 2009 Technical Specifications Proposed Change No. 288 Scram Discharge Volume Vent and Drain Valves BVY 09-055, Revision of Technical Specifications Bases Page2009-09-28028 September 2009 Revision of Technical Specifications Bases Page BVY 09-044, Revision of Technical Specifications Bases Pages2009-07-28028 July 2009 Revision of Technical Specifications Bases Pages BVY 09-021, Submittal of Revision of Technical Specification Bases Pages2009-03-31031 March 2009 Submittal of Revision of Technical Specification Bases Pages BVY 09-014, Submittal of Revised Technical Specification Bases Pages2009-02-24024 February 2009 Submittal of Revised Technical Specification Bases Pages BVY 08-087, Vermont Yankee Nuclear Power Station, Response to Request for Additional Information on Technical Specifications Proposed Change No. 273, Supplement 62008-12-18018 December 2008 Vermont Yankee Nuclear Power Station, Response to Request for Additional Information on Technical Specifications Proposed Change No. 273, Supplement 6 ML0836500072008-12-18018 December 2008 Vermont Yankee Nuclear Power Station, Response to Request for Additional Information on Technical Specifications Proposed Change No. 273, Supplement 6 BVY 08-087, Attachment 2, Technical Specification Proposed Change No. 273, Supplement 6, Sample Set-Point Calculations2008-12-18018 December 2008 Attachment 2, Technical Specification Proposed Change No. 273, Supplement 6, Sample Set-Point Calculations BVY 08-081, Submittal of Revision of Technical Specification Bases Page 292008-11-17017 November 2008 Submittal of Revision of Technical Specification Bases Page 29 BVY 08-076, Revision of Technical Specification Bases Pages2008-10-14014 October 2008 Revision of Technical Specification Bases Pages BVY 08-052, Technical Specifications Proposed Change No. 278, Changes to Main Steam Isolation Valve Surveillance Requirements2008-09-22022 September 2008 Technical Specifications Proposed Change No. 278, Changes to Main Steam Isolation Valve Surveillance Requirements BVY 08-069, Transmittal of Technical Specifications Proposed Change No. 281, Revision to Battery Systems2008-09-22022 September 2008 Transmittal of Technical Specifications Proposed Change No. 281, Revision to Battery Systems BVY 08-060, Submittal of Revision of Technical Specification Bases Page 2202008-08-25025 August 2008 Submittal of Revision of Technical Specification Bases Page 220 BVY 08-046, Revision of Technical Specification Bases Page 972008-07-28028 July 2008 Revision of Technical Specification Bases Page 97 BVY 08-031, Revision of Technical Specification Bases Page2008-05-29029 May 2008 Revision of Technical Specification Bases Page BVY 07-052, Revision of Technical Specification Bases Pages2007-07-31031 July 2007 Revision of Technical Specification Bases Pages BVY 07-043, Revision of Technical Specification Bases Pages2007-06-21021 June 2007 Revision of Technical Specification Bases Pages BVY 07-015, Technical Specifications Proposed Change No. 272 - Transmittal of Final Retyped Technical Specifications Pages2007-03-14014 March 2007 Technical Specifications Proposed Change No. 272 - Transmittal of Final Retyped Technical Specifications Pages BVY 06-028, Technical Specifications Proposed Change No. 272, Relocation of LCO 3.6.I and SR 4.6.I and Addition of LCO 3.0.8 Regarding Snubbers2006-04-22022 April 2006 Technical Specifications Proposed Change No. 272, Relocation of LCO 3.6.I and SR 4.6.I and Addition of LCO 3.0.8 Regarding Snubbers BVY 06-001, Vermont Yankee - Technical Specification Proposed Change No. 263 - Supplement No. 44 Extended Power Uprate - Revised License and Technical Specifications2006-01-10010 January 2006 Vermont Yankee - Technical Specification Proposed Change No. 263 - Supplement No. 44 Extended Power Uprate - Revised License and Technical Specifications BVY 05-099, Vermont Yankee, Technical Specification Proposed Change No. 263 - Supplement No. 39 Extended Power Uprate - Risk Analysis of Containment Overpressure2005-10-26026 October 2005 Vermont Yankee, Technical Specification Proposed Change No. 263 - Supplement No. 39 Extended Power Uprate - Risk Analysis of Containment Overpressure BVY 05-074, Transmittal of Vermont Yankee Technical Specification Proposed Change No. 263 - Supplement No. 31 Extended Power Uprate - Response for Additional Information2005-08-0404 August 2005 Transmittal of Vermont Yankee Technical Specification Proposed Change No. 263 - Supplement No. 31 Extended Power Uprate - Response for Additional Information BVY 05-072, Vermont Yankee, Technical Specification Proposed Change No. 263 - Supplement No. 30 Extended Power Uprate - Response to Request for Additional Information2005-08-0101 August 2005 Vermont Yankee, Technical Specification Proposed Change No. 263 - Supplement No. 30 Extended Power Uprate - Response to Request for Additional Information ML0511902932005-04-22022 April 2005 Response to Request for Additional Information - Technical Specification Proposed Change No. 268. One- Time Integrated Leak Rate Test (ILRT) . One-time Integrated Leak Rate Test (ILRT) Interval Extension 2015-03-25
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Entergy Nuclear Operations, Inc.
Vermont Yankee 320 Governor Hunt Rd Vernon, VT 05354 SEntergy Tel 802 257 7711 Coley C. Chappell Licensing Manager BVY 15-024 March 25, 2015 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Revision of Technical Specifications Bases Pages Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28
REFERENCE:
Letter, USNRC to Entergy Nuclear Operations, Inc., "Vermont Yankee Nuclear Power Station - Issuance of Amendment to Renewed Facility Operating License RE: Eliminate Operability Requirements for Secondary Containment when Handling Sufficiently Decayed Irradiated Fuel or a Fuel Cask (TAC NO. MF3068)," NVY 15-013, dated February 12, 2015 (ML14304A588)
Dear Sir or Madam:
This letter provides revised Vermont Yankee Nuclear Power Station (VYNPS) Technical Specification (TS) Bases pages. The TS Bases were revised in conjunction with an Amendment to Renewed Facility Operating License DPR-28 issued in the referenced letter.
These changes, processed in accordance with our Technical Specification Bases Control Program (TS 6.7.E), were determined not to require prior NRC approval. The revised Bases pages are provided for your information and for updating and inclusion with your copy of the VYNPS TS. No NRC action is required in conjunction with this submittal.
There are no new regulatory commitments being made in this submittal.
Should you have any questions concerning this submittal, please contact me at 802-451-3374.
Sincerely, Ccc/lAcc
BVY 15-024 / Page 2 of 2
Attachment:
- 1. Revised Technical Specifications Bases Pages (5 pages) cc: Mr. Daniel H. Dorman Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 Mr. James S. Kim, Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 08D15 Washington, DC 20555 USNRC Resident Inspector Mr. Christopher Recchia, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, Vermont 05620-2601
BVY 15-024 Docket No. 50-271 Attachment 1 Vermont Yankee Nuclear Power Station Revised Technical Specifications Bases Pages (5 pages)
VYNPS BASES: 3.2.C/4.2.C REACTOR BUILDING VENTILATION ISOLATION AND STANDBY GAS TREATMENT SYSTEM INITIATION APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY (continued) instrumentation are implicitly assumed in the safety analyses of References 2, 3, and 4, to initiate closure of the RBAVSIVs and start the SGT System to limit offsite doses.
Reactor building ventilation isolation and Standby Gas Treatment System initiation instrumentation satisfies Criterion 3 of 10 CFR 50.36(c) (2) (ii).
The operability of the reactor building ventilation isolation and Standby Gas Treatment System initiation instrumentation is dependent on the operability of the individual instrumentation channel Trip Functions specified in Table 3.2.3.
Each Trip Function must have the required number of operable channels in each trip system, with their trip setpoints within the calculational as-found tolerances specified in plant procedures. Operation with actual trip setpoints within calculational as-found tolerances provides reasonable assurance that, under worst case design basis conditions, the associated trip will occur within the Trip Settings specified in Table 3.2.3. As a result, a channel is considered inoperable if its actual trip setpoint is not within the calculational as-found tolerances specified in plant procedures. The actual trip setpoint is calibrated consistent with applicable setpoint methodology assumptions.
In general, the individual Trip Functions are required to be OPERABLE in RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (with reactor coolant temperature
> 212'F), during operations with the potential for draining the reactor vessel (OPDRVs) and during movement of recently irradiated fuel assemblies in secondary containment, and during Alteration of the Reactor Core; consistent with the Applicability for the SGT System and secondary containment requirements in Specifications 3.7.B and 3.7.C. Trip Functions that have different Applicabilities are discussed below in the individual Trip Functions discussion.
"Recently irradiated" fuel is defined as fuel that has occupied part of a critical reactor core within the previous 13 days, i.e. reactor fuel that has decayed less than 13 days following reactor shutdown. This minimum decay period is enforced to maintain the validity of the Fuel Handling Accident dose consequence analysis.
The specific Applicable Safety Analyses, LCO, and Applicability discussions are listed below on a Trip Function by Trip Function basis.
- 1. Low Reactor Vessel Water Level Low reactor pressure vessel (RPV) water level indicates that the capability to cool the fuel may be threatened. Should RPV water level decrease too far, fuel damage could result. An isolation of the secondary containment and actuation of the SGT System are initiated in order to minimize the potential of an offsite release. The Low Reactor Vessel Water Level Trip Function is one of the Trip Functions assumed to be operable and capable of providing isolation and initiation signals. The isolation and initiation of systems on Low Reactor Vessel Water Level support actions to ensure that any offsite releases are within the limits calculated in the safety analysis.
Low Reactor Vessel Water Level signals are initiated from level transmitters that sense the difference between the pressure due to a constant column of water (reference leg) and the pressure due to the actual water level (variable leg) in the vessel. Four channels of Low Reactor Vessel Water Level Trip Function are available and are required to be operable to ensure that no single instrument failure can preclude the isolation and initiation function.
Amendment No. 2-34, 262 76p
VYNPS BASES: 3.2.C/4.2.C REACTOR BUILDING VENTILATION ISOLATION AND STANDBY GAS TREATMENT SYSTEM INITIATION APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY (continued) have originated from the primary containment due to a break in the RCPB or the refueling floor due to a fuel handling accident. When High Reactor Building Ventilation Radiation or High Refueling Floor Zone Radiation is detected, secondary containment isolation and actuation of the SGT System are initiated to support actions to limit the release of fission products as assumed in the UFSAR safety analyses (Ref. 4).
The High Reactor Building Ventilation Radiation and High Refueling Floor Zone Radiation signals are initiated from radiation detectors that are located on the ventilation exhaust duct coming from the reactor building and the refueling floor zones, respectively. Two channels of High Reactor Building Ventilation Radiation Trip Function and two channels of High Refueling Floor Radiation Trip Function are available and are required to be operable to ensure that no single instrument failure can preclude the isolation and initiation function.
The Trip Settings are chosen to promptly detect gross failure of the fuel cladding.
The High Reactor Building Ventilation Radiation and High Refueling Floor Zone Radiation Trip Functions are required to be operable in RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (with reactor coolant temperature > 212'F) where considerable energy exists in the RCS; thus, there is a possibility of pipe breaks resulting in significant releases of radioactive steam and gas. In COLD SHUTDOWN and Refuel (with reactor coolant temperature < 212'F), the probability and consequences of these events are low due to the RCS pressure and temperature limitations of these Modes; thus, these Trip Functions are not required. In addition, the Trip Functions are also required to be operable during OPDRVs and during movement of recently irradiated fuel assemblies in the secondary containment, and during Alteration of the Reactor Core, because the capability of detecting radiation releases due to fuel failures (due to fuel uncovery or dropped fuel assemblies) must be provided to ensure that offsite dose limits are not exceeded.
"Recently irradiated" fuel is defined as fuel that has occupied part of a critical reactor core within the previous 13 days, i.e. reactor fuel that has decayed less than 13 days following reactor shutdown. This minimum decay period is enforced to maintain the validity of the Fuel Handling Accident dose consequence analysis.
ACTIONS Table 3.2.3 ACTION Note 1 Because of the diversity of sensors available to provide isolation signals and the redundancy of the isolation design, an allowable out of service time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> depending on the Trip Function (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for those Trip Functions that have channel components common to RPS instrumentation, i.e.,
Trip Functions 1 and 2, and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for those Trip Functions that do not have channel components common to RPS instrumentation, i.e., all other Trip Functions), has been shown to be acceptable (Refs. 5 and 6) to permit restoration of any inoperable channel to operable status. This out of service time is only acceptable provided the associated Trip Function is still maintaining isolation capability (refer to next paragraph). If the inoperable channel cannot be restored to operable status within the allowable out of service time, the channel must be placed in the tripped condition per Table 3.2.3 Note l.a.l) or l.a.2), as applicable. Placing the inoperable channel in trip would conservatively compensate for the inoperability, restore capability to accommodate a single failure, and allow operation to continue. Alternately, Amendment No. 2-34, 262 76r
VYNPS BASES: 3.7 (Cont'd) surveillances such as monthly torus to drywell vacuum breaker tests.
Procedurally, when AC-6A is open, AC-6 and AC-7 are closed to prevent overpressurization of the SBGT system or the reactor building ductwork, should a LOCA occur. For this and similar analyses performed, a spurious opening of AC-6 or AC-7 (one of the closed containment isolation valves) is not assumed as a failure simultaneous with a postulated LOCA. Analyses demonstrate that for normal plant operation system alignments, including surveillances such as those described above, that SBGT integrity would be maintained if a LOCA was postulated. Therefore, during normal plant operations, the 90 hour0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> clock does not apply. Accordingly, opening of the 18 inch atmospheric control isolation valves AC-7A, AC-7B, AC-8 and AC-10 will be limited to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per calendar year (except for performance of the subject valve stroke time surveillances - in which case the appropriate corresponding valves are closed to protect equipment should a LOCA occur). This restriction will apply whenever primary containment integrity is required. The 90 hour0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> clock will apply anytime purge and vent evolutions can not assure the integrity of the SBGT trains or related equipment.
B. and C. Standby Gas Treatment System and Secondary Containment System The secondary containment is designed to minimize any ground level release of radioactive materials which might result from a serious accident. The Reactor Building provides secondary containment during reactor operation, when the drywell is sealed and in service; the Reactor Building provides primary containment when the reactor is shutdown and the drywell is open, as during refueling. Because the secondary containment is an integral part of the complete containment system, secondary containment is required at all times that primary containment is required except, however, for initial fuel loading and low power physics testing.
In the Cold Shutdown condition or the Refuel Mode, the probability and consequences of the LOCA are reduced due to the pressure and temperature limitations in these conditions. Therefore, maintaining Secondary Containment Integrity is not required in the Cold Shutdown condition or the Refuel Mode, except for other situations for which significant releases of radioactive material can be postulated, such as during operations with a potential for draining the reactor vessel, during alteration of the Reactor Core, or during movement of recently irradiated fuel assemblies in the secondary containment.
"Recently irradiated" fuel is defined as fuel that has occupied part of a critical reactor core within the previous 13 days, i.e. reactor fuel that has decayed less than 13 days following reactor shutdown. This minimum decay period is enforced to maintain the validity of the Fuel Handling Accident dose consequence analysis.
In order for secondary containment integrity to be met, the secondary containment must function properly in conjunction with the operation of the Standby Gas Treatment System to ensure that the required vacuum can be established and maintained. This means that the reactor building is intact with at least one door in each access opening closed, and all reactor building automatic ventilation system isolation valves are operable or the affected penetration flow path is isolated.
With the reactor in the Run Mode, the Startup Mode, or the Hot Shutdown condition, if Secondary Containment Integrity is not maintained, Secondary Containment Integrity must be restored within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> provides a period of time to correct the problem that is commensurate with the importance of maintaining secondary containment during the Run Mode, the Startup Mode, and the Hot Shutdown condition.
This time period also ensures that the probability of an accident (requiring Secondary Containment Integrity) occurring during periods where Secondary Containment Integrity is not maintained, is minimal.
Amendment No. 4-, 4-43, 4-44, 4-6-, 4-9-4, 262 165a
VYNPS BASES: 3.7 (Cont'd)
If Secondary Containment Integrity cannot be restored within the required time period, the plant must be brought to a mode or condition in which the LCO does not apply.
Movement of recently irradiated fuel assemblies in the secondary containment, alteration of the Reactor Core, and operations with the potential for draining the reactor vessel can be postulated to cause fission product release to the secondary containment. In such cases, the secondary containment is the only barrier to release of fission products to the environment. Alteration of the Reactor Core and movement of recently irradiated fuel assemblies must be immediately suspended if Secondary Containment Integrity is not maintained.
Suspension of these activities shall not preclude completing an action that involves moving a component to a safe position. Also, action must be immediately initiated to suspend operations with the potential for draining the reactor vessel to minimize the probability of a vessel draindown and subsequent potential for fission product release.
Actions must continue until operations with the potential for draining the reactor vessel are suspended.
Amendment No. 4-4-3, 4-44, 4-64-, 262 165b
VYNPS BASES: 3.7 (Cont'd)
The Standby Gas Treatment System (SGTS) is designed to filter and exhaust the Reactor Building atmosphere to the stack during secondary containment isolation conditions, with a minimum release of radioactive materials from the Reactor Building to the environs. To insure that the standby gas treatment system will be effective in removing radioactive contaminates from the Reactor Building air, the system is tested periodically to meet the intent of ANSI N510-1975. Laboratory charcoal testing will be performed in accordance with ASTM D3803-1989, except, as allowed by GL 99-02, testing can be performed at 70%
relative humidity for systems with humidity control. Both standby gas treatment fans are designed to automatically start upon containment isolation and to maintain the Reactor Building pressure to approximately a negative 0.15 inch water gauge pressure; all leakage should be in-leakage. Should the fan fail to start, the redundant alternate fan and filter system is designed to start automatically.
Each of the two fans has 100% capacity. This substantiates the availability of the operable train and results in no added risk; thus, reactor operation or refueling operation can continue. If neither train is operable, the plant is brought to a condition where the system is not required.
When the reactor is in cold shutdown or refueling the drywell may be open and the Reactor Building becomes the only containment system.
During cold shutdown the probability and consequences of a DBA LOCA are substantially reduced due to the pressure and temperature limitations in this mode. However, for other situations under which significant radioactive release can be postulated, such as during operations with a potential for draining the reactor vessel, during core alterations, or during movement of recently irradiated fuel in the secondary containment, operability of standby gas treatment is required.
Both trains of the Standby Gas Treatment System are normally operable when secondary containment integrity is required. However, Specification 3.7.B.3 provides Limiting Conditions for Operation when one train of the Standby Gas Treatment System is inoperable.
Provisional, continued operation is permitted since the remaining operable train is adequate to perform the required radioactivity release control function. If the applicable conditions of Specification 3.7.B.3 cannot be met, the plant must be placed in a mode or condition where the Limiting Conditions for Operation do not apply.
Entry into a refueling condition with one train of SBGTS inoperable is acceptable and there is no prohibition on mode or condition entry in this situation. In this case, the requirements of TS 3.7.B.3.b are sufficient to ensure that adequate controls are in place. During refueling conditions, accident risk is significantly reduced, and the primary activities of concern involve core alterations, movement of recently irradiated fuel assemblies and OPDRVs.
During refueling and cold shutdown conditions Specification 3.7.B.3.b provides for the indefinite continuance of refueling operations with one train of the Standby Gas Treatment System inoperable. When the seven-day completion time associated with Specification 3.7.B.3.b is not met and secondary containment integrity is required, the operable train of the Standby Gas Treatment System should immediately be placed into operation. This action ensures that the remaining train is operable, that no failures that could prevent automatic actuation have occurred, and that any other failure would be readily detected. An alternative to placing the operable train of Standby Gas Treatment in operation is to immediately suspend activities that represent a potential for releasing radioactive material to the secondary containment, thus placing the plant in a condition that minimizes risk.
Amendment No. 4-&, 4-9, 4-4-3, 4*4-, 4-94, 262 166