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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:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARBVY 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 3F1120-02, and Crystal River Nuclear Plant - Application for Order Approving Indirect Transfers of Control of Licenses in Connection with Internal Corporate Reorganization2020-11-19019 November 2020 and Crystal River Nuclear Plant - Application for Order Approving Indirect Transfers of Control of Licenses in Connection with Internal Corporate Reorganization BVY 17-004, Technical Specifications Proposed Change No. 313: Revision to License and Permanently Defueled Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool2017-07-20020 July 2017 Technical Specifications Proposed Change No. 313: Revision to License and Permanently Defueled Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool BVY 17-022, License Amendment Request - Cyber Security Plan License Condition Removal Proposed Change No. 3162017-07-13013 July 2017 License Amendment Request - Cyber Security Plan License Condition Removal Proposed Change No. 316 BVY 17-005, Application for Order Consenting to Direct and Indirect Transfers of Control of Licenses and Approving Conforming License Amendment and Notification of Amendment to Decommissioning Trust Agreement2017-02-0909 February 2017 Application for Order Consenting to Direct and Indirect Transfers of Control of Licenses and Approving Conforming License Amendment and Notification of Amendment to Decommissioning Trust Agreement BVY 15-040, License Amendment Request - Revised Cyber Security Plan Implementation Schedule - Proposed Change No. 3112015-06-24024 June 2015 License Amendment Request - Revised Cyber Security Plan Implementation Schedule - Proposed Change No. 311 BVY 14-083, Technical Specifications Proposed Change No. 307, Revision to Technical Specification Administrative Controls for Permanently Defueled Condition - Supplement 32014-12-0505 December 2014 Technical Specifications Proposed Change No. 307, Revision to Technical Specification Administrative Controls for Permanently Defueled Condition - Supplement 3 BVY 14-062, Proposed Change No. 310 - Deletion of Renewed Facility Operating License Conditions Related to Decommissioning Trust Provisions2014-09-0404 September 2014 Proposed Change No. 310 - Deletion of Renewed Facility Operating License Conditions Related to Decommissioning Trust Provisions BVY 13-109, Cyber Security Plan Implementation Schedule, Proposed Change No. 3082013-12-19019 December 2013 Cyber Security Plan Implementation Schedule, Proposed Change No. 308 BVY 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 ML13323A5182013-11-14014 November 2013 Technical Specifications Proposed Change No. 306 Eliminate Certain ESF Requirements During Movement of Irradiated Fuel BVY 12-084, License Amendment Request; Changes to 10CFR50.63 Licensing Basis2012-12-21021 December 2012 License Amendment Request; Changes to 10CFR50.63 Licensing Basis BVY 12-085, Technical Specifications Proposed Change No. 302 Inoperable Control Rods2012-12-17017 December 2012 Technical Specifications Proposed Change No. 302 Inoperable Control Rods 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 12-016, License Amendment Request to Revise License Renewal Commitments2012-03-12012 March 2012 License Amendment Request to Revise License Renewal Commitments 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 11-085, Proposed Change No. 296, Steam Dryer License Condition Change2011-12-22022 December 2011 Proposed Change No. 296, Steam Dryer License Condition Change BVY 11-069, Technical Specifications Proposed Change No. 295 Proposed Emergency License Amendment for Single Loop Operation2011-09-29029 September 2011 Technical Specifications Proposed Change No. 295 Proposed Emergency License Amendment for Single Loop Operation 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 10-045, Technical Specifications Proposed Change No. 289 Suppression Chamber-Drywell Vacuum Breakers and Differential Pressure2010-08-19019 August 2010 Technical Specifications Proposed Change No. 289 Suppression Chamber-Drywell Vacuum Breakers and Differential Pressure BVY 10-036, Technical Specifications Proposed Change No. 292, License Amendment Withdrawal and Request - Cyber Security Plan2010-07-16016 July 2010 Technical Specifications Proposed Change No. 292, License Amendment Withdrawal and Request - Cyber Security Plan 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 09-063, Technical Specification Proposed Change No. 287 Safety Limit Minimum Critical Power Ratio Change2009-10-27027 October 2009 Technical Specification Proposed Change No. 287 Safety Limit Minimum Critical Power Ratio Change 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 ML0912001622009-05-31031 May 2009 Safety Evaluation Report Related to the License Renewal of Vermont Yankee Nuclear Power Station Supplement 1 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 09-012, 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 BVY 08-079, Technical Specifications Proposed Change No. 280, Supplement 1 Relocation of Reactor Building Crane Technical Specifications2008-10-31031 October 2008 Technical Specifications Proposed Change No. 280, Supplement 1 Relocation of Reactor Building Crane Technical Specifications BVY 08-055, Technical Specifications Proposed Change No. 277, License Amendment Request Application for Licensee Name Changes2008-09-30030 September 2008 Technical Specifications Proposed Change No. 277, License Amendment Request Application for Licensee Name Changes 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 08-052, 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 08-053, Technical Specifications Proposed Change No. 279 Sale or Lease of Property within the Exclusion Boundary2008-09-0404 September 2008 Technical Specifications Proposed Change No. 279 Sale or Lease of Property within the Exclusion Boundary 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 ML0806602032008-02-12012 February 2008 Vermont Yankee, Technical Specifications Proposed Change No. 273, Instrumentation Technical Specifications BVY 08-007, Technical Specification Proposed Change No. 276 Revision to TS Sections 3.3/4.3 for Control Rod System2008-02-0606 February 2008 Technical Specification Proposed Change No. 276 Revision to TS Sections 3.3/4.3 for Control Rod System ML0804202202008-02-0505 February 2008 Vermont Yankee - License Renewal Application, Amendment 35 ML0736502282007-12-11011 December 2007 (PA-LR) VY Response to RAI 4.3.3-2 BVY 07-056, Technical Specification Proposed Change No. 274, Changes to Technical Specifications for Emergency Diesel Generator Fuel Oil and Reactor Building Crane Surveillance Requirements2007-10-18018 October 2007 Technical Specification Proposed Change No. 274, Changes to Technical Specifications for Emergency Diesel Generator Fuel Oil and Reactor Building Crane Surveillance Requirements BVY 07-063, Technical Specifications Proposed Change No. 275 Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Limits2007-10-18018 October 2007 Technical Specifications Proposed Change No. 275 Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Limits BVY 07-018, License Renewal Application, Amendment 262007-03-23023 March 2007 License Renewal Application, Amendment 26 ML0702402042007-01-10010 January 2007 Email: (PA-LR) Other Word File ML0701105042007-01-0404 January 2007 Vermont Yankee - License Renewal Application, Amendment 23 ML0634201782006-12-0404 December 2006 2006/12/04-Vermont Yankee Nuclear Power Station, License Renewal Application, Amendment 22, Clarification of Aging Management Program and Environmental Report Items ML0634004532006-11-0909 November 2006 2006/11/09-E-Mail: (NPA-PD-LR) VYNPS License Renewal Application Am. 20, Vermont Yankee BVY 06-097, 2006/10/31-Vermont Yankee License Renewal Application, Amendment 192006-10-31031 October 2006 2006/10/31-Vermont Yankee License Renewal Application, Amendment 19 ML0627801222006-10-12012 October 2006 Summary of a Telephone Conference Call Held on September 19, 2006, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc ML0626800342006-09-19019 September 2006 2006/09/19-Vermont Yankee License Renewal Application, Amendment 13 ML0625504392006-09-0505 September 2006 License Renewal Application, Amendment 12 2023-10-10
[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:Amendment
MONTHYEARBVY 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 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 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 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 09-029, 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 09-012, 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 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 08-066, Submittal of Corrected Technical Specification Page2008-08-26026 August 2008 Submittal of Corrected Technical Specification 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 ML0535301802005-12-12012 December 2005 Technical Specification Proposed Change No. 266, Revision to Control Rod Operability, Scram Time Testing and Control Rod Accumulators - Response to Request for Additional Information BVY 05-101, Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 263 - Supplement No. 41 Re Extended Power Uprate - Condensate and Feedwater Transient Response Engineering Analysis2005-11-0202 November 2005 Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 263 - Supplement No. 41 Re Extended Power Uprate - Condensate and Feedwater Transient Response Engineering Analysis BVY 05-088, Vermont Yankee, Technical Specification Proposed Change No. 263 - Supplement No. 35 Extended Power Uprate - Response to Request for Additional Information2005-09-28028 September 2005 Vermont Yankee, Technical Specification Proposed Change No. 263 - Supplement No. 35 Extended Power Uprate - Response to Request for Additional Information BVY 05-086, Vermont Yankee - Technical Specifications Proposed Change No. 263 - Supplement No. 34 Extended Power Uprate - Additional Information2005-09-18018 September 2005 Vermont Yankee - Technical Specifications Proposed Change No. 263 - Supplement No. 34 Extended Power Uprate - Additional Information ML0524402132005-08-31031 August 2005 Technical Specification Page, Revision to One-Time Extension of Integrated Leak Rate Test Interval ML0508402532005-03-22022 March 2005 Tech Spec Pages for Amendment 222 Regarding Elimination of Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports ML0505401492005-02-18018 February 2005 Corrected Page 7 to License DPR-28 and Page 97 to Technical Specifications for Vermont Yankee BVY 04-098, Vermont Yankee - Technical Specification Proposed Change No. 263 - Supplement No. 14 Extended Power Uprate - Response to Request for Additional Information2004-09-15015 September 2004 Vermont Yankee - Technical Specification Proposed Change No. 263 - Supplement No. 14 Extended Power Uprate - Response to Request for Additional Information ML0408602662004-03-22022 March 2004 Technical Specification, Safety Limit Minimum Critical Power Ratio Values in Technical Specification 1.1.A.1 to Incorporate Results in cycle-specific Core Reload Analysis for Cycle 24 Operation ML0329301432003-10-10010 October 2003 Technical Specification Proposed Change No. 262, Supplement No. 1 Regarding Alternative Source Term ML0328104472003-10-0101 October 2003 Vermont Yankee - Technical Specification Proposed Change No. 263, Supplemental No. 1 Regarding Extended Power Uprate, Technical Review Guidance ML0321906462003-07-31031 July 2003 TS Proposed Change No. 262, Alternative Source Term ML0226302842002-09-18018 September 2002 Technical Specifications, Remove Existing Scram Function & Group 1 Isolation Valve Closure Functions of Main Steam Line Radiation Monitors ML17037B7791974-02-0707 February 1974 Letter Regarding Petition for Derating of Certain Boiling Water Reactors and Enclosed Before the Atomic Safety and Licensing Appeal Board in the Matter of Vermont Yankee Nuclear Power Corporation - Vermont Yankee Nuclear ... 2014-06-11
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4l Entergy Nuclear Operations, Inc.
Vermont Yankee P.O. Box 0250 Entergy Governor Hunt Road Vernon, VT 05354 Tel 802 257 7711 Michael J Colomb Site Vice President May 5, 2009 BVY 09-029 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Technical Specifications Proposed Change No. 283 Change to Requirements for Performing the 10CFR50, Appendix J, Type A Test Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28
Dear Sir or Madam:
Pursuant to 10CFR50.90, Entergy Nuclear Operations, Inc. (ENO) is proposing to amend Operating License DPR-28 for the Vermont Yankee Nuclear Power Station (VY). The proposed change would revise the Operating License Technical Specifications (TS) Section 6.7.C to change the portion of the specification that defines requirements related to the schedule for performing the 10CFR50, Appendix J, Type A test. Specifically, the proposed change would change the TS from requiring the test "no later than April 2010" to "prior to startup from the April 2010 refuel outage."
ENO has reviewed the proposed amendment in accordance with 10CFR50.92 and concludes it does not involve a significant hazards consideration. In accordance with 1 OCFR50.91, a copy of this application, with attachments, was provided to the State of Vermont, Department of Public Service.
Attachment 1 to this letter provides an evaluation of the proposed change. Attachment 2 contains a markup of the current TS page. Attachment 3 contains the retyped TS page.
To support our April 2010 refueling outage schedule, ENO requests approval of the proposed amendment by February 1,2010 with a 60 day implementation period.
There are no new regulatory commitments made in this letter.
,407
BVYO09-029 /Page 2of 2 If you have any questions on this transmittal, please contact Mr. David Mannai at (802) 451-3304.
I declare under penalty of perjury that the foregoing is true and correct. Executed on May 5, 2009.
Sincerely, MJC/JMD : Evaluation of the Proposed Change : Markup of the Current Technical Specifications Page : Retyped Technical Specification Page 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 S. Kim, Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 08C2A 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
BVY 09-029 Docket No. 50-271 Attachment 1 Vermont Yankee Nuclear Power Station Proposed Change 283 Evaluation of the Proposed Change
BVY 09-029 / Attachment 1 / Page 1 of 5 EVALUATION OF THE PROPOSED CHANGE
- 1. Description of Change Entergy Nuclear Operations, Inc. (ENO) is requesting to amend Operating License DPR-28 for Vermont Yankee Nuclear Power Station (VY). The proposed change would revise the Operating License Technical Specifications (TS) Section 6.7.C to change the portion ofthe specification that defines requirements related to the schedule for performing the 10CFR50, Appendix J, Type A test. Specifically, the proposed change would change the TS from performing the next Type A test "no later than April 2010" to "prior to startup from the April 2010 refuel outage."
- 2. Proposed Chanqe The following change is proposed to the current TS Section 6.7.C:
Current TS 6.7.C The first.Type A test after the April 1995 Type A test shall be performed no later than April 2010. (This is an exception to Section 9.2.3 of NEI 94-01, Rev. 0, "Industry Guidelines for Implementing Performance-Based Option of 10CFR50, Appendix J.")
Proposed TS 6.7.C The first Type A test after the April 1995 Type A test shall be performed prior to startup from the April 2010 refuel outage. (This is an exception to Section 9.2.3 of NEI 94-01, Rev. 0, "Industry Guidelines for Implementing Performance-Based Option of 10CFR50, Appendix J.")
All other provisions contained in TS 6.7.C remain unchanged.
- 3. Background In License Amendment 227 (Reference (a)), the NRC approved a change to the VY TS that extended the Type A test interval from 10 years to 15 years on a one-time basis.
Subsequent Type A tests would be preformed on a schedule consistent with 10CFR50 Appendix J. The resulting TS required the next Type A test to be performed no later than April 2010. The last Type A test was performed in April 1995.
VY's next refuel outage (RFO) is scheduled to begin in April 2010, however, the Type A test, which is performed just prior to start-up, is currently scheduled to be performed during May 2010. This proposed change will require the Type A test to be performed prior to startup following the April 2010 RFO. This is considered an administrative change since it does not affect the risk impact assessment that formed the basis for allowing the frequency to be extended from 10 years to 15 years
BVY 09-029 / Attachment 1 / Page 2 of 5
- 4. Technical Analysis 10CFR50, Appendix J, Option B, requires that a Type A test be conducted at a periodic interval based on historical performance of the overall containment system. VY TS 6.7.C requires that leakage rate testing be performed as required by 10CFR50, Appendix J, Option B, as modified by approved exemptions and in accordance with guidelines contained in Regulatory Guide (RG) 1.163, "Performance-Based Containment Leak-Test Program." The RG endorses, with certain exceptions, Nuclear Energy Institute (NEI) report NEI 94-01 "Industry Guidelines for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J."
The Type A Test is an overall integrated leakage rate test of the containment structure. NEI 94-01 allows an extended interval of 10 years, based upon two consecutive successive tests. The two most recent Type A tests at VY have been successful, so the norm al interval would be 10 years.
In Reference (b), ENO submitted a proposed change to request a one-time extension of the frequency for performing the Type A test to 15 years. This submittal was supplemented by Reference (c) to address requests for additional information. NRC approved the proposed change and issued Amendment 227 to the VY Operating License (Reference (a)).
Because the last Type A test was conducted in April 1995, VY TS 6.7.C requires that the next Type A test be completed no later than April 2010 (i.e., no more than 15 years from the last test). This is an issue because, although the plant will be shutdown in April 2010, the actual performance of the test will not occur until just prior to startup from the refuel outage.
To address this ENO proposes to change TS 6.7.C to require the Type A test to be performed prior to start-up from the April 2010 refuel outage. This is considered an administrative change since it does not affect the risk impact assessment that formed the basis for allowing the frequency to be extended to 15 years.
VY is scheduled to start a refuel outage on April 24, 2010. VY TS 3.7.A.2 requires, in part, that primary containment integrity be maintained at all times when the reactor is critical or when the reactor water temperature is above 212 degrees F and fuel is in the reactor vessel. Plant shutdown is controlled by procedure OP 0105 "Reactor Operations." The process normally takes less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to bring the reactor to a subcritical condition where reactor water temperature is less than 212 degrees F and primary containment is no longer required.
The primary justification for the requested one-time extension to 15 years was a risk impact assessment of extending the Type A test interval, from 10 to 15 years, that was provided in Reference (b). The risk impact assessment was based on the guidelines of NEI 94-01, Electric Power Research Institute (EPRI) report TR-1 04285, "Risk Assessment of Revised Containment Leak Rate Testing Intervals" and NRC Regulatory Guide 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis."
BVY 09-029 / Attachment 1 / Page 3 of 5 The risk impact assessment determined that the additional risk associated with changing the Type A test frequency from 10 years to 15 years was acceptably low. A full 15 years was used for the time frame that containment integrity was assumed subject to the credible events (fault exposure period). Credit was not taken for periods of time when containment integrity was not required (e.g., outage periods). This provides for a conservative assumption relative to fault exposure time that bounds the proposed change.
VY will shut down the plant in late April 2010 and put the plant in a condition that will not require primary containment integrity prior to the end of April 2010. Primary containment integrity will not be reestablished until successful completion of the Type A test. Therefore, the proposed rewording of TS 6.7.C does not impact the assumptions made in the risk impact assessment which formed the basis for the existing TS.
This is consistent with NEI 94-01, Section 9.2.2 that states "if the test interval ends while primary containment integrity is either not required or is required solely for shutdown activities, the test interval may be extended indefinitely. However a successful Type A test shall be completed prior to entering the operating mode requiring primary containment integrity." This position was restated in NRC Regulatory Issue Summary 2008-27 "Staff Position on Extension of the Containment Type A Test Interval Beyond 15 Years Under Option B of Appendix J to 10CFR Part 50."
Based on the above, ENO considers this an administrative change that is consistent with regulatory guidance and the safety basis for the existing TS.
- 5. Regulatory Safety Analysis No Significant Hazards Consideration Entergy Nuclear Operations, Inc. (ENO) is proposing to modify the Vermont Yankee, Nuclear Power Station Operating License Technical Specifications requirements to change the portion of the specification that define requirements related to the schedule for performing the 10CFR50, Appendix J, Type A Test. Specif ically, the proposed change would change the TS from performing the Test "no later than April 2010" to "prior to startup from the April 2010 Refueling Outage."
ENO has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 1 OCFR50.92, "Issuance of amendment," as discussed below:
1.0 Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No. The change does not impact the function of any structure, system or component that affects the probability of an accident or that supports mitigation or consequences of an accident previously evaluated. The proposed change involves testing of Primary Containment but does not impact containment design or performance requirements. The proposed change ensures that the Type A test is performed prior to establishing Primary Containment following the April 2010 Refuel Outage. The proposed change does not affect reactor operations or accident analysis and there is no change to the radiological consequences of a
BVY 09-029 / Attachment 1 / Page 4 of 5 previously analyzed accident. The operability requirements for accident mitigation systems remain consistent with the licensing and design basis. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
2.0 Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No. The proposed change does not involve any physical alteration of plant equipment and does not change the method by which any safety-related system performs its function. The proposed change involves the scheduling of the Type A test and does not alter the way the test is performed. Type A tests have been previously performed and are well within the design capability of station structures, systems or components. No new or different types of equipment will be permanently installed or operated. Operation of existing installed equipment is unchanged. The methods governing plant operation and testing remain consistent with current safety analysis assumptions. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
3.0 Does the proposed change involve a significant reduction in a margin of safety?
Response: No. These changes do not change any existing design or operational requirements and do not adversely affect existing plant safety margins or the reliability of the equipment assumed to operate in the safety analysis. The proposed change affects the schedule for performing the Type A test and does not affect the way the test is performed or margins for the existing Primary Containment. As such, there are no changes being made to safety analysis assumptions, safety limits or safety system settings that would adversely affect plant safety as a result of the proposed change. Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, ENO concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 1 OCFR50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
- 5. Environmental Consideration A review has determined that the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10CFR51.22(c)(9). Therefore, pursuant to 1 OCFR51.22(b), no environmental impact statement or environrnental assessment needs to be prepared in connection with the proposed amendment.
BVY 09-029 / Attachment 1 / Page 5 of 5
- 6. Precedents None
- 7. References
- a. Letter, USNRC to Entergy Nuclear Operations, Inc., "Vermont Yankee Nuclear Power Station - Issuance of Amendment Re: One-Time Extension of IntegratedLeak Rate Test Interval (TAC No. MC4662), NVY 05-108, dated August 31, 2005
- b. Letter, Entergy Nuclear Operations, Inc. to USNRC, 'Technical Specification Proposed Change No. 268, One-time Integrated Leak Rate Test (ILRT) Interval Extension," BVY 04-77, dated October 5, 2004
- c. Letter, Entergy Nuclear Operations, Inc. to USNRC, "Response to Request for Additional Information - Technical Specification Proposed Change No. 268, One-time Integrated Leak Rate Test (ILRT) Interval Extension," BVY 05-40, dated April 22, 2005
BVY 09-029 Docket 50-271 Attachment 2 Vermont Yankee Nuclear Power Station Proposed Change 283 Markup of the Current Technical Specifications Page
VYNPS Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating thearea of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.
C. PRIMARY CONTAINMENT LEAKAGE RATE TESTING PROGRAM A program shall be established to implement the leakage rate testing of the primary containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, entitled "Performance Based Containment Leak-Test Program," dated September 1995, as modified by the following: r' *
- The first Type A test after the ApYll 1995 Type A test shall be performed : April 2010. (This is an exception to Section 9.2.3 of NEI 94-01, Rev. 0, "Industry Guideline for Implementing Performance-Based Option of 10CFR50, Appendix J.")
The leakage contributions from the main steam pathways are excluded from the sum of the leakage rates from Type B and C tests specified in (1)Section III.B of 10CFR50, Appendix J -
Option B; (2) Section 6.4.4 of ANSI/ANS 56.8-1994; and (3)
Section 10.2 of NEI 94-01, Rev. 0.
The leakage contributions from the main steam pathways are excluded from the overall integrated leakage rate from Type A tests specified in (1)Section III.A of 10CFR50, Appendix J -
Option B; (2) Section 3.2 of ANSI/ANS 56.8-1994; and (3)
Sections 8.0 and 9.0 of NEI 94-01, Rev. 0.
The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 44 psig.
The maximum allowable primary containment leakage rate, La, at Pa, shall be 0.8% of primary containment air weight per day.
Leakage rate acceptance criteria are:
- 1. Primary containment leakage rate acceptance criterion
- 2. The as-left primary containment integrated leakage rate test (Type A test) acceptance criterion is : 0.75 La.
- 3. The combined local leakage rate test acceptance criterion for Type B and Type C tests (excluding the leakage contributions from the main steam pathways) is
- 0.6 La, calculated on a maximum pathway basis, prior to entering a mode of operation where primary containment integrity is required.
- 4. The combined local leakage rate test acceptance criterion for Type B and Type"C tests (excluding the leakage contributions from the main steam pathways) is
- 0.6 La, calculated on a minimum pathway basis, at all times when primary containment integrity is required.
Amendment No. 15 -,- 5 r---t 21--5,
- 2-2-4, ;26 265
BVY 09-029 Docket 50-271 Attachment 3 Vermont Yankee Nuclear Power Station Proposed Change 283 Retyped Technical Specification Page
VYNPS Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.
C. PRIMARY CONTAINMENT LEAKAGE RATE TESTING PROGRAM A program shall be established to implement the leakage rate testing of the primary containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, entitled "Performance Based Containment Leak-Test Program," dated September 1995, as modified by the following:
" The first Type A test after the April 1995 Type A test shall be performed prior to startup from the April 2010 refuel outage.
(This is an exception to Section 9.2.3 of NEI 94-01, Rev. 0, "Industry Guideline for Implementing Performance-Based Option of 10CFR50, Appendix J.")
Option B; (2) Section 6.4.4 of ANSI/ANS 56.8-1994; and (3)
Section 10.2 of NEI 94-01, Rev. 0.
" The leakage contributions from the main steam pathways are excluded from the overall integrated leakage rate from Type A tests specified in (1)Section III.A of 10CFR50, Appendix J -
Option B; (2) Section 3.2 of ANSI/ANS 56.8-1994; and (3)
Sections 8.0 and 9.0 of NEI 94-01, Rev. 0.
The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 44 psig.
The maximum allowable primary containment leakage rate, La, at Pa, shall be 0.8% of primary containment air weight per day.
Leakage rate acceptance criteria are:
- 1. Primary containment leakage rate acceptance criterion
- 2. The as-left primary containment integrated leakage rate test (Type A test) acceptance criterion is
- 3. The combined local leakage rate test acceptance criterion for Type B and Type C tests (excluding the leakage contributions from the main steam pathways) is < 0.6 La, calculated on a maximum pathway basis, prior to entering a mode of operation where primary containment integrity is required.
- 4. The combined local leakage rate test acceptance criterion for Type B and Type C tests (excluding the leakage cohtributions from the main steam pathways) is
- 0.6 La, calculated on a minimum pathway basis, at all times when primary containment integrity is required.
Amendment No. 1-r- i-*-7r 171,' 215-r, 3, 2-2 265