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Category:Letter type:BVY
MONTHYEARBVY 24-024, Pre-Notice of Disbursement from Decommissioning Trust2024-07-30030 July 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-023, Pre-Notice of Disbursement from Decommissioning Trust2024-07-0202 July 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-022, Pre-Notice of Disbursement from Decommissioning Trust2024-05-30030 May 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-020, Biennial Update of Quality Assurance Program Manual2024-05-22022 May 2024 Biennial Update of Quality Assurance Program Manual BVY 24-019, 2023 Radiological Environmental Operating Report2024-05-0909 May 2024 2023 Radiological Environmental Operating Report BVY 24-017, Pre-Notice of Disbursement from Decommissioning Trust2024-05-0606 May 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-018, 2023 Radiological Effluent Release Report2024-05-0505 May 2024 2023 Radiological Effluent Release Report BVY 24-016, 2023 Individual Monitoring NRC Form 5 Report2024-04-18018 April 2024 2023 Individual Monitoring NRC Form 5 Report BVY 24-014, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-04-0101 April 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-015, Pre-Notice of Disbursement from Decommissioning Trust2024-04-0101 April 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-012, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-03-14014 March 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-011, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-03-0606 March 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-010, Pre-Notice of Disbursement from Decommissioning Trust2024-03-0505 March 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-009, Withdrawal of License Amendment Request to Add License Condition 3.K, “License Termination Plan;” Proposed Change No. 3172024-02-27027 February 2024 Withdrawal of License Amendment Request to Add License Condition 3.K, “License Termination Plan;” Proposed Change No. 317 BVY 24-008, ISFSI, Annual Radioactive Effluent Release Report2024-02-26026 February 2024 ISFSI, Annual Radioactive Effluent Release Report BVY 24-006, Pre-Notice of Disbursement from Decommissioning Trust2024-02-0606 February 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 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 2024-07-30
[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 Specifications
MONTHYEARML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML18347B3592019-01-11011 January 2019 12-13-18-License Transfer Conforming Amendment Markup ML18253A2022018-10-11011 October 2018 Conforming License Amendment Approval of License Transfer Request(License DPR-28, Docket 50-271 and 72-59) ML18156A1812018-08-15015 August 2018 ISFSI Only Tech Spec Amendment Package ML16014A1692016-03-14014 March 2016 Vermont Yankee Nuclear Power Station - Issuance of Amendment No. 265 to Renewed Facility Operating License Re: Cyber Security Plan Implementation Schedule (CAC No. MF6403) ML15117A5512015-10-0707 October 2015 Issuance of Amendment for Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition 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 ML14346A0652015-02-0404 February 2015 Issuance of Amendment No. 261, Revise Site Emergency Plan for Permanently Defueled Condition to Reflect Change in On-Shift Staffing and Emergency Response Staffing ML14217A0722014-12-22022 December 2014 Issuance of Amendment No. 260, Revise and Remove Certain Requirements from Technical Specification Section 6.0, Administrative Controls, No Longer Applicable for Its Permanently Defueled Condition 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 ML13212A2012013-08-15015 August 2013 Issuance of Amendment No. 258 Change to Licensing Basis Regarding Station Blackout 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 CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications 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 11-069, 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 10-045, 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 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 ML0917400402009-07-13013 July 2009 License Amendment, Relocation of Reactor Building Crane Technical Specification BVY 09-035, Technical Specifications Proposed Change No. 273, Supplement 8, Transmittal of Final Technical Specification Pages2009-05-20020 May 2009 Technical Specifications Proposed Change No. 273, Supplement 8, Transmittal of Final Technical Specification Pages ML0901206582009-02-11011 February 2009 Issuance of Amendment Battery Systems BVY 08-084, Technical Specifications Proposed Change No. 273, Supplement 5, Response to Request for Additional Information2008-12-18018 December 2008 Technical Specifications Proposed Change No. 273, Supplement 5, Response to Request for Additional Information BVY 08-075, Technical Specifications Proposed Change No. 273, Supplement 4, Response to Request for Additional Information Related to Supplement 22008-12-15015 December 2008 Technical Specifications Proposed Change No. 273, Supplement 4, Response to Request for Additional Information Related to Supplement 2 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 08-062, Technical Specifications Proposed Change No. 273, Supplement 2, Response to Request for Additional Information2008-09-15015 September 2008 Technical Specifications Proposed Change No. 273, Supplement 2, Response to Request for Additional Information 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 08-047, Technical Specification Proposed Change No. 276, Response to Request for Additional Information2008-07-29029 July 2008 Technical Specification Proposed Change No. 276, Response to Request for Additional Information ML0817601182008-06-23023 June 2008 Technical Specifications, Amendments to Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Limits ML0811201212008-04-17017 April 2008 Technical Specifications, Amendment No. 231 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 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 ML0708607332007-03-26026 March 2007 Technical Specifications, Modify Requirements for Inoperable Snubbers by Relocating the Current TS Requirements Limiting Condition for Operation (LCO) 3.6.1 and Surveillance Requirement (SR) 4.6.1 ML0629103402006-08-28028 August 2006 Correction to Technical Specification Page 255 Amendment No. 226 BVY 06-067, Correction to Technical Specification Page2006-07-27027 July 2006 Correction to Technical Specification Page ML0603901072006-03-0202 March 2006 Vermont Yankee, Tech Spec Pages for Amendment 229 Regarding Extended Power Uprate BVY 06-018, Vermont Yankee, Technical Specification Proposed Change No. 263 - Supplement No. 45, Extended Power Uprate - Revised Technical Specification Pages2006-02-22022 February 2006 Vermont Yankee, Technical Specification Proposed Change No. 263 - Supplement No. 45, Extended Power Uprate - Revised Technical Specification Pages ML0604101192006-02-0303 February 2006 2006/02/03-Vermont Yankee - Technical Specification Proposed Change No. 263 Extended Power Uprate - Regulatory Commitment Information Regarding Potential Adverse Flow Effects BVY 05-105, Vermont Yankee Nuclear Power Station Correction to Technical Specifications Pages2005-12-12012 December 2005 Vermont Yankee Nuclear Power Station Correction to Technical Specifications Pages ML0526400902005-09-20020 September 2005 Technical Specifications, Drywell Spray Header and Nozzle Air Test Frequency BVY 05-083, Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 263 - Supplement No. 32 Extended Power Uprate - Additional Information2005-09-10010 September 2005 Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 263 - Supplement No. 32 Extended Power Uprate - Additional Information ML0522800592005-08-15015 August 2005 Tech Spec Pages for Amendment 226 Administrative Changes ML0519202762005-07-0707 July 2005 Tech Spec Pages for Amendment 225 Regarding Extend Intermediate Range Monitor Surveillance Test Frequencies ML0519202462005-06-30030 June 2005 Attachment 1 - Response to Request for Additional Information - Instrumentation Technical Specifications, Vermont Nuclear Power Station, Technical Specifications BVY 05-032, Vermont Nuclear Power Station - Response to Request for Additional Information Regarding Intermediate Range Monitor Surveillance Test Frequencies2005-03-31031 March 2005 Vermont Nuclear Power Station - Response to Request for Additional Information Regarding Intermediate Range Monitor Surveillance Test Frequencies ML0509003992005-03-29029 March 2005 Technical Specification Pages Re Alternative Source Term ML0508004322005-03-16016 March 2005 TS Pages for Amendment 221 to License DPR-28, Relocating Current Definition of Surveillance Frequency to New Technical Specification (TS) Sections 4.0.2 and 4.0.3 and Revises Requirements for Missed Surveillance in TS Section 4.0.3 ML0435102452004-12-14014 December 2004 Technical Specification Pages, Elimination of Requirements for Hydrogen/Oxygen Monitors ML0514500312004-06-0909 June 2004 E-Mail from R. Ennis of USNRC to Various, Regarding State of Vermont Comments on EPU and AST ML0411202522004-04-14014 April 2004 Technical Specification Pages for Vermont Yankee Nuclear Power Station, License Amendment, Issuance of Amendment Implementation of Arts/Mellla 2019-09-11
[Table view] |
Text
Entergy Nuclear Operations, Inc.
Vermont Yankee 320 Governor Hunt Rd Vernon, VT 05354 Tel 802 257 7711 Michael J. Colomb Site Vice President BVY 11-069 September 29, 2011 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Technical Specifications ProposedChange No. 295 Proposed Emergency License Amendment for Single Loop Operation Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28
Dear Sir or Madam:
Pursuant to 10CFR50.90, Vermont Yankee (VY) hereby proposes to amend the Technical Specifications (TS) 3.6.G "Single Loop Operation." Specifically, section 3.6.G.1 .c is proposed to be revised to add an alternate method of electrically isolating the idle recirculation loop motor generator set. provides a discussion, and evaluation of the proposed license amendment, including a significant hazards consideration review in accordance with 10CFR50.92. VY has determined that the proposed change does not result in a significant hazards consideration. Enclosure 2 provides marked-up TS and Bases pages. Enclosure 3 provides new TS and Bases pages with the proposed changes incorporated. The TS Bases pages are provided for information only.
VY has reviewed the proposed change against the criteria of 1 OCFR51.22 and has concluded that it meets the criteria provided in 1 OCFR51.22(c)(9) for categorical exclusion from the requirements for an Environmental Impact Statement or an Environmental Assessment.
VY is requesting that this license amendment request be processed as an emergency TS change in accordance with 1 OCFR50.91 (a)(5) where failure to act in a timely way could result "in prevention of either resumption of operation or of increase in power output up to the plant's licensed power level."
The VY onsite Safety Review Committee has reviewed and concurs with this proposed change.
In accordance with 10CFR50.91, a copy of this application, with attachments, is being provided to the designated state of Vermont official.
BVY 11-069 / page 2 of 2 There are no new regulatory commitments being made in this submittal.
If you have any questions on this transmittal, please contact Mr. Robert Wanczyk at 802-451-3166.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on September 29, 2011.
Sincerely,
[MJC/JTM]
Enclosures:
(1) Description and Evaluation of Proposed Change (2) Marked-up Technical Specification and Bases Pages (3) Technical Specification and Bases Pages with Changes Incorporated cc: Mr. William M. Dean 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 320 Governor Hunt Rd Vernon, Vermont 05354 Ms. Elizabeth Miller, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, Vermont 05620-2601
BVY 11-069 Docket No. 50-271 Enclosure 1 Vermont Yankee Nuclear Power Station Proposed Change No. 295 Description and Evaluation of Proposed Change
/ page 1 of 4
- 1. DESCRIPTION AND REASON FOR THE PROPOSED CHANGE Vermont Yankee (VY) Technical Specification (TS) 3.6.G "Single Loop Operation" allows the reactor to continue operation with a single recirculation loop provided certain conditions are satisfied. TS 3.6.G.1 .c specifies that the idle recirculation loop be isolated by electrically disarming the breaker to the recirculation pump motor generator (MG) set drive motor prior to startup or if disabled during reactor operation, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and until such time as the inactive recirculation loop is to be returned to service. The safety basis for this action is to prevent a cold water injection transient caused by an inadvertent pump start.
There is no specific action statement associated with a failure to comply with TS 3.6.G.1, however, should this specification not be met, action would need to be taken to shut down the plant in a timely manner consistent with 10CFR50.36(c)(2).
On September 25, 2011, the "B" recirculation pump MG tripped and VY entered TS 3.6.G.1 for single loop operation. The requirements contained in the TS for operation with a single recirculation loop were satisfied.
On September 28, 2011, during the repair effort, it was determined that it may be necessary to run the drive motor to perform maintenance prior to putting the system back in service.
To perform this maintenance, the breaker for the MG set drive motor would need to be closed which is not allowed by TS 3.6.G.1 .c.
Therefore, VY requests a revision to TS 3.6.G.1 .c to add another means of electrical isolation of the recirculation pump motor by preventing closure of the associated field breaker. This will allow the necessary maintenance to be performed and still provide appropriate protection against inadvertent recirculation pump restart.
- 2. DETAILED DESCRIPTION The Reactor Recirculation System is designed so that adequate fuel barrier thermal margin is assured following recirculation pump system malfunctions and that failure of the piping integrity does not compromise the ability of the reactor vessel internals to provide a refloodable volume. The Reactor Recirculation System consists of two pumps that are normally operating. However, operation with a single recirculation pump is allowed provided minimum critical power ratio and maximum average planar linear heat generation rate limits are changed to values specified in the Core Operating Limits Report.
During single loop operation, the idle recirculation loop is currently isolated per TS 3.6.G.1 .c by electrically disarming the recirculation pump MG set drive motor breaker, until ready to resume two loop operation. This is done to prevent a cold water injection transient caused by an inadvertent pump startup.
The event of concern is an inadvertent startup of an idle recirculation pump. The VY design bases initial conditions and assumptions for this event were chosen to maximize the severity of the transient. When the recirculation pump MG set drive motor breaker closes, the motor reaches synchronous speed quickly and the generator reaches full speed in approximately 5 seconds. When the generator field breaker is closed, loading the generator and applying starting torque to the pump motor, generator speed decreases as the generator tries to start the pump. A rise in core flow occurs from the surge in flow of the startup loop jet pump diffusers accompanied by a short duration neutron flux peak.
/ page 2 of 4 Throughout the transient diffuser flow in the startup loop jet pumps is either reversed or remains less than 10 percent. For this reason the cold loop water does not significantly, affect the transient. A rise in core flow occurs from the surge in flow of the startup loop jet pump diffusers accompanied by a short duration neutron flux peak at less than 120%.
In order to restore the recirculation pump MG set to service, it may be necessary to run its drive motor to perform maintenance. The amendment request proposes a functionally equivalent means for preventing inadvertent pump startup by electrically disarming the recirculation pump MG's field breaker preventing its closure. With the field breaker open, the generator will not develop output voltage and the recirculation motor cannot drive the associated pump.
The effects of residual voltage are not a concern because, with an initially open field breaker, the generator cannot develop any output voltage. The field breaker for VY's recirculation MG set consists of two poles which apply or remove field voltage from the generator field. A third pole inserts a resistor across the generator field when the field breaker opens. The resistor is used to rapidly reduce field voltage and to cause generator residual voltage to decay rapidly and speed coastdown of the pump motor.
VY has evaluated the proposed change from a risk standpoint. This assessment is based on the qualitative argument that a functionally equivalent means for preventing a power excursion from occurring due to inadvertent start of Recirculation Pump is provided, thus the change will not cause risk to exceed the level determined acceptable during normal work controls and, therefore, there is no net increase in radiological risk to the public.
The proposed change to provide an alternate method of electrical isolation for an idle recirculation motor generator set is acceptable based on the equivalent level of protection provided against an inadvertent transient.
- 3. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION No Significant Hazards Assessment The proposed change revises Technical Specification (TS) 3.6.G.1 .c to allow electrically disarming the idle recirculation loop using either the recirculation pump motor generator (MG) set drive motor breaker or the recirculation pump MG set field breaker. This is considered functionally equivalent since with the MG set field breaker open the MG set will not develop output voltage and the MG cannot drive the recirculation pump.
VY has evaluated whether or not a significant hazards consideration is involved with the proposed change by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No. The Reactor Recirculation System is not an initiator or mitigator of any Updated Final Safety Analysis Report (UFSAR) Chapter 14.6 Design Basis Accidents.
UFSAR Chapter 14.5 evaluates malfunctions associated with the Reactor Recirculation System and concludes that none of these malfunctions results in any fuel damage. This proposed change provides an alternative for preventing the recirculation pump from starting. The TS will now allow either electrically disarming the MG set drive motor
/ page 3 of 4 breaker or electrically disarming the MG set field breaker. This is considered a functionally equivalent level of protection. System operation continues to be bounded by the station safety analysis. This request does not in any way affect operability of systems required by the TS that will be used to mitigate the consequences of an accident. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. 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 provides the alternative of electrically disarming the MG set drive motor breaker or electrically disarming the MG set field breaker. This is considered functionally equivalent and is consistent with normal tagging practices for plant equipment. As such, no new or different types of equipment will be installed, and the operation of installed equipment is unchanged. This configuration is in support of maintenance on the MG set and 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. Does the proposed change involve a significant reduction in a margin of safety?
Response: No. The plant TS allow for operation with one recirculation loop in service.
The proposed change provides the alternative and electrically disarming the MG set drive motor breaker or electrically disarming the MG set field breaker. The request does not adversely affect existing plant safety margins or the reliability of the equipment assumed to operate in the safety analysis. 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, VY concludes that the request presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
- 4. ENVIRONMENTAL CONSIDERATIONS This amendment request meets the eligibility criteria for categorical exclusion from environmental review set forth in 10 CFR 51.22(c)(9) as follows:
(i) The amendment involves no significant hazards determination.
As described in Section 3 of this evaluation, the proposed change involves no significant hazards consideration.
(ii) There is no significant change in the types or significant increase in the amounts of any effluent that may be released offsite.
The proposed amendment does not involve any physical alterations to the plant configuration that could lead to a change in the type or amount of effluent release offsite.
/ page 4 of 4 (iii) There is no significant increase in individual or cumulative occupational radiation exposure.
The proposed amendment does not involve a significant increase in individual or cumulative occupational radiation exposure.
Based on the above, VY concludes that the proposed change meets the eligibility criteria for categorical exclusion as set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
BVY 11-069 Docket No. 50-271 Enclosure 2 Vermont Yankee Nuclear Power Station Proposed Change No. 295 Marked-Up Technical Specification and Bases Pages
VYNPS 3.6 LIMITING CONDITIONS FOR 4.6 SURVEILLANCE REQUIREMENTS OPERATION
- b. The requirements for avoiding
( potentially
) unstable thermal hydraulic conditions defined K in Technical Specification 3.6.J are met.
)
- c. The idle loop is K
) isolated by electrically disarming the breaker to the recirculation pump motor gener4tor se drive motoripr-Hor (;aWN.A7A' *A Wdl ,-4au to startup or, if disabled during reactor operation,
< within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
< and until such time as the inactive recirculation loop is to be returned I
to service.
)) d. The recirculation system controls will be placed in the manual flow control mode.
Amendment No. 94, t+2 123
VYNPS BASES: 3.6 and 4.6 (Cont'd)
Agreement of indicated core flow with established power-core flow relationships provides the most assurance that recirculation flow is not bypassing the core through inactive or broken jet pumps. This bypass flow is reverse with respect to normal jet pump flow. The indicated total core flow is a summation of the flow indications for the twenty individual jet pumps. The total core flow measuring instrumentation sums reverse jet pump flow as though it were forward flow (except in the case of single loop operation when reverse flow is subtracted from the total jet pump flow). Thus, the indicated flow is higher than actual core flow by at least twice the normal flow through any backflowing pump. Reactivity inventory is known to a high degree of confidence so that even if a jet pump failure occurred during a shutdown period, subsequent power ascension would promptly demonstrate abnormal control rod withdrawal for any power-flow operating map point.
A nozzle-riser system failure could also generate the coincident failure of a jet pump body; however, the converse is not true. The lack of any substantial stress in the jet pump body makes failure impossible without an initial nozzle-riser system failure.
G. Single Loop Operation Continuous operation with one recirculation loop was justified in "Vermont Yankee Nuclear Power Station Single Loop Operation",
NEDO-30060, February 1983, with the adjustments specified in Technical Specification 3.6.G.l.a.
During single loop operation, the idle recirculation loop is isolated by electrically disarming the recirculation pump motor generator set drive motor, until ready to resume two loop operation. This is done to prevent a cold water injection transient caused by an inadvertent pump star p.
Under si le loop operation, the flow control is placed in the manual mode to void control oscillations which may occur in the recircu ation flow control system under these conditions.
H. Recirc lation System Twelv hours is a reasonable period of time to reach hot shutdown condi ions. Operation of the reactor may not occur without forced rec culation flow.
e.."
ri 'b /a #
d,0 i AO. 4' 7*kd Z1,.9 Amendment No. -i-, 42, 94, -41, 441 144
BVY 11-069 Docket No. 50-271 Enclosure 3 Vermont Yankee Nuclear Power Station Proposed Change No. 295 Technical Specification and Bases Pages with Changes Incorporated
VYNPS 3.6 LIMITING CONDITIONS FOR 4.6 SURVEILLANCE REQUIREMENTS OPERATION
- b. The requirements for avoiding potentially unstable thermal hydraulic conditions defined in Technical Specification 3.6.J are met.
- c. The idle loop is isolated by electrically disarming the breaker to the recirculation pump motor generator set drive motor or the recirculation pump motor generator set field breaker prior to startup or, if disabled during reactor operation, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and until such time as the inactive recirculation loop is to be returned to service.
- d. The recirculation system controls will be placed in the manual flow control mode.
Amendment No. -4, 4-41 123
VYNPS BASES: 3.6 and 4.6 (Cont'd)
Agreement of indicated core flow with established power-core flow relationships provides the most assurance that recirculation flow is not bypassing the core through inactive or broken jet pumps. This bypass flow is reverse with respect to normal jet pump flow. The indicated total core flow is a summation of the flow indications for the twenty individual jet pumps. The total core flow measuring instrumentation sums reverse jet pump flow as though it were forward flow (except in the case of single loop operation when reverse flow is subtracted from the total jet pump flow). Thus, the indicated flow is higher than actual core flow by at least twice the normal flow through any backflowing pump. Reactivity inventory is known to a high degree of confidence so that even if a jet pump failure occurred during a shutdown period, subsequent power ascension would promptly demonstrate abnormal control rod withdrawal for any power-flow operating map point.
A nozzle-riser system failure could also generate the coincident failure of a jet pump body; however, the converse is not true. The lack of any substantial stress in the jet pump body makes failure impossible without an initial nozzle-riser system failure.
G. Single Loop Operation Continuous operation with one recirculation loop was justified in "Vermont Yankee Nuclear Power Station Single Loop Operation",
NEDO-30060, February 1983, with the adjustments specified in Technical Specification 3.6.G.l.a.
During single loop operation, the idle recirculation loop is isolated by electrically disarming the recirculation pump motor generator set drive motor breaker or the recirculation pump motor generator set field breaker, until ready to resume two loop operation. This is done to prevent a cold water injection transient caused by an inadvertent pump startup.
Under single loop operation, the flow control is placed in the manual mode to avoid control oscillations which may occur in the recirculation flow control system under these conditions.
H. Recirculation System Twelve hours is a reasonable period of time to reach hot shutdown conditions. Operation of the reactor may not occur without forced recirculation flow.
Amendment No. --&, 491, -94, 4-4-1, 4-41 144