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MONTHYEARBVY 13-095, Request for Approval of Certified Fuel Handler Training Program2013-10-31031 October 2013 Request for Approval of Certified Fuel Handler Training Program Project stage: Request BVY 13-105, Request for Rescission of Security Orders2013-12-18018 December 2013 Request for Rescission of Security Orders Project stage: Request BVY 14-010, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2014-03-28028 March 2014 Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition Project stage: Request BVY 14-030, Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 12014-04-24024 April 2014 Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 1 Project stage: Supplement ML14140A3102014-05-20020 May 2014 NRR E-mail Capture - Acceptance Review for Vermont Yankee Defueled TS Amendment Project stage: Acceptance Review BVY 14-037, Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 22014-06-0909 June 2014 Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 2 Project stage: Supplement 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 Project stage: Supplement ML14210A1612014-07-29029 July 2014 NRR E-mail Capture - RAI - Defueld Technical Specification Amendment Project stage: RAI ML14231A0172014-08-13013 August 2014 Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 4 Project stage: Supplement BVY 15-001, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2015-01-12012 January 2015 Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel Project stage: Request ML15033A0532015-01-30030 January 2015 NRR E-mail Capture - VY RAI from Dss/Srxb for MF3714 Project stage: RAI BVY 15-012, Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 52015-05-0404 May 2015 Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 5 Project stage: Supplement ML15117A5512015-10-0707 October 2015 Issuance of Amendment for Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition Project stage: Approval 2014-06-09
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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 24-007, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-02-26026 February 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G 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 23-021, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-08-0202 August 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-020, Pre-Notice of Disbursement from Decommissioning Trust2023-08-0202 August 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-019, Update to 2022 Radiological Effluent Release Report2023-07-24024 July 2023 Update to 2022 Radiological Effluent Release Report BVY 23-018, Update to Nuclear Onsite Property Damage Insurance2023-07-12012 July 2023 Update to Nuclear Onsite Property Damage Insurance BVY 23-017, Pre-Notice of Disbursement from Decommissioning Trust2023-06-29029 June 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-015, Report of Investigation Pursuant to 1O CFR 20, Appendix G2023-06-0505 June 2023 Report of Investigation Pursuant to 1O CFR 20, Appendix G BVY 23-016, 10 CFR 72.48 Report2023-06-0505 June 2023 10 CFR 72.48 Report BVY 23-014, Pre-Notice of Disbursement from Decommissioning Trust2023-05-31031 May 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-011, 2022 Radiological Effluent Release Report2023-05-10010 May 2023 2022 Radiological Effluent Release Report BVY 23-013, 2022 Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Radiological Environmental Operating 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 2024-07-30
[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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V, k Entergy Entergy Nuclear Operations, Inc.Vermont Yankee 320 Governor Hunt Rd Vernon, VT 05354 Tel 802 257 7711 Christopher J. Wamser Site Vice President BVY 14-049 June 11, 2014 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition-Supplement 3 (TAC No. MF3714)Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28
REFERENCES:
- 1. Letter, Entergy Nuclear Operations, Inc. to USNRC, "Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition," BVY 14-010, dated March 28, 2014 (TAC No.MF3714)
Dear Sir or Madam:
By letter dated March 28, 2014 (Reference 1), Entergy Nuclear Operations, Inc. (ENO) proposed an amendment to Renewed Facility Operating License (OL) DPR-28 for Vermont Yankee Nuclear Power Station (VY). The proposed amendment would revise the VY OL and Technical Specifications (TS) to be consistent with the expected permanently shutdown and defueled condition of VY.ENO has identified an administrative error, in that justification for the changes to current TS 3/4.6, Reactor Coolant System, and TS 3/4.12, Refueling and Spent Fuel Handling, were not provided in their entirety with Reference
- 1. Attachment 1 of this letter provides the complete description of changes and justification for TS 3/4.6 and TS 3/4.12 and also provides a correction to the TS 3/4.12.F, Fuel Movement, reference in the justification.
This correction is shown in strikethrough/underline format.The conclusions of the no significant hazards consideration and the environmental considerations contained in Reference 1 are not affected by, and remain applicable to, this supplement.
There are no new regulatory commitments made in this letter.If you have any questions on this transmittal, please contact Mr. Philip Couture at 802-451-3193.
BVY 14-049/ page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct.Executed on June 11, 2014.Sincerely, CJW/plc
Attachment:
- 1. Technical Specification 3/4.6 and 3/4.12 Changes and Justification cc: Mr. William M. Dean Region 1 Administrator U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 Mr. James S. Kim, Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 08D15 Washington, DC 20555 USNRC Resident Inspector Vermont Yankee Nuclear Power Station 320 Governor Hunt Road Vernon, VT 05354 Mr. Christopher Recchia, Commissioner VT Department of Public Service 112 State Street, Drawer 20 Montpelier, VT 05620-2601 BVY 14-049 Docket 50-271 Attachment 1 Vermont Yankee Nuclear Power Station Proposed Change 309 -Supplement 3 Technical Specification 3/4.6 and 3/4.12 Changes and Justification BVY 14-049 / Attachment 1 / Page 1 of 6 TS SECTION 3/4.6, REACTOR COOLANT SYSTEM Current TS 3/4.6 A. Pressure and Temperature Limitations B. Coolant Chemistry C. Coolant Leakage D. Safety and Relief Valves E. Structural Integrity and Operability Testing F. Jet Pumps G. Single Loop Operation H. Recirculation System J. Thermal Hydraulic Stability Proposed TS 3/4.6 A. Deleted B. Deleted C. Deleted D. Deleted E. Deleted F. Deleted G. Deleted H. Deleted J. Deleted Basis Existing TS Section 3/4.6, "Reactor Coolant System," contains LCOs and SRs that provide assurance of the integrity and safe operation of the RCS and the operation of the related safety devices. Because the VY Part 50 license will no longer authorize emplacement or retention of fuel in the reactor vessel, the LCOs (and associated SRs) that do not apply (or are no longer needed)in a defueled condition are being proposed for deletion.
Note that TS 3/4.6.1 has previously been deleted.Pressure and TemDerature Limitations TS 3/4.6.A specifies maximum specified heatup and cooldown rates during reactor startup and shutdown to be consistent with the design assumptions and satisfy the stress limits for cyclic operation.
These limitations are not required for a plant that will be in the permanently defueled condition since the Part 50 license will prohibit reactor operation and may be deleted.Accordingly, TS Figures 3.6.1, 3.6.2 and 3.6.3, which are referenced in TS 3.6.A and contain the reactor vessel pressure-temperature limitations may also be deleted.Coolant Chemistry TS 3/4.6.B specifies the radiochemistry limits for the reactor coolant in the RCS. Limits on the maximum allowable level of radioactivity in the coolant are established to ensure that in the event of a release of any radioactive material to the environment during a DBA, radiation doses are maintained within the limits of 10 CFR 50.67. This specification may be deleted because it is not BVY 14-049 / Attachment 1 / Page 2 of 6 applicable to the safe storage and handling of spent fuel when the plant is in the permanently defueled condition.
Additionally, the FHA, which will be the only credible DBA, will not result in a release of reactor coolant to the environment.
Coolant Leakage TS 3/4.6.C specifies the maximum leakage rates of reactor coolant from the RCS. This specification may be deleted because it is not applicable the safe storage and handling of spent fuel when the plant is in the permanently defueled condition.
Safety and Relief Valves TS 3/4.6.D specifies the operability requirements for the safety and relief valves. These valves provide overpressure protection to the reactor during operation.
The Part 50 license will prohibit operation of the reactor once the certifications required by 10 CFR 50.82(a)(1) have been submitted.
Therefore, this specification may be deleted.Structural Integrity and Operability Testing TS 3/4.6.E specifies the requirements for structural integrity and operability testing of safety-related components.
The inservice inspection and testing programs will no longer be required in the permanently defueled condition.
10 CFR 50.55a(f) and (g) are applicable only to operating nuclear power reactors.
Once VY is certified to be permanently defueled, it will no longer be an operating power reactor.As discussed in Regulatory Guide 1.184, "Decommissioning of Nuclear Power Reactors," the maintenance rule, 10 CFR 50.65, "Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," requires monitoring the performance or condition of certain SSCs that could affect safety. Once the certifications for cessation of operation and for permanent fuel removal specified in 10 CFR 50.82(a)(1) have been submitted, the maintenance rule will be used to monitor the performance or condition of the SSCs associated with the storage, control, and maintenance of spent fuel in a safe condition.
The monitoring will be sufficient to provide reasonable assurance that such SSCs are capable of fulfilling their intended functions as specified in 10 CFR 50.65(a)(1).
Therefore, this specification may be deleted.Jet Pumps TS 3/4.6.F specifies the operability requirements for the jet pumps. The jet pumps function as part of the reactor recirculation system to provide sufficient coolant circulation through the core during normal power operation to maintain normal operating temperatures.
Failure of a jet pump nozzle assembly hold down mechanism, nozzle assembly and/or riser, would increase the cross-sectional flow area for blowdown following the design basis double-ended line break (LOCA). The Part 50 license will prohibit operation of the reactor once the certifications required by 10 CFR 50.82(a)(1) have been submitted and the LOCA will not be a credible DBA once the plant is in the permanently defueled condition.
Therefore, this specification may be deleted.Single Loop Operation TS 3/4.6.G specifies the system settings and configuration necessary to operate the reactor with one recirculation loop. The Part 50 license will prohibit operation of the reactor once the certifications required by 10 CFR 50.82(a)(1) have been submitted.
Therefore, this specification may be deleted.
BVY 14-049 / Attachment 1/ Page 3 of 6 Recirculation System TS 3.6.H specifies requirements for reactor operation with the recirculation system. The Part 50 license will prohibit operation of the reactor once the certifications required by 10 CFR 50.82(a)(1) have been submitted.
Therefore, this specification may be deleted. There is no corresponding TS 4.6.H.Thermal Hydraulic Stability TS 3.6.J specifies restrictions against operating the reactor in the power flow exclusion area. The Part 50 license will prohibit operation of the reactor once the certifications required by 10 CFR 50.82(a)(1) have been submitted.
Therefore, this specification may be deleted. There is no corresponding TS 4.6.J.Summary The protection and monitoring functions of the RCS have been designed to ensure safe operation of the reactor required to protect the integrity of a fission product barrier. The requirements of 10 CFR 50, Appendix G, will no longer apply in the permanently defueled condition because the reactor coolant pressure boundary will no longer be used as a fission product barrier.Once VY dockets the certifications required by 10 CFR 50.82(a)(1), the 10 CFR Part 50 license will no longer authorize operation of the reactor or placement or retention of fuel in the reactor vessel, in accordance with 10 CFR 50.82(a)(2).
The maintenance rule will be used to monitor the performance or condition of the SSCs associated with the storage, control, and maintenance of spent fuel in a safe condition.
Based on the above, the proposed deletion of TS Section 3/4.6 in its entirety is acceptable.
TS SECTION 3/4.12, REFUELING AND SPENT FUEL HANDLING*(Note: This section appears renumbered as new TS Section 3/4.2 in the markup and retyped TS pages. Proposed TS 3/4.12.C is renumbered to TS 3/4.2.A and proposed TS 3/4.12.H is renumbered to TS 3/4.2.B.)Current TS 3/4.12. REFUELING AND SPENT FUEL HANDLING 3.12 Applicability:
Applies to fuel handling, core reactivity limitations, and spent fuel handling.3.12 Obiective:
To assure core reactivity is within capability of the control rods, to prevent criticality during refueling, and to assure safe handling of spent fuel casks.4.12 Applicability:
Applies to the periodic testing of those interlocks and instruments used during refueling.
Proposed TS 3/4.12*, SPENT FUEL STORAGE 3.12* Applicability:
Applies to storage of spent fuel.3.12* Obiective:
To assure safe storage of spent fuel.4.12* Applicability:
Applies to the parameters which monitor the storage of spent fuel.4.12 Obeective:
To verify the operability of 4.12* Obiective:
To verify that Went fuel is 4.2 .ici.:T.eif.h praiiyo 4.2 Obetv:T eiyta on uli BVY 14-049 / Attachment 1 / Page 4 of 6 instrumentation and interlocks used in instrumentation and interlocks used in refueling.
3/4.12.A Refueling Interlocks 3/4.12.B Core Monitoring 3/4.12.C Fuel Storage Pool Water Level 3/4.12.D Control Rod and Control Rod Drive Maintenance 3/4.12.E Extended Core Maintenance 3/4.12.F Fuel Movement 3/4.12.G Deleted 3.12.H Spent Fuel Pool Water Temperature 4.12.H Spent Fuel Pool Water Temperature Whenever irradiated fuel is in the spent fuel pool, the pool water temperature shall be recorded daily. If the pool water temperature reaches 150 0 F, all refueling operations tending to raise the pool water temperature shall cease and measures taken immediately to reduce the pool water temperature below 150 0 F.being stored safely.3/4.12.A Deleted 3/4.12.B Deleted 3/4.12.C*
No Change 3/4.12.D Deleted 3/4.12.E Deleted 3/4.12.F Deleted 3/4.12.G Deleted 3.12.H* No Change 4.12.H* Spent Fuel Pool Water Temperature Whenever irradiated fuel is in the spent fuel pool, the pool water temperature shall be recorded daily. If the pool water temperature reaches 150'F, all operations tending to raise the pool water temperature shall cease and measures taken immediately to reduce the pool water temperature below 150°F.Basis The existing TS Section 3/4.12, "Refueling and Spent Fuel Handling," contains LCOs and SRs that provide for appropriate functional capability of parameters and equipment within containment that are required for mitigation of design basis accidents during refueling operations (moving irradiated fuel to or from the reactor core). Because the VY Part 50 license will no longer authorize emplacement or retention of fuel in the reactor vessel, the LCOs (and associated SRs)that do not apply in a defueled condition are being proposed for deletion.
The title of this section is proposed to be changed to "Spent Fuel Storage" to reflect that refueling of the reactor will no longer be possible.
The applicability and objectives are also proposed to be changed to reflect the focus on safe storage of spent fuel. This specification is being renumbered to TS 3/4.2. The table of contents is also revised to reflect the numbering changes.Refueling Interlocks TS 3/4.12.A specifies requirements for refueling interlocks and restriction of certain refueling procedures such that there is assurance that inadvertent criticality does not occur during refueling.
Refueling will not be permitted by the Part 50 license following certification of permanent removal of the fuel. Therefore, this specification will no longer be required.
BVY 14-049 / Attachment 1 / Page 5 of 6 Core Monitoring TS 3/4.12.B specifies requirements for monitoring the core during periods of station shutdown and to guide the operator during refueling operations and station startup. When all of the fuel has been permanently removed from the reactor, core monitoring will no longer be required.Fuel Storage Pool Water Level TS 3/4.12.C specifies requirements to assure that there is adequate water to shield and cool the irradiated fuel assemblies stored in the pool, a minimum pool water level is established.
This minimum water level of 36 feet is established because it would be a significant change from the normal level, well above a level to assure adequate cooling (just above active fuel). Since the reactor core will be offloaded to the SFP following shutdown, this specification will remain with no changes except for being renumbered to TS 3/4.2.A.Control Rod and Control Rod Drive Maintenance TS 3/4.12.D specifies requirements for performing control rod/control rod drive maintenance and maintaining adequate shutdown margin during such activities to provide assurance that inadvertent criticality does not occur during such maintenance.
With all fuel permanently removed from the reactor, this specification will no longer be required.Extended Core Maintenance TS 3/4.12.E specifies requirements for unloading of a portion of the reactor core for such purposes as in-service inspection requirements, examination of the core support plate, control rod, control rod drive maintenance, etc. This specification provides assurance that inadvertent criticality does not occur during such operation.
With all fuel permanently removed from the reactor, this specification will no longer be required.Fuel Movement TS 3/4.12.G-F specifies requirements to assure that the reactor core has been shut down for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following power operation and prior to fuel handling or movement.
The analysis (Reference
- 2) based on the postulated FHA assumed that the reactor had been shut down for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for fission product decay prior to any fuel handling which could result in dropping of a fuel assembly.
With all fuel permanently removed from the reactor, this specification will no longer be required.Spent Fuel Pool Water Temperature TS 3/4.12.H specifies requirements for maintaining SFP water temperature less than 150°F whenever there is irradiated fuel in the SFP. Since the reactor core will be offloaded into the SFP following shutdown, the requirements in this specification will continue to apply in the permanently defueled condition.
A change to TS 4.12.H is proposed to remove the word "refueling" since the reactor will never be able to be refueled again. The resultant TS 4.12.H will require action to be taken to cease any SFP operation that increases SFP temperature once the SFP temperature reaches 150'F and take immediate action to lower SFP temperature.
This specification is being renumbered to TS 3/4.2.B.Summary The above TS are related to assuring the appropriate functional capability of plant equipment, and BVY 14-049 / Attachment 1 / Page 6 of 6 control of process variables, design features, or operating restrictions required for safe refueling operation of the facility only when the reactor is in REFUEL mode, during movement of irradiated fuel assemblies, or during safe storage of fuel assemblies in the SFP. However, 10 CFR 50.82(a)(2) prohibits operation of the plant or placing fuel in the reactor vessel, which thereby precludes entry into the REFUEL mode. Therefore, the TS listed in the previous paragraphs, which only address these specific plant systems, control of process variables, design features, or operating restrictions are no longer applicable.
The specifications for SFP water level and temperature will remain.The protection and monitoring functions of TS 3/4.12, Refueling and Spent Fuel Handling have been designed to ensure safe handling of the fuel in the reactor and in the SFP during refueling.
Once VY dockets the certifications required by 10 CFR 50.82(a)(1), the 10 CFR Part 50 license will no longer authorize operation of the reactor or placement or retention of fuel in the reactor vessel, in accordance with 10 CFR 50.82(a)(2).
Therefore, this specification other than SFP water level and temperature restrictions will not be needed once VY is in the permanently defueled condition.
Based on the above, the proposed deletion of the noted TS in Section 3/4.12 is acceptable.