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MONTHYEARBVY 13-096, Technical Specifications Proposed Change No. 307 Revision to Mitigation Strategy License Condition and Technical Specification Administrative Controls for Permanently Defueled Condition Vermont Yankee Nuclear Power Station2013-10-31031 October 2013 Technical Specifications Proposed Change No. 307 Revision to Mitigation Strategy License Condition and Technical Specification Administrative Controls for Permanently Defueled Condition Vermont Yankee Nuclear Power Station Project stage: Request BVY 14-028, RAI on Technical Specifications Proposed Change No. 307, Revision to Mitigation Strategy License Condition and Technical Specification Administrative Controls for Permanently Defueled Condition - Supplement 12014-04-24024 April 2014 RAI on Technical Specifications Proposed Change No. 307, Revision to Mitigation Strategy License Condition and Technical Specification Administrative Controls for Permanently Defueled Condition - Supplement 1 Project stage: Supplement ML14202A2062014-07-16016 July 2014 Technical Specifications Proposed Change No. 307, Revision to Technical Specification Administrative Controls for Permanently Defueled Condition - Supplement 2 Project stage: Supplement 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 Project stage: Supplement 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No. 260, Revise and Remove Certain Requirements from Technical Specification Section 6.0, Administrative Controls, No Longer Applicable for Its Permanently Defueled Condition Project stage: Approval 2014-12-05
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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 SEntergy Tel 802 257 7711 Christopher J. Wamser Site Vice President BVY 14-083 December 5, 2014 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Technical Specifications Proposed Change No. 307, Revision to Technical Specification Administrative Controls for Permanently Defueled Condition -
Supplement 3 (TAC No. MF2991)
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. 307, Revision to Mitigation Strategy License Condition and Technical Specification Administrative Controls for Permanently Defueled Condition," BVY 13-096, dated October 31, 2013 (ML13316A004)
- 2. Letter, Entergy Nuclear Operations, Inc. to USNRC, "Technical Specifications Proposed Change No. 307, Revision to Mitigation Strategy License Condition and Technical Specification Administrative Controls for Permanently Defueled Condition -
Supplement 1 (TAC No. MF2991)," BVY 14-028, dated April 24, 2014 (ML14119A099)
- 3. Letter, Entergy Nuclear Operations, Inc. to USNRC, "Technical Specifications Proposed Change No. 307, Revision to Mitigation Strategy License Condition and Technical Specification Administrative Controls for Permanently Defueled Condition -
Supplement 2 (TAC No. MF2991)," BVY 14-052, dated July 16, 2014 (ML142024A206)
Dear Sir or Madam:
By letter dated October 31, 2013 (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). This amendment request proposed changes to the staffing, training and programmatic requirements contained in Section 6.0, Administrative Controls, of the VY Technical Specifications (TS) to support the transition of the VY facility to a permanently defueled condition.
BVY 14-083 /page 2of 3 Based on teleconference held with NRC staff on December 4, 2014, ENO has identified additional changes to Section 6.0 of the TS that are needed to reflect the transition of VY from an operating unit to a decommissioning facility. to this letter provides a detailed description and evaluation of the proposed changes. contains a markup of the TS pages that builds on the markups provided in References 1, 2 and 3. Attachment 3 contains the retyped TS pages incorporating the changes proposed in this supplement and those in Reference 1.
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.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on December 5, 2014.
Sincerely, CJW/plc Attachments: 1. Description and Evaluation of Proposed Changes
- 2. Markup of Technical Specification Pages
- 3. Retyped Technical Specification Pages cc: Mr. Daniel H. Dorman 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
BVY 14-083 / page 3 of 3 cc list continued:
Mr. Christopher Recchia, Commissioner VT Department of Public Service 112 State Street, Drawer 20 Montpelier, VT 05620-2601
BVY 14-083 Docket 50-271 Attachment 1 Vermont Yankee Nuclear Power Station Proposed Change 307 - Supplement 3 Description and Evaluation of Proposed Changes
BVY 14-083 / Attachment 1 / Page 1 of 1
- 1.
SUMMARY
DESCRIPTION In Reference 1, Entergy Nuclear Operations, Inc. (ENO) provided notification of the intention to permanently cease power operations of Vermont Yankee Nuclear Power Station (VY) in accordance with 10 CFR 50.82(a)(1)(i) at the end of the current operating cycle.
In Reference 2, ENO submitted proposed changes that would revise and remove certain requirements contained within Section 6.0, Administrative Controls, of the VY Technical Specifications (TS) consistent with the planned transition to a permanently defueled facility.
Additional changes to Section 6.0 of the TS have been identified that are needed to reflect the transition of VY from an operating unit to a decommissioning facility.
- 2. DETAILED DESCRIPTION AND BASIS FOR THE CHANGES The following table identifies each section that is being changed, the proposed changes, and the basis for the changes:
Proposed Changes to VY Technical Specification Section 6.0, Administrative Controls Affected Sections Proposed Changes Basis 6.1.A, 6.2.A, Replace the term The change from "unit" to "facility" and "unit 6.2.A.2, 6.2.B, "unit" with "facility" operation" to "facility staff' is administrative and 6.2.C, 6.2.C.1, throughout. reflects that VY will be permanently shutdown and 6.6.D, 6.6.E, defueled and are appropriate for activities 6.7.D.d, 6.7.D.h, For 6.2.A only - associated with a decommissioning reactor. Overall 6.7.D.i replace "unit management and staff responsibilities and the operation" with "facility description of the plant are unchanged. These staff' changes are consistent with those recently approved for Crystal River Unit 3 (Reference 3) and San Onofre Nuclear Generating Station, Units 2 and 3 (Reference 4).
References
- 1. Letter, Entergy Nuclear Operations, Inc. to USNRC, "Notification of Permanent Cessation of Power Operations," BVY 13-079, dated September 23, 2013 (ML13273A204)
- 2. Letter, Entergy Nuclear Operations, Inc. to USNRC, "Technical Specifications Proposed Change No. 307, Revision to Mitigation Strategy License Condition and Technical Specification Administrative Controls for Permanently Defueled Condition," BVY 13-096, dated October 31, 2013 (ML13316A004) (TAC No. MF2991)
- 3. Letter, USNRC to Crystal River Nuclear Plant, "Crystal River Unit 3- Issuance of Amendment to the Facility Operating License Regarding Changes to the Administrative Controls Section of the Technical Specifications (TAC No. MF1 504) (ML14097A145)
- 4. Letter, USNRC to San Onofre Nuclear Generating Station, "San Onofre Nuclear Generating Station, Units 2 and 3 - Issuance of Amendments Regarding Changes to the Administrative Controls Section of the Technical Specifications (TAC Nos. MF2954 and MF2955)
(ML14183B240)
BVY 14-083 Docket 50-271 Attachment 2 Vermont Yankee Nuclear Power Station Proposed Change 307 - Supplement 3 Markup of Technical Specification Pages
VYNPS 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY A. The plant manager shall be responsible for overall u operation and shall delegate in writing the succession to this responsibility during absences.
B. The plant manager or designee shall approve, prior to implementation, each proposed test, experiment, or modification to systems or equipment that affect nuclear safety.
C. The shift supervisor shall be responsible for the shift command function.
6.2 ORGANIZATION A. Onsite and Offsite Organizations facility staff Organizations shall be. established for unit operation and corporate management. These organizations shall include the positions for activities affecting safety of the nuclear fuel.
- 1. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organizational positions. These relationships shall be documented and updated, as appropriate, in the form of organizational charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Quality Assurance Program Manual. The plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications shall be documented in the Technical Requirements Manual._--fclt
- 2. The plant manager shall be responsible for overall ;4. safe operation and shall have control over those on-site activities necessary for safe storage and maintenance of the nuclear fuel.
- 3. A specified corporate officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure safe management of nuclear fuel.
Amendment No. ", --&, 4-24, 4-74, 2-14, 2-2-2 255
VYNPS 6.2 ORGANIZATION (Cont'd)
- 4. The individuals who train the Certified Fuel Handlers, carry out health physics, or perform quality assurance functions may report to the appropriate on-site manager; however, these Facility individuals shall have sufficient organizational freedom to ensure their ability to perform their assigned functions.
B. Staff facility The ; staff organization shall include the following:
- 1. Each duty shift shall be composed of at least one shift supervisor and one Non-certified Operator. The Non-certified Operator position may be filled by a Certified Fuel Handler.
- 2. At least one person qualified to stand watch in the control room (Non-certified Operator or Certified Fuel Handler) shall be present in the control room when nuclear fuel is stored in the spent fuel pool.
- 3. All fuel handling operations shall be directly supervised by a Certified Fuel Handler.
- 4. Shift crew composition shall meet the requirements stipulated herein. Shift crew composition may be less than the minimum requirement of Specification 6.2.B.1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members, provided immediate action is taken to restore the shift crew composition to within the minimum requirements and all of the following conditions are met:
- a. no fuel movements are in progress; and
- b. no movement of loads over fuel are in progress; and
- c. no unmanned shift positions during shift turnover shall be permitted while the shift crew is less than the minimum.
- 5. An individual qualified in radiation protection procedures shall be present on-site during the movement of fuel and during the movement of loads over fuel.
- 6. Deleted
- 7. The shift supervisor shall be a Certified Fuel Handler.
- 8. Deleted Amendment No. &3,*,- *-4, 9-4, -0, 40, 4-34-, 4-68, 4-74-, ,, -44 , 256 2-5-3
VYNPS 6.2 ORGANIZATION (Cont' Facility C. Staff Qualifications nii4-t. a
- 1. Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1978 for comparable positions with exceptions specified in the Quality Assurance Program Manual (QAPM).
- 2. An NRC approved training and retraining program for Certified Fuel Handlers shall be maintained.
I 6.3 Deleted 6.4 PROCEDURES Written procedures shall be established, implemented, and maintained covering the following activities:
A. Normal startup, operation and shutdown of systems and components needed for the safe storage of nuclear fuel.
B. Fuel handling operations.
C. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components needed for the safe storage of nuclear fuel.
D. Emergency conditions involving potential or actual release of radioactivity.
E. Preventive and corrective maintenance operations which could have an effect on the safety of the nuclear fuel.
F. Surveillance and testing requirements.
G. Fire protection program implementation.
H. Process Control Program in-plant implementation.
I. Off-Site Dose Calculation Manual implementation.
6.5 HIGH RADIATION AREA As provided in paragraph 20.1601(c) of 10 CFR 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraphs 20.1601(a) and 20.1601(b) of 10 CFR 20:
A. High Radiation Areas with dose rates greater than 0.1 rem/hour at 30 centimeters, but not exceeding 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation:
Amendment No. 3-6, 4-, 4-3, -83, 4-5 4, 4-6-,---7-, 2-104, 2--4, 2 5-3 257
VYNPS Report /
D. Radioactie Effluent Release The Rad active Effluent Release Rep rt covering the operation of the 4 shall be submitted by May p5 of each year and in accordance with 10 CFR 50.36a. Th report shall include a summary of the quantities of radioactive quid and gaseous effluents and solid waste released from the The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM) and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section Iv.E.1.
a a A cfanci ityi E. Annual Radiological Environmtal Operating Report The Annual Radiological >vironmental Operating Report covering the operation of the n during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.
The Annual Radiological Environmental Operating Report shall include summarized and tabulated results of all radiological environmental samples taken during the report period pursuant to the table and figures in the ODCM. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.
6.7 PROGRAMS AND MANUALS The following programs shall be established, implemented and maintained:
A. Deleted Amendment No. &- , 4-1-4, 4-2-6, 444, 4-5-, 4-47, 4-64, 4-7-16 263
VYNPS D. Radioactive Effluent Controls Program This program conforming to 10 CFR 50.36a provides for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by operating procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
- a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;
- b. Limitations on the concentrations of radioactive material released in liquid effluents from the site to unrestricted areas, conforming to 10 times the concentration values in Appendix B, Table 2, Column 2, to 10 CFR 20.1001 - 20.2402;
- c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents pursuant to 10 CFR 20.1302 and with the methodology and parameters in the ODCM;
- d. Limitations on the annual and quarterly doses or dos commitment to a member of the public from radioact e materials in liquid effluents released from the ".a to unrestricted areas, conforming to 10 CFR 50, Appendix I;
- e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days;
- f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2 percent of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;
- g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be limited to the following:
- 1. For noble gases: less than or equal to a dose rate of 500 mrems/yr to the total body and less than or equal to a dose rate of 3000 mrems/yr to the skin, and
- 2. For iodine-131, iodine-133, tritium, and for all radionuclides in particulate form with half lives greater than 8 days: less than or equal to a dose rate of 1500 mrems/yr to any organ; Amendment No. 4-7-4, 2-24, 2-2-2 266
VYNPS
- h. Limitations on the annual and quarterly air doses resultiý from noble gases released in gaseous effluents from the unit to areas at or beyond the site boundary, conforming to 10 CFR 50, Appendix I;
- i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all facility radionuclides in particulate form with half lives grea to than 8 days in gaseous effluents released from the to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and
- j. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.
E. TECHNICAL SPECIFICATIONS (TS) BASES CONTROL PROGRAM This program provides a means for processing changes to the Bases of these Technical Specifications,
- a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.
- b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:
- 1. A change in the TS incorporated in the license, or
- 2. A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.
- c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR.
- d. Proposed changes that meet the criteria of Specification 6.7.E.b above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
Amendment No. 4-74, 2--26 267
BVY 14-083 Docket 50-271 Attachment 3 Vermont Yankee Nuclear Power Station Proposed Change 307 - Supplement 3 Retyped Technical Specification Pages
VYNPS 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY A. The plant manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during absences.
B. The plant manager or designee shall approve, prior to implementation, each proposed test, experiment, or modification to systems or equipment that affect nuclear safety.
C. The shift supervisor shall be responsible for the shift command function.
6.2 ORGANIZATION A. Onsite and Offsite Organizations Organizations shall be established for facility staff and corporate management. These organizations shall include the positions for I ac-t-i-vi-ti-es a-f-fect-ing safety of the nuclear fuel.
- 1. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organizational positions. These relationships shall be documented and updated, as appropriate, in the form of organizational charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Quality Assurance Program Manual. The plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications shall be documented in the Technical Requirements Manual.
- 2. The plant manager shall be responsible for overall facility safe operation and shall have control over those on-site activities necessary for safe storage and maintenance of the nuclear fuel.
- 3. A specified corporate officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure safe management-of nuclear-fuel.
Amendment No. "-, 7&-, 4-2-1, 4-7, 244, 2-2-2 255
VYNPS 6.2 ORGANIZATION (Cont'd)
- 4. The individuals who train the Certified Fuel Handlers, carry out health physics, or perform quality assurance functions may report to the appropriate on-site manager; however, these individuals shall have sufficient organizational freedom to ensure their ability to perform their assigned functions.
B. Facility Staff The facility staff organization shall include the following:
- 1. Each duty shift shall be composed of at least one shift supervisor and one Non-certified Operator. The Non-certified Operator position may be filled by a Certified Fuel Handler.
- 2. At least one person qualified to stand watch in the control room (Non-certified Operator or Certified Fuel Handler) shall be present in the control room when nuclear fuel is stored in the spent fuel pool.
- 3. All fuel handling operations shall be directly supervised by a Certified Fuel Handler.
- 4. Shift crew composition shall meet the requirements stipulated herein. Shift crew composition may be less than the minimum requirement of Specification 6.2.B.1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members, provided immediate action is taken to restore the shift crew composition to within the minimum
'd(iredffdr1fs and ll of the following conditions are met:
- a. no fuel movements are in progress; and
- b. no movement of loads over fuel are in progress; and
- c. no unmanned shift positions during shift turnover shall be permitted while the shift crew is less than the minimum.
- 5. An individual qualified in radiation protection procedures shall be present on-site during the movement of fuel and during the movement of loads over fuel.
- 6. Deleted
- 7. The shift supervisor shall be a Certified Fuel Handler.
- 8. Deleted Amendment No. &3 , , 4-, .9,4& - 44, 4-64, 44--, 1-9, 244, 253 256
VYNPS 6.2 ORGANIZATION (Cont'd)
C. Facility Staff Qualifications
- 1. Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1978 for comparable positions with exceptions specified in the Quality Assurance Program Manual (QAPM).
- 2. An NRC approved training and retraining program for Certified Fuel Handlers shall be maintained.
6.3 Deleted 6.4 PROCEDURES Written procedures shall be established, implemented, and maintained covering the following activities:
A. Normal startup, operation and shutdown of systems and components needed for the safe storage of nuclear fuel.
B. Fuel handling operations.
C. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components needed for the safe storage of nuclear fuel.
D. Emergency conditions involving potential or actual release of radioactivity.
E. Preventive and corrective maintenance operations which could have an effect on the safety of the nuclear fuel.
F. Surveillance and testing requirements.
G. Fire protection program implementation.
H. Process Control Program in-plant implementation.
I. Off-Site Dose Calculation Manual implementation.
6.5 HIGH RADIATION AREA As provided in paragraph 20.1601(c) of 10 CFR 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraphs 20.1601(a) and 20.1601(b) of 10 CFR 20:
A. High Radiation Areas with dose rates greater than 0.1 rem/hour at 30 centimeters, but not exceeding 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation:
Amendment No. -, 4-3, 4-3, 4-3, 4-54-, 4-6, 1 , 2 -i-, 4, , 2 2-4-, -- 3 257
VYNPS D. Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the facility shall be submitted by May 15 of each year and in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM) and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.
E. Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the facility during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.
The Annual Radiological Environmental Operating Report shall include summarized and tabulated results of all radiological environmental samples taken during the report period pursuant to the table and figures in the ODCM. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.
6.7 PROGRAMS AND MANUALS The following programs shall be established, implemented and maintained:
A. Deleted Amendment No. -ý 4r 44-4, 4-4, 444., 14*-,&, 4 263
VYNPS D. Radioactive Effluent Controls Program This program conforming to 10 CER 50.36a provides for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as. reasonably achievable. The program shall be contained in the ODCM, shall be implemented by operating procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
- a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;
- b. Limitations on the concentrations of radioactive material released in liquid effluents from the site to unrestricted areas, conforming to 10 times the concentration values in Appendix B, Table 2, Column 2, to 10 CFR 20.1001 - 20.2402;
- c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents pursuant to 10 CFR 20.1302 and with the methodology and parameters in the ODCM;
- d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from the facility to unrestricted areas, conforming to 10 CFR 50, Appendix I;
- e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days;
- f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2 percent of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;
- g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be limited to the following:
- 1. For noble gases: less than or equal to a dose rate of 500 mrems/yr to the total body and less than or equal to a dose rate of 3000 mrems/yr to the skin, and
- 2. For iodine-131, iodine-133, tritium, and for all radionuclides in particulate form with half lives greater than 8 days: less than or equal to a dose rate of 1500 mrems/yr to any organ; Amendment No. 4-74, 2_ 2-32 266
.11 VYNPS
- h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from the facility to areas at or beyond the site boundary, conforming to 10 CFR 50, Appendix I;
- i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released from the facility to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and
- j. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.
E. TECHNICAL SPECIFICATIONS (TS) BASES CONTROL PROGRAM This program provides a means for processing changes to the Bases of these Technical Specifications.
- a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.
- b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:
- 1. A change in the TS incorporated in the license, or
- 2. A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.
- c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR.
- d. Proposed changes that meet the criteria of Specification 6.7.E.b above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
Amendment No. 44-1, 2-2-26 267