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Category:Letter
MONTHYEARBVY 24-005, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-01-30030 January 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-004, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-01-23023 January 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-003, Nuclear Onsite Property Damage Insurance2024-01-0404 January 2024 Nuclear Onsite Property Damage Insurance BVY 24-001, Pre-Notice of Disbursement from Decommissioning Trust2024-01-0202 January 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-030, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-12-20020 December 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-029, Proof of Financial Protection2023-12-12012 December 2023 Proof of Financial Protection BVY 23-028, Pre-Notice of Disbursement from Decommissioning Trust2023-11-28028 November 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-027, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-11-21021 November 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-026, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-11-13013 November 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-025, Pre-Notice of Disbursement from Decommissioning Trust2023-11-0202 November 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-023, License Amendment Request Addition of License Condition 3.K, License Termination Plan; Proposed Change No. 3172023-10-10010 October 2023 License Amendment Request Addition of License Condition 3.K, License Termination Plan; Proposed Change No. 317 IR 07200059/20234012023-10-0505 October 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200059/2023401 BVY 23-022, Pre-Notice of Disbursement from Decommissioning Trust2023-08-23023 August 2023 Pre-Notice of Disbursement from Decommissioning Trust IR 05000271/20230012023-08-15015 August 2023 Northstar Nuclear Decommissioning Company, Llc., Vermont Yankee Nuclear Power Station, - NRC Inspection Report 05000271/2023001 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 23-013, 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 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment 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 23-007, 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 23-006, 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 23-005, 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 ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities IR 05000271/20220022023-02-22022 February 2023 Northstar Nuclear Decommissioning Company, LLC, Vermont Yankee Nuclear Power Station - NRC Inspection Report No. 05000271/2022002 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 ML22347A2792022-12-21021 December 2022 Independent Spent Fuel Storage Installation Security Inspection Plan Dated December 21, 2022 IR 05000271/20224012022-12-15015 December 2022 NRC Inspection Report No. 05000271/2022401, Northstar Nuclear Decommissioning Company, LLC, Vermont Yankee Nuclear Power Station, Vernon, Vermont (Letter Only) 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 ML22273A1492022-10-0404 October 2022 Review of Decommissioning Funding Status 2022 BVY 22-025, Pre-Notice of Disbursement from Decommissioning Trust2022-10-0404 October 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-023, Pre-Notice of Disbursement from Decommissioning Trust2022-09-0101 September 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-022, Report of Investigation Pursuant to 10 CFR 20, Appendix G2022-08-22022 August 2022 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 22-021, Report of Investigation Pursuant to 10 CFR 20, Appendix G2022-08-16016 August 2022 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 22-020, Pre-Notice of Disbursement from Decommissioning Trust2022-08-0101 August 2022 Pre-Notice of Disbursement from Decommissioning Trust IR 05000271/20220012022-08-0101 August 2022 NRC Inspection Report No. 05000271/2022001, Northstar Nuclear Decommissioning Company, LLC, Vermont Yankee Nuclear Power Station, Vernon, Vermont BVY 22-019, Pre-Notice of Disbursement from Decommissioning Trust2022-07-0606 July 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-013, Notification of Revised Decommissioning Cost Estimate2022-06-17017 June 2022 Notification of Revised Decommissioning Cost Estimate 2024-01-04
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARBVY 23-023, License Amendment Request Addition of License Condition 3.K, License Termination Plan; Proposed Change No. 3172023-10-10010 October 2023 License Amendment Request Addition of License Condition 3.K, License Termination Plan; Proposed Change No. 317 3F1120-02, and Crystal River Nuclear Plant - Application for Order Approving Indirect Transfers of Control of Licenses in Connection with Internal Corporate Reorganization2020-11-19019 November 2020 and Crystal River Nuclear Plant - Application for Order Approving Indirect Transfers of Control of Licenses in Connection with Internal Corporate Reorganization BVY 17-004, Technical Specifications Proposed Change No. 313: Revision to License and Permanently Defueled Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool2017-07-20020 July 2017 Technical Specifications Proposed Change No. 313: Revision to License and Permanently Defueled Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool BVY 17-022, License Amendment Request - Cyber Security Plan License Condition Removal Proposed Change No. 3162017-07-13013 July 2017 License Amendment Request - Cyber Security Plan License Condition Removal Proposed Change No. 316 BVY 17-005, Application for Order Consenting to Direct and Indirect Transfers of Control of Licenses and Approving Conforming License Amendment and Notification of Amendment to Decommissioning Trust Agreement2017-02-0909 February 2017 Application for Order Consenting to Direct and Indirect Transfers of Control of Licenses and Approving Conforming License Amendment and Notification of Amendment to Decommissioning Trust Agreement BVY 15-040, License Amendment Request - Revised Cyber Security Plan Implementation Schedule - Proposed Change No. 3112015-06-24024 June 2015 License Amendment Request - Revised Cyber Security Plan Implementation Schedule - Proposed Change No. 311 BVY 14-083, Technical Specifications Proposed Change No. 307, Revision to Technical Specification Administrative Controls for Permanently Defueled Condition - Supplement 32014-12-0505 December 2014 Technical Specifications Proposed Change No. 307, Revision to Technical Specification Administrative Controls for Permanently Defueled Condition - Supplement 3 BVY 14-062, Proposed Change No. 310 - Deletion of Renewed Facility Operating License Conditions Related to Decommissioning Trust Provisions2014-09-0404 September 2014 Proposed Change No. 310 - Deletion of Renewed Facility Operating License Conditions Related to Decommissioning Trust Provisions BVY 13-109, Cyber Security Plan Implementation Schedule, Proposed Change No. 3082013-12-19019 December 2013 Cyber Security Plan Implementation Schedule, Proposed Change No. 308 BVY 13-097, Proposed Change 306, Areva Document No. 32-9145461-001, Vynpp - Re-analysis of Ast/Fha Radiological Consequences with Open Containment2013-11-14014 November 2013 Proposed Change 306, Areva Document No. 32-9145461-001, Vynpp - Re-analysis of Ast/Fha Radiological Consequences with Open Containment ML13323A5182013-11-14014 November 2013 Technical Specifications Proposed Change No. 306 Eliminate Certain ESF Requirements During Movement of Irradiated Fuel BVY 12-084, License Amendment Request; Changes to 10CFR50.63 Licensing Basis2012-12-21021 December 2012 License Amendment Request; Changes to 10CFR50.63 Licensing Basis BVY 12-085, Technical Specifications Proposed Change No. 302 Inoperable Control Rods2012-12-17017 December 2012 Technical Specifications Proposed Change No. 302 Inoperable Control Rods BVY 12-018, Technical Specifications Proposed Change No. 299 Recirculation System Discharge Bypass Valve Change2012-04-17017 April 2012 Technical Specifications Proposed Change No. 299 Recirculation System Discharge Bypass Valve Change BVY 12-016, License Amendment Request to Revise License Renewal Commitments2012-03-12012 March 2012 License Amendment Request to Revise License Renewal Commitments BVY 12-006, Technical Specifications Proposed Change No. 298, Rod Worth Minimizer Bypass Allowance2012-02-0101 February 2012 Technical Specifications Proposed Change No. 298, Rod Worth Minimizer Bypass Allowance BVY 12-005, Technical Specifications Proposed Change No. 297, Suppression Chamber-Drywell Leak Rate Test Surveillance Frequency Change2012-02-0101 February 2012 Technical Specifications Proposed Change No. 297, Suppression Chamber-Drywell Leak Rate Test Surveillance Frequency Change BVY 11-085, Proposed Change No. 296, Steam Dryer License Condition Change2011-12-22022 December 2011 Proposed Change No. 296, Steam Dryer License Condition Change BVY 11-069, Technical Specifications Proposed Change No. 295 Proposed Emergency License Amendment for Single Loop Operation2011-09-29029 September 2011 Technical Specifications Proposed Change No. 295 Proposed Emergency License Amendment for Single Loop Operation BVY 10-059, Technical Specifications Proposed Change No. 294, Elimination of Provisions Allowing HPCI and RCIC Suctions to Be Aligned to the Suppression Pool2010-11-0808 November 2010 Technical Specifications Proposed Change No. 294, Elimination of Provisions Allowing HPCI and RCIC Suctions to Be Aligned to the Suppression Pool BVY 10-045, Technical Specifications Proposed Change No. 289 Suppression Chamber-Drywell Vacuum Breakers and Differential Pressure2010-08-19019 August 2010 Technical Specifications Proposed Change No. 289 Suppression Chamber-Drywell Vacuum Breakers and Differential Pressure BVY 10-036, Technical Specifications Proposed Change No. 292, License Amendment Withdrawal and Request - Cyber Security Plan2010-07-16016 July 2010 Technical Specifications Proposed Change No. 292, License Amendment Withdrawal and Request - Cyber Security Plan BVY 09-068, Technical Specifications Proposed Change No. 288 Scram Discharge Volume Vent and Drain Valves2009-12-0303 December 2009 Technical Specifications Proposed Change No. 288 Scram Discharge Volume Vent and Drain Valves BVY 09-063, Technical Specification Proposed Change No. 287 Safety Limit Minimum Critical Power Ratio Change2009-10-27027 October 2009 Technical Specification Proposed Change No. 287 Safety Limit Minimum Critical Power Ratio Change BVY 09-052, Technical Specifications Proposed Change No. 284 Change to Requirements for Inoperable Containment Isolation Valves2009-09-16016 September 2009 Technical Specifications Proposed Change No. 284 Change to Requirements for Inoperable Containment Isolation Valves BVY 09-051, Technical Specifications Proposed Change No. 285 Revision of High Radiation Area Controls2009-08-26026 August 2009 Technical Specifications Proposed Change No. 285 Revision of High Radiation Area Controls ML0912001622009-05-31031 May 2009 Safety Evaluation Report Related to the License Renewal of Vermont Yankee Nuclear Power Station Supplement 1 BVY 09-029, Technical Specifications Proposed Change No. 283 Change to Requirements for Performing 10 CFR 50, Appendix J, Type a Test2009-05-0505 May 2009 Technical Specifications Proposed Change No. 283 Change to Requirements for Performing 10 CFR 50, Appendix J, Type a Test BVY 09-012, Submittal of Proposed License Amendment for Technical Specifications No. 282, Revision of Drywell Vacuum Breaker Surveillance Requirements2009-02-24024 February 2009 Submittal of Proposed License Amendment for Technical Specifications No. 282, Revision of Drywell Vacuum Breaker Surveillance Requirements BVY 08-079, Technical Specifications Proposed Change No. 280, Supplement 1 Relocation of Reactor Building Crane Technical Specifications2008-10-31031 October 2008 Technical Specifications Proposed Change No. 280, Supplement 1 Relocation of Reactor Building Crane Technical Specifications BVY 08-055, Technical Specifications Proposed Change No. 277, License Amendment Request Application for Licensee Name Changes2008-09-30030 September 2008 Technical Specifications Proposed Change No. 277, License Amendment Request Application for Licensee Name Changes BVY 08-059, Technical Specifications Proposed Change No. 280 Relocation of Reactor Building Crane Technical Specifications2008-09-22022 September 2008 Technical Specifications Proposed Change No. 280 Relocation of Reactor Building Crane Technical Specifications BVY 08-052, Technical Specifications Proposed Change No. 278, Changes to Main Steam Isolation Valve Surveillance Requirements2008-09-22022 September 2008 Technical Specifications Proposed Change No. 278, Changes to Main Steam Isolation Valve Surveillance Requirements BVY 08-053, Technical Specifications Proposed Change No. 279 Sale or Lease of Property within the Exclusion Boundary2008-09-0404 September 2008 Technical Specifications Proposed Change No. 279 Sale or Lease of Property within the Exclusion Boundary BVY 08-001, Technical Specifications Proposed Change No. 273 Instrumentation Technical Specifications2008-02-12012 February 2008 Technical Specifications Proposed Change No. 273 Instrumentation Technical Specifications ML0806602032008-02-12012 February 2008 Vermont Yankee, Technical Specifications Proposed Change No. 273, Instrumentation Technical Specifications BVY 08-007, Technical Specification Proposed Change No. 276 Revision to TS Sections 3.3/4.3 for Control Rod System2008-02-0606 February 2008 Technical Specification Proposed Change No. 276 Revision to TS Sections 3.3/4.3 for Control Rod System ML0804202202008-02-0505 February 2008 Vermont Yankee - License Renewal Application, Amendment 35 ML0736502282007-12-11011 December 2007 (PA-LR) VY Response to RAI 4.3.3-2 BVY 07-056, Technical Specification Proposed Change No. 274, Changes to Technical Specifications for Emergency Diesel Generator Fuel Oil and Reactor Building Crane Surveillance Requirements2007-10-18018 October 2007 Technical Specification Proposed Change No. 274, Changes to Technical Specifications for Emergency Diesel Generator Fuel Oil and Reactor Building Crane Surveillance Requirements BVY 07-063, Technical Specifications Proposed Change No. 275 Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Limits2007-10-18018 October 2007 Technical Specifications Proposed Change No. 275 Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Limits BVY 07-018, License Renewal Application, Amendment 262007-03-23023 March 2007 License Renewal Application, Amendment 26 ML0702402042007-01-10010 January 2007 Email: (PA-LR) Other Word File ML0701105042007-01-0404 January 2007 Vermont Yankee - License Renewal Application, Amendment 23 ML0634201782006-12-0404 December 2006 2006/12/04-Vermont Yankee Nuclear Power Station, License Renewal Application, Amendment 22, Clarification of Aging Management Program and Environmental Report Items ML0634004532006-11-0909 November 2006 2006/11/09-E-Mail: (NPA-PD-LR) VYNPS License Renewal Application Am. 20, Vermont Yankee BVY 06-097, 2006/10/31-Vermont Yankee License Renewal Application, Amendment 192006-10-31031 October 2006 2006/10/31-Vermont Yankee License Renewal Application, Amendment 19 ML0627801222006-10-12012 October 2006 Summary of a Telephone Conference Call Held on September 19, 2006, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc ML0626800342006-09-19019 September 2006 2006/09/19-Vermont Yankee License Renewal Application, Amendment 13 ML0625504392006-09-0505 September 2006 License Renewal Application, Amendment 12 2023-10-10
[Table view] Category:Technical Specification
MONTHYEARBVY 15-055, Revision of Technical Specifications Bases Pages2015-11-16016 November 2015 Revision of Technical Specifications Bases Pages BVY 15-024, Revision of Technical Specifications Bases Pages2015-03-25025 March 2015 Revision of Technical Specifications Bases Pages ML14231A0172014-08-13013 August 2014 Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 4 ML14202A2062014-07-16016 July 2014 Technical Specifications Proposed Change No. 307, Revision to Technical Specification Administrative Controls for Permanently Defueled Condition - Supplement 2 BVY 14-049, Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 32014-06-11011 June 2014 Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 3 ML13323A5182013-11-14014 November 2013 Technical Specifications Proposed Change No. 306 Eliminate Certain ESF Requirements During Movement of Irradiated Fuel BVY 13-084, Revision of Technical Specification Bases Page2013-09-0909 September 2013 Revision of Technical Specification Bases Page BVY 13-053, Revision of Technical Specifications Bases Pages2013-07-24024 July 2013 Revision of Technical Specifications Bases Pages BVY 13-062, Revised of Technical Specification Bases Pages2013-06-26026 June 2013 Revised of Technical Specification Bases Pages BVY 13-043, Technical Specifications Proposed Change No. 304, Revision to Low Pressure Safety Limit2013-05-14014 May 2013 Technical Specifications Proposed Change No. 304, Revision to Low Pressure Safety Limit BVY 13-023, License Amendment Request; Changes to 10 CFR 50.63 Licensing Basis, Supplement 22013-04-29029 April 2013 License Amendment Request; Changes to 10 CFR 50.63 Licensing Basis, Supplement 2 BVY 13-022, Revision of Technical Specification Bases Pages2013-03-26026 March 2013 Revision of Technical Specification Bases Pages BVY 12-078, Technical Specifications Proposed Change 297, Supplement 2 Response to Request for Additional Information2012-11-20020 November 2012 Technical Specifications Proposed Change 297, Supplement 2 Response to Request for Additional Information BVY 12-055, Technical Specifications Proposed Change 297, Supplement 1, Response to Request for Additional Information2012-08-0707 August 2012 Technical Specifications Proposed Change 297, Supplement 1, Response to Request for Additional Information BVY 12-018, Technical Specifications Proposed Change No. 299 Recirculation System Discharge Bypass Valve Change2012-04-17017 April 2012 Technical Specifications Proposed Change No. 299 Recirculation System Discharge Bypass Valve Change BVY 12-006, Technical Specifications Proposed Change No. 298, Rod Worth Minimizer Bypass Allowance2012-02-0101 February 2012 Technical Specifications Proposed Change No. 298, Rod Worth Minimizer Bypass Allowance BVY 12-005, Technical Specifications Proposed Change No. 297, Suppression Chamber-Drywell Leak Rate Test Surveillance Frequency Change2012-02-0101 February 2012 Technical Specifications Proposed Change No. 297, Suppression Chamber-Drywell Leak Rate Test Surveillance Frequency Change BVY 11-068, Revision of Technical Specification Bases Pages Due to License Amendment 2482011-09-30030 September 2011 Revision of Technical Specification Bases Pages Due to License Amendment 248 BVY 11-042, Technical Specifications Proposed Change No. 293, Supplement 1 Revised Reactor Vessel Pressure-Temperature Limitation Curves2011-05-16016 May 2011 Technical Specifications Proposed Change No. 293, Supplement 1 Revised Reactor Vessel Pressure-Temperature Limitation Curves BVY 11-037, Revision of Technical Specification Bases Pages Due to License Amendment 2462011-04-21021 April 2011 Revision of Technical Specification Bases Pages Due to License Amendment 246 BVY 10-059, Technical Specifications Proposed Change No. 294, Elimination of Provisions Allowing HPCI and RCIC Suctions to Be Aligned to the Suppression Pool2010-11-0808 November 2010 Technical Specifications Proposed Change No. 294, Elimination of Provisions Allowing HPCI and RCIC Suctions to Be Aligned to the Suppression Pool BVY 10-056, Submittal of Revision of Technical Specification Bases Pages2010-10-0606 October 2010 Submittal of Revision of Technical Specification Bases Pages BVY 10-047, Revision of Technical Specifications Bases Page2010-08-18018 August 2010 Revision of Technical Specifications Bases Page BVY 10-027, Revision of Technical Specification Bases Pages2010-05-21021 May 2010 Revision of Technical Specification Bases Pages BVY 10-017, Technical Specifications Proposed Change No. 290 Administrative Changes2010-04-13013 April 2010 Technical Specifications Proposed Change No. 290 Administrative Changes BVY 10-021, Revision of Technical Specification Bases Pages2010-03-31031 March 2010 Revision of Technical Specification Bases Pages BVY 09-074, Revision of Technical Specifications Bases Pages2009-12-0909 December 2009 Revision of Technical Specifications Bases Pages BVY 09-072, Technical Specification Bases Pages Associated with License Amendment 2362009-12-0909 December 2009 Technical Specification Bases Pages Associated with License Amendment 236 BVY 09-068, Technical Specifications Proposed Change No. 288 Scram Discharge Volume Vent and Drain Valves2009-12-0303 December 2009 Technical Specifications Proposed Change No. 288 Scram Discharge Volume Vent and Drain Valves BVY 09-055, Revision of Technical Specifications Bases Page2009-09-28028 September 2009 Revision of Technical Specifications Bases Page BVY 09-052, Technical Specifications Proposed Change No. 284 Change to Requirements for Inoperable Containment Isolation Valves2009-09-16016 September 2009 Technical Specifications Proposed Change No. 284 Change to Requirements for Inoperable Containment Isolation Valves BVY 09-051, Technical Specifications Proposed Change No. 285 Revision of High Radiation Area Controls2009-08-26026 August 2009 Technical Specifications Proposed Change No. 285 Revision of High Radiation Area Controls BVY 09-044, Revision of Technical Specifications Bases Pages2009-07-28028 July 2009 Revision of Technical Specifications Bases Pages BVY 09-029, Technical Specifications Proposed Change No. 283 Change to Requirements for Performing 10 CFR 50, Appendix J, Type a Test2009-05-0505 May 2009 Technical Specifications Proposed Change No. 283 Change to Requirements for Performing 10 CFR 50, Appendix J, Type a Test BVY 09-021, Submittal of Revision of Technical Specification Bases Pages2009-03-31031 March 2009 Submittal of Revision of Technical Specification Bases Pages BVY 09-014, Submittal of Revised Technical Specification Bases Pages2009-02-24024 February 2009 Submittal of Revised Technical Specification Bases Pages BVY 09-012, Submittal of Proposed License Amendment for Technical Specifications No. 282, Revision of Drywell Vacuum Breaker Surveillance Requirements2009-02-24024 February 2009 Submittal of Proposed License Amendment for Technical Specifications No. 282, Revision of Drywell Vacuum Breaker Surveillance Requirements ML0836500072008-12-18018 December 2008 Vermont Yankee Nuclear Power Station, Response to Request for Additional Information on Technical Specifications Proposed Change No. 273, Supplement 6 BVY 08-087, Vermont Yankee Nuclear Power Station, Response to Request for Additional Information on Technical Specifications Proposed Change No. 273, Supplement 62008-12-18018 December 2008 Vermont Yankee Nuclear Power Station, Response to Request for Additional Information on Technical Specifications Proposed Change No. 273, Supplement 6 BVY 08-087, Attachment 2, Technical Specification Proposed Change No. 273, Supplement 6, Sample Set-Point Calculations2008-12-18018 December 2008 Attachment 2, Technical Specification Proposed Change No. 273, Supplement 6, Sample Set-Point Calculations BVY 08-081, Submittal of Revision of Technical Specification Bases Page 292008-11-17017 November 2008 Submittal of Revision of Technical Specification Bases Page 29 BVY 08-076, Revision of Technical Specification Bases Pages2008-10-14014 October 2008 Revision of Technical Specification Bases Pages BVY 08-052, Technical Specifications Proposed Change No. 278, Changes to Main Steam Isolation Valve Surveillance Requirements2008-09-22022 September 2008 Technical Specifications Proposed Change No. 278, Changes to Main Steam Isolation Valve Surveillance Requirements BVY 08-059, Technical Specifications Proposed Change No. 280 Relocation of Reactor Building Crane Technical Specifications2008-09-22022 September 2008 Technical Specifications Proposed Change No. 280 Relocation of Reactor Building Crane Technical Specifications BVY 08-069, Transmittal of Technical Specifications Proposed Change No. 281, Revision to Battery Systems2008-09-22022 September 2008 Transmittal of Technical Specifications Proposed Change No. 281, Revision to Battery Systems BVY 08-066, Submittal of Corrected Technical Specification Page2008-08-26026 August 2008 Submittal of Corrected Technical Specification Page BVY 08-060, Submittal of Revision of Technical Specification Bases Page 2202008-08-25025 August 2008 Submittal of Revision of Technical Specification Bases Page 220 BVY 08-046, Revision of Technical Specification Bases Page 972008-07-28028 July 2008 Revision of Technical Specification Bases Page 97 BVY 08-031, Revision of Technical Specification Bases Page2008-05-29029 May 2008 Revision of Technical Specification Bases Page BVY 08-001, Technical Specifications Proposed Change No. 273 Instrumentation Technical Specifications2008-02-12012 February 2008 Technical Specifications Proposed Change No. 273 Instrumentation Technical Specifications 2015-03-25
[Table view] Category:Amendment
MONTHYEARBVY 14-049, Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 32014-06-11011 June 2014 Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 3 BVY 12-018, Technical Specifications Proposed Change No. 299 Recirculation System Discharge Bypass Valve Change2012-04-17017 April 2012 Technical Specifications Proposed Change No. 299 Recirculation System Discharge Bypass Valve Change BVY 10-059, Technical Specifications Proposed Change No. 294, Elimination of Provisions Allowing HPCI and RCIC Suctions to Be Aligned to the Suppression Pool2010-11-0808 November 2010 Technical Specifications Proposed Change No. 294, Elimination of Provisions Allowing HPCI and RCIC Suctions to Be Aligned to the Suppression Pool BVY 09-052, Technical Specifications Proposed Change No. 284 Change to Requirements for Inoperable Containment Isolation Valves2009-09-16016 September 2009 Technical Specifications Proposed Change No. 284 Change to Requirements for Inoperable Containment Isolation Valves BVY 09-051, Technical Specifications Proposed Change No. 285 Revision of High Radiation Area Controls2009-08-26026 August 2009 Technical Specifications Proposed Change No. 285 Revision of High Radiation Area Controls BVY 09-029, Technical Specifications Proposed Change No. 283 Change to Requirements for Performing 10 CFR 50, Appendix J, Type a Test2009-05-0505 May 2009 Technical Specifications Proposed Change No. 283 Change to Requirements for Performing 10 CFR 50, Appendix J, Type a Test BVY 09-012, Submittal of Proposed License Amendment for Technical Specifications No. 282, Revision of Drywell Vacuum Breaker Surveillance Requirements2009-02-24024 February 2009 Submittal of Proposed License Amendment for Technical Specifications No. 282, Revision of Drywell Vacuum Breaker Surveillance Requirements BVY 08-059, Technical Specifications Proposed Change No. 280 Relocation of Reactor Building Crane Technical Specifications2008-09-22022 September 2008 Technical Specifications Proposed Change No. 280 Relocation of Reactor Building Crane Technical Specifications BVY 08-066, Submittal of Corrected Technical Specification Page2008-08-26026 August 2008 Submittal of Corrected Technical Specification Page BVY 08-001, Technical Specifications Proposed Change No. 273 Instrumentation Technical Specifications2008-02-12012 February 2008 Technical Specifications Proposed Change No. 273 Instrumentation Technical Specifications ML0535301802005-12-12012 December 2005 Technical Specification Proposed Change No. 266, Revision to Control Rod Operability, Scram Time Testing and Control Rod Accumulators - Response to Request for Additional Information BVY 05-101, Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 263 - Supplement No. 41 Re Extended Power Uprate - Condensate and Feedwater Transient Response Engineering Analysis2005-11-0202 November 2005 Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 263 - Supplement No. 41 Re Extended Power Uprate - Condensate and Feedwater Transient Response Engineering Analysis BVY 05-088, Vermont Yankee, Technical Specification Proposed Change No. 263 - Supplement No. 35 Extended Power Uprate - Response to Request for Additional Information2005-09-28028 September 2005 Vermont Yankee, Technical Specification Proposed Change No. 263 - Supplement No. 35 Extended Power Uprate - Response to Request for Additional Information BVY 05-086, Vermont Yankee - Technical Specifications Proposed Change No. 263 - Supplement No. 34 Extended Power Uprate - Additional Information2005-09-18018 September 2005 Vermont Yankee - Technical Specifications Proposed Change No. 263 - Supplement No. 34 Extended Power Uprate - Additional Information ML0524402132005-08-31031 August 2005 Technical Specification Page, Revision to One-Time Extension of Integrated Leak Rate Test Interval ML0508402532005-03-22022 March 2005 Tech Spec Pages for Amendment 222 Regarding Elimination of Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports ML0505401492005-02-18018 February 2005 Corrected Page 7 to License DPR-28 and Page 97 to Technical Specifications for Vermont Yankee BVY 04-098, Vermont Yankee - Technical Specification Proposed Change No. 263 - Supplement No. 14 Extended Power Uprate - Response to Request for Additional Information2004-09-15015 September 2004 Vermont Yankee - Technical Specification Proposed Change No. 263 - Supplement No. 14 Extended Power Uprate - Response to Request for Additional Information ML0408602662004-03-22022 March 2004 Technical Specification, Safety Limit Minimum Critical Power Ratio Values in Technical Specification 1.1.A.1 to Incorporate Results in cycle-specific Core Reload Analysis for Cycle 24 Operation ML0329301432003-10-10010 October 2003 Technical Specification Proposed Change No. 262, Supplement No. 1 Regarding Alternative Source Term ML0328104472003-10-0101 October 2003 Vermont Yankee - Technical Specification Proposed Change No. 263, Supplemental No. 1 Regarding Extended Power Uprate, Technical Review Guidance ML0321906462003-07-31031 July 2003 TS Proposed Change No. 262, Alternative Source Term ML0226302842002-09-18018 September 2002 Technical Specifications, Remove Existing Scram Function & Group 1 Isolation Valve Closure Functions of Main Steam Line Radiation Monitors ML17037B7791974-02-0707 February 1974 Letter Regarding Petition for Derating of Certain Boiling Water Reactors and Enclosed Before the Atomic Safety and Licensing Appeal Board in the Matter of Vermont Yankee Nuclear Power Corporation - Vermont Yankee Nuclear ... 2014-06-11
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lI~SdEntergy Entergy Nuclear Operations, Inc.Vermont Yankee P,. Box 0250 320 Governor Hunt Rd Vernon, VT 05354 Tel 802 257 7711 Michael J. Colomb Site Vice President BVY 09-051 August 26, 2009 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Technical Specifications Proposed Change No. 285 Revision of High Radiation Area Controls Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28
Dear Sir or Madam:
In accordance with 10CFR50.90, Entergy Nuclear Operations, Inc. (ENO) is proposing to amend Operating License DPR-28 for Vermont Yankee Nuclear Power Station (VY). The proposed change would modify the VY Technical Specifications (TS) that governs administrative control of High Radiation Areas (HRA) to incorporate the HRA administrative controls contained within the Standard Technical Specifications, NUREG-1433, Revision 3.ENO has reviewed the proposed amendment in accordance with 1 OCFR50.92 and concludes it does not involve a significant hazards consideration.
In accordance with 10CFR50.91, a copy of this application, with attachments, is being provided to the State of Vermont, Department of Public Service.Attachment 1 to this letter provides a detailed description and evaluation of the proposed change.Attachment 2 contains a markup of the current TS pages. Attachment 3 contains the retyped TS pages.ENO requests review and approval of the proposed license amendment by September 1, 2010 and a 60 day implementation period from the date of the amendment approval.There are no new regulatory commitments made in this letter.If you have any questions on this transmittal, please contact Mr. David Mannai at 802-451-3304.
4O /
-i BVY 09-051 / Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on August 26, 2009.Sincerely, MJC/PLC Attachments
- 1. Description and Evaluation of the Proposed Changes 2. Markup of the Current Technical Specifications Pages 3. Retyped Technical Specifications Pages cc: Mr. Samuel J. Collins Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. James S. Kim, Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 08C2A Washington, DC 20555 USNRC Resident Inspector Entergy Nuclear Vermont Yankee, LLC 320 Governor Hunt Rd Vernon, Vermont 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street -Drawer 20 Montpelier, Vermont 05620-2601 BVY 09-051 Docket No. 50-271 Attachment 1 Vermont Yankee Nuclear Power Station Proposed Change 285 Description and Evaluation of Proposed Changes BVY 09-051 / Attachment 1 / Page 1 of 4 PURPOSE OF THE PROPOSED CHANGES The proposed change to Vermont Yankee Nuclear Power Station (VY) Technical Specification (TS) Administrative Control 6.5 is as follows: Administrative Control 6.5 "High Radiation Area" is proposed to be changed to modify the access controls for high radiation areas. The proposed change replaces the current access controls for high radiation areas with the access controls described in section 5.7 of NUREG-1433, Revision 3, "Standard Technical Specifications General Electric Plants, BWR/4." The NUREG-1433 high radiation area access controls more explicitly describe the requirements for entry into high radiation areas both for areas with dose rates less than 1.0 rem/hr and for those areas exceeding 1.0 rem/hr than the current access controls and also provide additional requirements and options for the control of these areas.I1. DESCRIPTION OF CHANGES The proposed license amendment replaces the current access controls for high radiation areas with the access controls described in NUREG-1433.
Specifically, the changes proposed are: 1) Pages 257 and 258, Administrative Control 6.5 "High Radiation Area": This Administrative Control is being replaced with the high radiation area access controls of section 5.7 of NUREG-1433.
Administrative Control 6.5.A, which describes the access controls for high radiation areas with dose rates less than 1.0 rem/hr, will be replaced in its entirety by section 5.7.1 of NUREG-1433.
Administrative Control 6.5.B, which describes the access controls for high radiation areas with dose rates exceeding 1.0 rem/hr, will be replaced in its entirety by section 5.7.2 of NUREG-1433.
For clarification and consistency with the definition of high radiation area in 1OCFR20.1003, the lower bound of "greater than 0.1 rem/hr at 30 centimeters" is being added to the heading from section 5.7.1 of NUREG-1433.
Additionally, the words"and/or" are being added to the wording from section 5.7.2.a.1 of NUREG-1433 to J clarify that either the shift supervisor or radiation protection manager or both will have administrative control of the keys for locked high radiation areas.Ill. SAFETY IMPLICATIONS OF THE PROPOSED CHANGE The TS administrative access controls for high radiation areas, section 6.5, are proposed to be replaced with those contained in section 5.7 of NUREG-1433 to provide additional requirements and options for the control of these areas. The federal regulatory requirements that establish the standards for protection against radiation are contained in 1OCFR20. These regulations establish standards for protection against ionizing radiation resulting from activities conducted under licenses issued by the Nuclear Regulatory Commission.
The purpose of the 1OCFR20 regulations is in part to control activities in such a manner that the total dose to an individual does not exceed-the limits established in 1OCFR20. In addition, the programs for radiation protection strive to limit dose to a value that is as low as reasonably achievable.
BVY 09-051 / Attachment 1 / Page 2 of 4 The specific requirements relating to control of access to high radiation areas are provided in 10CFR20.1601.
These regulations provide controls to ensure that access to these areas is controlled and that inadvertent entry is prohibited.
This allows radiation protection personnel to establish requirements for personnel protection including contamination control and personnel monitoring.
This ensures that personnel are aware of radiation hazards and that activities in these areas can be closely monitored and controlled.
Section 6.5 "High Radiation Area" of the VY TS provides requirements for control of access to high radiation areas that are consistent with 10CFR20. The proposed change replaces the current TS with the equivalent requirements from NUREG-1433 section 5.7 "High Radiation Area." Section 5.7 of NUREG-1433 satisfies the regulatory requirements for high radiation controls contained in 10CFR20. The proposed requirements provide additional options for controlling radiation areas including controls for individual high radiation areas that are within larger areas where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed.
These requirements are not contained in the current TS and could be used to accommodate plant specific arrangements to ensure adequate protection of personnel.
The proposed amendment does not change any existing equipment operating requirements and does not adversely affect existing plant safety margins or the reliability of the equipment'assumed to operate in the safety analysis.
As such, there are no changes being made to safety analysis assumptions, safety limits or safety system settings that would adversely affect plant safety as a result of the proposed amendment.
IV. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION The proposed license amendment replaces the current Technical Specification administrative requirements, section 6.5, for high radiation area access control with the administrative access controls contained in section 5.7 of NUREG-1433, Revision 3, Standard Technical Specifications General Electric Plants, BWR/4." Pursuant to 10CFR50.92, Entergy Nuclear Operations, Inc. has reviewed the proposed change and concludes that the change does not involve a significant hazards consideration since the proposed change satisfies the criteria in 1 OCFR50.92(c).
These criteria require that operation of the facility in accordance with the proposed amendment would not (1)involve a significant increase in the probability or consequences of an accident previously evaluated; (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. The discussion below addresses each of these criteria and demonstrates that the proposed amendment does not constitute a significant hazard.The proposed change does not involve a significant hazards consideration because: 1. The operation of Vermont Yankee Nuclear Power Station (VY) in accordance with the proposed amendment will not involve a significant increase in the Probability or consequences of an accident Previously evaluated.
The proposed amendment does not impact the operability of any structure, system or component that affects the probability of an accident or that supports mitigation of an accident previously evaluated.
The proposed amendment does not affect reactor BVY 09-051 / Attachment 1 / Page 3 of 4 operations or accident analysis and has no radiological consequences.
The operability requirements for accident mitigation systems remain consistent with the licensing and design basis. Therefore, the proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. The operation of VY in accordance with the proposed amendment will not create the Possibility of a new or different kind of accident from any accident previously evaluated.
The proposed amendment does not change the design or function of any component or system. No new modes of failure or initiating events are being introduced.
Therefore, operation of VY in accordance with the proposed amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. The operation of VY in accordance with the proposed amendment will not involve a significant reduction in a margin of safety.The proposed amendment does not change the design or function of any component or system. The proposed amendment does not involve any safety limits, safety settings or safety margins. The TS administrative access controls for high radiation areas are being replaced with those contained in section 5.7 of NUREG-1433 to provide additional requirements and options for the control of these areas.Therefore, operation of VY in accordance with the proposed amendment will not involve a significant reduction in the margin to safety.V. ENVIRONMENTAL CONSIDERATIONS This amendment request meets the eligibility criteria for categorical exclusion from environmental review set forth in 1 OCFR51.22(c)(9) as follows: (i) The amendment involves no significant hazards determination.
As described in Section IV of this evaluation, the proposed change involves no significant hazards consideration.(ii) There is no significant change in the types or significant increase in the amounts of any effluent that may be released offsite.The proposed amendment does not involve any physical alterations to the plant configuration that could lead to a change in the type or amount of effluent release off'site.(iii) There is no significant increase in individual or cumulative occupational radiation exposure.The proposed amendment replaces the TS administrative access controls for high radiation areas, section 6.5, with the access controls contained in section 5.7 of BVY 09-051 / Attachment 1 / Page 4 of 4 NUREG-1433.
This proposed amendment does not change the dose rate levels used to define high radiation areas and will not increase individual or cumulative occupational radiation exposure.Based on the above, VY concludes that the proposed change meets the eligibility criteria for categorical exclusion as set forth in 10CFR51.22(c)(9).
Pursuant to 10CFR51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
VI. REFERENCES a) NUREG-1433, Revision 3, "Standard Technical Specifications General Electric Plants, BWR/4," dated March 2004.
BVY 09-051 Docket 50-271 Attachment 2 Vermont Yankee Nuclear Power Station Proposed Change 285 Markup of the Current Technical Specification Pages VYNPS 6.2 ORGANIZATION (Cont'd)C. Unit Staff Qualifications Each member of the unit staff shall meet or exceed the minimum qualifications of the American National Standards Institute N-18.1-1971, "Selection and Training of Personnel for Nuclear Power Plants," except for the radiation protection manager who shall meet the qualifications of Regulatory Guide 1.8, Revision 1 (September 1975) and the shift engineer, who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
6.3 ACTION
TO BE TAKEN IF A SAFETY LIMIT IS EXCEEDED Applies to administrative action to be followed in the event a safety limit is exceeded.If a safety limit is exceeded, the reactor shall be shutdown immediately.
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 of the facility.B. Refueling operations.
C. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, suspected Primary System leaks and abnormal reactivity changes.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 reactor.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 20.160,1(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: Amendment No. 4-6, 44, 4-, 4a, is-I., 1-6, -71,-- , 214 257 VYNPS t A. aaagraph 20.1601, "Control of Access to High Radiation Areas.In lieu of the "control device" or "alarm signal" required by Paragrap 20.1601(a), each high radiation area in which th intensity radiation is, greater than 100 mrem/hr at 30 -m, bu less than 1 0 mrem/hr at 30 cm, shall be barricaded a conspicuously osted as a high radiation area and ent ance thereto shall b controlled by requiring issuance o a Radiation Work Permit (RWP Radiation Protection personne qualified in radiation protecti n procedures (e.g., radiatio protection technicians) may be exempt from the RWP issua e requirement during the performan of their assigned du es in high radiatio areas, provided they e otherwise follow g plant radiation protection procedures r entry into suc high radiation areas.Any individual or group o individua permitted to enter such areas shall be provided wit one o more of the following:
- 1. A radiation monitoring d vce which continuously indicates the radiation dose rate the area.2. A radiation monitori devic which continuously integrate the radiation dose ate in th area and alarms when a pres t integrated dose i received.
try into such areas with this monitoring evice may be ma e after the dose rate levels in the rea have been esta:ished and personnel have been made k wledgeable of them.3. A Radiat' n Protection individual qua ified in radiation protection procedures (e.g., radiation rotection technicians) with a radiation dose rate onitoring device, who s responsible for providing positiv control over the\ac ivities within the area and who will pe form direct or\ (such as closed circuit TV cameras) periodic"radiation surveillance at the frequency specified in the RWP. The surveillance frequency will be established by the radiation protection manager.B. The above procedure shall also apply to each high ra .tion area in wh the intensity of radiation is greate n 1000 mrem/hr at 30 cm, b 4e-ss than 500 rad/hr at _mer. In addition, locked or contin ly guardedways shall be provided to prevent unauthorize e nto such areas and the keys shall b maintained un e addminist e control of the shift superLaitzron duty and/or the radiati otection manager.6.6 REPORTING REQUIREMENTS The following reports shall be submitted in accordance with 10 CFR 50.4.A. Deleted Amendment No. 44, 42/ 4-9-], 244, 222 258 High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20: 6, r-6,-lj4&
47 -o 4m,^*,,rt,, "I , sd r , JAI 6:/P4 rHiaqh Radiation Areas with Dose Rates Jlot Exceeding 1.0 rem/hour at 30 ,Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation if. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.
V'. Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.Individuals qualified in radiation protection procedures and personnel 3 continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.If. Each individual or group entering such an area shall possess: I- A radiation monitoring device that continuously displays radiation dose rates in the area, or o 2. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or ca. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or j4 /4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and,-)j. Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation d-15 monitoring device that continuously displays radiation dees 7do__/rates in the area; who is responsible for controlling personnel exposure within the area, or BWR/4 STS 5.7-1 Rev. 3.0, 03/31/04 High Radiation Area 5.7 5.7 High Radiation Area 5.71' Highl'Rdiation Areas with Dose Rates Not Exceedior,..I.0 rem/.our at 30 Centimeters o the on g-ureor any S Xace Wnetrat&H:-the R-a-intt-'F (continued)
Ni 7- t Be under the surveillance, as specified in the RWP or A, equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.
fd. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not. require documentation prior to initial entry.10,High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 e / Centimeters from the Radiation Source or from any Surface Penetrated by theje,/ Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or\from any Surface Penetrated by the Radiation I a(. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition: T. All such door and gate keys shall be maintained under the administrative control of the shift supervisorf radiation protection manager, or his or her designee.
4gooL k 2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.0 I. Access to, and activities in, each such area shall be controlled by eans of an RWP or equivalent that includes specification of radiation SA; rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.it Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.BWRI4 STS 5.7-2 Rev. 3.0, 03/31/04 BWR/4 STS 5.7-2 Rev. 3.0, 03/31/04 High Radiation Area 5.7 5.7 High Radiation Area..2 Hiqh Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters th Radiation.
Source or from any Surface Penetrated by than 50 ra our t11 om t ad " o roma Surface Penetrate by the Radition (co knued)Each individual an area shall possess one of the following:A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or 9' i. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or.,. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, I,(< Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or 2 Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, respohsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.In those cases where option () and (A), above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.f(. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted/personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require dou entation prior to initial entry. , r0 BWR/4 STS 5.7-3 Rev. 3.0, 03/31/04 High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 Hi h Radia Areas with Dose Rates Greater than 1.0rnm/hout 30 Centimet ers-/" t t~ion from eene~atehjji~b-e uura ds lou r t 1 meter fr m th 6-Rdiatioh--9burce or from any Suriarce Penetrated by the Radiation
"-continued)
- Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated the area as a warning device.BWPJ4 STS 5.7-4 Rev. 3.0, 03/31/04 BVY 09-051 Docket 50-271 Attachment 3 Vermont Yankee Nuclear Power Station Proposed Change 285 Retyped Technical Specification Pages VYNPS 6.2 ORGANIZATION (Cont'd)C. Unit Staff Qualifications Each member of the unit staff shall meet or exceed the minimum qualifications of the American National Standards Institute N-18.1-1971, "Selection and Training of Personnel foP Nuclear Power Plants," except for the radiation protection manager who shall meet the qualifications of Regulatory Guide 1.8, Revision 1 (September 1975) and the shift engineer, who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
6.3 ACTION
TO BE TAKEN IF A SAFETY LIMIT IS EXCEEDED Applies to administrative action to be followed in the event a safety limit is exceeded.If a safety limit is exceeded, the reactor shall be shutdown immediately.
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 of the facility.B. Refueling operations.
C. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, suspected Primary System leaks and abnormal reactivity changes.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 reactor.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. ,34, 3-,- 4-4-, 168, , .44, 2-4 257 VYNPS 1. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.
- 2. Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.3. Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.4. Each individual or group entering such an area shall possess: a. A radiation monitoring device that continuously displays radiation dose rates in the area, or b. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or c. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or d. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, 1. Be under the surveillance, as specified in the RWP or equivalent, while in the area, of .an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or 2. Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.
- 5. Except for individuals qualified in radiation protection procedures, or personnel, continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted.
personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does' not require, documentation prior to initial entry.Amendment No.257a VYNPS B. High Radiation Areas with dose rates greater than 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation, but less than 500 rads/hour at 1 meter from the radiation source or from any surface penetrated by the radiation:
- 1. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition: a. All such door and gate keys shall be maintained under the administrative control of the shift supervisor, and/or radiation protection manager, or his or her designee.b. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.2. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.3. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.4. Each individual or group entering such an area shall possess one of the following:
- a. A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or b. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or c. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, 1. Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or Amendment No.257b VYNPS 2. Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.d. In those cases where option (b) and (c), above, are impractical or determined to be inconsistent with the"As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.5. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.6. Such individual areas that are within a larger area where no enclosure exists for the purpose of locking andwhere no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.6.6 REPORTING REQUIREMENTS The following reports shall be submitted in accordance with 10 CFR 50.4.A. Deleted Amendment No. 3-r 42-, 131, 24, 2-22 258