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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-Operating (New/Renewal/Amendments) DKT 50
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 ML18347B3602019-01-11011 January 2019 Letter: Vermont Yankee Nuclear Power Station - Issuance of Amendment Application for Order Approving Direct and Indirect Transfer of Renewed Facility Operating License and Independent Spent Fuel Storage Installation General License. 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 ML18165A4232018-07-25025 July 2018 Issuance of Amendment to Change the Physical Security Plan to Reflect an ISFSI-Only Configuration ML18053A1122018-03-30030 March 2018 Issuance of Amendment to Change the Emergency Plan and Emergency Action Level Scheme to Reflect an ISFSI-Only Configuration 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) ML15233A1662015-12-11011 December 2015 Issuance of Amendment No. 264 to Renewed Facility Operating License Changes to the Emergency Plan and Emergency Action Levels 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 ML14206A7102014-11-12012 November 2014 Issuance of Amendment No. 259, Revise Operating License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date ML13212A2012013-08-15015 August 2013 Issuance of Amendment No. 258 Change to Licensing Basis Regarding Station Blackout ML13105A1752013-04-26026 April 2013 Issuance of Amendment No. 257 Request to Revise Requirement of the Recirculation Pump Discharge Bypass Valves ML13042A2722013-04-17017 April 2013 Issuance of Amendment 256 Revision to License Condition 3.P and 3.S ML13025A3062013-03-14014 March 2013 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Correction to Amendments Issued on 12/28/12, Revise QA Program Manual and Staff Qualification Technical Specifications ML1300903212013-01-30030 January 2013 Issuance of Amendment Rod Worth Minimizer Bypass Allowance TS Change (TAC No. Me 7927) ML1300902152013-01-30030 January 2013 Issuance of Amendment Change to Suppression Chamber Drywell Leak Rate Test Surveillance Frequency ML12261A2922012-11-13013 November 2012 Issuance of Amendment to Renewed Facility Operating License Cyber Security Plan Implementation Schedule Milestone ML1127904592011-11-0404 November 2011 Issuance of Amendment Revised Reactor Vessel Pressure-Temperature Limitation Curves ML1127205902011-09-30030 September 2011 Issuance of Emergency Amendment Modification of Technical Specification for Single Loop Operation ML1121014312011-08-25025 August 2011 Issuance of Amendment Elimination of Technical Specification Provisions Allowing HPCI and RCIC Suctions to Be Aligned to the Suppression Pool ML11152A0132011-07-20020 July 2011 License Amendment, Cyber Security Plan ML0921100542011-03-21021 March 2011 Renewed Facility Operating License DPR-28 ML1103400782011-02-23023 February 2011 Issuance of Amendment Control Rod Block Actuation Logic System Functional Test ML1100601792011-02-0909 February 2011 Issuance of Amendment Regarding Modification to Technical Specification 4.12 as Result of Changes Made by License Amendment Nos. 230 and 239 and to Revise Wording in TS 3.7.A.8 ML1025717732010-10-0606 October 2010 License Amendment, Issuance of Amendment Scram Discharge Volume Vent and Drain Valves ML1004316132010-03-0808 March 2010 Issuance of Amendment Safety Limit Minimum Critical Power Ratio Change ML1001203062010-01-26026 January 2010 Issuance of Amendment Revision to Requirements for Inoperable Containment Isolation Valves ML0933604432010-01-0404 January 2010 License Amendment 241 Revision of High Radiation Area Controls ML0928906522009-10-28028 October 2009 Issuance of Amendment Extension of Appendix J, Type a Integrated Leakage Rate Test Interval ML0917400402009-07-13013 July 2009 License Amendment, Relocation of Reactor Building Crane Technical Specification ML0916102242009-07-0606 July 2009 Issuance of Amendment Testing and Inspection of Suppression Chamber-To-Drywell Vacuum Breakers ML0915505702009-06-17017 June 2009 License Amendment, Main Steam Isolation Valve Surveillance Requirements ML0914103582009-06-12012 June 2009 License Amendment, Issuance of Amendment Instrumentation Technical Specifications ML0903704562009-02-26026 February 2009 License Amendment, Issuance of Amendment Sale of Lease of Property within the Exclusion Boundary ML0901206582009-02-11011 February 2009 Issuance of Amendment Battery Systems ML0833001292009-01-0707 January 2009 Issuance of Amendment Control Rod Systems ML0815701872008-06-23023 June 2008 Issuance of Amendment Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Limits ML0808003342008-04-17017 April 2008 Issuance of Amendment Emergency Diesel Generator Fuel Oil Tank Volume, Fuel Oil Testing and Reactor Building Crane Inspections ML0723302302007-08-23023 August 2007 Revised Pages of Facility Operating License DPR-28 B.5.b ML0705301592007-03-26026 March 2007 Issuance of Amendment Adoption of Technical Specification Task Force (TSTF) Change TSTF-372, the Addition of Limiting Condition for Operation (LCO) 3.0.8 on the Inoperability of Snubbers ML0600500222006-03-0202 March 2006 Vermont Yankee, License Amendment 229 Regarding Extended Power Uprate ML0523600022005-09-20020 September 2005 License Amendment, Drywell Spray Header and Nozzle Air Test Frequency ML0520000032005-08-31031 August 2005 License Amendment, Revise One-Time Extension of Integrated Leak Rate Test Interval ML0519201382005-08-15015 August 2005 Issuance of License Amendment 226 Administrative Changes ML0516700622005-07-0707 July 2005 License Amendment, Extend Intermediate Range Monitor Surveillance Test Frequencies ML0504201652005-06-0101 June 2005 License Amendment, Relocation of Inservice Testing Requirements to a Licensee - Controlled Program 2019-09-11
[Table view] Category:Safety Evaluation
MONTHYEARML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML21159A0422021-06-28028 June 2021 VY and CR Indirect License Transfer Package ML19175A0422019-09-11011 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 ML18242A6392018-10-11011 October 2018 Safety Evaluation of License Transfer Request (License DPR-28, Docket Nos. 50-271 and 72-59 ML18156A1802018-08-15015 August 2018 Enc 2 SER ISFSI Only Tech Spec Amendment Package ML18165A4232018-07-25025 July 2018 Issuance of Amendment to Change the Physical Security Plan to Reflect an ISFSI-Only Configuration ML18099A1662018-05-0101 May 2018 Entergy Vermont Yankee Quality Assurance Program Manual - Review and Acceptance of Changes ML18053A1132018-03-30030 March 2018 VY ISFSI Only EP Final SER - Jack Parrott ML17082A3102017-06-20020 June 2017 Request for Exemptions from 10 CFR 30.11 for Vermont Yankee Alternate Disposal of Low-Activity Waste Water at Us Ecology Idaho ML17013A3032016-12-12012 December 2016 Draft Final SER ML16165A4672016-06-16016 June 2016 Safety Evaluation of the Entergy Vermont Yankee, Quality Assurance Program Manual, Revision 4 ML16165A4662016-06-16016 June 2016 Quality Assurance Program Manual Vermont Yankee Nuclear Power Station and Independent Spent Fuel Storage Facility - Review and Acceptance of Changes 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) ML16008B1032016-01-20020 January 2016 Evaluation of 10CFR 50.54(p)(2) Changes to the Security Plans ML15233A1662015-12-11011 December 2015 Issuance of Amendment No. 264 to Renewed Facility Operating License Changes to the Emergency Plan and Emergency Action Levels ML15292A2562015-11-0202 November 2015 Correction Letter Regarding Staff Review of Entergy'S Update to the Irradiated Fuel Management Plan ML15117A5512015-10-0707 October 2015 Issuance of Amendment for Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition ML15274A3792015-10-0505 October 2015 Review of Update to the Irradiated Fuel Management Plan ML15120A3152015-05-0707 May 2015 Relief Request ISI-06, Inservice Inspection Limited Examinations for the Fourth 10-Year Interval ML15097A3612015-04-16016 April 2015 Request for Consent to Cancel Lines of Credit 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 ML14210A2662014-08-0808 August 2014 Arkansas, Units 1 & 2, Big Rock Point, James A. Fitzpatrick, Grand Gulf, Unit 1, Indian Point, Units 1, 2 & 3, Palisades, Pilgrim, River Bend, Unit 1, Vermont Yankee, Waterford, Safety Evaluation Quality Assurance Program Manual, Rev. 24 & ML13238A3982013-08-28028 August 2013 Relief Requests for the Fifth 10-Year Inservice Testing Program Interval ML13228A1972013-08-22022 August 2013 Relief Request ISI-05 - Fifth 10-Year ISI Interval - Alternative to Maintain Certain ISI Related Activities on 2001 Edition, 2003 Addenda ASME Section XI Code ML13212A2012013-08-15015 August 2013 Issuance of Amendment No. 258 Change to Licensing Basis Regarding Station Blackout ML13127A1762013-05-21021 May 2013 Staff Assessment in Response to Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13105A1752013-04-26026 April 2013 Issuance of Amendment No. 257 Request to Revise Requirement of the Recirculation Pump Discharge Bypass Valves ML13042A2722013-04-17017 April 2013 Issuance of Amendment 256 Revision to License Condition 3.P and 3.S ML13025A3062013-03-14014 March 2013 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Correction to Amendments Issued on 12/28/12, Revise QA Program Manual and Staff Qualification Technical Specifications ML13055A0092013-03-0101 March 2013 Relief Request ISI-PT-02 - Fourth 10-Year ISI Interval - Alternative to System Leakage Test for the Reactor Pressure Vessel Head Flange Leak-Off Lines ML1300903212013-01-30030 January 2013 Issuance of Amendment Rod Worth Minimizer Bypass Allowance TS Change (TAC No. Me 7927) ML1300902152013-01-30030 January 2013 Issuance of Amendment Change to Suppression Chamber Drywell Leak Rate Test Surveillance Frequency ML12261A2922012-11-13013 November 2012 Issuance of Amendment to Renewed Facility Operating License Cyber Security Plan Implementation Schedule Milestone ML1214501962012-05-31031 May 2012 Closeout of Bulletin 2011-01, Mitigating Strategies, ML1207601522012-03-28028 March 2012 Core Plate Hold Down Bolt Inspection Plan and Analysis - Vermont Yankee Nuclear Power Station ML1127904592011-11-0404 November 2011 Issuance of Amendment Revised Reactor Vessel Pressure-Temperature Limitation Curves ML1127205902011-09-30030 September 2011 Issuance of Emergency Amendment Modification of Technical Specification for Single Loop Operation ML1121014312011-08-25025 August 2011 Issuance of Amendment Elimination of Technical Specification Provisions Allowing HPCI and RCIC Suctions to Be Aligned to the Suppression Pool ML11152A0132011-07-20020 July 2011 License Amendment, Cyber Security Plan ML1103400782011-02-23023 February 2011 Issuance of Amendment Control Rod Block Actuation Logic System Functional Test ML1100601792011-02-0909 February 2011 Issuance of Amendment Regarding Modification to Technical Specification 4.12 as Result of Changes Made by License Amendment Nos. 230 and 239 and to Revise Wording in TS 3.7.A.8 ML1025717732010-10-0606 October 2010 License Amendment, Issuance of Amendment Scram Discharge Volume Vent and Drain Valves ML1026002492010-10-0101 October 2010 Relief Request VY-ISI-014, Alternative Examination Requirement for Nozzle-To-Vessel Weld and Inner Radius Using ASME Code Case N-702-Vermont Yankee Nuclear Power Station ML1004316132010-03-0808 March 2010 Issuance of Amendment Safety Limit Minimum Critical Power Ratio Change ML1001203062010-01-26026 January 2010 Issuance of Amendment Revision to Requirements for Inoperable Containment Isolation Valves ML0936208072010-01-22022 January 2010 Cover Letter, (Non-Proprietary) Order Extending the Effectiveness of the Approval of the Indirect Transfer of Facility Operating Licenses for Big Rock Point, Fitzpatrick, Indian Point, Palisades, Pilgrim, and Vermont Yankee Nuclear Power St ML0936208952010-01-22022 January 2010 Safety Evaluation,(Non-Proprietary) Order Extending the Effectiveness of the Approval of the Indirect Transfer of Facility Operating Licenses for Big Rock Point, Fitzpatrick, Indian Point,Palisades,Pilgrim, and Vermont Yankee Nuclear Power ML0933604432010-01-0404 January 2010 License Amendment 241 Revision of High Radiation Area Controls 2023-05-01
[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
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\.I:.P-R REGU,_ UNITED STATES
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~0 WASHINGTON, D.C. 20555-0001 In :
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- '" Site Vice President Entergy Nuclear Operations, Inc.
Vermont Yankee Nuclear Power Station P.O. Box 250 Governor Hunt Road Vernon, VT 05354
SUBJECT:
VERMONT YANKEE NUCLEAR POWER STATION -ISSUANCE OF AMENDMENT RE: RELOCATION OF REACTOR BUILDING CRANE TECHNICAL SPECIFICATION (TAC NO. MD9725)
Dear Sir or Madam:
The Commission has issued the enclosed Amendment No. 239 to Facility Operating License DPR-28 for the Vermont Yankee Nuclear Power Station, in response to your application dated September 22, 2008, as supplemented by letter dated October 31, 2008.
The amendment would relocate the contents of the Vermont Yankee (VY) Technical Specification (TS) relating to the Reactor Building crane to the VY Technical Requirements Manual.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
~ /?--~
James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-271
Enclosures:
- 1. Amendment No.239 to License No. DPR-28
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENTERGY NUCLEAR VERMONT YANKEE, LLC AND ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 239 License No. DPR-28
- 1. The Nuclear Regulatory Commission (the Commission) has found that A. The application for amendment filed by Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. (the licensee) dated September 22,2008, as supplemented by letter dated October 31,2008, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
-2
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-28 is hereby amended to read as follows:
(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 239 , are hereby incorporated in the license. Entergy Nuclear Operations, Inc. shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
~~~
Nancy L. Salgado, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: July 13, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 239 FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-271 Replace the following page of the Facility Operating License with the attached revised page.
The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove 3
Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 235 235 236 236
-3 E. Entergy Nuclear Operations, Inc., pursuant to the Act and 10 CFR Parts .30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility.
- 3. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20. Section 30.34 of 10 CFRPart 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
A. Maximum Power Level Entergy Nuclear Operations, Inc. is authorized to operate the facility at reactor core power levels not to exceed 1912 megawatts thermal in accordance with the Technical Specifications (Appendix A) appended hereto.
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 239are hereby incorporated in the license. Entergy Nuclear Operations, Inc. shall operate the facility in accordance with the Technical Specifications.
C. Reports Entergy Nuclear Operations, Inc. shall make reports in accordance with the requirements of the Technical Specifications.
D. This paragraph deleted by Amendment No. 226.
E. Environmental Conditions Pursuant to the Initial Decision of the presiding Atomic Safety and Licensing Board issued February 27, 1973, the following conditions for the protection of the environment are incorporated herein:
Amendment No.-200, aos. ~, ~, aso, ~, ~, 233, 234, 235, 239
VYNPS 3.12 LIMITING CONDITIONS FOR 4.12 SURVEILLANCE REQUIREMENTS OPERATION F. Fuel Movement F. Fuel Movement The reactor shall be shut Prior to any fuel handling or down for a minimum of 24 movement in the reactor core, hours prior to fuel movement the licensed operator shall within the reactor core.* verify that the reactor has been shut down for a minimum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
G. Deleted G. Deleted Amendment No. ~, ~, ~ 239 235
VYNPS 3.12 LIMITING CONDITIONS FOR 4.12 SURVEILLANCE REQUIREMENTS OPERATION H. Spent Fuel Pool Water H. Spent Fuel Pool Water Temperature Temperature Whenever irradiated fuel is Whenever irradiated fuel is stored in the spent fuel in the spent fuel pool, the pool, the pool water pool water temperature temperature shall be shall be recorded daily.
maintained below 150°F. If the pool water temperature reaches 150°F, all refueling operations tending to raise the pool water temperature shall cease and measures taken immediately to reduce the pool water temperature below 150°F.
Amendment No. ~, 239 236
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.239 TO FACILITY OPERATING LICENSE NO. DPR-28 ENTERGY NUCLEAR VERMONT YANKEE, LLC AND ENTERGY NUCLEAR OPERATIONS, INC.
VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271
1.0 INTRODUCTION
By application dated September 22, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082700458), as supplemented by letter dated October 31, 2008 (ML083110414), Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. (the licensee) submitted a request to amend the Vermont Yankee Nuclear Power Station (Vermont Yankee or VY) Technical Specifications (TSs). The amendment changes would relocate the contents of the VY TS relating to the Reactor Building crane to the VY Technical Requirements Manual (TRM). The supplemental letter dated October 31,2008, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination as published in the Federal Register on November 18, 2008 (73 FR 68454).
2.0 REGULATORY EVALUATION
2.1 Regulatory Discussion Content of Technical Specifications Section 182a of the Atomic Energy Act of 1954, as amended (the Act) requires applicants for nuclear power plant operating licenses to include the TSs as part of the license. The Commission's regulatory requirements related to the content of TSs are set forth in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, "Technical specifications." The regulation requires that the TSs include items in specific categories, including: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls.
The regulation does not specify the particular requirements to be included in the TSs.
The four criteria defined by 10 CFR 50.36(c)(2)(ii) for determining whether particular items are required to be included in the TS LCOs, are as follows:
-2 (A) Criterion 1. Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary; (B) Criterion 2. A process variable, design feature, or operating restriction that is an initial condition of a design-basis accident (DBA) or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; (C) Criterion 3. A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a DBA or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; (D) Criterion 4. A structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
The DBAs and transient analyses discussed in Criteria 2 and 3 include any design basis event described in the Safety Analysis Report (SAR), not just those events described in the accident analysis chapter. The "initial conditions" captured under Criterion 2 should not be limited to only "process variables" assumed in the safety analyses, but should also include certain active design features and operating restrictions needed to preclude unanalyzed accidents. In this context, "active design features" include only those design features under the control of operations personnel (i.e., licensed operators and personnel who perform control functions at the direction of licensed operators). Therefore, if the TS involves physical, designed-in features that prevent operations staff from immediately exceeding the assumptions in the bounding analysis in the course of operations, the TS would not meet Criterion 2 and could be relocated to the SAR or other similarly controlled document.
2.2 System Description The Reactor Building crane is a 11O-ton capacity overhead bridge crane that provides services for the reactor and refueling area. The crane handles new and spent fuel, in-core detectors, a large segmented concrete plug in the refueling level floor, the drywell head, the reactor vessel head, the segmented pool plugs, and the spent fuel shipping cask.
The Reactor Building crane was modified in 1976 by replacing the original trolley with one that has a dual load path on the main hoist when used for cask handling operations. The design of the new trolley satisfies the criteria for dual load path or "single-failure-proof' cranes, and, with issuance of Amendment 29 to the VY operating license on January 28, 1977, the NRC staff accepted the crane as "single-failure-proof."
In addition to the hardware improvements implemented to modify the crane to "single-failure proof," the licensee implemented a number of other improvements to enhance conformance with the guidelines of NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants." These improvements included:
- revising maintenance procedures to define safe load paths for major loads.
- revising procedures to include training and qualification requirements for crane operators, sling selection criteria, crane inspections prior to use, and supervisory oversight of heavy lift operations.
- procurement of special lifting devices and performance of periodic non-destructive examinations to monitor the condition of lifting devices.
-3 The NRC staff accepted these improvements through a safety evaluation transmitted by letter dated June 27, 1984.
3.0 TECHNICAL EVALUATION
In the letter dated September 22, 2008, the licensee stated that the proposed change is to relocate the sections of the TS relating to the Reactor Building crane to the VY TRM. The licensee proposed relocating the Reactor Building crane sections of the TS to the TRM because the Reactor Building crane is neither within the scope of equipment included in the "Standard Technical Specifications, General Electric Plants, BWR/4," NUREG-1433, nor equipment that satisfies the criteria of 10 CFR 50.36( d)(2)(ii) for establishment of an LCO.
Criterion 1. Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.
The licensee stated that the Reactor Building crane provides lifting services for the reactor and refueling area. The Reactor Building crane is not used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.
The NRC staff reviewed the licensee's explanation and agrees with the licensee that Criterion 1 does not apply to the Reactor Building crane.
Criterion 2. A process variable, design feature, or operating restriction that is an initial condition of a DBA or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
The licensee stated that the Reactor Building crane operability and SRs do not affect a process variable, design feature, or operating restriction that is an initial condition of DBAs or transients described in the VY's Updated Final Safety Analysis Report (UFSAR). The crane operability and SRs are related to handling and movement of a spent fuel cask and ensuing that the Reactor Building crane is inspected and tested prior to use. Additionally, the existing TS requires mechanical rail stops to be installed to prohibit movement of the cask over irradiated fuel. The TS is consistent with commitments made in response to NUREG-0612 to ensure that all cask handling operations are bounded by the DBAs and transients described in the UFSAR.
In a letter dated October 31,2008, the licensee further explained the basis for concluding the Reactor Building crane does not meet criterion 2 by stating the following:
Accidents that can result in the release of radioactive materials to the containment, when the drywell is open, are documented in the Vermont Yankee UFSAR. The UFSAR states that greatest potential for release occurs when the drywell head and reactor head have been removed. The UFSAR states that the only accident that could result in the release of significant quantities of fission products is the accidental dropping of a fuel bundle onto the top of the core.
The design basis Fuel Handling Accident (FHA) IS described in UFSAR Section 14.6.4. The FHA assumes an irradiated fuel assembly is dropped onto the reactor core from the maximum he:ght allowed by the fuel handling equipment.
The analysis assumes that the entire amount of potential energy is available for
- 4 application to the fuel assemblies involved in the accident. Also, none of the energy associated with the dropped fuel assembly is absorbed by the fuel material. The FHA is assumed to bound other credible fuel handling accidents.
The fuel handling equipment used to transport irradiated fuel from the fuel pool to the reactor core is the refueling platform and associated components (e.g., mast, grapple, controls). The refueling platform is independent of the Reactor Building crane. The Reactor Building crane is not used to move irradiated fuel from the fuel pool to the reactor core.
The single-failure-proof-crane, the procured special lifting devices, and the sling selection procedures provide reasonable assurance that the handling system used for heavy load movement near the spent fuel pool will have designed-in features to prevent a load drop. As outlined in NUREG-0612, the NRC staff accepts that provision of a single-failure-proof handling system, in conjunction with other actions implemented at VY, provides defense-in-depth against drops of loads heavier than one fuel assembly and its associated handling tool. Thus, actions and events necessary to result in a heavy load drop from the Reactor Building crane over spent fuel are not sufficiently credible that this event was included among design basis events.
The NRC staff reviewed the licensee's explanation of why Criterion 2 does not apply to the Reactor Building crane. The staff agrees with the licensee that Criterion 2 does not apply because VY uses the refueling platform for transporting irradiated fuel, which is independent of the Reactor Building crane.
Criterion 3. A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a DBA or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
The licensee stated that the Reactor Building crane is not a part of the primary success path and does not function or actuate to mitigate DBAs or transients described in the VY 8AR. The Reactor Building crane is used for lifting of objects within the Reactor Building. The Reactor Building crane is not used to mitigate the consequences of any DBA or transient.
The NRC staff reviewed the licensee's explanation of why Criterion 3 does not apply. The staff agrees with the licensee that the Reactor Building crane does not function or actuate to mitigate DBAs or transients.
Criterion 4. A structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
The licensee states that the Reactor Building crane is not modeled in the VY probabilistic risk assessment due to its low significance to public health and safety.
The NRC staff reviewed the VY probabilistic risk assessment (PRA). The staff agrees that the Reactor Building crane is not modeled in the VY PRA, and therefore agrees with the licensee that Criterion 4 does not apply.
The licensee further stated that the combination of hardware improvements and crane safety design features, commitments to establish safe load paths and the other commitments discussed above provide a level of assurance such that T8 level administrative controls are not necessary to assure safety. Following implementation of the proposed change, the VY TRM will
-5 contain all of the requirements and information related to the Reactor Building crane that had previously been contained in the VY TS. The TRM is maintained in accordance with VY administrative processes and changes to the TRM are evaluated per the requirements of 10 CFR 50.59. These controls are adequate to ensure the Reactor Building crane is operable and capable of performing its intended functions.
NRC staff has reviewed the proposed license amendment and found that the proposed changes do not change any existing requirements and do not adversely affect existing plant safety margins or the reliability of the equipment assumed to operate in the safety analysis. Therefore, 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.
Therefore, the NRC staff found that the proposed amendment to delete TS 3.12.G and SR 4.12.G and relocate the requirements to the VY TRM to be acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Vermont State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes SRs.
The NRC staff has determined that the amendment involves no significant increase in amounts, and no significant change in the types of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (73 FR 68454). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22( c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Ogbonna Hopkins Date: July 13, 2009
July 13, 2009 Site Vice President Entergy Nuclear Operations, Inc.
Vermont Yankee Nuclear Power Station P.O. Box 250 Governor Hunt Road Vernon, VT 05354
SUBJECT:
VERMONT YANKEE NUCLEAR POWER STATION -ISSUANCE OF AMENDMENT RE: RELOCATION OF REACTOR BUILDING CRANE TECHNICAL SPECIFICATION (TAC NO. MD9725)
Dear Sir or Madam:
The Commission has issued the enclosed Amendment No. 239 to Facility Operating License DPR-28 for the Vermont Yankee Nuclear Power Station, in response to your application dated September 22, 2008, as supplemented by letter dated October 31, 2008.
The amendment would relocate the contents of the Vermont Yankee (VY) Technical Specification (TS) relating to the Reactor Building crane to the VY Technical Requirements Manual.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, IRA!
James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-271
Enclosures:
- 1. Amendment No. 239 to License No. DPR-28
- 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
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