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| Issue date | Title | From | To | |
|---|---|---|---|---|
| NRC Generic Letter 1988-07 | 7 April 1988 | NRC Generic Letter 1988-007: Modified Enforcement Policy Relating to 10 CFR 50.49 Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants. | Miraglia F Office of Nuclear Reactor Regulation | |
| ML20154B191 | 9 May 1988 | Advises That Util Plans to Continue Operation Beyond Cycle 13 on Core Spray Safe Ends Acceptable,Providing Insp Results Satisfactory | Office of Nuclear Reactor Regulation Rooney V | VERMONT YANKEE NUCLEAR POWER CORP. Capstick R |
| ML20151K722 | 27 July 1988 | Responds to NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping,Per Generic Ltr 88-01.Evaluation of Plant for Compliance W/Nrc Position,Describing Measures Taken to Mitigate Igscc,Encl | VERMONT YANKEE NUCLEAR POWER CORP. Murphy W | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| IR 05000271/1989003 | 13 April 1989 | Insp Rept 50-271/89-03 on 890320-24.No Violations Noted. Major Areas Inspected:Inservice Insp Activities to Determine Compliance W/Applicable ASME Code & Regulatory Requirements & Actions on Generic Ltr 88-01 | Chaudhary S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) Mcbrearty R | |
| ML20247M898 | 24 May 1989 | Forwards Request for Addl Info Re 880727 Response to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. Response Should Be Sent to Viking Sys,Intl at Listed Address | Office of Nuclear Reactor Regulation Fairtile M | VERMONT YANKEE NUCLEAR POWER CORP. Capstick R |
| ML20247L754 | 25 July 1989 | Responds to NRC 890524 Request for Addl Info Re Generic Ltr 88-01, NRC Position on IGSCC in Austenitic Stainless Steel Piping | VERMONT YANKEE NUCLEAR POWER CORP. Capstick R | Office of Information Resources Management |
| NRC Generic Letter 1989-21 | 19 October 1989 | NRC Generic Letter 1989-021: Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements | Partlow J Office of Nuclear Reactor Regulation | |
| ML19332D380 | 22 November 1989 | Responds to NRC Generic Ltr 89-21 Re Request for Info Re Status of Implementation of USI Requirements.Encl Table Details Implementation Status for USIs for Which Final Technical Resolution Achieved | VERMONT YANKEE NUCLEAR POWER CORP. Tremblay L | Office of Information Resources Management |
| ML20012B616 | 8 March 1990 | Provides Suppl Info to Clarify Position Re Leakage Detection & Conformance W/Position C of Reg Guide 1.45.Util Concludes That Combination of Existing Tech Specs & Administrative Controls Fully Comply W/Intent of Staff Position on Leakage | VERMONT YANKEE NUCLEAR POWER CORP. Murphy W | Office of Information Resources Management |
| NRC Generic Letter 1990-04 | 25 April 1990 | NRC Generic Letter 1990-004: Request for Information on Status of Licensee Implementation of Generic Safety Issues Resolved with Imposition of Requirements or Corrective Actions | Partlow J Office of Nuclear Reactor Regulation | |
| NRC Generic Letter 1990-05 | 15 June 1990 | NRC Generic Letter 1990-005: Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping | Partlow J Office of Nuclear Reactor Regulation | |
| IR 05000271/1990017 | 23 November 1990 | Insp Rept 50-271/90-17 on 901105-09.No Violations Noted. Major Areas Inspected:Inservice Insp Activities to Ascertain Whether Licensee Activities Conducted in Compliance W/ Applicable ASME Code & Regulatory Requirements | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) Gray E Mcbrearty R | |
| BVY-92-107, Submits Info Re Util Position on Leakage Detection,Per GL 88-01 & Suppl 1.Plant Procedures Modified by Incorporating Addl Leakage Monitoring,Per GL 88-01.Relocating 2 Gpm Requirement Into TS Not cost-effective Nor Justified | 21 September 1992 | Submits Info Re Util Position on Leakage Detection,Per GL 88-01 & Suppl 1.Plant Procedures Modified by Incorporating Addl Leakage Monitoring,Per GL 88-01.Relocating 2 Gpm Requirement Into TS Not cost-effective Nor Justified | VERMONT YANKEE NUCLEAR POWER CORP. Murphy W | Office of Information Resources Management |
| BVY-92-123, Responds to Generic Ltr 88-01,position Concerning Leakage Detection of Formal Backfit Analysis Under 10CFR50.109 | 27 October 1992 | Responds to Generic Ltr 88-01,position Concerning Leakage Detection of Formal Backfit Analysis Under 10CFR50.109 | VERMONT YANKEE NUCLEAR POWER CORP. Murphy W | Office of Information Resources Management |
| ML20127L365 | 21 January 1993 | Responds to Util Position Concerning Leakage Rate Detection Re Generic Ltr 88-01, NRR Position on IGSCC in BWR Austenitic Stainless Steel Piping | Butler W Office of Nuclear Reactor Regulation | VERMONT YANKEE NUCLEAR POWER CORP. Murphy W |
| ML20128E768 | 4 February 1993 | Summary of 921216 Meeting W/Vynp in Rockville,Md Re Licensing Issues Related to Plant.List of Attendees Encl | Dan Dorman Office of Nuclear Reactor Regulation | Office of Nuclear Reactor Regulation |
| ML20056C722 | 14 July 1993 | Proposed Tech Specs Sections 3.6 & 4.6 for Compliance W/Gl 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping | VERMONT YANKEE NUCLEAR POWER CORP. | |
| BVY-93-068, Proposed Change 171 to License DPR-28,revising TS Sections 3.6 & 4.6 & Accompanying Bases Section to Comply W/Gl 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping | 14 July 1993 | Proposed Change 171 to License DPR-28,revising TS Sections 3.6 & 4.6 & Accompanying Bases Section to Comply W/Gl 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping | VERMONT YANKEE NUCLEAR POWER CORP. Reid D | Office of Information Resources Management |
| ML20059L835 | 9 November 1993 | Summary of 931025 Meeting W/Util in Bolton,Ma Re Status of Open Licensing Issues Involving Plant.Attendees Listed in Encl 1 | Dan Dorman Office of Nuclear Reactor Regulation | Office of Nuclear Reactor Regulation |
| ML20070K418 | 19 July 1994 | Reformatted TSs Current Through Amend 137 | VERMONT YANKEE NUCLEAR POWER CORP. | |
| ML20097C049 | 5 February 1996 | Proposed Tech Specs,Consisting of Proposed Change 180, Correcting Typos & Text Inconsistencies | VERMONT YANKEE NUCLEAR POWER CORP. | |
| ML20116J442 | 9 August 1996 | Proposed Tech Specs,Revising SLs for MCPR Based Upon Util Plant & Cycle Specific Analysis Performed by GE | VERMONT YANKEE NUCLEAR POWER CORP. | |
| ML20129A708 | 11 September 1996 | Proposed Tech Specs,Modifying Sections 2.2.B & 3.6.D.1 of Util & Accompanying Bases Section to Permit Operation W/ Increased SRV & SV Setpoint Tolerance & to Permit Operation Up to 100% of Rated Power W/Single Inoperable SRV | VERMONT YANKEE NUCLEAR POWER CORP. | |
| BVY-97-105, Provides NRC W/Degradation Mechanism Evaluation & Results of Element & Segment Risk Rankings.Util Intends to Submit Revised ISI Program Following NRC Review of Evaluations & Risk Ranking,As Stated in Ltr | 15 August 1997 | Provides NRC W/Degradation Mechanism Evaluation & Results of Element & Segment Risk Rankings.Util Intends to Submit Revised ISI Program Following NRC Review of Evaluations & Risk Ranking,As Stated in Ltr | VERMONT YANKEE NUCLEAR POWER CORP. Duffy J | Office of Information Resources Management |
| ML20211P499 | 9 October 1997 | Summary of 970917 Meeting W/Vynp in Rockville,Maryland Re ASME Code Case N560.List of Meeting Attendees,Meeting Agenda & Meeting Handouts Encl | NRC | NRC |
| BVY-97-137, Forwards Response to 971009 RAI Re Plans for Implementing ASME Code Case N560 at Vermont Yankee Nuclear Power Station | 23 October 1997 | Forwards Response to 971009 RAI Re Plans for Implementing ASME Code Case N560 at Vermont Yankee Nuclear Power Station | VERMONT YANKEE NUCLEAR POWER CORP. Reid D | Office of Information Resources Management |
| BVY-98-114, Provides Response to Request for Addl Info Re Implementation of ASME Code N560 at Plant | 31 July 1998 | Provides Response to Request for Addl Info Re Implementation of ASME Code N560 at Plant | VERMONT YANKEE NUCLEAR POWER CORP. Leach D | Office of Information Resources Management |
| ML20195C416 | 9 November 1998 | SER Accepting Request That NRC Approve ASME Code Case N-560, Alternative Exam Requirement for Class 1,Category B-J Piping Welds | NRC (Affiliation Not Assigned) | |
| ML20198D538 | 15 December 1998 | Proposed Tech Specs Page 142,correcting Wording to Reflect Previously Approved Wording,Last Revised in Amend 160 | VERMONT YANKEE NUCLEAR POWER CORP. | |
| ML20204G720 | 19 March 1999 | Forwards Response to NRC 981230 RAI Re Util Implementation of ASME Code Case N560 at Vermont Yankee Nuclear Power Station | VERMONT YANKEE NUCLEAR POWER CORP. Leach D | Office of Information Resources Management |
| ML20205S408 | 16 April 1999 | Proposed Tech Specs Modifying Inservice Insp Requirements of Section 4.6.E to Allow NRC-approved Alternatives to GL 88-01 | VERMONT YANKEE NUCLEAR POWER CORP. | |
| ML20205S403 | 16 April 1999 | Application for Amend to License DPR-28,modifying Inservice Insp Requirements of Section 4.6.E to Allow NRC-approved Alternatives to GL 88-01 | Wanczyk R VERMONT YANKEE NUCLEAR POWER CORP. | Office of Information Resources Management |
| ML20195F946 | 9 June 1999 | Supplement to 990416 Proposed Change 213 for License DPR-28, Allowing Use of Amse Code Case N-560,in Lieu of Certain Provisions of GL 88-01 | Wanczyk R VERMONT YANKEE NUCLEAR POWER CORP. | Office of Information Resources Management |
| ML20195F953 | 9 June 1999 | Proposed Tech Specs,Supplementing Proposed Change 213, Allowing Use of ASME Code Case N-560,per GL 88-01 | VERMONT YANKEE NUCLEAR POWER CORP. | |
| ML20212J054 | 17 June 1999 | Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First | NRC (Affiliation Not Assigned) Strosnider J | Terry C Niagara Mohawk |
| ML20210D248 | 20 July 1999 | Proposed Tech Specs Revising & Clarifying Operability & SRs of High Pressure Core Cooling Systems | VERMONT YANKEE NUCLEAR POWER CORP. | |
| ML010780094 | 27 March 2001 | Review of Request to Discontinue Intergranular Stress Corrosion Cracking Inspection of RWCU Piping Welds Outboard of the Second Containment Isolation Valves | Office of Nuclear Reactor Regulation Pulsifer R | Vermont Yankee Balduzzi M |
| ML092110065 | 31 July 2002 | Appendix a to Operating License Number DPR-28 | Office of Nuclear Reactor Regulation | |
| ML030850467 | 20 March 2003 | TS Proposed Change No.257, Implementation of Arts/Mella | Entergy Entergy Nuclear Vermont Yankee Balduzzi M | Office of Nuclear Reactor Regulation Document Control Desk |
| ML030990313 | 1 April 2003 | Fourth-Interval Inservice Inspection Program Plan, Fourth-Interval Inservice Inspection Pressure Test Program & Request for Approval of ISI Relief Requests | Entergy Entergy Nuclear Vermont Yankee Wanczyk R | Office of Nuclear Reactor Regulation Document Control Desk |
| ML030990328 | 1 April 2003 | Fourth-Interval Inservice Inspection Program Plan, Fourth-Interval Inservice Inspection Pressure Test Program & Request for Approval of ISI Relief Requests, Attachments 1 and 2, Appendix B | Entergy Entergy Nuclear Vermont Yankee Wanczyk R | Office of Nuclear Reactor Regulation Document Control Desk |
| ML032810447 | 1 October 2003 | Vermont Yankee - Technical Specification Proposed Change No. 263, Supplemental No. 1 Regarding Extended Power Uprate, Technical Review Guidance | Entergy Entergy Nuclear Vermont Yankee Thayer J | Office of Nuclear Reactor Regulation Document Control Desk |
| ML033100141 | 28 October 2003 | Vermont Yankee - Technical Specification Proposed Change No. 263 - Supplemental No. 3, Extended Power Uprate - Updated Information | Entergy Thayer J | Office of Nuclear Reactor Regulation Document Control Desk |
| BVY 04-008, Vermont Yankee July 2008 Evidentiary Hearing - Staff Exhibit 17, Letter Bvy 04-008, Dated January 31, 2004 | 31 January 2004 | Vermont Yankee July 2008 Evidentiary Hearing - Staff Exhibit 17, Letter Bvy 04-008, Dated January 31, 2004 | Entergy Thayer J | NRC/SECY Document Control Desk |
| ML040370066 | 5 March 2004 | Safety Evaluation of Relief Requests for the Fourth 10-Year Interval of the Inservice Inspection Program. (TAC Nos. MB8349 Through MB8358) | Darrell Roberts NRC/NRR/DLPM/LPD1 | Entergy Kansler M |
| ML041120252 | 14 April 2004 | Technical Specification Pages for Vermont Yankee Nuclear Power Station, License Amendment, Issuance of Amendment Implementation of Arts/Mellla | NRC/NRR/DLPM | |
| BVY 04-118, Technical Specification Proposed Change No. 270 Administrative Changes | 6 December 2004 | Technical Specification Proposed Change No. 270 Administrative Changes | Entergy Thayer J | Office of Nuclear Reactor Regulation Document Control Desk |
| ML052280059 | 15 August 2005 | Tech Spec Pages for Amendment 226 Administrative Changes | NRC/NRR/DLPM | |
| ML051920138 | 15 August 2005 | Issuance of License Amendment 226 Administrative Changes | Richard Ennis NRC/NRR/DLPM/LPD1 | Entergy Kansler M |
| ML082340632 | 30 September 2005 | Vermont Yankee July 2008 Evidentiary Hearing-Intervenor Exhibit NEC-UW_05, NRC, Generic Aging Lessons Learned (GALL) Report, Tabulation of Results, NUREG-1801, Vol 2, Rev. 1, (September 2005) (Excerpt) | Office of Nuclear Reactor Regulation | NRC/SECY/RAS |