Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: BVY 06-009, 2006/01/25-Vermont Yankee Nuclear Power Station Applicant'S Environmental Report Operating License Renewal Stage, Appendix E, BVY 06-076, 2006/08/10-Vermont Yankee - License Renewal Application, Amendment 8, BVY 06-079, 2006/08/22-Vermont Yankee License Renewal Application, Amendment 11, BVY 06-083, 2006/09/05-Vermont Yankee License Renewal Application, Amendment 12, BVY 06-095, E-mail: (PA-LR) Copy of SAMA Response, BVY 06-096, 2006/10/20-Vermont Yankee - License Renewal Application, Amendment No. 17, BVY 06-097, 2006/10/31-Vermont Yankee License Renewal Application, Amendment 19, BVY 06-098, E-mail: (PA-LR) Copy of Vhs RAI Response, BVY 07-003, Email: (PA-LR) Vermont Yankee Nuclear Power Station License Renewal Commitment List, Rev. 5, BVY 07-009, License Renewal Application, Amendment 24, BVY 07-018, License Renewal Application, Amendment 26, BVY 07-034, License Renewal Application Annual Update, BVY 07-035, (PA-LR) Bvy 07-035 VY Lr SER Comments, BVY 07-047, License Renewal Application, Amendment 27, Submitted on January 25, 2006, BVY 07-058, License Renewal Application, Amendment 29, BVY 07-062, License Renewal Application, Amendment 30, BVY 07-066, License Renewal Application, Amendment 31, BVY 08-016, (PA-LR) Emailing Bvy 08-016 Final SER Review Comments, BVY 10-069, License Renewal Application Annual Update Information, ML060950195, ML060950215, ML060950218, ML060950220, ML060950224, ML060950235, ML060950250, ML060950258, ML060950262, ML060950269, ML060950271, ML060950277, ML060950279, ML060950284, ML060950290, ML060950301, ML060950311, ML060950323, ML060950328, ML060950331, ML060950347, ML060950351, ML060950356, ML060950364, ML060950370, ML060950372, ML060950375, ML060950540, ML060950549, ML060950559, ML060950567... further results
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MONTHYEARML0629203681987-12-31031 December 1987 VY Annual Ecological Studies of the CT River Report 16-final.pdf Project stage: Other ML0629203651989-12-31031 December 1989 VY Annual Ecological Reports from the 1980's (1989) Project stage: Other ML0609503511998-02-28028 February 1998 GALL AMP: XI.M12, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) (Audit Worksheet GALL Report AMP) Project stage: Other BVY 06-009, 2006/01/25-Vermont Yankee Nuclear Power Station Applicant'S Environmental Report Operating License Renewal Stage, Appendix E2006-01-25025 January 2006 2006/01/25-Vermont Yankee Nuclear Power Station Applicant'S Environmental Report Operating License Renewal Stage, Appendix E Project stage: Other ML0609505792006-03-22022 March 2006 GALL AMP: XI.M24, Compressed Air Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506202006-03-22022 March 2006 GALL AMP: XI.M31, Reactor Vessel Surveillance (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505962006-03-22022 March 2006 GALL AMP: XI.M27, Fire Water System (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502792006-03-22022 March 2006 GALL AMP: XI.M3, Reactor Head Closure Studs (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609506292006-03-22022 March 2006 GALL AMP: XI.M33, Selective Leaching of Materials (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506372006-03-22022 March 2006 GALL AMP: XI.M36, External Surfaces Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502842006-03-22022 March 2006 GALL AMP: XI.M4, BWR Vessel Id Attachment Welds (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502202006-03-22022 March 2006 GALL AMP: X.S1, Concrete Containment Tendon Prestress (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001472006-03-22022 March 2006 GALL AMP: XI.S8, Protective Coating Monitoring and Maintenance Program (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001342006-03-22022 March 2006 GALL AMP: XI.S5, Masonry Wall Progam (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502182006-03-22022 March 2006 GALL AMP: X.M1, Metal Fatigue of Reactor Coolant Pressure Boundary (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609505592006-03-22022 March 2006 GALL AMP: XI.M20, Open-Cycle Cooling Water System (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503472006-03-22022 March 2006 GALL AMP: XI.M11A, Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of Pressurized Water Reactors Project stage: Other ML0609505402006-03-22022 March 2006 GALL AMP: XI.M18, Bolting Integrity (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505672006-03-22022 March 2006 GALL AMP: XI.M21, Closed-Cycle Cooling Water System (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001012006-03-22022 March 2006 GALL AMP: XI.S2, ASME Section XI, Subsection Iwl (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505732006-03-22022 March 2006 GALL AMP: XI.M23, Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506102006-03-22022 March 2006 GALL AMP: XI.M29, Aboveground Steel Tanks (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502902006-03-22022 March 2006 GALL AMP: XI.M5, BWR Feedwater Nozzle (Audit Worksheet, GALL Report AMP) Project stage: Other ML0610001382006-03-22022 March 2006 GALL AMP: XI.S6, Structures Monitoring Program (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001262006-03-22022 March 2006 GALL AMP: XI.S4, 10 CFR 50, Appendix J (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502242006-03-22022 March 2006 GALL AMP: XI.E1, Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506062006-03-22022 March 2006 GALL AMP: XI.M28, Buried Piping and Tanks Surveillance (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502152006-03-22022 March 2006 GALL AMP: X.E1. Environmental Qualification (EQ) of Electric Components (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503752006-03-22022 March 2006 GALL AMP: XI.M17, Flow-Accelerated Corrosion (Audit Worksheet GALL Report AMP) Project stage: Other ML0610000782006-03-22022 March 2006 GALL AMP: XI.M38, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505702006-03-22022 March 2006 GALL AMP: XI.M22, Boraflex Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503722006-03-22022 March 2006 GALL AMP: XI.M16, PWR Vessel Internals (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503642006-03-22022 March 2006 GALL AMP: XI.M14, Loose Part Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502772006-03-22022 March 2006 GALL AMP: XI.M2, Water Chemistry (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609506242006-03-22022 March 2006 GALL AMP: XI.M32, One-Time Inspection (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503112006-03-22022 March 2006 GALL AMP: XI.M7, BWR Stress Corrosion Cracking (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502352006-03-22022 March 2006 GALL AMP: XI.E2, Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506342006-03-22022 March 2006 GALL AMP: XI.M35, One-Time Inspection of ASME Code Class 1 Small Bore Piping (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502502006-03-22022 March 2006 GALL AMP: XI.E3, Inaccessible Medium-Voltage Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001432006-03-22022 March 2006 GALL AMP: XI.S7, Rg 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505492006-03-22022 March 2006 GALL AMP: XI.M19, Steam Generator Tube Integrity (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505872006-03-22022 March 2006 GALL AMP: XI.M26, Fire Protection (Audit Worksheet GALL Report AMP) Project stage: Other ML0609501952006-03-22022 March 2006 GALL AMP: Plant-Specific (Audit Worksheet - GALL Report AMP) Project stage: Other ML0609503702006-03-22022 March 2006 GALL AMP: XI.M15, Neutron Noise Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503012006-03-22022 March 2006 GALL AMP: XI.M6, BWR Control Rod Drive Return Line Nozzle (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503282006-03-22022 March 2006 GALL AMP: XI.M9, BWR Vessels Internals (Audit Worksheet GALL Report AMP) Project stage: Other ML0610000962006-03-22022 March 2006 GALL AMP: XI.S1, ASME Section XI, Subsection IWE (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502692006-03-22022 March 2006 GALL AMP: XI.E6, Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609502622006-03-22022 March 2006 GALL AMP: XI.E5, Fuse Holder (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503312006-03-22022 March 2006 GALL AMP: XI.M10, Boric Acid Corrosion (Audit Worksheet GALL Report AMP) Project stage: Other 1998-02-28
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Category:Audit Report
MONTHYEARML14002A4422014-02-19019 February 2014 Audit Report Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13351A0732014-01-10010 January 2014 Audit of Entergy'S Management of Regulatory Commitments ML1024202062010-09-13013 September 2010 Audit of Entergy'S Management of Regulatory Commitments ML1020704122010-09-0303 September 2010 Audit Report Regarding the Vermont Yankee Nuclear Power Station License Renewal Application ML0719100602007-07-19019 July 2007 Audit of the Licensee'S Management of Regulatory Commitments ML0708600052007-03-29029 March 2007 Audit and Review Report for Plant Aging Management Reviews and Programs, Vermont Yankee Nuclear Power Station ML0625803302006-09-22022 September 2006 2006/09/22-Audit Trip Report Regarding the Entergy Nuclear Vermont Yankee, LLC, License Renewal Application for the Vermont Yankee Nuclear Power Station ML0625801872006-09-14014 September 2006 2006/09/14-Audit Trip Report Regarding Entergy Nuclear Vermont Yankee, LLC, License Renewal Application for Vermont Yankee Power Station, Dated January 29, 2006 ML0610203662006-04-11011 April 2006 2006/04/11-License Renewal Audit and Review Plan for Plant Aging Management Programs and Reviews for the Vermont Yankee Nuclear Power Station Docket No. 50-271 ML0624802752006-04-11011 April 2006 Email: (PA) Pdf Version of Audit Plan ML0620704102006-04-0606 April 2006 Email: (PA) VYNPS Audit Plan and Initial Set of Questions ML0504504232005-02-11011 February 2005 Technical Audit of Vermont Yankee Steam Dryer Analysis in Support of Extended Power Uprate. ML0701701432005-01-21021 January 2005 VYNPS - SEIS Web Reference - Town of Brattleboro, VT, Independent Auditor'S Report ML0500600862004-11-12012 November 2004 Content of VY Steam Dryer Audit Report, Non-Proprietary 2014-02-19
[Table view] Category:Memoranda
MONTHYEARML19317D0762019-11-18018 November 2019 Summary of Meeting Near Vermont Yankee Power Station Regarding Establishment and Opration of Community Advisory Boards ML17271A0532017-09-29029 September 2017 2017 Summary of Annual Decommissioning Funding Status Reports for Reactors in Decommissioning ML17143A1552017-06-0606 June 2017 Memorandum to C. Bladey Notice of Availability of Exemption for Entergy Energy Operations, Inc., Vermont Yankee Nuclear Power Station Independent Spent Fuel Storage Installation ML17045A5282017-05-25025 May 2017 Memo to C. Bladey Notice of Availability of Environmental Assessment and Finding of No Significant Impact for Entergy Nuclear Operations, Inc., Vermont Yankee Nuclear Power Station, Independent Spent Fuel Storage Installation Exemption Requ ML17055A5042017-03-0101 March 2017 Revision of the NRC Vermont Yankee Decommissioning Webpage ML16176A3392016-10-28028 October 2016 Decommissioning Lessons Learned Report and Transmittal Memorandum ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML14209A7052014-08-0606 August 2014 Letter to FEMA Requesting Review and Concurrence of Certain Proposed Entergy Nuclear Operations, Inc. Emergency Response Organization Changes to the Vermont Yankee Site Emergency Plan ML14209A9352014-07-24024 July 2014 1st Quarter 2014 Performance Review ML13150A2182013-05-31031 May 2013 6/12/13 Notice of Conference Call with Entergy Nuclear Operations, Inc. to Discuss Draft Request for Additional Information for Vermont Yankee NRC Order Number EA-12-049 Related to Mitigation Strategies ML13108A3282013-04-22022 April 2013 Notice of Forthcoming Meeting with Petitioners Requesting Action Against Entergy Nuclear Operations, Inc., Regarding Operations at FitzPatrick, Pilgrim, and Vermont Yankee Nuclear Power Stations (TAC Nos. MF1092, MF1093, and MF1094) ML12298A0882012-10-24024 October 2012 Forthcoming Meeting to Discuss Proposed License Amendment Request to Revise 10 CFR 50.63 Alternate AC Power Source to SBO EDG ML13219A0472012-03-15015 March 2012 Memo from M. Murphy to G. Wilson, Subj: Safety Evaluation Regarding Vermont Yankee Nuclear Power Station Core Plate Hold Down Bolt Inspection Plan and Analysis ML13127A3692012-03-15015 March 2012 Memo from M. Murphy to G. Wilson, Subj: Safety Evaluation Regarding Vermont Yankee Nuclear Power Station Core Plate Hold Down Bolt Inspection Plan and Analysis ML11321A2282011-11-17017 November 2011 Third Quarter 2011 Performance Review Memorandum ML11250A1712011-09-14014 September 2011 Notice of Forthcoming Meeting with Petitioner Requesting Action Under 10 CFR 2.206 Regarding Immediate Suspension of the Operating Licenses of General Electric (GE) Mark 1 Boiling Water Reactors (Bwrs) ML1115704052011-06-0606 June 2011 Notice of Meeting with Entergy Operations, Inc., to Discuss Implementation of Quality Oversight and Verification Programs at Entergy Sites Including Actions Being Taken to Enhance Effectiveness ML11126A0962011-05-12012 May 2011 Notice of Meeting with Petitioner Requesting Action Under 10CFR2.206 Regarding Immediate Suspension of Operating Licenses of General Electric Mark 1 Boiling Water Reactors ML1107504052011-03-21021 March 2011 Notice of Meeting with Entergy Operations, Inc., to Discuss Fleetwide Submittal for Proposed Technical Specification and Quality Assurance Program Manual Changes Related to Unit Staff Qualification Requirements ML1100502522011-02-0909 February 2011 Memo to Chairman Jaczko Fm R. W. Borchardt, EDO Initiatives for Improved Communication of Groundwater Incidents ML1030101362010-10-28028 October 2010 Memorandum and Order (Ruling on Motion to Reopen Proffering New Contention) (LBP-10-19) ML1009904582010-04-0808 April 2010 Deviation from the Reactor Oversight Process to Provide Increase NRC Oversight to Specific Issues at Vermont Yankee Nuclear Power Station ML1009603212010-04-0505 April 2010 Request for Deviation from the Reactor Oversight Process Action Matrix to Provide Increased NRC Oversight of Specific Issues at Vermont Yankee ML1006401882010-03-0505 March 2010 Charter for the Groundwater Contamination Task Force ML0927301372009-10-0909 October 2009 Safety Evaluation by the Office of Nuclear Reactor Regulation Corporate Restructuring Conversion of Companies and Stock Split-Off by Entergy Nuclear Operations, Inc and Subsidiaries ML0915200092009-06-0808 June 2009 Forwarding of Supplement 1 to NUREG 1907 to the ACRS ML0913308232009-05-13013 May 2009 Summary of Annual Assessment Mtg - Vermont Yankee - 4/16/09 ML0904005422009-02-17017 February 2009 Audit Plan for Review of Confirmatory Analyses for the Core Spray and Reactor Recirculation Outlet Nozzles at the Vermont Yankee Nuclear Power Station ML0820601722008-08-0808 August 2008 Docketing of Additional Information Pertaining to the License Renewal Application of the Vermont Yankee Nuclear Power Station ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0805606272008-02-27027 February 2008 Advisory Committee on Reactor Safeguards Review of the Vermont Yankee Nuclear Power Station License Renewal Application - Safety Evaluation Report ML0802205082008-01-31031 January 2008 01/08/2008 Summary of Meeting Between the NRC Staff and Entergy Nuclear Operations, Inc. to Discuss the Response to a Request for Additional Information Pertaining to the Vermont Yankee License Renewal ML0801505932008-01-17017 January 2008 December 2007 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations (10 CFR) Section 2.206 ML0733001522007-11-26026 November 2007 Summary of Telephone Conference Call Held on October 16, 2007, Between U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning Audit Questions Pertaining to the Vermont Yankee Nuclear Power Station License Renewa ML0721804332007-08-0808 August 2007 Summary of Telephone Conference Call Held on July 18, 2007, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning Requests for Additional Information Pertaining to the Vermont Yankee Nuclear Power S ML0721805222007-08-0808 August 2007 Summary of Telephone Conference Call Held on June 29, 2007, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning Request for Additional Information Pertaining to the Vermont Yankee Nuclear Power St ML0718301872007-07-10010 July 2007 06/01/2007 Summary of Telephone Conference Call Between the NRC and Entergy Nuclear Operations, Inc., Concerning Items Pertaining to the Vermont Yankee License Renewal Safety Evaluation Report ML0716303702007-07-10010 July 2007 Trip Report Summarizing May 29, 2007 Visit to Vermont Yankee Nuclear Power Plant Regarding the License Renewal Environmental Review ML0713103192007-05-0808 May 2007 FRN - Plant License Renewal, June 5, 2007 ML0706101802007-05-0101 May 2007 Trip Report for a Trip Taken to Vermont, Massachusetts and New Hampshire ML0714104342007-04-25025 April 2007 Handouts to Applicants (Folder 3) ML0707406912007-04-0303 April 2007 ACRS Review of the Vermont Yankee Nuclear Power Station, License Renewal Application - Safety Evaluation Report ML0705305612007-02-20020 February 2007 Y020070028 - E-mail Hoch, NRR, to Becker, State of Vermont, Seismic and Flood Questions from Anr ML0704000852007-02-13013 February 2007 G20070068/LTR-07-0060/SECY-2007-0019 - Draft Supplemental Environmental Impact Statement for License Renewal of Vermont Yankee - Letters to Senator Leahy, Senator Sanders, Representative Welch from Luis Reyes ML0703605602006-11-0808 November 2006 Y020070028 - Informal Vermont Yankee Seismic and Hydrology Questions ML0627900712006-10-12012 October 2006 2006/10/12-Summary of a Telephone Conference Call Held on September 14, 2006, Between the U.S. NRC and Entergy Nuclear Operations, Inc, Concerning Information Pertaining to the Vermont Yankee Nuclear Power Station License Renewal Applicatio ML0627202182006-09-29029 September 2006 2006/09/29-Summary of a Telephone Conference Call Held on August 10, 2006, Between the U.S. NRC and Entergy Nuclear Operations, Inc., Concerning Information Pertaining to the Vermont Yankee Nuclear Power Station License Renewal Application ML0625801872006-09-14014 September 2006 2006/09/14-Audit Trip Report Regarding Entergy Nuclear Vermont Yankee, LLC, License Renewal Application for Vermont Yankee Power Station, Dated January 29, 2006 ML0617303972006-07-11011 July 2006 2006/07/11-Summary of Environmental Site Audit Related to the Review of the License Renewal Application for Vermont Yankee Nuclear Power Station 2019-11-18
[Table view] Category:Trip Report
MONTHYEARML0716303702007-07-10010 July 2007 Trip Report Summarizing May 29, 2007 Visit to Vermont Yankee Nuclear Power Plant Regarding the License Renewal Environmental Review ML0706101802007-05-0101 May 2007 Trip Report for a Trip Taken to Vermont, Massachusetts and New Hampshire ML0625803302006-09-22022 September 2006 2006/09/22-Audit Trip Report Regarding the Entergy Nuclear Vermont Yankee, LLC, License Renewal Application for the Vermont Yankee Nuclear Power Station ML0625801872006-09-14014 September 2006 2006/09/14-Audit Trip Report Regarding Entergy Nuclear Vermont Yankee, LLC, License Renewal Application for Vermont Yankee Power Station, Dated January 29, 2006 2007-07-10
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Text
September 14, 2006MEMORANDUM TO:P.T. Kuo, Deputy DirectorDivision of License Renewal Office of Nuclear Reactor RegulationFROM:Hossein Hamzehee, Chief /RA/ Bill Rogers for Quality & Vendor Branch BDivision of Engineering Office of Nuclear Reactor Regulation
SUBJECT:
AUDIT TRIP REPORT REGARDING THE ENTERGY NUCLEARVERMONT YANKEE, LLC, LICENSE RENEWAL APPLICATION FOR THE VERMONT YANKEE NUCLEAR POWER STATION, DATEDJANUARY 29, 2006Plant Name:Vermont Yankee Nuclear Power StationUtility Name:Entergy Nuclear Vermont Yankee, LLC Docket No.:50-271 (DPR-28)
TAC No.:MC9668 Review Branch:Quality & Vendor Branch BDuring the week of April 24 - 28, 2006, the Quality and Vendor Branch B(EQVB)performed an audit of the Entergy Nuclear Vermont Yankee, LLC (the applicant) license renewal scoping and screening methodology developed to support the Vermont Yankee Nuclear Power Station license renewal application (LRA), dated January 29, 2006. The focusof the staff's audit was on the applicant's administrative controls governing implementation ofthe LRA scoping and screening methodology, and review of the technical basis for selected scoping and screening results for various plant systems, structures, and components. Theaudit team also reviewed quality attributes for aging management programs and training for personnel that developed the LRA. A trip report containing a summary of the audit results is attached.
Enclosure:
As stated CONTACT:Greg S. Galletti, NRR/DE/EQVB(301) 415-1831 September 14, 2006MEMORANDUM TO:P.T. Kuo, Deputy DirectorDivision of License Renewal Office of Nuclear Reactor RegulationFROM:Hossein Hamzehee, Chief /RA/ Bill Rogers for Quality & Vendor Branch B Division of Engineering Office of Nuclear Reactor Regulation
SUBJECT:
AUDIT TRIP REPORT REGARDING THE ENTERGY NUCLEARVERMONT YANKEE, LLC, LICENSE RENEWAL APPLICATION FOR THE VERMONT YANKEE NUCLEAR POWER STATION, DATEDJANUARY 29, 2006Plant Name:Vermont Yankee Nuclear Power StationUtility Name:Entergy Nuclear Vermont Yankee, LLC Docket No.:50-271 (DPR-28)
TAC No.:MC9668 Review Branch:Quality & Vendor Branch BDuring the week of April 24 - 28, 2006, the Quality and Vendor Branch B(EQVB)performed an audit of the Entergy Nuclear Vermont Yankee, LLC (the applicant) license renewal scoping and screening methodology developed to support the Vermont Yankee Nuclear Power Station license renewal application (LRA), dated January 29, 2006. The focusof the staff's audit was on the applicant's administrative controls governing implementation ofthe LRA scoping and screening methodology, and review of the technical basis for selected scoping and screening results for various plant systems, structures, and components. Theaudit team also reviewed quality attributes for aging management programs and training for personnel that developed the LRA. A trip report containing a summary of the audit results is attached.
Enclosure:
As stated CONTACT:Greg S. Galletti, NRR/DE/EQVB301-415-1831DISTRIBUTION:EQVB R/F RidsNrrOd JRowley, PM, JZimmerman, LLund, GGalletti ADAMS ACCESSION NO.: ML062580187 OFFICEEQV/DEBC/EQV/DENAMEGGallettiHHamzeheeDATE 09/14/06 09/14/06 OFFICIAL RECORD COPY
EnclosureAUDIT TRIP REPORT REGARDING THE ENTERGY NUCLEAR VERMONT YANKEE, LLC,LICENSE RENEWAL APPLICATION FOR THE VERMONT YANKEE NUCLEAR POWERSTATION, DATED JANUARY 29, 2006I. IntroductionDuring the week of April 24 - 28, 2006, Greg Galletti, B ill Rogers, and Steve Tingen of theQuality and Vendor Branches A & B, audited the Entergy Nuclear Vermont Yankee (the applicant) license renewal scoping and screening methodology developed to support the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application (LRA). The audit was performed at the applicant's facility outside of Brattleboro, Vermont. The focus of thestaff's audit was on the applicant's administrative controls governing implementation of the LRAscoping and screening methodology and review of the technical basis for selected scoping and screening results for various plant systems, structures, and components. The audit team alsoreviewed quality attributes for aging management programs, training for personnel that developed the LRA, and quality practices used by the applicant to develop the LRA. II. Backgr oundTitle 10 of the Code of Federal Regulations, Part 54 (10 CFR Part 54), "Requirements forRenewal of Operating Licenses for Nuclear Power Plants," Section 54.21, "Contents ofApplication - Technical Information," requires that each application for license renewal containan integrated plant assessment (IPA). Furthermore, the IPA must list and identify those structures and components (SCs) that are subject to an aging management review (AMR) from the systems, structures, and components (SSCs) that are within the scope of license renewal. 10 CFR 54.4(a) identifies the plant SSCs within the scope of license renewal. SCs within the scope of license renewal are screened to determine if they are long-lived, passive equipment that is subject to an aging management review in accordance with 10 CFR 54.21(a)(1). III. Scoping MethodologyThe scoping evaluations for the VYNPS LRA were performed by the applicant's license renewalproject personnel and contractor personnel. The audit team conducted detailed discussions with the applicant's license renewal project management personnel and reviewed documentation pertinent to the scoping process. The audit team assessed if the scoping methodology outlined in the LRA and implementation procedures was appropriately implemented and if the scoping results were consistent with current licensing basis requirements. The audit team also reviewed a sample of system scoping results for thefollowing systems: Core Spray System and Intake Structure (structural review). In general, the team determined that the applicant's overall approach to license renewal SSCscoping appeared to be adequate. However, the audit team identified several issues where additional information will be required to complete the LRA review. These issues aredocumented in a request for additional information and are briefly described below.*During the scoping and screening methodology audit, the NRC audit team questionedhow non-accident design basis events, particularly design basis events that may not be described in the Updated Final Safety Analysis Report (UFSAR), were consideredduring scoping. The NRC audit team noted that limiting the review of design basesevents to those described in the UFSAR accident analysis could result in omission of safety-related functions described in the current licensing basis. The audit team, therefore, requested the applicant to provide a list of the design basis events evaluatedas part of the license renewal scoping process, and describe the methodology used to ensure that all design bases events (including conditions of normal operation, anticipated operational occurrences, design basis accidents, external events, and natural phenomena) were addressed during license renewal scoping. *Based on a review of the LRA, the applicant's scoping and screening implementationprocedures, and discussions with the applicant, the audit team determined that additional information is required with respect to certain aspects of the applicant's evaluation of the 10 CFR 54.4(a)(2) criteria. The audit team requested that theapplicant provide supplemental information regarding how the structural boundary, which includes the portion of the non-safety piping system outside the safety-relatedpressure boundary and relied upon to provide structural support for the pressure boundary, was developed. Additionally, the team requested the applicant to defineequivalent anchors and indicate whether equivalent anchors were used to determine any plant system structural boundary.*Based on the review of the applicant's scoping evaluation related to the 10 CFR54.4(a)(3) Station Blackout (SBO) criterion as described in License renewal Project Document (LRPD)-01, "System and Structure Scoping Results," Revision 0, the NRC audit team was unable to determine the extent to which the mechanical and electrical portions of the Vernon Hydroelectric Station were evaluated as part of the scoping evaluation. As a result the team requested the applicant to describe the scoping andscreening methodology applied to the mechanical and electrical systems associatedwith the Vernon Hydroelectric Station, and identify those mechanical and electricalSSCs that are in the scope of license renewal and subject to an AMR.
IV.Screening MethodologyThe audit team reviewed the methodology used by the applicant to determine ifmechanical, structural, and electrical components within the scope of license renewal would be subject to further aging management review. The applicant provided the audit team with a detailed discussion of the processes used for each discipline and provided administrative documentation that described the screening methodology. The auditteam also reviewed the screening results reports for the Core Spray system and IntakeStructure. The team noted that the applicant's screening process was performed inaccordance with its written requirements and was consistent with the guidance provided in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications forNuclear Power Plants," Revision 1, (LR-SRP), and the Nuclear Energy Institute (NEI) 95-10, "Industry Guidelines for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule," Revision 6, (NEI 95-10). The audit team determined that the screening methodology was consistent with the requirements of the Rule for theidentification of SSCs that meet the screening criteria of 10 CFR 54.21(a)(1).V.Aging Management Program Quality Assurance AttributesThe NRC audit team reviewed the applicant's Aging Management Programs (AMPs) describedin Appendix A, "Updated Safety Analysis Report Supplement," and Appendix B, "Aging Management Programs and Activities," of the Vermont Yankee Nuclear Power Station LRA In addition, the NRC audit team reviewed each individual AMP basis document to ensureconsistency in the use of the quality assurance attributes for each program. The purpose of this review was to assure that the aging management activities were consistent with the staff's guidance described in NUREG-1800, Section A.2, "Quality Assurance for Aging ManagementPrograms (Branch Technical Position IQMB-1)."Based on the NRC audit team's evaluation, the descriptions and applicability of the plant-specific AMPs and their associated quality attributes provided in Appendix A, Section A.2.1, andAppendix B, Section B.0.3, of the LRA are generally consistent with the staff's positionregarding quality assurance for aging management. However, the applicant has not sufficiently described the use of the quality assurance program and its associated attributes (corrective action, confirmation process, and administrative controls). Specifically, the applicant did not identify those AMPs which do not credit the VYNPS 10 CFR Part 50, Appendix B, QualityAssurance Program, for the corrective action, confirmation process, and administrative control attributes, or provide a description of the process used in lieu of the VYNPS Quality Assurance Program. Additionally, the NRC audit team noted that the AMP basis documents did not consistentlydescribe the application of the VYNPS 10 CFR Part 50, Appendix B, Quality AssuranceProgram, or an alternative for the corrective action, confirmation process, and administrative control attributes in each AMP. The NRC team, therefore, requested that the applicant providethe following information to address these issues:*A supplement to the description in the Appendix A, Section A.2.1, of the LRA to clearlyindicate the application of the VYNPS 10 CFR Part 50, Appendix B, Quality Assurance Program, or an alternative for the corrective action, conformation process, and administrative control attributes in each program.*If any alternative approaches are identified in Item a above in lieu of the VYNPS 10 CFRPart 50, Appendix B, Quality Assurance Program, their descriptions provided should be of sufficient detail for the staff to determine if the quality attributes for the AMPs are consistent with the review acceptance criteria contained in NUREG-1800, SectionA.2,"Quality Assurance for Aging Management Programs (Branch Technical Position IQMB-1)."*A consistent description for each AMP bases document which describes the applicationof the VYNPS 10 CFR Part 50, Appendix B, Quality Assurance Program, or an alternative for the corrective action, confirmation process, and administrative control attributes in each AMP. VI. Quality Assurance Controls Applied to LRA DevelopmentThe NRC audit team reviewed the quality controls used by the applicant to ensure that scopingand screening methodologies utilized in the LRA were adequately implemented. Although theapplicant did not develop the LRA under a 10 CFR 50, Appendix B, QA program, the applicantutilized the following quality assurance (QA) processes during the LRA development:*Implementation of the scoping and screening methodology was governed by writtenprocedures.*The applicant reviewed previous LRA NRC requests for additional information to ensurethat applicable issues were addressed in the LRA.*The LRA was reviewed by the Off-Site and On-Site Safety Review Committees prior tosubmittal to the NRC.*The applicant performed an industry peer review of the LRA.
- The applicant's QA organization performed an independent review of the LRA. Thepurpose of this review was to ensure that the technical information used to develop the LRA was updated and approved in accordance with the station's QA program, and that the issues raised by industry peer and Off-Site and On-Site Safety Review Committee were resolved and associated corrective actions implemented. The audit team concluded that these quality assurance activities, which exceeded currentregulatory requirements, provided additional assurance that LRA development activities were performed consistently with the LRA descriptions.VII.Training for License Renewal Project Personnel The audit team reviewed the applicant's training process to ensure the guidelines andmethodology for the scoping and screening activities would be performed in a consistent and appropriate manner. The NRC audit team reviewed the applicant's training process to ensurethe guidelines and methodology for the scoping and screening activities were performed in a consistent and appropriate manner. The License Renewal Project Guidelines (LRPGs) provided the guidance and requirements forthe training of the license renewal (LR) project and site personnel. The training consisted of a combination of reading and attending training sessions. The attachment specified the level of training which was required for the various groups participating in the development of the LRA and began with initial training, documented on a qualification card. The training was required for both the LR project personnel who prepared the application and for the site personnel who reviewed the application. In addition, LR refresher training was provided for the LR project and site personnel participating in the review. Refresher training included information on the LR process and information specific to the site. LR project and site personnel were required toreview applicable LR regulations, NEI 95-10 and associated procedures. The applicant developed periodic production meetings in which the LR project personnel shared their knowledge and experience of a given subject with each other. The NRC audit team reviewed completed qualification and training records of several of theapplicant's LR project personnel and also reviewed completed check lists. The audit team found these records adequately documented the required training for the LR project personnel.
Additionally, based on discussions with the applicant's LR project personnel during the audit, the audit team verified that the applicant's LR project personnel were knowledgeable on the LR process requirements and the specific technical issues within their areas of responsibility. On the basis of discussions with the applicant's license renewal project personnel responsiblefor the scoping and screening process, and a review of selected design documentation in support of the process, the audit team concluded that the applicant's LR project personnel understood the requirements of and adequately implemented the scoping and screening methodology established in the applicant's renewal application. The audit team did not identifyany concerns regarding the training of the applicant's LR project or site personnel.VIII. Exit Meeting A public exit meeting was held with the applicant on July 27, 2006, to discuss the results of thescoping and screening methodology audit. The audit team identified preliminary areas where additional information would be required to support completion of the staff's LRA review.
Requests for additional information related to the applicant's scoping and screening methodology were forwarded to the applicant on July 10, 2006 (ADAMS Accession No.ML061720212).IX.Documents Reviewed 1.AMRC-03, "Aging Management Review of the Intake Structure," Revision 0.2.AMRC-05, "Aging Management Review of Yard Structures," Revision 0.
3.AMRC-06, "Aging Management Review of Bulk Commodities," Revision 0.
4.AMRE-01, "Electrical Screening and Aging Management Reviews," Revision 0.
5.AMRM-03, "Aging Management Review of the Core Spray System," Revision 0.
6.AMRM-26, "Aging Management Review of the Main Condenser and MSIV leakage Pathway,"Revision 0.7.AMRM-30, "Aging Management Review of Nonsafety-related Systems and ComponentsAffecting Safety-related Systems," Revision 1.8.CS, "Design Basis Document for Core Spray," Revision 2 9.ENN-MS-S-009-VY, "Vermont Yankee Site Specific Guidance and System Safety FunctionSheets," Revision 0.10.ENN-DC-167, "Classification of Structures, Systems and Components," Revision 2.
11.EXEV, "Topical Design Basis Document for External Events: Earthquakes (seismic),Tornadoes, External Flooding, Low Water," Revision 2.12.IF, "Topical Design Basis Document for Internal Flooding," Revision 1.
13.License Renewal Project Document (LRPD)-01, "System and Structure Scoping Results,"Revision 0.14.LRPD-02, "Aging Management Program Evaluation Reports," Revision 1 15.License Renewal Project Guideline (LRPG)-01, "License Renewal Project Plan," Revision 1.
16.LRPG-03, "System and Structure Scoping," Revision 1.
17.LRPG-04, "Mechanical System Screening and Aging Management Reviews," Revision 1.
18.LRPG-05, "Electrical System Scoping, Screening and Aging Management Reviews," Rev. 1.
19.LRPG-06, "Structural Screening and Aging Management Reviews," Revision 1.
20.Letter from the NRC to ENTERGY, "REQUEST FOR ADDITIONAL INFORMATION FORTHE REVIEW OF THE VERMONT YANKEE NUCLEAR POWER STATION LICENSERENEWAL APPLICATION," dated July 10, 2006 (ADAMS Accession No. ML061720212).21.NUREG-1800, "Standard Review Plan for Review of License Renewal Applications forNuclear Power Plants," Revision 1, dated September 2005.22.NEI 95-10, "Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - TheLicense Renewal Rule," Revision 6, dated September 2005.23.SADBD, "Topical Design Basis Document for Safety Analysis," Revision 4.
- 24. VYNPS License Renewal application, dated January 29, 2006.
- 25. VYNPS Maintenance Rule SSC Basis Documents, Change 49.
26.Vermont Yankee Environmental Qualification Program Manual, Section 6.0, "MasterEquipment List," Revision 18. X.Personnel Contacted During Methodology Audit Garry YoungENTERGY License Renewal TeamPaul RaineyVYNPS Mechanical Design Engineer Stephen VekasyVYNPS System Engineer David LachENTERGY License Renewal Ted IveyENTERGY License Renewal Team Julie JacksENTERGY License Renewal TeamMike MetellVYNPS Design EngineeringMike HamerVYNPS Licensing John HoffmanVYNPS License Renewal Project Manager Mike StroudENTERGY License Renewal Team Jim CallaghanVYNPS Design Engineering Manager Jim DeVincentisENTERGY Licensing ManagerJohnny EadsNRC License Renewal Project Manager, NRRJonathan Rowley NRC License Renewal Project Manager, NRRDevender Reddy NRC/NRR/DLRJacob Zimmerman NRC/NRR/DLR Branch Chief