Letter Sequence Draft RAI |
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Category:Memoranda
MONTHYEARML19317D0762019-11-18018 November 2019
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ML17271A0532017-09-29029 September 2017
2017 Summary of Annual Decommissioning Funding Status Reports for Reactors in Decommissioning
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Memorandum to C. Bladey Notice of Availability of Exemption for Entergy Energy Operations, Inc., Vermont Yankee Nuclear Power Station Independent Spent Fuel Storage Installation
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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
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Revision of the NRC Vermont Yankee Decommissioning Webpage
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Decommissioning Lessons Learned Report and Transmittal Memorandum
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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)
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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
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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
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1st Quarter 2014 Performance Review
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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
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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)
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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
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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)
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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
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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
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Draft Regulatory Guide for Comment
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Advisory Committee on Reactor Safeguards Review of the Vermont Yankee Nuclear Power Station License Renewal Application - Safety Evaluation Report
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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
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Y020070028 - Informal Vermont Yankee Seismic and Hydrology Questions
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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
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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
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2006/09/14-Audit Trip Report Regarding Entergy Nuclear Vermont Yankee, LLC, License Renewal Application for Vermont Yankee Power Station, Dated January 29, 2006
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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
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Text
April 8, 2005 MEMORANDUM TO: Darrell J. Roberts, Acting Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager, Section 2 /RA/
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
VERMONT YANKEE NUCLEAR POWER STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MC5850)
The attached draft request for information (RAI) was transmitted on April 7, 2005, to Ms. Ronda Daflucas of Entergy (the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensees request dated February 7, 2005. The licensee requested the Nuclear Regulatory Commissions approval to use a more recent edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for the pressure testing requirements of Class 1, 2, and 3 items following repair/replacement activities performed by welding or brazing on a pressure-retaining boundary at Vermont Yankee Nuclear Power Station.
This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request.
Docket No. 50-271
Attachment:
Draft RAI
April 8, 2005 MEMORANDUM TO: Darrell J. Roberts, Acting Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager, Section 2 /RA/
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
VERMONT YANKEE NUCLEAR POWER STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MC5850)
The attached draft request for information (RAI) was transmitted on April 7, 2005, to Ms. Ronda Daflucas of Entergy (the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensees request dated February 7, 2005. The licensee requested the Nuclear Regulatory Commissions approval to use a more recent edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for the pressure testing requirements of Class 1, 2, and 3 items following repair/replacement activities performed by welding or brazing on a pressure-retaining boundary at Vermont Yankee Nuclear Power Station.
This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request.
Docket No. 50-271
Attachment:
Draft RAI DISTRIBUTION PUBLIC DRoberts MMitchell VBucci, OIG PDI-2 Reading REnnis CSydnor ACCESSION NO.: ML050980068 OFFICE PDI-2/PM NAME REnnis DATE 04/07/05 OFFICIAL RECORD COPY
DRAFT REQUEST FOR ADDITIONAL INFORMATION REQUEST TO USE SUBSEQUENT EDITION AND ADDENDA OF ASME CODE, SECTION XI FOR PRESSURE TESTING REQUIREMENTS FOR REPAIRS/REPLACEMENTS PERFORMED BY WELDING OR BRAZING VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271 By letter dated February 7, 2005, Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. (Entergy or the licensee) requested the Nuclear Regulatory Commissions (NRCs or Commissions) approval to use a more recent edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) for the pressure testing requirements of Class 1, 2, and 3 items following repair/replacement activities performed by welding or brazing on a pressure-retaining boundary at Vermont Yankee Nuclear Power Station (VYNPS).
The NRC staff has reviewed the information the licensee provided that supports the proposed request and would like to discuss the following issues to clarify the submittal:
- 1. Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(g)(4)(iv), states that inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda of the ASME Code,Section XI that are incorporated by reference in paragraph (b) of 10 CFR 50.55a, subject to the limitations and modifications listed therein, and subject to Commission approval. The regulation also states that portions of editions or addenda may be used provided that all related requirements of the respective editions or addenda are met.
Pursuant to 10 CFR 50.55a(g)(4)(iv), the licensee has requested in its letter dated February 7, 2005, to use the 2001 Edition 2003 Addenda of the ASME Code,Section XI, Article IWA-4540, subparagraph (a), as applicable, for pressure testing of Class 1, 2, and 3 items following repair/replacement activities performed by welding or brazing on a pressure-retaining boundary. Specifically, the licensee has proposed to implement the requirements of the 2003 Addenda of the ASME Section XI Code, Article IWA-4540, subparagraph (a) in the VYNPS Repair/Replacement Program.
The licensees request to use the subsequent edition and addenda for the ASME Code subparagraph discussed above did not include the related requirements of the 2003 Addenda of the ASME Code,Section XI, Article IWA-4540, subparagraphs (c) and (d),
which read as follows:
(c) Replacement components and appurtenances shall be pressure tested in accordance with the Construction Code selected for use in accordance with IWA-4221.
ATTACHMENT
(d) Brazed joints and welds in replacement parts and piping subassemblies, fabricated by the Repair/Replacement Organization, or fabricated in accordance with the Construction Code without a hydrostatic pressure test, shall be tested as required by IWA-4540(a).
The licensees request also did not include the related requirements of Article IWA-4540, subparagraph (b) in the 2003 Addenda of the ASME Code,Section XI.
However, the licensees Code of Record for the Fourth Inservice Inspection Interval at VYNPS, the 1998 Edition through the 2000 Addenda of the ASME Code,Section XI contains requirements in Article IWA-4540, subparagraph (b) that are identical to those in the corresponding subparagraph in the 2003 Addenda of the ASME Code,Section XI.
Please clarify your pressure testing program for Class 1, 2, and, 3 systems and components following repair/replacement activities which specifically involve the use of replacement components and/or piping subassemblies containing welded or brazed joints that make up part of a pressure-retaining boundary. Please discuss whether you intend to use all requirements related to the 2003 Addenda of the ASME Code,Section XI, Article IWA-4540, subparagraph (a), specifically subparagraphs (c) and (d) of IWA-4540 in the 2003 Addenda.
- 2. Please clarify the ASME Code,Section XI Edition and Addenda that VYNPS proposes to use for the requirements of Article IWA-5000 that are referenced by Article IWA-4540, subparagraph (a).
