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MONTHYEARML0402601972004-01-12012 January 2004 G20040041/LTR-04-0031 - Rep. Patrick Leahy Ltr License Amendment to Modify Certain Generation Facilities at Vermont Yankee Nuclear Power Station Project stage: Other ML0403309032004-02-20020 February 2004 G20040041/LTR-04-0031 - Ltr to Honorable Patrick Leahy Re Request by Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. to Amend Vermont Yankee License to Increase the Power Level of the Facility Project stage: Acceptance Review 2004-01-12
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Category:Letter
MONTHYEARBVY 24-028, Pre-Notice of Disbursement from Decommissioning Trust2024-10-31031 October 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-027, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-10-30030 October 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-026, Pre-Notice of Disbursement from Decommissioning Trust2024-10-0202 October 2024 Pre-Notice of Disbursement from Decommissioning Trust ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status BVY 24-024, Pre-Notice of Disbursement from Decommissioning Trust2024-07-30030 July 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-023, Pre-Notice of Disbursement from Decommissioning Trust2024-07-0202 July 2024 Pre-Notice of Disbursement from Decommissioning Trust IR 05000271/20240012024-06-28028 June 2024 NRC Inspection Report No. 05000271/2024001, Northstar Nuclear Decommissioning Company, LLC, Vermont Yankee Nuclear Power Station, Vernon, Vermont ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities BVY 24-022, Pre-Notice of Disbursement from Decommissioning Trust2024-05-30030 May 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-020, Biennial Update of Quality Assurance Program Manual2024-05-22022 May 2024 Biennial Update of Quality Assurance Program Manual BVY 24-019, 2023 Radiological Environmental Operating Report2024-05-0909 May 2024 2023 Radiological Environmental Operating Report BVY 24-017, Pre-Notice of Disbursement from Decommissioning Trust2024-05-0606 May 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-018, 2023 Radiological Effluent Release Report2024-05-0505 May 2024 2023 Radiological Effluent Release Report BVY 24-016, 2023 Individual Monitoring NRC Form 5 Report2024-04-18018 April 2024 2023 Individual Monitoring NRC Form 5 Report BVY 24-015, Pre-Notice of Disbursement from Decommissioning Trust2024-04-0101 April 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-014, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-04-0101 April 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-013, Status of Decommissioning and Spent Fuel Management Fund for the Year Ending 20232024-03-27027 March 2024 Status of Decommissioning and Spent Fuel Management Fund for the Year Ending 2023 BVY 24-012, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-03-14014 March 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-011, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-03-0606 March 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-010, Pre-Notice of Disbursement from Decommissioning Trust2024-03-0505 March 2024 Pre-Notice of Disbursement from Decommissioning Trust ML24053A2572024-03-0101 March 2024 Withdrawal of Requested Licensing Action for a License Amendment Submitted for Approval of the License Termination Plan BVY 24-009, Withdrawal of License Amendment Request to Add License Condition 3.K, License Termination Plan; Proposed Change No. 3172024-02-27027 February 2024 Withdrawal of License Amendment Request to Add License Condition 3.K, License Termination Plan; Proposed Change No. 317 BVY 24-008, ISFSI, Annual Radioactive Effluent Release Report2024-02-26026 February 2024 ISFSI, Annual Radioactive Effluent Release Report BVY 24-007, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-02-26026 February 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G IR 05000271/20230022024-02-20020 February 2024 NRC Inspection Report Nos. 05000271/2023002 and 07200059/2023001, Northstar Nuclear Decommissioning Company, LLC, Vermont Yankee Nuclear Power Station, Vernon, Vermont BVY 24-006, Pre-Notice of Disbursement from Decommissioning Trust2024-02-0606 February 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 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 23-011, 2022 Radiological Effluent Release Report2023-05-10010 May 2023 2022 Radiological Effluent Release Report BVY 23-013, 2022 Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Radiological Environmental Operating Report 2024-09-18
[Table view] Category:Congressional Correspondence
MONTHYEARML17068A1402017-03-0808 March 2017 03-08-17 Acknowledgement Letters to Honorable Patrick Leahy, Bernie Sanders and Peter Welch from Eugene Dacus Requesting a Public Meeting on Proposed License Transfer for Vermont Yankee ML17067A2112017-03-0707 March 2017 LTR-17-0100 - Senator Patrick Leahy Et Al., Letter Request for a Public Meeting in Vermont ML15303A1212015-11-30030 November 2015 Letter to Representative Peter Welch from Chairman Burns Responds to His Letter Raising Concerns Regarding the Decommissioning of Entergy'S Vermont Yankee Plant. (Response) ML15288A4992015-10-14014 October 2015 LTR-15-0516 Representative Peter Welch, Letter Concerns Regarding the Decommissioning of Entergy'S Vermont Yankee Plant ML14066A0712014-03-0606 March 2014 03-06-14 Acknowledgement Letter to Honorable Patrick Leahy - Bernard Sanders - Peter Welch - Vermont Yankee ML12083A1282012-03-16016 March 2012 G20120192/LTR-12-0108/EDATS: SECY-2012-0131 - Ltr. Rep. Edward J. Markey Regulations and Policies to Undertake Safety and Other Improvements by NRC Licensees as Part of License Extension Proceedings ML1205408622012-02-23023 February 2012 Response to Letter from Senator Jeanne Shaheen Vermont Yankee Annual Assessment Meeting ML11298A0832011-10-21021 October 2011 G20110761/LTR-11-0574/EDATS: SECY-2011-0564 - Ltr. Rep. Edward J. Markey Nuclear Regulatory Commission'S Regulations and Expectations Related to Licensees' Statements to the Media and Other Members of the Public - Entergy Nuclear and Vermon CY-92-223, G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 19712011-07-14014 July 2011 G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. 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John W. Olver Ltr. Re Request for Independent Safety Assessment of the Vermont Yankee Nuclear Power Plant 2017-03-08
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February 20, 2004 The Honorable Patrick Leahy United States Senate Washington, D.C. 20510
Dear Senator Leahy:
I am responding on behalf of the U.S. Nuclear Regulatory Commission (NRC) to your letter of January 12, 2004, concerning the request by Entergy Nuclear Vermont Yankee, LLC, and Entergy Nuclear Operations, Inc. (Entergy), to amend the Vermont Yankee Nuclear Power Station (Vermont Yankee) license to increase the power level of the facility. Based on concerns from your constituents, your letter requested an overview of what the NRC staffs review will entail for this license amendment request and how the public can participate in the review.
Extended power uprates (EPUs) result in power level increases that usually require modifications to major plant equipment. The NRC has approved EPUs for increases as high as 20 percent. The Vermont Yankee request is considered an EPU since the licensee is seeking to increase the licensed power level by 20 percent.
The facility operating license and technical specifications for a commercial nuclear power plant specify the maximum power level at which the plant may operate. NRC approval is required for any changes to the facility operating license or technical specifications. The process for making changes to facility operating licenses and technical specifications, called the license amendment process, is governed by Title 10 of the Code of Federal Regulations (10 CFR),
Part 50. The specific sections that apply are 10 CFR 50.90, Application for amendment of license or construction permit; 10 CFR 50.91, Notice for public comment; State consultation; and 10 CFR 50.92, Issuance of amendment. Power uprates are submitted to the NRC as license amendment requests.
The process the NRC will use to review the Vermont Yankee EPU license amendment request is described in NRC Review Standard RS-001, Revision 0, Review Standard for Extended Power Uprates, dated December 2003. The review standard is available on the NRC Web site at http://www.nrc.gov/reactors/operating/licensing/power-uprates.html. The purpose of this review standard is to provide guidance for the NRC staffs review of EPU applications to enhance consistency, quality, and completeness of reviews. This review standard also informs licensees and the public of the staffs guidance and criteria concerning specific areas of review.
The development of the review standard included an evaluation of NUREG-0800, Standard Review Plan [SRP] for the Review of Safety Analysis Reports for Nuclear Power Plants, to determine the applicability and adequacy of the various SRP sections for the review of EPU applications. To determine the need for guidance beyond that in the SRP, the staff reviewed: (1) safety evaluations for previously approved power uprates; (2) previously approved topical reports for EPUs; (3) various reports related to Lessons Learned from the Maine Yankee experience (e.g., Report of the Maine Yankee Lessons Learned Task Group,
P. Leahy 2 dated December 1996); and (4) generic communications. The staff also considered feedback from internal and external stakeholders.
After a licensee submits an application for an EPU license amendment, the NRC staff performs an acceptance review to determine if the licensee has addressed the areas of review described in RS-001 in sufficient detail to allow the staff to proceed with its detailed technical review. The acceptance review for the Vermont Yankee EPU license amendment request is documented in an NRC letter to Entergy dated December 15, 2003. As described in this letter, the NRC staff determined that further information was required in several areas. Entergys letter dated January 31, 2004, provided information to address the NRCs acceptance review letter. The NRC staff has evaluated Entergys submittal and determined that the necessary information was provided. Therefore, the staff has accepted Entergys application and has established a forecast review completion date of January 31, 2005. As you requested, we have contacted Ms. Susanne Fleek, of your staff, on February 18, 2004, to inform her that the detailed review is in progress.
As shown in RS-001, Figure 1.1-1, EPU Process Flow Chart, after the NRC determines that the licensee's application is acceptable such that the detailed technical review may proceed, a Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for a Hearing is prepared and published in the Federal Register. The Federal Register notice provides a brief description of the amendment request and gives members of the public an opportunity to request a hearing. The NRC's regulations concerning the hearing process are described in 10 CFR Part 2, Rules of Practice for Domestic Licensing Proceedings and Issuance of Orders. This regulation was recently revised to make the hearing process more efficient and effective. One of the changes to the rule, which became effective as of February 13, 2004, was to change the time period to request a hearing from 30 days after the Federal Register notice is published to 60 days. Further information on public involvement in hearings can be found on the NRC Web site at http://www.nrc.gov/what-we-do/regulatory/adjudicatory/hearing.html.
The NRC's detailed technical review for the Vermont Yankee EPU amendment request involves reviewers in 17 different technical areas and it is estimated that the review will require approximately 4,000 staff-hours. As a comparison, the NRC staff review for a typical license amendment requires approximately 80 staff-hours. The specific technical areas included in an EPU amendment review are detailed in the matrices in Section 2.1 of RS-001. The NRC staff reviews the information submitted by the licensee and, if necessary, requests additional information in order to make a regulatory decision regarding the proposed change. For EPU amendment requests, the NRC staff typically asks 100 to 200 questions of the licensee in requests for additional information.
In addition to the review of the submitted information, the detailed technical review may involve the performance of audits at the plant or vendor sites and performance of independent calculations by the NRC staff. Review Standard RS-001 provides guidance for determining when and what type of audits and/or independent calculations are appropriate to supplement the review of the EPU amendment request.
P. Leahy 3 When the NRC staff completes its detailed technical review of an EPU amendment request, a draft safety evaluation is prepared and sent to the Advisory Committee on Reactor Safeguards (ACRS) for review. The ACRS is independent of the NRC staff and reports directly to the Commission, which appoints its members. The ACRS is structured to provide a forum where experts representing many technical perspectives can provide independent advice that is factored into the Commissions decisionmaking process. As part of the ACRS review process, a meeting is held between the NRC staff and the ACRS in order to discuss the draft safety evaluation. All portions of this meeting except discussions of proprietary information are open to the public. Members of the public may request an opportunity to make an oral statement during the meeting. After the ACRS completes its review, it makes a recommendation to the Commission regarding whether the proposed EPU amendment should be approved.
In parallel with the detailed technical review, the NRC staff performs an environmental review to assess any potential environmental impacts of the proposed EPU amendment. Based on this review, a draft environmental assessment is prepared and published in the Federal Register for public comment. The NRC staff finalizes the environmental assessment after collecting and considering all public comments that were received.
After the final environmental assessment is issued, if the ACRS recommends approval, the NRC staff prepares the amendment package, including a final safety evaluation. For EPU license amendments, NRC procedures require that the Director for the Office of Nuclear Reactor Regulation sign the package. Typical license amendments can be signed by the NRC project manager for the plant.
In addition to the license amendment review described above, for power uprates greater than 7.5 percent, the NRC staff uses Inspection Procedure 71004, "Power Uprates, as guidance to inspect plant modifications, procedure changes, plant testing, and other issues related to the EPU license amendment. The procedure provides guidance with a focus on inspecting risk-significant issues. This inspection procedure is available on the NRC Web site at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/ip71004.pdf.
I hope this information is useful in addressing your constituents' concerns.
Sincerely,
/RA Carl J. Paperiello Acting For/
William D. Travers Executive Director for Operations
P. Leahy 3 When the NRC staff completes its detailed technical review of an EPU amendment request, a draft safety evaluation is prepared and sent to the Advisory Committee on Reactor Safeguards (ACRS) for review. The ACRS is independent of the NRC staff and reports directly to the Commission, which appoints its members. The ACRS is structured to provide a forum where experts representing many technical perspectives can provide independent advice that is factored into the Commissions decisionmaking process. As part of the ACRS review process, a meeting is held between the NRC staff and the ACRS in order to discuss the draft safety evaluation. All portions of this meeting except discussions of proprietary information are open to the public. Members of the public may request an opportunity to make an oral statement during the meeting. After the ACRS completes its review, it makes a recommendation to the Commission regarding whether the proposed EPU amendment should be approved.
In parallel with the detailed technical review, the NRC staff performs an environmental review to assess any potential environmental impacts of the proposed EPU amendment. Based on this review, a draft environmental assessment is prepared and published in the Federal Register for public comment. The NRC staff finalizes the environmental assessment after collecting and considering all public comments that were received.
After the final environmental assessment is issued, if the ACRS recommends approval, the NRC staff prepares the amendment package, including a final safety evaluation. For EPU license amendments, NRC procedures require that the Director for the Office of Nuclear Reactor Regulation sign the package. Typical license amendments can be signed by the NRC project manager for the plant.
In addition to the license amendment review described above, for power uprates greater than 7.5 percent, the NRC staff uses Inspection Procedure 71004, "Power Uprates, as guidance to inspect plant modifications, procedure changes, plant testing, and other issues related to the EPU license amendment. The procedure provides guidance with a focus on inspecting risk-significant issues. This inspection procedure is available on the NRC Web site at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/ip71004.pdf.
I hope this information is useful in addressing your constituents' concerns.
Sincerely,
/RA Carl J. Paperiello Acting For/
William D. Travers Executive Director for Operations Distribution: See page 4
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