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Category:Code Relief or Alternative
MONTHYEARML21299A0032021-10-28028 October 2021 and Waterford Steam Electric Station, Unit 3 - Approval of Request for Alternative EN-20-RR-003 from Certain Requirements of the ASME Code ML15120A3152015-05-0707 May 2015 Relief Request ISI-06, Inservice Inspection Limited Examinations for the Fourth 10-Year Interval ML14147A2162014-06-18018 June 2014 Request for Exemption from Requirements of 10 CFR 50.54(m) Related to Minimum Staffing Requirements for Licensed and Senior Reactor Operators BVY 13-018, Inservice Inspection Program for the Fifth Ten-Year Interval2013-03-27027 March 2013 Inservice Inspection Program for the Fifth Ten-Year Interval 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 ML0911701112009-04-30030 April 2009 Relief Request ISI-2008-1, Use of Later ASME Section XI Code Edition and Addenda for Repair and Replacement, Pressure Testing, and Destructive Testing Activities-Vermont Yankee CNRO-2009-00003, Letter from Entergy Response to Request for Additional Information Regarding Request ISI-2008-1 Use of Later ASME Section Xl Code Edition and Addenda for Repair and Replacement, Pressure Testing, and Non Destructive Examination Activ2009-03-17017 March 2009 Letter from Entergy Response to Request for Additional Information Regarding Request ISI-2008-1 Use of Later ASME Section Xl Code Edition and Addenda for Repair and Replacement, Pressure Testing, and Non Destructive Examination Activities ML0735304772008-01-31031 January 2008 Relief Request No. ISI-PT-01, Alternate Pressure Testing for Buried Piping Components, Fourth Inservice Inspection Interval BVY 07-017, Relief Request No. ISI-PT-01, Alternate Pressure Testing for Buried Piping Components, Fourth Inservice Inspection Interval2007-04-20020 April 2007 Relief Request No. ISI-PT-01, Alternate Pressure Testing for Buried Piping Components, Fourth Inservice Inspection Interval ML0523702442005-09-19019 September 2005 Safety Evaluation of Relief, Use Various Boiling Water Reactor Vessels Internal Program Guidelines as an Alternative to Certain Requirements of Section XI of ASME Code for Inservice Inspection of Reactor Vessel Internal (Rvi) Components BVY 05-071, Clarifications to Relief Request RI-01 Table2005-08-0101 August 2005 Clarifications to Relief Request RI-01 Table ML0410700882004-07-0606 July 2004 Relief Request to Use American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Case N-600 ML0403700662004-03-0505 March 2004 Safety Evaluation of Relief Requests for the Fourth 10-Year Interval of the Inservice Inspection Program. (TAC Nos. MB8349 Through MB8358) ML0331804692003-12-22022 December 2003 Relief Requests for Fourth 10-year Inservice Testing Program Interval (TAC No. MB7489 Through MB7494) ML0320203882003-10-0606 October 2003 Relief Request Nos. RR-P01, RR-P02, RR-P03, RR-P04, RR- V01, and RR-V02 (TAC Nos MB7489 Through MB7494) JPN-03-020, Indian Point Nuclear Generating Station, Units 2 & 3, Pilgrim Nuclear Power Station, Vermont Yankee Nuclear Power Station, Relief, Relief Request to Use ASME Code Case N-6002003-08-11011 August 2003 Indian Point Nuclear Generating Station, Units 2 & 3, Pilgrim Nuclear Power Station, Vermont Yankee Nuclear Power Station, Relief, Relief Request to Use ASME Code Case N-600 ML0222000942002-08-26026 August 2002 Third 10-Year Interval Inservice Inspection Program Plan Request for Relief No. P-4 ML0219701172002-08-14014 August 2002 Safety Evaluation of Inservice Testing Relief Request for Safety Related Pumps ML0214005802002-05-31031 May 2002 Relief Request RR-V20, Revision 0, Correction Letter Related to the Inservice Testing Program ML0208505052002-04-23023 April 2002 Relief Request RR-V20, Revision 0, Related to the Inservice Testing Program (Tac No. MB3469) ML0210800132002-04-15015 April 2002 Use of ASME Code Case N-566-1 2021-10-28
[Table view] Category:Letter
MONTHYEARBVY 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 24-014, 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 24-015, Pre-Notice of Disbursement from Decommissioning Trust2024-04-0101 April 2024 Pre-Notice of Disbursement from Decommissioning Trust 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 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 2024-09-18
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 18, 2014 Governor Hunt Road Vernon, VT 05354
SUBJECT:
VERMONTYANKEE NUCLEAR POWER STATION- REQUEST FOR EXEMPTION FROM THE REQUIREMENTS OF 10 CFR 50.54(m)
(TAC NO. MF2990)
Dear Sir or Madam:
By letter dated October 31, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13325B016), Entergy Nuclear Operations, Inc. (the licensee) requested an exemption from certain requirements of Title 10 of the Code of Federal Regulations (10 CFR or§), Section 50.54(m) for Vermont Yankee Nuclear Power Station (VY) to be effective following submittal of the certifications required by 10 CFR 50.82(a)(1 ). These requirements establish the minimum staffing for reactor operators and senior reactor operators at licensed nuclear power reactors. The purpose of this letter is to provide you with the results of the U.S. Nuclear Regulatory Commission (NRC) staff's evaluation.
Pursuant to 10 CFR 50.12, "Specific exemptions," the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR Part 50 when: (1) the exemptions are authorized by law, will not present an undue risk to public health or safety, and are consistent with the common defense and security; and (2) when special circumstances are present.
The NRC staff reviewed the proposed exemption from§ 50.54(m) to determine the applicability of the license conditions established by § 50.54(m) to VY. The staff determined that § 50.54(m) prescribes the conditions of applicability in terms of operational modes (consistent with definition of modes in technical specifications) for each section in§ 50.54(m). The operational mode statements within § 50.54(m) indicate that this regulation is not intended to be applicable to reactors that are decommissioning. Specifically, a facility that has submitted certifications under
§ 50.82(a)(1 )(i) and (ii), is no longer authorized to operate the reactor or load fuel into the reactor vessel. Therefore, facilities in this configuration are no longer in a condition under which the operational modes described in § 50.54(m) apply. For example, § 50.54(m)(1) discusses startup, shutdown, and refueling modes; Footnote 2 of the table in § 50.54(m)(2)(i) describes a nuclear power unit as operating when it is in a mode other than cold shutdown or refueling;
§ 50.54(m)(2)(ii) refers to fueled units; § 50.54(m)(2)(iii) applies to units in a mode other than cold shutdown or refueling; and § 50.54(m)(2)(iv) concerns core alterations. Since all the subsections in § 50.54(m) refer to modes that require fuel to be in the core or anticipate a return to an operational mode, the regulation is not applicable to a permanently shut down and defueled reactor.
Therefore, the NRC staff concludes that the requirements in§ 50.54(m) do not apply and an exemption would not be needed for facilities that have submitted certifications under
§ 50.82(a)(1 )(i) and (ii).
By letter dated September 23, 2013 (ADAMS Accession No. ML13273A204), the licensee submitted "Notification Of Permanent Cessation Of Power Operations~* for VY. In this letter, Entergy provided notification to the NRC of its intent to permanently cease power operation at the end of the current operating cycle which is expected to occur in the fourth calendar quarter of 2014. In addition, Entergy indicated its intent to supplement the letter certifying ttie date on which operations have ceased, or will cease, in accordance with § 50.82(a)(1 )(i) and
§ 50.4(b)(8). With the certifications required by 10 CFR 50.82(a)(1) in place, the requirements of§ 50.54(m) will be no longer applicable and an exemption from 10 CFR 50.54(m) for VY will be unnecessary. Therefore, the NRC staff will not process the exemption request and is terminating its review.
Since no further action is required on this licensing request, the NRC staff will close Technical Assignment Control (TAC) No. MF2990. If you have any questions, please contact me at (301) 415-4125 or via e-mail at James.Kim@nrc.gov.
Sincerely, .
James Kim, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Rea.ctor Regulation .
Docket No. 50-271.
cc: Distribution via ListServ
ML13273A204), the licensee submitted "Notification Of Permanent Cessation Of Power Operations" for VY. In this letter, Entergy provided notification to the NRC of its intent to permanently cease power operation at the end of the current operating cycle which is expected to occur in the fourth calendar quarter of 2014. In addition, Entergy indicated its intent to supplement the letter certifying t,he date on which operations have ceased, or will cease, in accordance with § 50.82(a)(1 )(i) and
§ 50.4(b)(8). With the certifications required by 10 CFR 50.82(a)(1) in place, the requirements of§ 50.54(m) will be no longer applicable and an exemption from 10 CFR 50.54(m) for VY will be unnecessary. Therefore, the NRC staff will no_t process the exemption request and is terminating its review.
Since no further action is required on this licensing request, the NRC staff will close Technical Assignment Control (TAC) No. MF2990. If you have any questions, please contact me at (301) 415-4125 or via e-mail at James.Kim@nrc.gov.
Sincerely, IRA!
James Kim, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division 'of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-271 cc: Distribution via ListServ DISTRIBUTION:
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