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Category:Federal Register Notice
MONTHYEARML22313A0952022-12-0101 December 2022
Staffing Technical Specification License Amendment Federal Register Notice
ML22313A0102022-12-0101 December 2022
Cyber Security License Amendment Federal Register Notice
ML22217A0152022-11-0909 November 2022
FRN: Holtec Decommissioning International, LLC, Indian Point Energy Center, Independent Spent Fuel Storage Installation
ML22215A0992022-10-26026 October 2022
Environmental Assessment and Finding of No Significant Impact Federal Register Notice
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ML21356B4972022-02-14014 February 2022
Enclosure - Indian Point Exemption Request 10 CFR Part 20 Appendix G
ML21181A0282021-07-12012 July 2021
Individual Federal Register Notice, Notification of Public Meeting for Public Comments on Post-Shutdown Decommissioning Activities Report
ML21162A0022021-06-15015 June 2021
Individual Federal Register Notice, Notification of the Availability of the Post-Shutdown Decommissioning Activities Report
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Transmittal Letter, Notification of the Availability of the Post-Shutdown Decommissioning Activities Report in the Federal Register
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Exemption from 10 CFR 50.82 and 10 CFR 50.75
ML20297A3602020-11-23023 November 2020
Federal Register Notice for Order Approving Transfer of Facility Operating Licenses to Holtec International, Owner, and Holtec Decommissioning International, LLC, Operator
ML20309A7852020-11-23023 November 2020
Federal Register Notice for Exemption from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) for Holtec Decommissioning International, LLC
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Letter with Environmental Assessment and Finding of No Significant Impact Use of Decommissioning Trust Funds for Spent Fuel Management and Site Restoration
ML20274A0012020-11-0505 November 2020
Federal Register Notice: Environmental Assessment and Finding of No Significant Impact and Exemption
ML20236K1302020-09-29029 September 2020
Federal Register Notice Partial Exemption from Record Retention Requirements
ML20177A6452020-07-15015 July 2020
FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for June 2020
ML20109A0032020-04-22022 April 2020
FRN - Indian Point Nuclear Generating Unit Nos. 2 and 3 - Exemption from the Requirements of 10 CFR Part 50, Appendix R, Section Iii.H, Related to Fire Brigade Annual Physical Examinations
ML20024F0532020-02-13013 February 2020
Extension of Comment Period Consideration of Approval of Transfer of Control of Licenses and Conforming Amendments
ML20024F0632020-02-11011 February 2020
Extension of Comment Period for Notice of Consideration of Approval of Transfer of Control of Licenses and Conforming Amendments and Opportunity for a Hearing
ML20006E1222020-01-15015 January 2020
Individual Federal Register Notice for Consideration of Approval of Transfer of Licenses and Conforming Amendments
ML20003D0892020-01-13013 January 2020
Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing
ML20003D0882020-01-13013 January 2020
Letter with Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing
ML19085A2172019-03-29029 March 2019
Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 04/09/2019
ML18211A5782018-09-17017 September 2018
Federal Register Notice - Announcing the Issuance of the Indian Point Renewed Licenses
ML18096B3972018-05-16016 May 2018
Federal Register Notice for Issuance of Supplement 2 to the Indian Point Final Environmental Impact Statement for License Renewal
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Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 2018
ML17353A1922017-12-21021 December 2017
Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 2018
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OEDO-16-00411: Federal Register Notice Final Director'S Decision Under 10 CFR 2.206
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OEDO-16-00411: Federal Register Notice Final Director'S Decision Under 10 CFR 2.206
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Federal Register Notice of Issuance of Order for Mta Transfer of Indian Pt 3 and FitzPatrick to Entergy Nuclear Operations, Inc.
NRC-2017-0015, Federal Register Notice of Issuance of Order for Mta Transfer of Indian Pt 3 and FitzPatrick to Entergy Nuclear Operations, Inc. (CAC Nos. MF8286 and MF8287)2017-01-27027 January 2017
Federal Register Notice of Issuance of Order for Mta Transfer of Indian Pt 3 and FitzPatrick to Entergy Nuclear Operations, Inc. (CAC Nos. MF8286 and MF8287)
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Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 27, 2016
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OEDO-16-00411: Acknowledgement Letter for Petitioner Lochbaum Concerning the Reactor Vessel Baffle-Former Bolt Degradation Identified During the Spring 2016 Refueling Outage at Indian Point Nuclear Generating Unit 2
NRC-2016-0197, OEDO-16-00411: Federal Register Notice Regarding 10 CFR 2.206 Petition for Indian Point Nuclear Generating, Unit No. 22016-09-0707 September 2016
OEDO-16-00411: Federal Register Notice Regarding 10 CFR 2.206 Petition for Indian Point Nuclear Generating, Unit No. 2
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OEDO-16-00411: Federal Register Notice Regarding 10 CFR 2.206 Petition for Indian Point Nuclear Generating, Unit No. 2
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Federal Register Notice: 05/04/16 - Short Notice
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Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: March 15, 2016
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Final Environmental Assessment and Finding of No Significant Impact Related to Preemption Authority Requests
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Final Environmental Assessment and Finding of No Significant Impact Related to Preemption Authority Requests
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Draft Environmental Assessment and Finding of No Significant Impact Related to Preemption Authority Requests (CAC Nos. MF2603 - MF2605 and MF2637 - MF2639)
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Draft Environmental Assessment (TAC Nos. MF2603-MF2605 and MF2637 - MF2639)
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Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 4, 2015
ML15190A0362015-07-22022 July 2015
Federal Register Notice Withdrawal of an Amendment Request
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Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Published June 9, 2015
NRC-2015-0123, Application and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for2015-05-20020 May 2015
Application and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Acce
ML15125A4952015-05-20020 May 2015
Application and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Acce
2022-02-14
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Text
[7590-01-P]
NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-247 and 50-286; NRC-2016-0197]
Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit Nos. 2 and 3 AGENCY: Nuclear Regulatory Commission.
ACTION: 10 CFR 2.206 request; receipt.
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) is giving notice that by petition dated June 30, 2016, Mr. David A. Lochbaum of the Union of Concerned Scientists (the petitioner) requested that the NRC take action with regard to Indian Point Nuclear Generating Unit Nos. 2 and 3. The petitioner's requests are included in the SUPPLEMENTARY INFORMATION section of this document.
ADDRESSES:
Please refer to Docket ID NRC-2016-0197 when contacting the NRC about the availability of information regarding this document. You may obtain publicly-available information related to this document using any of the following methods:
Carol.Gallagher@nrc.gov.
- NRC's Agencywide Documents Access and Management System (ADAMS):
You may obtain publicly-available documents online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select "
ADAMS Public Documents" and then select "Begin Web-based ADAMS Search." For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or by e-mail to pdr.resource@nrc.gov. The ADAMS accession number for each document referenced (if it is available in ADAMS) is provided the first time that it is mentioned in this document.
- NRC's PDR: You may examine and purchase copies of public documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland
20852.
SUPPLEMENTARY INFORMATION:
On June 30, 2016, the petitioner requested that the NRC take action with regard to Indian Point Nuclear Generating Unit Nos. 2 and 3 (ADAMS Accession No. ML16187A186).
The petitioner requested that the NRC take the following enforcement actions:
- 1. Issue an Order requiring the Indian Point licensee to inspect the reactor vessel baffle-former bolts and to install the downflow to upflow modification on Unit 2 during its next refueling outage; 2. Issue a Demand for Information requiring the Indian Point licensee to submit an operability determination to the agency regarding continued operation of Unit 3 until its reactor vessel baffle-former bolts can be inspected per Material Reliability Project-227-A; and 3. Issue a Demand for Information requiring the Indian Point licensee to submit an evaluation of the performance, role and operating experience of the metal impact monitoring system in detecting and responding to indications of loose parts (such as broken baffle bolts) within the reactor coolant system. As the basis for this request, the petitioner cited Licensee Event Report 2016-004-00 "Unanalyzed Condition due to Degraded Reactor Baffle-Former Bolts," submitted by the licensee on May 31, 2016 (ADAMS Accession No. ML16159A219) that describes an event where there was an unanalyzed condition due to degraded reactor vessel baffle-former bolts at Indian Point Unit 2, which is reportable under § 50.73(a)(2)(ii)(B) of title 10 of the Code of Federal Regulations (10 CFR). Furthermore, the petitioner states that (1) an order is the proper means for ensuring that the bolts are inspected and that the downflow to upflow modification is installed during the next refueling outage at Indian Point Unit 2; (2) Indian Point Unit 3 is potentially operating with degraded baffle-former bolts and an operability determination is the mechanism established by the NRC to properly evaluate situations such as this; and (3) the metal impact monitoring system as described in the Updated Final Safety Analysis Report, has the potential to act as an alternate monitoring system to identify degraded baffle-former bolts, yet neither the NRC nor the licensee have refe rred to this system in publicly available documents relating to this issue.
The request is being treated pursuant to Section 2.206 of Title 10 of the Code of Federal Regulations (10 CFR) of the Commission's regulations. The request has been referred to the Director of the Office of Nuclear Reactor Regulation. As provided by 10 CFR 2.206, appropriate action will be taken on this petition within a reasonable time. The petitioner met with the Petition Review Board on July 28, 2016, to discuss the petition; the transcript of that meeting is an additional supplement to the petition (ADAMS Accession No. ML16215A391).
Dated at Rockville, Maryland, this 7 th day of September 2016.
For the Nuclear Regulatory Commission.
/RA/ William M. Dean, Director, Office of Nuclear Reactor Regulation.
