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Category:Memoranda
MONTHYEARML24297A6392024-10-30030 October 2024 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML24128A2402024-05-0808 May 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23047A3822023-03-21021 March 2023 Summary of December 15, 2022 Periodic Advanced Reactor Stakeholder Public Meeting ML22349A5052023-02-0808 February 2023 Results of a Reactor Oversight Process Self Assessment Effectiveness Review of the Recommendations from IP 95003 at Arkansas Nuclear One ML22147A0932022-06-0606 June 2022 2021 Annual Assessment Public Meeting Summary ML22034A3932022-02-16016 February 2022 Calendar Year 2021 Security Baseline Completion Memo ML21295A0882021-10-21021 October 2021 Fiscal Year 2021 Research and Test Reactors Inspection Program Completion Status ML21288A0392021-10-18018 October 2021 September 14, 2021, Summary of Public Workshop on Scale/Melcor Source Term Demonstration Project - Pebble-Bed Molten-Salt-Cooled Reactor ML21273A1772021-10-0101 October 2021 Fiscal Year 2021 Research and Test Reactors Inspection Program Completion Status ML21181A3352021-07-0101 July 2021 June 23, 2021, Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project ML21158A2232021-06-0808 June 2021 Meeting Summary for Ticap Workshop 3 ML21140A3892021-05-24024 May 2021 Riv Column 1 EOC 2020 Public Meeting Summary ML21132A2952021-05-14014 May 2021 Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project ML20337A1572020-12-0808 December 2020 Summary of Teleconference Meeting with Entergy Operations, Inc. to Discuss the Forthcoming Supplemental Response Concerning Generic Letter 2004-02 for Arkansas Nuclear One, Units 1 and 2 ML20149K5412020-11-23023 November 2020 Memo to File: Environmental Assessment and Finding of No Significant Impact and NRC Financial Analysis for Entergy Operations, Inc. Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for Arkansas Nuclear One I ML20150A4212020-11-23023 November 2020 Memo to File: Environmental Assessment and Finding of No Significant Impact and NRC Financial Analysis for Entergy Nuclear Company, LLC Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for Grand Gulf ISFSI ML19204A2972019-07-31031 July 2019 Memo to Management Review Board Arkansas Follow-up FY2019 Proposed Final Report ML18173A0082018-06-20020 June 2018 Cancelling Numerous Inspection Report Numbers ML17153A0012017-06-0606 June 2017 Staff Observations of Testing for Generic Safety Issue 191 During a May 10 to May 11, 2017, Trip to the Alden Test Facility for Control Components Inc. Strainer Tests ML16145A3392016-05-24024 May 2016 NRC Supplemental Inspection Procedure 95003 (Report - 05000313/2016007, and 05000368/2016007) List of Documents Reviewed 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 ML16076A2212016-03-16016 March 2016 NRC Supplemental Inspection Procedure 95003 (Report 05000313/2016007, 05000368/2016007) Request for Information ML16061A3622016-03-0101 March 2016 OEDO-15-00641 DPO-2015-001 on the Significance Determination Process Evaluation for a Finding at Arkansas Nuclear One Involving the March 2013, Unit 1 Stator Drop Event, Redacted-Public ML15292A2412015-10-21021 October 2015 October 28, 2015, Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Arkansas Nuclear One, Units 1 and 2 ML15218A6042015-08-0606 August 2015 Inspection Procedure 95003 Communication Team Charter ML15089A1642015-04-27027 April 2015 Summary of February 25, 2015, Partially Closed Meeting with Industry Stakeholders Regarding the Babcock and Wilcox Loss of Coolant Accident Evaluation Model Analysis ML14356A1722014-12-22022 December 2014 Summary of Site Audit to Support the Review of a License Amendment Request for Arkansas Nuclear One, Unit 2 to Transition to the National Fire Protection Association (NFPA) Standard 805 Fire Protection Licensing Basis ML14351A2602014-12-19019 December 2014 Memo C K Bladey Re Notice of Issuance of Exemption from Holtec Intl CoC No. 1014 Fuel Specification and Loading Conditions at Arkansas Nuclear One ISFSI ML14356A5612014-12-17017 December 2014 Third-Party Assessment of Safety Culture ML14345B0652014-12-11011 December 2014 Memo C Bladey Re Federal Register Notice of Issuance of Environmental Assessment and Finding of No Significant Impact ANO Units 1 & 2 ISFSI 72-12 and 72-1014 ML14213A4272014-09-12012 September 2014 Summary of July 16, 2014, Closed Meeting Between Representatives of the U.S. Army Corps of Engineers Nuclear Regulatory Commission, and Entergy Operations Inc. to Discuss Flooding Analysis Associated with Arkansas Nuclear One, Units 1 and 2 ML14184B2432014-07-10010 July 2014 Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Arkansas Nuclear One, Units 1 and 2 ML14163A0502014-06-13013 June 2014 Summary of Conference Call with Arkansas Nuclear One, Unit 2, Regarding the Spring Steam Generator Inspections ML13269A2082013-12-12012 December 2013 Cover Memo from B. 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September 16, 2010 MEMORANDUM TO: Docket File FROM: Nageswaran Kalyanam, Project Manager /RA/
Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 - FINAL NO SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS AND ENVIRONMENTAL FINDINGS RELATED TO PROPOSED EXEMPTION FROM CERTAIN REQUIREMENTS OF 10 CFR 50.36a(a)(2) (TAC NOS. ME3548 AND ME3549)
By letter dated March 18, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100780094), Entergy Operations Inc. (Entergy, the licensee),
requested an exemption from paragraph 50.36a(a)(2) of Title 10 of the Code of Federal Regulations (10 CFR). Specifically, the requested exemption requests a change to the submittal date of the Radioactive Effluent Release Report to that of the Technical Specification (TS) date of prior to May 1 of each year.
The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of the requested exemption and is processing it for issuance. Meanwhile, the NRC staff has evaluated the proposed exemption against the standard set forth in 10 CFR 51.22, and has determined that the requested exemption meets the provisions of categorical exclusion 10 CFR 51.22(c)(25); the NRC staffs evaluation is set forth below.
No Significant Hazards Consideration (NSHC) Analysis Since there is no regulatory standard specifically promulgated for NSHC associated with exemptions, the NRC staff used the standard provided by 10 CFR 50.92 for amendments to evaluate the subject exemption. The NRC staff's review is presented below:
- 1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed exemption is administrative in nature and requests a change to the submittal date of the Radioactive Effluent Release Report to that of the TS date of prior to May 1 of each year. The change does not affect plant equipment or operating practices and therefore does not significantly increase the probability or consequences of an accident previously evaluated.
The proposed change does not affect any plant structures, systems, and components, and will have no effect on plant operations. The proposed change is administrative and does not affect any existing limits. Accident initial conditions, probability, and assumptions remain as previously analyzed. The proposed change will have no effect on accident initiation frequency and does not invalidate the assumptions used in evaluating the radiological consequences of any accident.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed change requests a change to the submittal date of the Radioactive Effluent Release Report. The change does not add new plant equipment, change existing plant equipment, or affect the operating practices of the facility. All systems, structures, and components previously required for the mitigation of a transient remain capable of fulfilling their intended design functions. The proposed change has no adverse effect on any safety-related system or component and does not challenge the performance or integrity of any safety related system.
The proposed change does not involve any change in the design, configuration, or operation of the plant. The current plant design and design bases will remain the same. The current plant safety analyses remain complete and accurate in addressing the design basis events and in analyzing plant response and consequences. The limiting conditions for operations, limiting safety system settings, and safety limits specified in the TSs are not affected by the change.
The change does not introduce a new mode of plant operation or new accident precursors, does not involve any physical alterations to plant configurations, or make changes to system setpoints that could initiate a new or different kind of accident.
Therefore, the change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No.
The proposed change requests a change to the submittal date of the Radioactive Effluent Release Report. The change does not introduce any new or different accident initiators. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated. The
proposed changes does not affect plant equipment or operating practices and therefore does not involve a significant reduction in a margin of safety.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, the NRC staff makes a final determination that the requested exemption involves no significant hazards consideration.
Environmental Considerations This action is categorically excluded under 10 CFR 51.22(c)(25)(vi)(B), and there are no extraordinary circumstances present that would preclude reliance on this exclusion. The NRC staff has made this finding because this action applies to granting of an exemption from the requirements of a regulation of Chapter I of Title 10 of the Code of Federal Regulations (i.e.,
10 CFR 50.36(a)(2)) and under (vi)(B), the requirements from which this exemption is sought involve reporting requirements. In addition, there would be would be no significant hazards consideration, no significant change in the types or significant increase in the amounts of any effluents that may be released offsite, no significant increase in individual or cumulative public or occupational radiation exposure, no significant construction impact, no significant increase in the potential for or consequences from radiological accidents, and no significant impacts to biota, water resources, cultural resources, or socioeconomic conditions in the region. Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the exemption.
Docket Nos. 50-313 and 50-368
ML101900162 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DLR/RERB NRR/LPL4/BC NRR/LPL4/PM NAME NKalyanam JBurkhardt AImboden MMarkley NKalyanam DATE 9/13/10 9/13/10 9/13/10 9/16/10 9/16/10