Letter Sequence Other |
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MONTHYEAR1CAN041002, Fourth 10-Year Inservice Inspection Interval, Request for Alternative ANO1-R&R-013, Repairs to the Pressurizer Instrumentation Penetrations2010-04-0505 April 2010
Fourth 10-Year Inservice Inspection Interval, Request for Alternative ANO1-R&R-013, Repairs to the Pressurizer Instrumentation Penetrations
Project stage: Request
1CAN041004, Supplemental Information to Fourth 10-Year Inservice Inspection Interval Request for Alternative ANO1-R&R-013 Repairs to Pressurizer Instrumentation Penetrations2010-04-12012 April 2010
Supplemental Information to Fourth 10-Year Inservice Inspection Interval Request for Alternative ANO1-R&R-013 Repairs to Pressurizer Instrumentation Penetrations
Project stage: Supplement
ML1010302132010-04-13013 April 2010
Acceptance Review Email, Relief Request ANO1-R&R-013, Proposed Alternative to Requirements Associated with Repair of Components
Project stage: Acceptance Review
ML1012604132010-05-13013 May 2010
Request for Withholding Information from Public Disclosure - Affidavit Executed by Gayle Elliott, Areva Np Inc. on April 9, 2010
Project stage: Withholding Request Acceptance
ML1010406012010-05-13013 May 2010
Request for Withholding Information from Public Disclosure - Affidavit Executed by M. Taylor, Structural Integrity Associates on 4/9/2010
Project stage: Withholding Request Acceptance
ML1032703482010-11-23023 November 2010
Responses to Branch Chief'S Questions, Arkansas Nuclear One, Unit 1 - E-mail Fourth 10-Year Inservice Inspection Interval, Request for Alternative ANO1-R&R-013, Repairs to Pressurizer Instrumentation Penetrations
Project stage: Request
ML1032703402010-11-23023 November 2010
Email Fourth 10-Year Inservice Inspection Interval, Request for Alternative ANO1-R&R-013, Repairs to Pressurizer Instrumentation Penetrations
Project stage: Request
ML1034807502010-12-14014 December 2010
Request for Additional Information Email Sent 10-13-2010, Request for Alternative ANO1-R&R-013, Fourth 10-Year Inservice Inspection Interval, Repairs to the Pressurizer Instrumentation Penetrations
Project stage: RAI
ML1034806822010-12-14014 December 2010
Request for Additional Information Email, Request for Alternative ANO1-R&R-013, Fourth 10-Year Inservice Inspection Interval, Repairs to the Pressurizer Instrumentation Penetrations
Project stage: RAI
ML1035703332011-01-0303 January 2011
Verbal Authorization of Request for Alternative ANO1-R&R-013
Project stage: Other
1CAN011101, Response to Request for Additional Information, Regarding the Request for Alternative ANO1-R&R-013, Repairs to the Pressurizer Instrumentation Penetrations2011-01-0606 January 2011
Response to Request for Additional Information, Regarding the Request for Alternative ANO1-R&R-013, Repairs to the Pressurizer Instrumentation Penetrations
Project stage: Response to RAI
ML1034301562011-01-10010 January 2011
Relief Request ANO1-R&R-013, Proposed Alternative to Requirements Associated with Repair of Components, for Duration of ANO-1 Spring 2010 Refueling Outage 1R22
Project stage: Acceptance Review
2010-04-05
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Category:Memoranda
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Summary of December 15, 2022 Periodic Advanced Reactor Stakeholder Public Meeting
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Results of a Reactor Oversight Process Self Assessment Effectiveness Review of the Recommendations from IP 95003 at Arkansas Nuclear One
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2021 Annual Assessment Public Meeting Summary
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Calendar Year 2021 Security Baseline Completion Memo
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September 14, 2021, Summary of Public Workshop on Scale/Melcor Source Term Demonstration Project - Pebble-Bed Molten-Salt-Cooled Reactor
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Fiscal Year 2021 Research and Test Reactors Inspection Program Completion Status
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June 23, 2021, Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project
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Meeting Summary for Ticap Workshop 3
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Riv Column 1 EOC 2020 Public Meeting Summary
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Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project
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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
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Memo to Management Review Board Arkansas Follow-up FY2019 Proposed Final Report
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Cancelling Numerous Inspection Report Numbers
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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
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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
ML16076A2212016-03-16016 March 2016
NRC Supplemental Inspection Procedure 95003 (Report 05000313/2016007, 05000368/2016007) Request for Information
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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
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October 28, 2015, Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Arkansas Nuclear One, Units 1 and 2
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Inspection Procedure 95003 Communication Team Charter
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Summary of February 25, 2015, Partially Closed Meeting with Industry Stakeholders Regarding the Babcock and Wilcox Loss of Coolant Accident Evaluation Model Analysis
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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
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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
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Third-Party Assessment of Safety Culture
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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
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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
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2024-05-08
[Table view] |
Text
January 3, 2011 MEMEORANDUM TO: Docket File FROM: N. Kalyanam, Project Manager /RA/
Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT 1 - VERBAL AUTHORIZATION OF REQUEST FOR ALTERNATIVE, ANO1-R&R-013 (TAC NO. ME3701)
By letter dated April 5, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100950255), Entergy Operations, Inc. (the licensee), requested U.S. Nuclear Regulatory Commission (NRC) approval of a proposed alternative in Relief Request ANO1-R&R-013 to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) associated with the repair of pressurizer instrumentation penetration, RC-1001 A/B, at the Arkansas Nuclear One, Unit 1 (ANO-1). By letter dated April 12, 2010 (ADAMS Accession No. ML101050404), the licensee submitted its response to the NRC staffs request for additional information regarding the design, repair procedures, inspection, and flaw evaluations of the proposed instrumentation penetration repair.
Due to the immediate need of this relief request, the licensee requested a verbal authorization for the use of the request for alternative, ANO1-R&R-013, to facilitate the plant restart.
On the basis of its review, the NRC staff concluded that the proposed alternative would provide an acceptable level of quality and safety. In accordance with the Office of Nuclear Reactor Regulation procedure, and pursuant to 10 CFR 50.55a(a)(3)(i), the NRC staff granted verbal authorization for the use of Relief Request ANO1-R&R-013 for the repair of pressurizer instrumentation nozzle RC-1001 A/B at ANO-1 as of April 12, 2010, at 13:07 hours.
The participants from the NRC staff were:
Mike Markley, NRR/DORL Branch Chief Tim Lupold, NRR/DCI/CPNB Branch Chief John Tsao, NRR/DCI/CPNB Rezai Ali, NRR/DCI/CPNB Kaly N. Kalyanam, NRR/DORL Project Manager
The participants from the licensee were:
Dale James (Director, Nuclear Safety Assurance)
William Sims (Manager, Major Projects)
David Bice (Acting Manager, Licensing)
Jamie Gobell (Project Manager)
Bob Clark (Licensing)
The NRC staff will proceed with completion of the written safety evaluation for the subject relief request. The NRC may ask additional clarification questions to complete its written safety evaluation, if necessary. It is expected that the licensee will provide response to those questions.
All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
The licensee was also informed that if additional information was required later for the NRC staff to complete the safety evaluation, it will be submitted and the staff expects satisfactory response.
Docket No. 50-313
ML103570333 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DCI/CPNB NRR/LPL4/BC NRR/LPL4/PM NAME NKalyanam JBurkhardt TLupold MMarkley NKalyanam DATE 1/3/11 1/3/11 1/3/11 1/3/11 1/3/11
