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| | number = ML110950646 | | | number = ML110950646 |
| | issue date = 04/11/2011 | | | issue date = 04/11/2011 |
| | title = Arkansas Nuclear One, Unit 1 - Verbal Authorization of Request for Alternative ANO1-R&R-015, Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05, Fourth 10-Year Interval (TAC No. ME5924) | | | title = Verbal Authorization of Request for Alternative ANO1-R&R-015, Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05, Fourth 10-Year Interval |
| | author name = Kalyanam N | | | author name = Kalyanam N |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
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| | page count = 3 | | | page count = 3 |
| | project = TAC:ME5924 | | | project = TAC:ME5924 |
| | stage = Request | | | stage = Other |
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MONTHYEARML1109506462011-04-11011 April 2011 Verbal Authorization of Request for Alternative ANO1-R&R-015, Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05, Fourth 10-Year Interval Project stage: Other 2011-04-11
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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. Caldwell to M. Markley RAI for Arkansas Nuclear One (ANO) Revision 15 Security Plan Review ML13255A4872013-09-10010 September 2013 Request for Additional Information to Entergy Operations, Arkansas Nuclear One-Units 1 and 2, Regarding NTTF Recommendation 9.3 Phase 1 Staffing Assessment Submittal ML12324A4222012-11-14014 November 2012 Meeting Notice with Entergy Operations, Inc. to Discuss the Status of the Revised Application for Arkansas Nuclear One, Unit 2 to Transition to National Fire Protection Association (NFPA) Standard 805 ML12319A1222012-11-14014 November 2012 Notice of Forthcoming Meeting with Entergy Operations, Inc. to Discuss Resubmittal of License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 at Arkansas Nuclear One, Unit 2 ML12271A2482012-09-27027 September 2012 10/9/2012 Notice of Forthcoming Meeting with Entergy Operations, Inc. to Discuss Resubmittal of License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 at Arkansas Nuclear One, Unit 2 ML12166A1002012-06-18018 June 2012 Forthcoming Meeting on 6/29/12 with Entergy Operations, Inc. to Discuss License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 at Arkansas Nuclear One, Unit 2 ML1214600172012-05-30030 May 2012 June 12-13, 2012, Notice of Meeting at the Plant Site in Russellville, AR to Discuss Entergy Operations, Inc.'S License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 at Arkansas Nuclear One, Unit 2 ML1134801002011-12-19019 December 2011 Notice of Forthcoming Meeting with Exelon Generation Company, LLC, and Entergy Operations, Inc., to Discuss Steam Generator Inspection Results at Three Mile Island, Unit 1, and Arkansas Nuclear One, Unit 1 ML1116101632011-09-0707 September 2011 Review of Amendment 22 of Safety Analysis Report - Period from 10/6/2008 Through 3/18/2010 ML1123506752011-08-31031 August 2011 Notice of Meeting with Entergy Operations, Inc. to Discuss a Proposed License Amendment Request for Arkansas Nuclear One, Unit 2, for Its Revised Fuel Handling Accident (Fha) Analysis and Several Technical Specification Task Force Travel ML1115704052011-06-0606 June 2011 Notice of Meeting with Entergy Operations, Inc., to Discuss Implementation of Quality Oversight and Verification Programs at Entergy Sites Including Actions Being Taken to Enhance Effectiveness ML11116A0332011-04-29029 April 2011 Monthly Operating Reports for the 1st Quarter of 2011 ML1111009242011-04-29029 April 2011 Summary of 3/15/11 (P.M. Session) Meeting with Entergy Operations, Inc. to Discuss Arkansas Nuclear One, Unit 1 Planned License Amendment Request for Technical Specification Change Service Water System Related Support Features ML1109506462011-04-11011 April 2011 Verbal Authorization of Request for Alternative ANO1-R&R-015, Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05, Fourth 10-Year Interval ML1108804522011-03-30030 March 2011 Notice of Forthcoming Meeting with Entergy Operations, Inc., to Discuss Proposed License Amendment Request to Adopt NFPA 805 for Arkansas Nuclear One, Units 1 and 2 ML1107504052011-03-21021 March 2011 Notice of Meeting with Entergy Operations, Inc., to Discuss Fleetwide Submittal for Proposed Technical Specification and Quality Assurance Program Manual Changes Related to Unit Staff Qualification Requirements 2024-05-08
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Text
April 11, 2011
MEMORANDUM 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-015 (TAC NO. ME5924)
By letter dated March 29, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110900049), Entergy Operations, Inc. (Entergy, the licensee),
requested U.S. Nuclear Regulatory Commission (NRC) approval of a proposed temporary non-Code repair to service water (SW) piping for Arkansas Nuclear One, Unit 1 (ANO-1). The request was submitted in accordance with NRC Generic Letter (GL) 90-05, "Guidance for Performing Temporary Non-Code Repair of [American Society of Mechanical Engineers Boiler and Pressure Vessel Code] ASME Code Class 1, 2, and 3 Piping."
On June 23, 2010, with ANO-1 in operation at 100 percent power, Entergy identified a through-wall leak of approximately 2 - 4 drops per minute in a section of SW system piping. Ultrasonic testing was conducted and the evaluation concluded that the leakage was a result of wall thinning due to localized corrosion on the inside of the pipe. The leak was addressed under GL 90-05. A subsequent re-inspection, with a smaller grid and a 0.2-inch diameter transducer, indicated a change in the data pertaining to the thickness of the flawed area. While the SW system operability was established, the evaluation also concluded that, assuming ongoing corrosion at a rate consistent with the most recent data, operability cannot be assured for the remainder of the operating cycle, which ends in the fall of 2011, and a near-term repair was necessary.
Since ASME Code, Section IWA-4422.1 requires that a defect be removed as part of a repair and since defect removal is not possible with the system in service in this case, Entergy designed a temporary repair, consisting of installing a steel plate (approximately 3 by 4 inches), on the degraded SW line, covering the small pinhole leak. Entergy requested relief from the ASME Code Section IWA-4422.1 requirement.
The NRC staff concludes that the design calculation for the plate thickness, the design drawing, the pre-installation examination, post-installation examination, system leakage test, and inservice monitoring of the repair satisfy the relevant requirements of American National Standards Institute (ANSI) B31.1, "Power Piping"; ASME Code, Sections III and XI; ASME Code Case N-661-1, "Alternative Requirements for Wall Thickness Restoration of Class 2 and 3 Carbon Steel Piping for Raw Water Service,Section XI, Division 1"; and GL 90-05. The licensee also performed the extent of condition examination and found no unacceptable degradation at five locations. The staff concludes that the licensee has provided sufficient information to support its argument that compliance with the Code requirements and a subsequent plant shutdown to perform an ASME Code repair of the subject degradation would result in hardship or unusual difficulty without a compensating increase in the level of quality
and safety.
The NRC staff has determined that the proposed temporary non-Code repair will provide reasonable assurance that the subject SW supply line will maintain its structural integrity until it is permanently repaired during the next refueling outage, currently scheduled to start on
October 16, 2011.
Pursuant to paragraph 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations , the NRC staff authorizes the use of Relief Request ANO1-R&R-015 for the temporary non-Code repair of the degraded SW supply line to the reactor building cooling coils at ANO-1, as discussed during a conference call with the licensee on April 1, 2011. Relief Request ANO1-R&R-015 is thereby authorized for use up to the next scheduled outage exceeding 30 days, but no later than the next refueling outage, which is scheduled for the fall of 2011.
All other requirements in ASME Code,Section XI, ANSI B31.1, Code Case N-661-1, and GL 90-05 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.
This verbal authorization does not preclude the NRC staff from asking additional clarification questions regarding Relief Request ANO1-R&R-015 while preparing its subsequent written safety evaluation.
The participants in the April 1, 2011, telephone call in which the NRC staff verbally authorized the temporary non-Code repair are identified below.
NRR REGION IV ENTERGY M. Markley J. Clark S. Pyle R. Jones T. Lupold A. Sanchez D. Bice P. Butler J. Tsao J. Rotton W. Greeson D. Torgerson N. Kalyanam D. McKenney D. Meatheany K. Panther J. Weicks
Docket No. 50-313
ML110950646 *via e-mail OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DCI/CPNB NRR/LPL4/BC NRR/LPL4/PM NAME NKalyanam JBurkhardt* TLupold* MMarkley (JRHall for) NKalyanam DATE 4/11/2011 4/7/11 4/1/11 4/11/11 4/11/11