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| | issue date = 02/09/2015 | | | issue date = 02/09/2015 |
| | title = Correction to Relief Request ANO1-ISI-024 Issued December 23, 2014; Revises 10 CFR 50.55a Citations as a Result of Changes from Final Rule Effective December 5, 2014 | | | title = Correction to Relief Request ANO1-ISI-024 Issued December 23, 2014; Revises 10 CFR 50.55a Citations as a Result of Changes from Final Rule Effective December 5, 2014 |
| | author name = George A E | | | author name = George A |
| | author affiliation = NRC/NRR/DORL/LPLIV-1 | | | author affiliation = NRC/NRR/DORL/LPLIV-1 |
| | addressee name = | | | addressee name = |
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| | docket = 05000313 | | | docket = 05000313 |
| | license number = DPR-051 | | | license number = DPR-051 |
| | contact person = George A E | | | contact person = George A |
| | case reference number = TAC MF4022 | | | case reference number = TAC MF4022 |
| | document type = Code Relief or Alternative, Letter | | | document type = Code Relief or Alternative, Letter |
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| =Text= | | =Text= |
| {{#Wiki_filter:Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc. 1448 S.R. 333 Russellville, AR 72802 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 9, 2015 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 9, 2015 Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc. |
| | 1448 S.R. 333 Russellville, AR 72802 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ARKANSAS NUCLEAR ONE, UNIT NO. 1 -CORRECTION TO RELIEF REQUEST AN01-ISI-024 ALTERNATIVE TO THE SURFACENOLUMETRIC EXAMINATION FREQUENCY REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS CODE CASE N-729-1 (TAC NO. MF4022) | | ARKANSAS NUCLEAR ONE, UNIT NO. 1 -CORRECTION TO RELIEF REQUEST AN01-ISI-024 ALTERNATIVE TO THE SURFACENOLUMETRIC EXAMINATION FREQUENCY REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS CODE CASE N-729-1 (TAC NO. MF4022) |
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| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
| By letter dated April 28, 2014, as supplemented by letter dated October 2, 2014, Entergy Operations, Inc. (Entergy, the licensee), submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the use of an alternative to certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code), Section XI requirements at Arkansas Nuclear One, Unit 1 (AN0-1). Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR) 50.55a(a)(3)(i), the licensee requested to use a proposed alternative to the examination frequency requirements of ASME Code Case N-729-1 for the reactor vessel closure head at AN0-1, on the basis that the proposed alternative provides an acceptable level of quality and safety. By letter dated December 23, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14330A207), the U.S. Nuclear Regulatory Commission (NRC) staff authorized the use of request for alternative AN01-ISI-024 at AN0-1 for the duration up to, and including the AN0-1 27th refueling outage that is scheduled to commence in April2018 and will occur in the fifth 1 0-year inservice inspection interval. | | |
| By Federal Register notice 79 FR 65776, dated November 5, 2014, which became effective on December 5, 2014, the paragraph headings in 10 CFR 50.55a were revised. Accordingly, the citation in the NRC letter dated December 23, 2014, of 10 CFR 50.55a(a)(3)(ii) should have cited 10 CFR 50.55a(z)(2). | | By letter dated April 28, 2014, as supplemented by letter dated October 2, 2014, Entergy Operations, Inc. (Entergy, the licensee), submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the use of an alternative to certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code), Section XI requirements at Arkansas Nuclear One, Unit 1 (AN0-1). |
| I apologize for any confusion that may have resulted from the revision. If you have any questions, please contact me at (301) 415-1081 or by e-mail at Andrea. George@nrc.gov. | | Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR) 50.55a(a)(3)(i), |
| Docket No. 50-313 cc: Distribution via Listserv Sincerely, Andrea E. George, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation If you have any questions, please contact me at (301) 415-1081 or by e-mail at Andrea.George@nrc.gov.
| | the licensee requested to use a proposed alternative to the examination frequency requirements of ASME Code Case N-729-1 for the reactor vessel closure head at AN0-1, on the basis that the proposed alternative provides an acceptable level of quality and safety. |
| Docket No. 50-313 cc: Distribution via Listserv DISTRIBUTION: | | By letter dated December 23, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14330A207), the U.S. Nuclear Regulatory Commission (NRC) staff authorized the use of request for alternative AN01-ISI-024 at AN0-1 for the duration up to, and including the AN0-1 27th refueling outage that is scheduled to commence in April2018 and will occur in the fifth 10-year inservice inspection interval. |
| PUBLIC LPL4-1 Reading RidsAcrsAcnw_MaiiCTR Resource RidsNrrDeEpnb Resource RidsNrrDoriDpr Resource RidsNrrDorllpl4-1 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMANO Resource RidsRgn4MaiiCenter Resource SVitto, NRR/DE/EPNB MWaters, EDO RIV ADAMS Accession No. ML 15030A239 Sincerely, IRA/ Andrea E. George, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
| | By Federal Register notice 79 FR 65776, dated November 5, 2014, which became effective on December 5, 2014, the paragraph headings in 10 CFR 50.55a were revised. Accordingly, the citation in the NRC letter dated December 23, 2014, of 10 CFR 50.55a(a)(3)(ii) should have cited 10 CFR 50.55a(z)(2). I apologize for any confusion that may have resulted from the revision. |
| *via email OFFICE NRRIDORULPL4-1/PM NRR/DORLILPL4-1 | | |
| /LA NRRIDORL/LPL4-1 | | If you have any questions, please contact me at (301) 415-1081 or by e-mail at Andrea. George@nrc.gov. |
| /BC(A) NRR/DORULPL4-1 | | Sincerely, Andrea E. George, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-313 cc: Distribution via Listserv |
| /PM NAME AGeorge JBurkhardt* | | |
| EOesterle A George DATE 2/5/15 2/5/15 2/9/15 2/9/15 OFFICIAL RECORD COPY}} | | ML15030A239 *via email OFFICE NRRIDORULPL4-1/PM NRR/DORLILPL4-1 /LA NRRIDORL/LPL4-1 /BC(A) NRR/DORULPL4-1 /PM NAME AGeorge JBurkhardt* EOesterle A George DATE 2/5/15 2/5/15 2/9/15 2/9/15}} |
Letter Sequence Other |
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MONTHYEARML14140A2922014-05-20020 May 2014
Acceptance Review Email, Relief Request ANO1-ISI-024, Alternative from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-1, Fourth 10-year ISI Interval
Project stage: Acceptance Review
ML14258A0202014-09-12012 September 2014
NRR E-mail Capture - Request for Additional Information - ANO1-ISI-024 (MF4022)
Project stage: RAI
ML14330A2072014-12-23023 December 2014
Relief Request ANO1-ISI-024, Alternative from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-1, Fourth 10-year Inservice Inspection Interval
Project stage: Other
ML15030A2392015-02-0909 February 2015
Correction to Relief Request ANO1-ISI-024 Issued December 23, 2014; Revises 10 CFR 50.55a Citations as a Result of Changes from Final Rule Effective December 5, 2014
Project stage: Other
2014-05-20
[Table View] |
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Category:Code Relief or Alternative
MONTHYEARML23142A1062023-05-24024 May 2023
Authorization and Safety Evaluation for Alternative Request No. ANO1-ISI-035
ML22073A0952022-04-0707 April 2022
Approval of Request for Alternative from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (EPID L-2021-LLR-0084) (NON-PROPRIETARY)
ML21299A0032021-10-28028 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
ML21293A0962021-10-28028 October 2021
Relief ANO2-R&R-012 Concerning Proposed Alternative for Repair of Reactor Vessel Closure Head Penetration 46
ML21168A0562021-07-0909 July 2021
Approval of Request for Alternative from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code
ML21118B0392021-05-19019 May 2021
Approval of Request for Alternative from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code
CNRO-2020-00016, Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-08-12012 August 2020
Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)
ML20121A1932020-05-0606 May 2020
Alternative Requests for the Fifth 10 Year Interval Inservice Testing of Low Pressure Safety Injection Pumps and Service Water Valves
ML20119A0732020-04-29029 April 2020
Withdrawal of Requested Alternatives for the Fifth 10-Year Interval Inservice Testing of Service Water Pumps and Visual Examination of Snubbers
ML20083J9682020-03-26026 March 2020
Approval of Request for Alternative ANO 2-PT-002 End-of-Internal System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping
ML19254A6032019-09-19019 September 2019
Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1
2CAN071902, Request for Alternative ANO 2-PT-002 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping2019-07-25025 July 2019
Request for Alternative ANO 2-PT-002 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping
ML19184A5542019-07-15015 July 2019
Request for Relief ANO1-ISI-032 from the ASME Code Section XI Visual Examination Requirements for the Fourth 10-Year Inservice Inspection Interval
ML19156A4002019-06-11011 June 2019
Request for Alternative ANO2-ISI-021 to Permit Continued Application of the 2007 Edition Through the 2008 Addenda of ASME Code
CNRO-2019-00002, Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-01-31031 January 2019
Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1
ML18128A0672018-06-0808 June 2018
Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4
1CAN041801, Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements Fourth 10-Year Interval, Second and Third Period2018-04-23023 April 2018
Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements Fourth 10-Year Interval, Second and Third Period
CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 12017-11-17017 November 2017
Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1
ML17174B1442017-07-12012 July 2017
Relief Request for EN-ISI-16-1 Regarding Use of Later Edition and Addenda of the ASME Code
ML16130A4712016-12-0909 December 2016
Request for Alternative Test Plan to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (CAC Nos. MF7537 and MF7538)
ML16237A0822016-08-29029 August 2016
Relief Request No. ANO1-ISI-025, Relief from American Society of Mechanical Engineers Section XI Table IWB-2500-1 Requirements
ML16096A2692016-06-0606 June 2016
Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1
CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D2015-06-0505 June 2015
Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, Division
ML15070A4282015-03-16016 March 2015
Relief Request ANO2-ISI-017, Alternative to Utilize ASME Code Case N-513-4 for the Fourth 10-Year Inservice Inspection Interval
ML15030A2392015-02-0909 February 2015
Correction to Relief Request ANO1-ISI-024 Issued December 23, 2014; Revises 10 CFR 50.55a Citations as a Result of Changes from Final Rule Effective December 5, 2014
ML14330A2072014-12-23023 December 2014
Relief Request ANO1-ISI-024, Alternative from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-1, Fourth 10-year Inservice Inspection Interval
ML14282A4792014-10-29029 October 2014
Relief Request ANO1-ISI-023, Volumetric Examination Frequency Requirements, for the Fourth 10-Year Inservice Inspection Interval
ML14150A1632014-06-0606 June 2014
Relief Request ANO2-ISI-004 - Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations
ML14099A4522014-04-15015 April 2014
Relief Request ANO2-ISI-016, from ASME Code Case N-770-1 Successive Examination, for the Fourth 10-Year Inservice Inspection Interval
ML13179A1162013-07-24024 July 2013
Request for Relief ANO1-ISI-022 from ASME Code Examination Requirements for Pressure-Retaining Welds in Piping; Fourth 10-Year Inservice Inspection Interval
ML13179A1102013-07-16016 July 2013
Request for Relief No. ANO1-ISI-021, from ASME Volumetric Requirements for Full Penetration Welded Nozzles in Vessels - Inspection Program B; Fourth 10-Year ISI Interval
ML13161A2412013-06-27027 June 2013
Relief Request ANO2-ISI-015, from Pressure Testing Requirements for Reactor Vessel Flange Seal Leak Detection Piping for the Fourth 10-Year Inservice Inspection Interval
ML13071A6342013-03-22022 March 2013
Relief Request ANO2-ISI-014, from Volumetric and Surface Exam Requirements for Pressure Retaining Welds in Austenitic Stainless Steel, Third 10-Year Inservice Inspection Interval
ML13071A6632013-03-21021 March 2013
Relief Request ANO2-ISI-010, from Volumetric and Surface Exam Requirements for Pressure Retaining Welds in Piping, Third 10-Year Inservice Inspection Interval
ML13032A5732013-02-21021 February 2013
Relief Request Nos. ANO2-ISI-009, ANO2-ISI-011, and ANO2-ISI-012, ASME Code Volumetric and Surface Exam Requirements for Integral Attachment and Pressure-Retaining Welds, Third 10-Year Inservice Inspection Interval
ML12319A3672012-11-27027 November 2012
Relief Request ANO2-ISI-007, Alternative to Use ASME Code Case N-770-1 Baseline Examination, Fourth 10-Year Inservice Inspection Interval
1CAN071202, Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements, Fourth 10-Year Interval, First Period2012-07-25025 July 2012
Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements, Fourth 10-Year Interval, First Period
2CAN111101, Use of Alternate ASME Code Case N-770-1 Baseline Examination Request for Alternative ANO2-ISI-0072011-11-30030 November 2011
Use of Alternate ASME Code Case N-770-1 Baseline Examination Request for Alternative ANO2-ISI-007
ML1117107982011-08-10010 August 2011
Relief, ANO1-R&R-016, Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05, Fourth 10-Year Interval. ME6107
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
ML1035005322011-01-0505 January 2011
Request for Alternative ANO2-ISI-006, Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716 for the Fourth 10-Year ISI Interval
ML1025001282010-09-23023 September 2010
Relief Request ANO2-ISI-005 to Extend the Inservice Inspection Interval for the Visual Examination of Accessible Interior to Reactor Vessel Attachment Weld, for Fourth 10-Year Interval
ML1024506542010-09-21021 September 2010
Relief Request ANO2-ISI-004 to Extend Third Inservice Inspection Interval from 10 to 20 Years for Reactor Vessel Weld Examinations
ML1009103502010-08-19019 August 2010
Request for Relief PRR-ANO2-2010-1, Relief from the Requirements of Operation and Maintenance Code Section ISTB-5221 and ITSB-5223 for the Service Water Pumps
ML1011701272010-06-0202 June 2010
Request for Alternative ANO1-ISI-014, to Implement a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
ML1011701192010-05-0505 May 2010
Request for Relief Nos. ANO1-ISI-015, ANO1-ISI-016, ANO1-ISI-017, ANO1-ISI-018, ANO1-ISI-019, and ANO1-ISI-020, Relief from Requirements of the ASME Code, Section XI
ML1009706592010-04-26026 April 2010
Request for Alternative ANO2-ISI-003 to Use 2001 Edition Through 2003 Addenda in Lieu of the 2004 Edition for Fourth 10-Year Inservice Inspection Interval
2CAN021002, Request for Relief PRR-ANO2-2010-1 from the Requirements of OM Code Section ISTB-5221 and ISTB-5223 for the Service Water Pumps2010-02-17017 February 2010
Request for Relief PRR-ANO2-2010-1 from the Requirements of OM Code Section ISTB-5221 and ISTB-5223 for the Service Water Pumps
2CAN011005, Supplement to Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-7162010-01-28028 January 2010
Supplement to Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
ML0923005512009-08-27027 August 2009
Request for Alternative ANO2-ISI-002 to 10 CFR 50.55a(g)(6)(ii)(D) Examination Requirements, for Remainder of Current 10-Year Inservice Inspection Interval and Fourth ISI Interval Until the Head Is Replaced
2023-05-24
[Table view]
Category:Letter
MONTHYEARML23326A0392024-01-24024 January 2024
Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML24017A1582024-01-17017 January 2024
Submittal of Emergency Plan Revision 50
IR 05000313/20234202024-01-10010 January 2024
Security Baseline Inspection Report 05000313/2023420 and 05000368/2023420
IR 05000313/20234022024-01-0202 January 2024
Security Baseline Inspection Report 05000313/2023402 and 05000368/2023402
ML23354A0022023-12-21021 December 2023
Request for Withholding Information from Public Disclosure
ML23349A1672023-12-21021 December 2023
Request for Withholding Information from Public Disclosure
ML23348A3572023-12-14014 December 2023
Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting
ML23352A0292023-12-13013 December 2023
Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection
ML23340A1592023-12-13013 December 2023
Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment
IR 05000313/20234052023-12-12012 December 2023
Security Baseline Inspection Report 05000313/2023405 and 05000368/2023405
ML23341A0832023-12-11011 December 2023
Material Control and Accounting Program Inspection Report 05000313/368/2023404- Cover Letter
ML23305A0922023-12-0707 December 2023
Summary of Regulatory Audit Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b
ML23333A1362023-11-29029 November 2023
Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23275A2072023-11-28028 November 2023
Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
ML23325A1412023-11-21021 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
IR 05000313/20230032023-11-21021 November 2023
Revised - ANO Revised Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/ 2023001
ML23243B0452023-11-13013 November 2023
Request for Withholding Information from Public Disclosure
ML23313A0962023-11-13013 November 2023
Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023001
ML23311A2082023-11-0909 November 2023
Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV
IR 05000313/20230112023-10-10010 October 2023
Commercial Grade Dedication Inspection Report 05000313/2023011 and 05000368/2023011
IR 05000313/20230052023-08-21021 August 2023
Updated Inspection Plan for Arkansas Nuclear One, Units 1 and 2 (Report 05000313/2023005 and 05000368/2023005) - Mid Cycle
IR 05000313/20243012023-08-14014 August 2023
Notification of NRC Initial Operator Licensing Examination 05000313/2024301
IR 05000313/20230022023-08-11011 August 2023
Integrated Inspection Report 05000313/2023002 and 05000368/2023002 and Notice of Violation
ML23209A6022023-08-0909 August 2023
Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk- Informed Completion Times
IR 05000416/20230022023-08-0808 August 2023
Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001
ML23208A2132023-08-0303 August 2023
Regulatory Audit Summary Concerning Review of License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
ML23208A2112023-07-27027 July 2023
Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions
ML23188A1732023-07-12012 July 2023
Request for Withholding Information from Public Disclosure
ML23142A2022023-06-29029 June 2023
Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements
IR 05000313/20234032023-06-28028 June 2023
Security Baseline Inspection Report 05000313/2023403 and 05000368/2023403
ML23178A0892023-06-26026 June 2023
August 2023 Emergency Preparedness Program Inspection-Request for Information
ML23166B0902023-06-21021 June 2023
Request for Relief ANO1 ISI 036 Regarding Volumetric Examination Requirements
ML23180A1082023-06-20020 June 2023
ANO Unit 1 SAR Amendment 31, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report
IR 05000313/20234012023-06-13013 June 2023
Cyber Security Inspection Report 05000313/2023401 and 05000368/2023401
ML23130A2972023-05-17017 May 2023
Notification of Inspection (NRC Inspection Report 05000313/2023003) and Request for Information
ML23121A3012023-05-10010 May 2023
Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk - Informed Completion Times
ML23114A3572023-05-10010 May 2023
Regulatory Audit Summary Concerning Review of Request for Alternative ANO-CISI-002 Regarding Containment Inservice Inspection Frequency
ML23130A2732023-05-10010 May 2023
and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
IR 05000313/20230012023-05-0909 May 2023
Integrated Inspection Report 05000313/2023001 and 05000368/2023001
ML23118A3202023-05-0808 May 2023
Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000313;05000368/2023010)
IR 05000368/20233012023-05-0101 May 2023
NRC Examination Report 05000368/2023301
ML23117A2172023-05-0101 May 2023
Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment
ML23108A1362023-04-24024 April 2023
Approval of Request for Half-Nozzle Repair of Reactor Vessel Closure Head Penetration No. 46
ML23110A1122023-04-20020 April 2023
Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G
2024-01-24
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 9, 2015 Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT NO. 1 -CORRECTION TO RELIEF REQUEST AN01-ISI-024 ALTERNATIVE TO THE SURFACENOLUMETRIC EXAMINATION FREQUENCY REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS CODE CASE N-729-1 (TAC NO. MF4022)
Dear Sir or Madam:
By letter dated April 28, 2014, as supplemented by letter dated October 2, 2014, Entergy Operations, Inc. (Entergy, the licensee), submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the use of an alternative to certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI requirements at Arkansas Nuclear One, Unit 1 (AN0-1).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR) 50.55a(a)(3)(i),
the licensee requested to use a proposed alternative to the examination frequency requirements of ASME Code Case N-729-1 for the reactor vessel closure head at AN0-1, on the basis that the proposed alternative provides an acceptable level of quality and safety.
By letter dated December 23, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14330A207), the U.S. Nuclear Regulatory Commission (NRC) staff authorized the use of request for alternative AN01-ISI-024 at AN0-1 for the duration up to, and including the AN0-1 27th refueling outage that is scheduled to commence in April2018 and will occur in the fifth 10-year inservice inspection interval.
By Federal Register notice 79 FR 65776, dated November 5, 2014, which became effective on December 5, 2014, the paragraph headings in 10 CFR 50.55a were revised. Accordingly, the citation in the NRC letter dated December 23, 2014, of 10 CFR 50.55a(a)(3)(ii) should have cited 10 CFR 50.55a(z)(2). I apologize for any confusion that may have resulted from the revision.
If you have any questions, please contact me at (301) 415-1081 or by e-mail at Andrea. George@nrc.gov.
Sincerely, Andrea E. George, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-313 cc: Distribution via Listserv
ML15030A239 *via email OFFICE NRRIDORULPL4-1/PM NRR/DORLILPL4-1 /LA NRRIDORL/LPL4-1 /BC(A) NRR/DORULPL4-1 /PM NAME AGeorge JBurkhardt* EOesterle A George DATE 2/5/15 2/5/15 2/9/15 2/9/15
