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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:Safety Evaluation
MONTHYEARML24185A2602024-10-0404 October 2024
Issuance of Amendment No. 335 to Revise Typographical Errors in Technical Specifications
ML24185A1522024-08-13013 August 2024
Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205
ML24101A1792024-06-25025 June 2024
Issuance of Amendment No. 333 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML24086A5412024-04-10010 April 2024
Authorization of Request for Alternative ANO1-ISI-037 Regarding Extension of Reactor Vessel Inservice Inspection Interval
ML24031A6442024-03-14014 March 2024
Issuance of Amendment No. 282 to Modify Technical Specification 3.3.1, Reactor Pressure System (RPS) Instrumentation, Turbine Trip Function on Low Control Oil Pressure
ML23326A0392024-01-24024 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
ML23275A2072023-11-28028 November 2023
Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
ML23142A2022023-06-29029 June 2023
Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements
ML23166B0902023-06-21021 June 2023
Request for Relief ANO1 ISI 036 Regarding Volumetric Examination Requirements
ML23142A1062023-05-24024 May 2023
Authorization and Safety Evaluation for Alternative Request No. ANO1-ISI-035
ML23117A2172023-05-0101 May 2023
Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment
ML22342B1602023-01-10010 January 2023
Requests for Relief ANO2-ISI-023, -024, -025, -026, -027, and -028 to Permit Reduction of Inspection Area Due to Interference (EPIDs L-2022-LLR-0022,-0023, -0024, -0025, -0026, and -0027)
ML22263A1912022-12-0909 December 2022
Issuance of Amendment No. 278 Revision to Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations (EPID L-2021-LLA-0181) - Non-Proprietary
ML22236A5452022-08-26026 August 2022
Correction to Issuance of Amendment No. 331 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
ML22138A4312022-06-23023 June 2022
Issuance of Amendment No. 277 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
ML22104A2222022-05-12012 May 2022
Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554
ML22083A1242022-04-28028 April 2022
Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2
ML22039A2822022-03-15015 March 2022
Issuance of Amendment Nos. 274 and 328 One-Time Change to Support Proactive Upgrade of the Emergency Cooling Pond Supply Piping
ML22007A3172022-01-18018 January 2022
1, River Bend Station 1, and Waterford Steam Electric Station 3 - Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
ML21225A0552021-12-17017 December 2021
Issuance of Amendment No. 327 Addition of Technical Specification Limiting Condition for Operation 3.0.6 and Adoption of Safety Function Determination Program
ML21341B2262021-12-13013 December 2021
Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations
ML21313A0082021-12-0808 December 2021
Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
ML21208A4492021-09-20020 September 2021
Issuance of Amendment No. 325 Revise Loss of Voltage Relay Allowable Values and Number of Degraded Voltage Channels
ML21132A2792021-05-19019 May 2021
Request for Approval of Change to the Entergy Quality Assurance Program Manual
ML21088A4332021-04-14014 April 2021
Issuance of Amendment No. 324 Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition
ML21027A4282021-03-23023 March 2021
Issuance of Amendment No. 272 Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent
ML21040A5132021-03-10010 March 2021
Issuance of Amendment No. 271 Revision to Loss of Voltage Relay Allowable Values
ML20351A1532021-02-0808 February 2021
Issuance of Amendment No. 323 Technical Specification Deletions, Additions, and Relocations
ML20288A8242020-11-16016 November 2020
Regulatory Audit Summary Concerning License Amendment Request to Replace the Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent
NUREG-1432, Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-14322020-10-30030 October 2020
Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-1432
ML20226A2722020-08-18018 August 2020
Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI
ML20160A1472020-06-30030 June 2020
Issuance of Amendment No. 270 to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program
ML20135H1412020-06-30030 June 2020
Issuance of Amendment Nos. 269 and 321 Request to Incorporate the Tornado Missile Risk Evaluator Into the Licensing Basis
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
ML20107J3172020-04-23023 April 2020
Relief Request ANO1-ISI-033 Related to ASME Code Case N-729-4 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles
ML20087L8032020-04-0808 April 2020
Issuance of Amendment No. 320 to Revise Control Element Assembly Drop Times
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
ML19231A2972020-01-29029 January 2020
Issuance of Amendment No. 318 Addition of Technical Specification Actions to Address Inoperability of the Containment Building Sump
ML19220A9382019-09-27027 September 2019
Issuance of Amendment No. 266 Adoption of Technical Specifications Task Force Traveler TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues
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
ML19175A0422019-09-11011 September 2019
Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules
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
ML19098A9552019-05-22022 May 2019
Issuance of Amendment No. 264 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-425, Revision 3
ML19063B9482019-04-23023 April 2019
Issuance of Amendment No. 315 Adoption of Technical Specification Task Force Traveler TSTF-425, Revision 3
ML18337A2472019-01-17017 January 2019
Issuance of Amendment Nos. 263 and 314 Revision to Emergency Action Level Scheme
ML18346A3142019-01-0707 January 2019
Relief Nos. ANO1-ISI-027, -028, -029, -030, and -031 from ASME Code, Section XI, Examination Requirements for Fourth 10-Year Inservice Inspection Interval (EPID L-2018-LLR-0063, -0064, -0065, -0066, -0067)
ML18317A3822018-12-19019 December 2018
Issuance of Amendment No. 313, Revise Technical Specification 3.3.3.6, Post-Accident Instrumentation
ML18298A0122018-11-27027 November 2018
Issuance of Amendment No. 311 Updating the Reactor Coolant System Pressure Temperature Limits
ML18260A3392018-10-24024 October 2018
Issuance of Amendment No. 261 Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves
2024-08-13
[Table view] |
Text
March 8, 2007 Mr. Timothy G. Mitchell Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc.
1448 SR 333 Russellville, AR 72802
SUBJECT:
ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 - REQUEST NO. ISI-2006-1 TO USE LATER EDITION AND ADDENDA OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE, SECTION XI, FOR REPAIR AND/OR REPLACEMENT ACTIVITIES (TAC NOS. MD2702 AND MD2703)
Dear Mr. Mitchell:
By letter dated August 2, 2006, Entergy Operations, Inc., requested to use Subarticle IWA-4461.4 of Section XI of the 1995 Edition, 1997 Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME) Code at Arkansas Nuclear One, Units 1 and 2 (ANO-1 and ANO-2). Subarticle IWA-4461.4 provides requirements for qualification of thermal removal processes as an alternative to mechanical processing of thermally cut surfaces. The licensee submitted Request ISI-2006-1 in accordance with the Nuclear Regulatory Commission (NRC) Regulatory Issue Summary 2004-16, Use of Later Editions and Addenda to ASME Code,Section XI, for Repair/Replacement Activities, dated October 19, 2004.
On the basis of information submitted, the NRC staff concludes that the proposed request is acceptable and approves the use of the 1995 Edition, 1997 Addenda of the ASME Code,Section XI, for the repair/replacement activities for the remainder of the third 10-year inservice inspection (ISI) interval at ANO-1 and ANO-2, in accordance with paragraph 50.55a(g)(4)(iv) of Title 10 of the Code of Federal Regulations. The start date of the next 10-year ISI interval for ANO-1 and ANO-2 is June 1, 2007, and March 26, 2010, respectively.
The NRC staff's safety evaluation is enclosed. This completes the NRC staffs review under TAC Nos. MD2702 and MD2703. If you have any questions concerning this matter, please call Farideh Saba of my staff at 301-415-1447.
Sincerely,
/RA/
David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-313 and 50-368
Enclosure:
Safety Evaluation
cc w/encl: See next page March 8, 2007 Mr. Timothy G. Mitchell Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc.
1448 SR 333 Russellville, AR 72802
SUBJECT:
ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 - REQUEST NO. ISI-2006-1 TO USE LATER EDITION AND ADDENDA OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE, SECTION XI, FOR REPAIR AND/OR REPLACEMENT ACTIVITIES (TAC NOS. MD2702 AND MD2703)
Dear Mr. Mitchell:
By letter dated August 2, 2006, Entergy Operations, Inc., requested to use Subarticle IWA-4461.4 of Section XI of the 1995 Edition, 1997 Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME) Code at Arkansas Nuclear One, Units 1 and 2 (ANO-1 and ANO-2). Subarticle IWA-4461.4 provides requirements for qualification of thermal removal processes as an alternative to mechanical processing of thermally cut surfaces. The licensee submitted Request ISI-2006-1 in accordance with the Nuclear Regulatory Commission (NRC) Regulatory Issue Summary 2004-16, Use of Later Editions and Addenda to ASME Code,Section XI, for Repair/Replacement Activities, dated October 19, 2004.
On the basis of information submitted, the NRC staff concludes that the proposed request is acceptable and approves the use of the 1995 Edition, 1997 Addenda of the ASME Code,Section XI, for the repair/replacement activities for the remainder of the third 10-year inservice inspection (ISI) interval at ANO-1 and ANO-2, in accordance with paragraph 50.55a(g)(4)(iv) of Title 10 of the Code of Federal Regulations. The start date of the next 10-year ISI interval for ANO-1 and ANO-2 is June 1, 2007, and March 26, 2010, respectively.
The NRC staff's safety evaluation is enclosed. This completes the NRC staffs review under TAC Nos. MD2702 and MD2703. If you have any questions concerning this matter, please call Farideh Saba of my staff at 301-415-1447.
Sincerely,
/RA/
David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-313 and 50-368
Enclosure:
Safety Evaluation cc w/encl: See next page DISTRIBUTION:
PUBLIC RidsNrrLAJBurkhardt RidsRgn4MailCenter LPLIV r/f RidsNrrDciCvib (KGruss) DCullison, EDO Region IV RidsAcrsAcnwMailCenter RidsNrrPMFSaba JTsao, NRR RidsNrrDorlLpl4 RidsOgcRp ADAMS Accession No.: ML070460007
OFFICE DORL/LPL4/PM DORL/LPL4/LA DCI/CVIB/BC OGC - NLO DORL/LPL4/BC NAME FSaba LFeizollahi KGruss* JRund DTerao DATE 3/1/07 3/1/07 2/8/07 3/8/07 3/8/07
OFFICIAL AGENCY RECORD Arkansas Nuclear One cc:
Executive Vice President Section Chief, Division of Health
& Chief Operating Officer Emergency Management Section Entergy Operations, Inc. Arkansas Department of Health and P.O. Box 31995 Human Services Jackson, MS 39286-1995 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 General Manager Plant Operations Senior Resident Inspector Entergy Operations, Inc. U.S. Nuclear Regulatory Commission Arkansas Nuclear One P.O. Box 310 1448 SR 333 London, AR 72847 Russellville, AR 72802 Regional Administrator, Region IV Director, Nuclear Safety Assurance U.S. Nuclear Regulatory Commission Entergy Operations, Inc. 611 Ryan Plaza Drive, Suite 400 Arkansas Nuclear One Arlington, TX 76011-8064 1448 SR 333 Russellville, AR 72802 County Judge of Pope County 100 W. Main Street Manager, Licensing Russellville, AR 72801 Entergy Operations, Inc.
Arkansas Nuclear One Vice President, Operations Support 1448 SR 333 Entergy Operations, Inc.
Russellville, AR 72802 P.O. Box 31995 Jackson, MS 39286-1995 Director, Nuclear Safety & Licensing Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213-8298 Section Chief, Division of Health Radiation Control Section Arkansas Department of Health and Human Services 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 February 2007
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION USE OF LATER ASME CODE, SECTION XI FOR THERMAL REMOVAL PROCESSES ENTERGY OPERATIONS, INC.
ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 DOCKET NUMBERS 50-313 AND 50-368
1.0 INTRODUCTION
By letter dated August 2, 2006 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML062200491), Entergy Operations, Inc., requested to use Subarticle IWA-4461.4 of Section XI of the 1995 Edition, 1997 Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME) Code at Arkansas Nuclear One, Units 1 and 2 (ANO-1 and ANO-2). Subarticle IWA-4461.4 provides requirements for qualification of thermal removal processes as an alternative to mechanical processing of thermally cut surfaces.
The licensee submitted Request ISI-2006-1 in accordance with the Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2004-16, Use of Later Editions and Addenda to ASME Code,Section XI, for Repair/Replacement Activities, dated October 19, 2004. RIS 2004-16 states that licensees who wish to use provisions of subsequent editions and addenda of the ASME Code,Section XI, for activities, including repair/replacement activities, must receive prior NRC approval as required by paragraph 50.55a(g)(4)(iv) of Title 10 of the Code of Federal Regulations (10 CFR).
2.0 REGULATORY REQUIREMENTS Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code,Section XI, "Rules for Inservice Inspection [ISI] of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. Paragraph 50.55a(g)(4)(ii) of 10 CFR requires that ISI examination of components and system pressure tests conducted during successive 120-month inspection intervals must comply with the requirements in the latest edition and addenda of Section XI of the ASME Code, incorporated by reference in 10 CFR 50.55a(b), 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein.
The repair, replacement, and modification of plant components are not explicitly mentioned in 10 CFR 50.55a(g)(4) and associated subparagraphs. However, these activities are specifically
mentioned in the ASME Code,Section XI. The NRC staff maintains that these activities are not separate and distinct from, but are included under, inservice examinations. Therefore, the requirements of 10 CFR 50.55a(g)(4)(iv) are applicable to repair/replacement activities.
Paragraph 10 CFR 50.55a(g)(4)(iv) states that inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda of the ASME Code provided that they are incorporated by reference in 10 CFR 50.55a(b),
subject to the limitations and modifications listed in 10 CFR 50.55a(b), and subject to Commission approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions or addenda are met. Currently, paragraph 50.55a(b)(2) of 10 CFR incorporates by reference the ASME Code,Section XI, from the 1970 Edition through the 1976 Winter Addenda, and the 1977 Edition through the 2003 Addenda.
3.0 LICENSEES REQUEST ISI-2006-1
3.1 ASME Code Components Affected
All Class 1, 2, and 3 vessels, piping, pumps, and valves in the Section XI pressure boundary at ANO-1 and ANO-2.
3.2 Applicable Code Edition and Addenda Repair/replacement activities at ANO-1 and ANO-2 are currently performed in accordance with the 1992 Edition of ASME Code,Section XI, with portions of the 1993 Addenda for pressure testing.
The start date of the next 120-month ISI interval (the fourth interval) for ANO-1 and ANO-2 is June 1, 2007, and March 26, 2010, respectively.
3.3 Proposed Subsequent Code Edition and Addenda (or Portion)
The licensee currently performs repair/replacement activities in accordance with the 1992 Edition of ASME Code,Section XI, with portions of the 1993 Addenda for pressure testing.
However, Subarticle IWA-4000 in the 1992 Edition does not contain rules for qualifying thermal removal processes, such as electrodischarge machining, that can be used without mechanical processing of thermally cut surfaces.
The 1997 Addenda of the 1995 Edition of the ASME Code,Section XI, revised the rules applicable to thermal removal processes for all repair/replacement activities. The 1997 Addenda also added new rules that exempted mechanical processing of thermally cut surfaces provided the thermal removal process was qualified in accordance with Subarticle IWA-4461.4 of the ASME Code,Section XI.
Pursuant to 10 CFR 50.55a(g)(4)(iv), the licensee requested permission to use Subarticle IWA-4461.4 in the 1995 Edition, 1997 Addenda of ASME Code,Section XI. Subarticle IWA-4461.4 provides rules for qualifying thermal removal processes as an alternative to mechanical processing of thermally cut surfaces of P-Numbers 3, 4, 5, 6, 7, 8, 9, 10, 11A, and 43 materials.
The NRC approved the use of the 1995 Edition, 1997 Addenda as documented in 10 CFR 50.55a(b)(2) with no limitations, conditions, or modifications on Subarticle IWA-4461.4.
3.4 Related Requirements Subarticle IWA-4461.4 of the 1995 Edition, 1997 Addenda specifies rules for qualification of a thermal removal process as an alternative to mechanical processing of thermally cut surfaces.
When applying Subarticle IWA-4461.4, the following related requirement also applies:
Subarticle IWA-4461.4 states that [m]echanical processing of thermally cut surfaces for materials identified in IWA-4461.2 and IWA-4461.3 is not required when using a thermal removal process qualified as follows Because
[Subarticle] IWA-4461.4 is an alternative to mechanical processing of thermally cut surfaces for the materials identified in [Subarticles] IWA-4461.2 and IWA-4461.3, it is only applicable to P-Number[s] 3, 4, 5, 6, 7, 8, 9, 10, 11A, and 43 materials; it cannot be applied to P-Number 1 materials of [Subarticle]
IWA-4461.1.
Therefore, when invoking Subarticle IWA-4461.4 in the 1995 Edition, 1997 Addenda, the licensee will also apply this related requirement.
The NRC prohibition on evaluation of thermally cut surfaces in 10 CFR 50.55a(b)(2)(xxiii) does not apply to the qualification alternative of IWA-4461.4. Rather, this NRC prohibition applies to Subarticle IWA-4461.4.2, Evaluation of Thermally Cut Surfaces, which was not included into the ASME Code,Section XI, until the 2001 Edition.
3.5 Duration of Proposed Request ANO-1 and ANO-2 are currently under the third ISI interval. The duration of Request ISI-2006-1 will be effective from the date of the NRC approval to June 1, 2007, for ANO-1 and March 26, 2010, for ANO-2. These are the dates for the start of the next (fourth) ISI interval. Therefore, the duration of the proposed request is for the remainder of the third ISI interval at ANO-1 and ANO-2.
4.0 STAFF EVALUATION The NRC staff evaluated the licensee's request ISI-2006-1 pursuant to 10 CFR 50.55a(g)(4)(iv),
which states that inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda of the ASME Code provided certain criteria are satisfied.
The first criterion is that the edition and addenda of the ASME Code,Section XI, that will be used in the proposed request is incorporated by reference in 10 CFR 50.55a(b). Currently, paragraph 50.55a(b)(2) incorporates by reference the ASME Code,Section XI, from the 1970 Edition through the 1976 Winter Addenda, and the 1977 Edition (Division 1) through the 2003 Addenda (Division 1), which includes the 1995 Edition, 1997 Addenda of the ASME Code,Section XI, which was proposed by the licensee. Therefore, the NRC staff finds that the first criterion has been satisfied.
The second criterion is that the limitations and modifications listed in 10 CFR 50.55a(b) are satisfied for the specific use of the proposed subsequent edition and addenda of the ASME Code,Section XI. Paragraph 50.55a(b) of 10 CFR sets no limitations and modifications on Subarticle IWA-4461.4 of the 1995 Edition, 1997 Addenda of the ASME Code,Section XI.
Therefore, the NRC staff finds that the second criterion has been satisfied.
The third criterion is that if portions of subsequent editions or addenda of the ASME Code,Section XI, are used, all related requirements of the respective editions or addenda must be met. The NRC staff is satisfied that the licensee has listed all related requirements in Subarticle IWA-4461.4 of the 1995 Edition, 1997 Addenda of the ASME Code,Section XI, that are relevant to the stated repair/replacement activities. Therefore, the NRC staff finds that the third criterion has been satisfied.
Based on the above, the NRC staff finds that the criteria of 10 CFR 50.55a(g)(4)(iv) are satisfied and that the licensees request to use the 1995 Edition, 1997 Addenda of the ASME Code,Section XI, for repair/replacement activities is acceptable.
5.0 CONCLUSION
On the basis of evaluating the information submitted, the NRC staff concludes that the proposed request ISI-2006-1 is acceptable and approves the use of Subarticle IWA-4461.4 of the 1995 Edition, 1997 Addenda of the ASME Code,Section XI, for the specified repair/replacement activities for the remainder of the third 10-year ISI intervals at ANO-1 and ANO-2.
All other requirements of the ASME Code, Sections III and XI, for which relief has not been specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: John Tsao Date: March 8, 2007
