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| {{#Wiki_filter:1CAN110804 | | {{#Wiki_filter:Entergy Operations, Inc. |
| | | 1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4619 Dale E. James Manager, Licensing Arkansas Nuclear One 1CAN110804 November 19, 2008 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 |
| November 19, 2008 | |
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| U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Summary of Weld Overlay Ultrasonic Examinations of Hot Leg Nozzle Dissimilar Metal Weld for Alloy 600 Mitigation at ANO-1 | | Summary of Weld Overlay Ultrasonic Examinations of Hot Leg Nozzle Dissimilar Metal Weld for Alloy 600 Mitigation at ANO-1 Arkansas Nuclear One, Unit 1 Docket No. 50-313 License No. DPR-51 |
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| Arkansas Nuclear One, Unit 1 | |
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| Docket No. 50-313 License No. DPR-51 | |
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| ==REFERENCE:== | | ==REFERENCE:== |
| NRC Letter to Entergy dated June 18, 2008 Approval of Relief Request ANO1-R&R-011 to Use a Proposed Alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Requirements for Weld Overlay Repairs (1CNA060801) | | NRC Letter to Entergy dated June 18, 2008 Approval of Relief Request ANO1-R&R-011 to Use a Proposed Alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Requirements for Weld Overlay Repairs (1CNA060801) |
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| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
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| By the reference letter dated June 18, 2008, the NRC approved the request by Entergy Operations, Inc (Entergy) for relief from the requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, Subsection IWA-4000 for mitigating primary water stress corrosion cracking (PWSCC) on a dissimilar metal weld (DMW) of the "A" hot leg nozzle to decay heat piping using the full structural weld overlay for Arkansas | | By the reference letter dated June 18, 2008, the NRC approved the request by Entergy Operations, Inc (Entergy) for relief from the requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, Subsection IWA-4000 for mitigating primary water stress corrosion cracking (PWSCC) on a dissimilar metal weld (DMW) of the A hot leg nozzle to decay heat piping using the full structural weld overlay for Arkansas Nuclear One, Unit 1 (ANO-1). |
| | As part of the request and repeated in the reference letter, Entergy committed to submit the following information to the NRC within 14 days following completion of final Ultrasonic (UT) examinations of the weld overlays: |
| | (a) the weld overlay examination results including a listing of indications detected, (b) the disposition of all indications using the standards of ASME Code, Section XI, IWB-3514-2 and/or IWB-3514-3 criteria and, if possible, the type and nature of the indications, and (c) a discussion of any repairs to the weld overlay material and/or base metal and the reason for the repairs. |
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| Nuclear One, Unit 1 (ANO-1).
| | 1CAN110804 Page 2 of 2 This information is provided in the attachment to this letter. The final UT examination of the weld overlay was completed on November 10, 2008. |
| | | This letter contains no new commitments. |
| As part of the request and repeated in the reference letter, Entergy committed to submit the following information to the NRC within 14 days following completion of final Ultrasonic (UT) examinations of the weld overlays:
| | If you have any questions or require additional information, please contact Dale James at 479-858-4619. |
| | | Sincerely, DEJ/dbb |
| (a) the weld overlay examination results including a listing of indications detected, (b) the disposition of all indications using the standards of ASME Code, Section XI, IWB-3514-2 and/or IWB-3514-3 criteria and, if possible, the type and nature of the indications, and
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| (c) a discussion of any repairs to the weld overlay material and/or base metal and the reason for the repairs.
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| Entergy Operations, Inc. 1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4619 Dale E. James Manager, Licensing Arkansas Nuclear One
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| 1CAN110804 Page 2 of 2 | |
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| This information is provided in the attachment to this letter. The final UT examination of the weld overlay was completed on November 10, 2008. | |
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| This letter contains no new commitments. | |
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| If you have any questions or require additional information, please contact Dale James at 479-858-4619. | |
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| Sincerely, DEJ/dbb | |
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| ==Attachment:== | | ==Attachment:== |
| Summary of Weld Overlay Ultrasonic Examination of Hot Leg Nozzle Dissimilar Metal Weld for Alloy 600 Mitigation at ANO-1 cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission | | Summary of Weld Overlay Ultrasonic Examination of Hot Leg Nozzle Dissimilar Metal Weld for Alloy 600 Mitigation at ANO-1 cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U.S. Nuclear Regulatory Commission Attn: Mr. Alan B. Wang MS O-7 D1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Director Division of Radiation Control and Emergency Management Arkansas Department of Health & Human Services P.O. Box 1437 Slot H-30 Little Rock, AR 72203-1437 |
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| Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125
| | ATTACHMENT 1CAN110804 |
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| NRC Senior Resident Inspector
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| Arkansas Nuclear One P.O. Box 310 London, AR 72847
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| U.S. Nuclear Regulatory Commission Attn: Mr. Alan B. Wang MS O-7 D1 Washington, DC 20555-0001
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| Mr. Bernard R. Bevill
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| Director Division of Radiation Control and Emergency Management Arkansas Department of Health & Human Services P.O. Box 1437 Slot H-30 Little Rock, AR 72203-1437
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| ATTACHMENT 1CAN110804 | |
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| ==SUMMARY== | | ==SUMMARY== |
| OF WELD OVERLAY ULTRASONIC EXAMINATION OF HOT LEG NOZZLE DISSIMILAR METAL WELD FOR ALLOY 600 MITIGATION AT ANO-1 | | OF WELD OVERLAY ULTRASONIC EXAMINATION OF HOT LEG NOZZLE DISSIMILAR METAL WELD FOR ALLOY 600 MITIGATION AT ANO-1 |
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| Attachment to 1CAN110804
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| Page 1 of 1 Summary of Weld Overlay Ultrasonic Examination of Hot Leg Nozzle Dissimilar Metal Weld for Alloy 600 Mitigation at ANO-1
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| Ultrasonic Examination Procedure SI-UT-126, Revision 3, Procedure for the Phased Array Ultrasonic Examination of Weld Overlaid Similar and Dissimilar Metal Welds, was used for examination of the Hot Leg Decay Heat Nozzle weld overlay (WOL). This procedure, and the examiners who applied the procedure, are qualified through the PDI Program at the EPRI NDE Center.
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| Hot Leg Decay Heat Nozzle Weld Overlay Examination
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| Component Identification: Hot Leg Decay Heat Nozzle Weld Overlay (Weld: 17-017)
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| Examination Date:
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| 11/10/08
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| Examination Time: 18:01 - 19:25 CST Weld Overlay Regions Examined: Overlay, Weld and Base Material (Outer 25%) Dissimilar Metal (DM) Weld
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| Axial Examination Angles: | | Attachment to 1CAN110804 Page 1 of 1 Summary of Weld Overlay Ultrasonic Examination of Hot Leg Nozzle Dissimilar Metal Weld for Alloy 600 Mitigation at ANO-1 Ultrasonic Examination Procedure SI-UT-126, Revision 3, Procedure for the Phased Array Ultrasonic Examination of Weld Overlaid Similar and Dissimilar Metal Welds, was used for examination of the Hot Leg Decay Heat Nozzle weld overlay (WOL). This procedure, and the examiners who applied the procedure, are qualified through the PDI Program at the EPRI NDE Center. |
| 0° through 84° Circumferential Examination Angles: 0° through 62° (Minimum Range) | | Hot Leg Decay Heat Nozzle Weld Overlay Examination Component Identification: Hot Leg Decay Heat Nozzle Weld Overlay (Weld: 17-017) |
| | Examination Date: 11/10/08 Examination Time: 18:01 - 19:25 CST Weld Overlay Regions Examined: Overlay, Weld and Base Material (Outer 25%) Dissimilar Metal (DM) Weld Axial Examination Angles: 0° through 84° Circumferential Examination Angles: 0° through 62° (Minimum Range) |
| Examination Summary No suspected flaw indications were observed during the examination. The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact / coupling effectiveness during the examination. During the course of the examination, 100% coverage of the weld overlay material was achieved and 100% coverage of the Code-required volume (CRV) for the DM weld was achieved.}} | | Examination Summary No suspected flaw indications were observed during the examination. The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact / coupling effectiveness during the examination. During the course of the examination, 100% coverage of the weld overlay material was achieved and 100% coverage of the Code-required volume (CRV) for the DM weld was achieved.}} |
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Category:Letter type:
MONTHYEAR2CAN072401, Proposed Alternative for Implementation of Extended Reactor Vessel In-Service Inspection Interval (ANO2-ISI-24-02)2024-07-19019 July 2024 Proposed Alternative for Implementation of Extended Reactor Vessel In-Service Inspection Interval (ANO2-ISI-24-02) 0CAN072401, Annual 10 CFR 50.46 Report for Calendar Year 2023 Emergency Core Cooling System Evaluation Changes2024-07-0808 July 2024 Annual 10 CFR 50.46 Report for Calendar Year 2023 Emergency Core Cooling System Evaluation Changes 1CAN072401, Request for Review and Approval of Changes to the Safety Analysis Report and to a Confirmatory Order Clarifying an Alternate Means of Compliance for Pressurizer Heaters Emergency Power Supply2024-07-0202 July 2024 Request for Review and Approval of Changes to the Safety Analysis Report and to a Confirmatory Order Clarifying an Alternate Means of Compliance for Pressurizer Heaters Emergency Power Supply 0CAN062403, Groundwater Protection Initiative - Voluntary Special Report for Tritium Levels2024-06-25025 June 2024 Groundwater Protection Initiative - 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Annual Radiological Environmental Operating Report for 20222023-05-0909 May 2023 Units 1 and 2 - Annual Radiological Environmental Operating Report for 2022 2CAN052301, Cycle 30 Core Operating Limits Report (COLR)2023-05-0303 May 2023 Cycle 30 Core Operating Limits Report (COLR) 0CAN042302, Annual Occupational Radiation Exposure Report for 20222023-04-27027 April 2023 Annual Occupational Radiation Exposure Report for 2022 0CAN042301, Radioactive Effluent Release Report for 20222023-04-14014 April 2023 Radioactive Effluent Release Report for 2022 2CAN042301, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-04-0505 April 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure2023-03-30030 March 2023 License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure 2CAN032304, Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032303, Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032305, 03 Post Examination Analysis2023-03-23023 March 2023 03 Post Examination Analysis 1CAN032302, Inspection Summary Report for the Thirtieth Refueling Outage (1R30)2023-03-20020 March 2023 Inspection Summary Report for the Thirtieth Refueling Outage (1R30) 1CAN012301, Responses to Request for Additional Information for Request for Relief ANO1-ISI-0352023-01-30030 January 2023 Responses to Request for Additional Information for Request for Relief ANO1-ISI-035 2CAN012303, U.S. Additional Protocol2023-01-23023 January 2023 U.S. Additional Protocol 2CAN012302, Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-01-20020 January 2023 Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 1CAN122201, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42022-12-22022 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN122202, Registration of Cask Use2022-12-21021 December 2022 Registration of Cask Use 0CAN122201, Reply to a Notice of Violation; EA-22-0992022-12-0808 December 2022 Reply to a Notice of Violation; EA-22-099 0CAN112201, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2022-11-10010 November 2022 Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2022-10-31031 October 2022 Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 1CAN102203, Cycle 31 Core Operating Limits Report2022-10-24024 October 2022 Cycle 31 Core Operating Limits Report 1CAN102201, Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-10-13013 October 2022 Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 2024-07-08
[Table view] |
Text
Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4619 Dale E. James Manager, Licensing Arkansas Nuclear One 1CAN110804 November 19, 2008 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Summary of Weld Overlay Ultrasonic Examinations of Hot Leg Nozzle Dissimilar Metal Weld for Alloy 600 Mitigation at ANO-1 Arkansas Nuclear One, Unit 1 Docket No. 50-313 License No. DPR-51
REFERENCE:
NRC Letter to Entergy dated June 18, 2008 Approval of Relief Request ANO1-R&R-011 to Use a Proposed Alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Requirements for Weld Overlay Repairs (1CNA060801)
Dear Sir or Madam:
By the reference letter dated June 18, 2008, the NRC approved the request by Entergy Operations, Inc (Entergy) for relief from the requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Subsection IWA-4000 for mitigating primary water stress corrosion cracking (PWSCC) on a dissimilar metal weld (DMW) of the A hot leg nozzle to decay heat piping using the full structural weld overlay for Arkansas Nuclear One, Unit 1 (ANO-1).
As part of the request and repeated in the reference letter, Entergy committed to submit the following information to the NRC within 14 days following completion of final Ultrasonic (UT) examinations of the weld overlays:
(a) the weld overlay examination results including a listing of indications detected, (b) the disposition of all indications using the standards of ASME Code,Section XI, IWB-3514-2 and/or IWB-3514-3 criteria and, if possible, the type and nature of the indications, and (c) a discussion of any repairs to the weld overlay material and/or base metal and the reason for the repairs.
1CAN110804 Page 2 of 2 This information is provided in the attachment to this letter. The final UT examination of the weld overlay was completed on November 10, 2008.
This letter contains no new commitments.
If you have any questions or require additional information, please contact Dale James at 479-858-4619.
Sincerely, DEJ/dbb
Attachment:
Summary of Weld Overlay Ultrasonic Examination of Hot Leg Nozzle Dissimilar Metal Weld for Alloy 600 Mitigation at ANO-1 cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U.S. Nuclear Regulatory Commission Attn: Mr. Alan B. Wang MS O-7 D1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Director Division of Radiation Control and Emergency Management Arkansas Department of Health & Human Services P.O. Box 1437 Slot H-30 Little Rock, AR 72203-1437
ATTACHMENT 1CAN110804
SUMMARY
OF WELD OVERLAY ULTRASONIC EXAMINATION OF HOT LEG NOZZLE DISSIMILAR METAL WELD FOR ALLOY 600 MITIGATION AT ANO-1
Attachment to 1CAN110804 Page 1 of 1 Summary of Weld Overlay Ultrasonic Examination of Hot Leg Nozzle Dissimilar Metal Weld for Alloy 600 Mitigation at ANO-1 Ultrasonic Examination Procedure SI-UT-126, Revision 3, Procedure for the Phased Array Ultrasonic Examination of Weld Overlaid Similar and Dissimilar Metal Welds, was used for examination of the Hot Leg Decay Heat Nozzle weld overlay (WOL). This procedure, and the examiners who applied the procedure, are qualified through the PDI Program at the EPRI NDE Center.
Hot Leg Decay Heat Nozzle Weld Overlay Examination Component Identification: Hot Leg Decay Heat Nozzle Weld Overlay (Weld: 17-017)
Examination Date: 11/10/08 Examination Time: 18:01 - 19:25 CST Weld Overlay Regions Examined: Overlay, Weld and Base Material (Outer 25%) Dissimilar Metal (DM) Weld Axial Examination Angles: 0° through 84° Circumferential Examination Angles: 0° through 62° (Minimum Range)
Examination Summary No suspected flaw indications were observed during the examination. The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact / coupling effectiveness during the examination. During the course of the examination, 100% coverage of the weld overlay material was achieved and 100% coverage of the Code-required volume (CRV) for the DM weld was achieved.