|
|
(One intermediate revision by the same user not shown) |
Line 3: |
Line 3: |
| | issue date = 04/18/2008 | | | issue date = 04/18/2008 |
| | title = Withdrawal of Relief Request ANO1-ISI-011 | | | title = Withdrawal of Relief Request ANO1-ISI-011 |
| | author name = James D E | | | author name = James D |
| | author affiliation = Entergy Operations, Inc | | | author affiliation = Entergy Operations, Inc |
| | addressee name = | | | addressee name = |
Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:1CAN040803 | | {{#Wiki_filter:Entergy Operations, Inc. |
| | | 1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4619 Dale E. James Manager, Licensing Nuclear Safety Assurance Arkansas Nuclear One 1CAN040803 April 18, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 |
| April 18, 2008 | |
| | |
| U.S. Nuclear Regulatory Commission | |
| | |
| Attn: Document Control Desk Washington, DC 20555 | |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Withdrawal of Relief Request ANO1-ISI-011 Arkansas Nuclear One, Unit 1 | | Withdrawal of Relief Request ANO1-ISI-011 Arkansas Nuclear One, Unit 1 Docket No. 50-313 License No. DPR-51 |
| | |
| Docket No. 50-313 License No. DPR-51 | |
|
| |
|
| ==REFERENCE:== | | ==REFERENCE:== |
| Entergy letter dated January 22, 2008, "Request for Relief from ASME Section XI Table IWB-2500-1 Requirements" (1CAN010801) | | Entergy letter dated January 22, 2008, Request for Relief from ASME Section XI Table IWB-2500-1 Requirements (1CAN010801) |
| (TAC No. MD8018) | | (TAC No. MD8018) |
|
| |
|
| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
|
| |
|
| By the reference letter, Entergy Operations, Inc. (Entergy) requested approval of proposed alternatives to the requirements of the 1992 Edition of ASME Section XI for Arkansas Nuclear One, Unit 1 (ANO-1), specifically the requirements of Examination Category B-J of Table IWB-2500-1 (ANO1-ISI-011). | | By the reference letter, Entergy Operations, Inc. (Entergy) requested approval of proposed alternatives to the requirements of the 1992 Edition of ASME Section XI for Arkansas Nuclear One, Unit 1 (ANO-1), specifically the requirements of Examination Category B-J of Table IWB-2500-1 (ANO1-ISI-011). |
| | | On September 22, 1999, 10CFR50.55a was revised mandating the implementation of the 1995 Edition, through and including the 1996 Addenda of ASME Section XI, Appendix VIII, Performance Demonstration for Ultrasonic Examination Systems. These requirements are now implemented, as applicable, in the in-service inspection program for ANO-1. |
| On September 22, 1999, 10CFR50.55a was revised mandating the implementation of the 1995 Edition, through and including the 1996 Addenda of ASME Section XI, Appendix VIII, "Performance Demonstration for Ultrasonic Ex amination Systems". These requirements are now implemented, as applicable, in the in-service inspection program for ANO-1. | | The subject relief request identified a statement in the 1995 Edition with the 1996 Addenda of ASME Section XI, Appendix VIII, Supplement 2 that could not be complied with, e.g., "...the specimen inside surface and identification shall be concealed from the candidate". The applicable technique for examining the reactor vessel nozzle-to-pipe and pipe-to-nozzle welds is remotely from the inside surface. The qualification for the piping welds required access to the ID of the pipe, therefore the inside surface cannot be "concealed". This was addressed in the later addenda (2002) of Section XI, however; this addenda has not been approved by the Staff via a change to 10CFR50.55a. |
| | | Code Case N-696, Qualification Requirements for Appendix VIII Piping Examinations Conducted from the Inside Surface, Section XI, Division 1, addresses this very issue. In |
| The subject relief request identified a statement in the 1995 Edition with the 1996 Addenda of ASME Section XI, Appendix VIII, Supplement 2 that could not be complied with, e.g., "...the specimen inside surface and identification shall be concealed from the candidate". The applicable technique for examining the reactor vessel nozzle-to-pipe and pipe-to-nozzle welds is remotely from the inside surface. The qualification for the piping welds required access to the ID of the pipe, therefore the inside surface cannot be "concealed". This was addressed in the later addenda (2002) of Section XI, however; this addenda has not been approved by the Staff via a change to 10CFR50.55a. | |
| | |
| Code Case N-696, "Qualification Requirements for Appendix VIII Piping Examinations Conducted from the Inside Surface, Section XI, Division 1", addresses this very issue. In Entergy Operations, Inc. 1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4619 Dale E. James Manager, Licensing Nuclear Safety Assurance Arkansas Nuclear One | |
| | |
| 1CAN040803 Page 2 of 3
| |
| | |
| paragraph 39(b) of the code case, it states, "The flaw location and specimen identification shall be obscured as to maintain a 'blind test'." These are essentially the same words in the 2002 Addenda of Section XI, Appendix VIII, Supplement 2 as noted above.
| |
| | |
| At the time the request for alternative was made, the NRC had not approved Code Case N-696 in Regulatory Guide (RG) 1.147. The latest revision to RG 1.147, (Rev. 15) was issued by the NRC in late January 2008, which documents the NRC approval of Code Case N-696.
| |
| Based on the latest revision of the RG, Entergy hereby withdraws its request for the NRC approval of relief request ANO1-ISI-011.
| |
| | |
| The vendor procedures and personnel will be qualified for this application to the requirements of Code Case N-696. These requirements are identical to the requirements that were proposed in the subject relief request. This provides assurance that the piping welds are free of service related flaws and ensures plant safety and reliability.
| |
| | |
| This letter does not change any previous commitments.
| |
| | |
| If you have any questions or require additional information, please contact me.
| |
| | |
| Sincerely, DEJ/rwc
| |
| | |
| 1CAN040803 Page 3 of 3
| |
| | |
| cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064
| |
| | |
| 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
| | 1CAN040803 Page 2 of 3 paragraph 39(b) of the code case, it states, The flaw location and specimen identification shall be obscured as to maintain a blind test. These are essentially the same words in the 2002 Addenda of Section XI, Appendix VIII, Supplement 2 as noted above. |
| | At the time the request for alternative was made, the NRC had not approved Code Case N-696 in Regulatory Guide (RG) 1.147. The latest revision to RG 1.147, (Rev. 15) was issued by the NRC in late January 2008, which documents the NRC approval of Code Case N-696. |
| | Based on the latest revision of the RG, Entergy hereby withdraws its request for the NRC approval of relief request ANO1-ISI-011. |
| | The vendor procedures and personnel will be qualified for this application to the requirements of Code Case N-696. These requirements are identical to the requirements that were proposed in the subject relief request. This provides assurance that the piping welds are free of service related flaws and ensures plant safety and reliability. |
| | This letter does not change any previous commitments. |
| | If you have any questions or require additional information, please contact me. |
| | Sincerely, DEJ/rwc |
|
| |
|
| 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}} | | 1CAN040803 Page 3 of 3 cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 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}} |
Letter Sequence Withdrawal |
---|
|
|
|
|
---|
Category:Letter type:
MONTHYEAR2CAN012401, U.S. Additional Protocol2024-01-17017 January 2024 U.S. Additional Protocol 2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42024-01-11011 January 2024 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN012401, Registration of Cask Use2024-01-10010 January 2024 Registration of Cask Use 1CAN122301, Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)2023-12-14014 December 2023 Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037) 2CAN112302, Submittal of Amendment 31 to Safety Analysis Report2023-11-16016 November 2023 Submittal of Amendment 31 to Safety Analysis Report 0CAN102303, Registration of Cask Use2023-10-24024 October 2023 Registration of Cask Use 0CAN102302, (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 32023-10-11011 October 2023 (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 3 0CAN102301, Evacuation Time Estimate (ETE) Study2023-10-0404 October 2023 Evacuation Time Estimate (ETE) Study 1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-09-21021 September 2023 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN092302, Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2023-09-14014 September 2023 Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 2CAN092301, Reply to a Notice of Violation2023-09-0808 September 2023 Reply to a Notice of Violation 0CAN092301, Emergency Plan Implementing Procedure Revision2023-09-0505 September 2023 Emergency Plan Implementing Procedure Revision 0CAN082301, Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 03412023-08-17017 August 2023 Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 0341 2CAN082301, Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29)2023-08-10010 August 2023 Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29) 0CAN072301, Registration of Cask Use2023-07-18018 July 2023 Registration of Cask Use 1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2023-06-29029 June 2023 Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 0CAN062301, Status of Actions to Return to Compliance2023-06-26026 June 2023 Status of Actions to Return to Compliance 0CAN062302, Submittal of Revision 22 of the ANO Fire Hazards Analysis2023-06-20020 June 2023 Submittal of Revision 22 of the ANO Fire Hazards Analysis 1CAN062301, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037)2023-06-0808 June 2023 Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037) 0CAN052303, Annual 10 CFR 50.46 Report for Calendar Year 20222023-05-24024 May 2023 Annual 10 CFR 50.46 Report for Calendar Year 2022 0CAN052302, Emergency Plan Rev. 482023-05-11011 May 2023 Emergency Plan Rev. 48 0CAN052301, Units 1 and 2 - 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 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 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 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 0CAN092201, Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-09-29029 September 2022 Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN092201, Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-09-0808 September 2022 Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 0CAN082201, License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-08-30030 August 2022 License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN082201, Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-08-24024 August 2022 Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 2CAN072201, Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-07-20020 July 2022 Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods 0CAN072201, Registration of Cask Use2022-07-14014 July 2022 Registration of Cask Use 0CAN062202, Registration of Cask Use2022-06-0909 June 2022 Registration of Cask Use 1CAN062201, Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-06-0202 June 2022 Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 1CAN052201, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-0352022-05-31031 May 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-035 2024-01-17
[Table view] |
Text
Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4619 Dale E. James Manager, Licensing Nuclear Safety Assurance Arkansas Nuclear One 1CAN040803 April 18, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Withdrawal of Relief Request ANO1-ISI-011 Arkansas Nuclear One, Unit 1 Docket No. 50-313 License No. DPR-51
REFERENCE:
Entergy letter dated January 22, 2008, Request for Relief from ASME Section XI Table IWB-2500-1 Requirements (1CAN010801)
(TAC No. MD8018)
Dear Sir or Madam:
By the reference letter, Entergy Operations, Inc. (Entergy) requested approval of proposed alternatives to the requirements of the 1992 Edition of ASME Section XI for Arkansas Nuclear One, Unit 1 (ANO-1), specifically the requirements of Examination Category B-J of Table IWB-2500-1 (ANO1-ISI-011).
On September 22, 1999, 10CFR50.55a was revised mandating the implementation of the 1995 Edition, through and including the 1996 Addenda of ASME Section XI, Appendix VIII, Performance Demonstration for Ultrasonic Examination Systems. These requirements are now implemented, as applicable, in the in-service inspection program for ANO-1.
The subject relief request identified a statement in the 1995 Edition with the 1996 Addenda of ASME Section XI, Appendix VIII, Supplement 2 that could not be complied with, e.g., "...the specimen inside surface and identification shall be concealed from the candidate". The applicable technique for examining the reactor vessel nozzle-to-pipe and pipe-to-nozzle welds is remotely from the inside surface. The qualification for the piping welds required access to the ID of the pipe, therefore the inside surface cannot be "concealed". This was addressed in the later addenda (2002) of Section XI, however; this addenda has not been approved by the Staff via a change to 10CFR50.55a.
Code Case N-696, Qualification Requirements for Appendix VIII Piping Examinations Conducted from the Inside Surface,Section XI, Division 1, addresses this very issue. In
1CAN040803 Page 2 of 3 paragraph 39(b) of the code case, it states, The flaw location and specimen identification shall be obscured as to maintain a blind test. These are essentially the same words in the 2002 Addenda of Section XI, Appendix VIII, Supplement 2 as noted above.
At the time the request for alternative was made, the NRC had not approved Code Case N-696 in Regulatory Guide (RG) 1.147. The latest revision to RG 1.147, (Rev. 15) was issued by the NRC in late January 2008, which documents the NRC approval of Code Case N-696.
Based on the latest revision of the RG, Entergy hereby withdraws its request for the NRC approval of relief request ANO1-ISI-011.
The vendor procedures and personnel will be qualified for this application to the requirements of Code Case N-696. These requirements are identical to the requirements that were proposed in the subject relief request. This provides assurance that the piping welds are free of service related flaws and ensures plant safety and reliability.
This letter does not change any previous commitments.
If you have any questions or require additional information, please contact me.
Sincerely, DEJ/rwc
1CAN040803 Page 3 of 3 cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 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