|
|
| (One intermediate revision by the same user not shown) |
| Line 2: |
Line 2: |
| | number = ML071370230 | | | number = ML071370230 |
| | issue date = 05/10/2007 | | | issue date = 05/10/2007 |
| | title = Request for Use of Later Edition to ASME Code, Section Xi for Inservice Inspection Program | | | title = Request for Use of Later Edition to ASME Code, Section XI for Inservice Inspection Program |
| | author name = Laughlin G J | | | author name = Laughlin G |
| | author affiliation = Constellation Energy Group | | | author affiliation = Constellation Energy Group |
| | addressee name = | | | addressee name = |
| Line 15: |
Line 15: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:P.O. Box 63 Lycoming, New York 13093 Constellation Energy Nine Mile Point Nuclear Station May 10, 2007 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 ATTENTION: | | {{#Wiki_filter:P.O. Box 63 Lycoming, New York 13093 Constellation Nine Mile Point Nuclear Station Energy May 10, 2007 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 ATTENTION: Document Control Desk |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Document Control Desk Nine Mile Point Nuclear Station Unit No. 1; Docket No. 50-220 Request for Use of Later Edition to ASME Code, Section XI for the Nine Mile Point Unit 1 Inservice Inspection Program Telecon Between Nine Mile Point Nuclear Station and NRR/NRC (D. Pickett, M. David, M. Mitchell, J. White, T. Bums, and B. Bickett), on April 05, 2007, to "Discuss Inservice Inspection Results for Nine Mile Point Unit 1 Reactor Pressure Vessel Nozzle N2D."
| | Nine Mile Point Nuclear Station Unit No. 1; Docket No. 50-220 Request for Use of Later Edition to ASME Code, Section XI for the Nine Mile Point Unit 1 Inservice Inspection Program |
|
| |
|
| ==REFERENCE:== | | ==REFERENCE:== |
| | Telecon Between Nine Mile Point Nuclear Station and NRR/NRC (D. Pickett, M. David, M. Mitchell, J. White, T. Bums, and B. Bickett), |
| | on April 05, 2007, to "Discuss Inservice Inspection Results for Nine Mile Point Unit 1 Reactor Pressure Vessel Nozzle N2D." |
| | Pursuant to 10 CFR 50.55a(g)(4)(iv), and as clarified in NRC Regulatory Issue Summary (RIS) 2004-12, "Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI," Nine Mile Point Nuclear Station, LLC (NMPNS) hereby requests NRC approval to use a later edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI at Nine Mile Point Unit 1. |
| | This request is associated with an identified flaw indication discovered during the Alternate Risk-Informed Inservice Inspection (ISI) Program's automated ultrasonic examination of the reactor pressure vessel (RPV) nozzle N2D (reactor recirculation) to safe end weld 32-WD-164, during the recently completed refuel outage. |
| | Attachment (1) provides NMPNS's request for approval to use a later Edition of the ASME Code, SectionXI; Attachment (2) provides the results of the analytical evaluation of the subject flaw for your review and approval; Attachment (3) contains the results of an independent review of the reported flaw indication (weld 32-WD-164) performed by the Electric Power Research Institute's (EPRI) |
|
| |
|
| Pursuant to 10 CFR 50.55a(g)(4)(iv), and as clarified in NRC Regulatory Issue Summary (RIS) 2004-12,"Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI," Nine Mile Point Nuclear Station, LLC (NMPNS) hereby requests NRC approval to use a later edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI at Nine Mile Point Unit 1.This request is associated with an identified flaw indication discovered during the Alternate Risk-Informed Inservice Inspection (ISI) Program's automated ultrasonic examination of the reactor pressure vessel (RPV) nozzle N2D (reactor recirculation) to safe end weld 32-WD-164, during the recently completed refuel outage.Attachment (1) provides NMPNS's request for approval to use a later Edition of the ASME Code, SectionXI; Attachment (2) provides the results of the analytical evaluation of the subject flaw for your review and approval; Attachment (3) contains the results of an independent review of the reported flaw indication (weld 32-WD-164) performed by the Electric Power Research Institute's (EPRI)
| |
| Document Control Desk May 10, 2007 Page 2 Nondestructive Examination (NDE) Program personnel; and Attachment (4) contains the automated ultrasonic examination summary report for weld 32-WD-164. | | Document Control Desk May 10, 2007 Page 2 Nondestructive Examination (NDE) Program personnel; and Attachment (4) contains the automated ultrasonic examination summary report for weld 32-WD-164. |
| Should you have any questions regarding this matter, please contact M. H. Miller, Licensing Director, at (315) 349-5219.Manager Engineering Services GJL/GB/Attachments: | | Should you have any questions regarding this matter, please contact M. H. Miller, Licensing Director, at (315) 349-5219. |
| (1)Request for Approval to Use Later Edition of the ASME Code.(2) Flaw Evaluation of the Nine Mile Point Unit 1 Recirculation Inlet Nozzle-to-Safe End Weld (32-WD- 164) Indication and Allowable Flaw Size Calculation, Revision 1, dated April 4, 2007.(3) Evaluation of Dissimilar Metal Weld Examinations Performed at Nine Mile Point Unit 1 During Refueling Outage 19 (N1R19).(4) Automated Utrasonic Weld Examination Summary Report For Recirculation Inlet Nozzle-to-Safe End Weld No. 32-WD-164. | | Manager Engineering Services GJL/GB/ |
| cc: S. J. Collins, NRC Regional Administrator, Region I L. M. Cline, NRC Senior Resident Inspector M. J. David, NRR Project Manager M. A. Mitchell, NRR J. R. White, NRC Region 1 T. F. Bums, NRC Region 1 B. Bickett, NRC Region 1 ATTACHMENT (1)REQUEST FOR APPROVAL TO USE LATER EDITION OF THE ASME CODE Nine Mile Point Nuclear Station, LLC May 10, 2007 ATTACHMENT (1)REQUEST FOR APPROVAL TO USE LATER EDITION OF THE ASME CODE ASME CODE COMPONENT(S) | | Attachments: (1) Request for Approval to Use Later Edition of the ASME Code. |
| AFFECTED System: Reactor Recirculation System Weld Number: 32-WD-164 | | (2) Flaw Evaluation of the Nine Mile Point Unit 1 Recirculation Inlet Nozzle-to-Safe End Weld (32-WD- 164) Indication and Allowable Flaw Size Calculation, Revision 1, dated April 4, 2007. |
| | (3) Evaluation of Dissimilar Metal Weld Examinations Performed at Nine Mile Point Unit 1 During Refueling Outage 19 (N1R19). |
| | (4) Automated Utrasonic Weld Examination Summary Report For Recirculation Inlet Nozzle-to-Safe End Weld No. 32-WD-164. |
| | cc: S. J. Collins, NRC Regional Administrator, Region I L. M. Cline, NRC Senior Resident Inspector M. J. David, NRR Project Manager M. A. Mitchell, NRR J. R. White, NRC Region 1 T. F. Bums, NRC Region 1 B. Bickett, NRC Region 1 |
| | |
| | ATTACHMENT (1) |
| | REQUEST FOR APPROVAL TO USE LATER EDITION OF THE ASME CODE Nine Mile Point Nuclear Station, LLC May 10, 2007 |
| | |
| | ATTACHMENT (1) |
| | REQUEST FOR APPROVAL TO USE LATER EDITION OF THE ASME CODE ASME CODE COMPONENT(S) AFFECTED System: Reactor Recirculation System Weld Number: 32-WD-164 |
|
| |
|
| == Description:== | | == Description:== |
| | Nozzle-to-Safe End Weld Nozzle Location: RPV Inlet Nozzle N2D Nozzle Material: SA 336 Safe End Material: 316 NG Pipe Size & Thickness of weld: 28.0" Dia., 1.70" t II. APPLICABLE CODE EDITION AND ADDENDA The Code of Record for the Nine Mile Point Unit 1 (NMP1) Third Inservice Inspection Interval is the ASME Code, Section XI, 1989 Edition, no Addenda. |
| | III. PROPOSED SUBSEOUENT CODE EDITION AND ADDENDA NMP1 proposes to use 1995 ASME Boiler and Pressure Vessel Code, Section XI, Subsection IWB, "Class 1 Components," Article 3000, "Acceptance Standards," Subarticle 3600, "Analytical Evaluation of Flaws," Subsubarticle 3640, "Evaluation Procedures and Acceptance Criteria for Austenitic Piping" by reference in 10 CFR 50.55a(b)(2) with the following limitations. The request for use and application of Subsubarticle 3640 is specifically limited to the Reactor Recirculation System Nozzle-to-Safe End Weld No. 32-WD-164 and the evaluation of the associated planar flaw indication as detailed in "Flaw Evaluation of the Nine Mile Point Unit 1 Recirculation Inlet Nozzle-to-Safe End Weld (32-WD-164) Indication and Allowable Flaw Size Calculation" (Attachment 2). |
| | IV. RELATED REOUIREMENTS The proposed use of the 1995 Edition of the Code does not affect other parts of the Code. All paragraphs, subparagraphs and related acceptance standards and requirements listed under Subsubarticle 3640 will be met with implementation of ASME Code, Section XI 1995 Edition. |
| | Pursuant to 10 CFR 50.55a(g)(4)(iv), the use of a later Code edition is requested on the basis that the proposed alternative would provide an acceptable level of quality and safety. |
| | V. BASIS FOR REOUEST NMP1 recently completed its first refuel outage of the Third Inspection Period of the Third Ten-Year Inservice Inspection Interval. During the outage, NMPNS performed inservice examinations on the reactor recirculation system welds in accordance with the Alternate Risk-Informed Inservice Inspection Program and the ASME Section XI (1989 Edition no Addenda). |
| | Page 1 of 2 |
|
| |
|
| Nozzle-to-Safe End Weld Nozzle Location:
| | ATTACHMENT (1) |
| RPV Inlet Nozzle N2D Nozzle Material:
| | REQUEST FOR APPROVAL TO USE LATER EDITION OF THE ASME CODE The automated ultrasonic (UT) examinations were performed by WesDyne, in accordance with ASME Section XI, Appendix VIII (1995 Edition thru 1996 Addenda) as modified by the Performance Demonstration Initiative - Dissimilar Metals (PDI). The examination results identified a surface planar flaw indication on nozzle-to-safe end weld 32-WD-164 located on the N2D recirculation nozzle. The results of the UT examination were compared against the acceptance standards of ASME Section XI, Table IWB-3514-2, "Allowable Planar Flaws" and were determined to exceed the acceptance criteria. Attachment (4) provides the documented results of the WesDyne automated UT weld examination. |
| SA 336 Safe End Material:
| | NMPNS, through its review of previous examination records and comparison of the flaw indication to the original fabrication radiographs and associated repair records, has determined that the indication is a fabrication type flaw (incomplete fusion). The flaw resulted from previous weld repairs performed during the recirculation piping and safe end replacement activity in 1982-1983. NMPNS also requested the Electric Power Research Institute's (EPRI) |
| 316 NG Pipe Size & Thickness of weld: 28.0" Dia., 1.70" t II. APPLICABLE CODE EDITION AND ADDENDA The Code of Record for the Nine Mile Point Unit 1 (NMP1) Third Inservice Inspection Interval is the ASME Code, Section XI, 1989 Edition, no Addenda.III. PROPOSED SUBSEOUENT CODE EDITION AND ADDENDA NMP1 proposes to use 1995 ASME Boiler and Pressure Vessel Code, Section XI, Subsection IWB, "Class 1 Components," Article 3000, "Acceptance Standards," Subarticle 3600,"Analytical Evaluation of Flaws," Subsubarticle 3640, "Evaluation Procedures and Acceptance Criteria for Austenitic Piping" by reference in 10 CFR 50.55a(b)(2) with the following limitations.
| | Nondestructive Examination (NDE) Program personnel to provide a technical and independent review of the reported flaw indication. Attachment 3 provides the results of the EPRI NDE Center evaluation. |
| The request for use and application of Subsubarticle 3640 is specifically limited to the Reactor Recirculation System Nozzle-to-Safe End Weld No. 32-WD-164 and the evaluation of the associated planar flaw indication as detailed in "Flaw Evaluation of the Nine Mile Point Unit 1 Recirculation Inlet Nozzle-to-Safe End Weld (32-WD-164)
| | NMPNS, with assistance from Structural Integrity Associates, Inc., performed a flaw evaluation (Attachment 2) in accordance with ASME Code, Section XI, TWB-3600, 1995 Edition. The evaluation results concluded that the flaw would meet the requirements of IWB-3640. |
| Indication and Allowable Flaw Size Calculation" (Attachment 2).IV. RELATED REOUIREMENTS The proposed use of the 1995 Edition of the Code does not affect other parts of the Code. All paragraphs, subparagraphs and related acceptance standards and requirements listed under Subsubarticle 3640 will be met with implementation of ASME Code, Section XI 1995 Edition.Pursuant to 10 CFR 50.55a(g)(4)(iv), the use of a later Code edition is requested on the basis that the proposed alternative would provide an acceptable level of quality and safety.V. BASIS FOR REOUEST NMP1 recently completed its first refuel outage of the Third Inspection Period of the Third Ten-Year Inservice Inspection Interval.
| | VI. DURATION OF THE PROPOSED REOUEST NMP1 requests use of the 1995 ASME Code, Section XI, Subsubsection 3640, 1995 Edition for the analysis of the subject flaw in weld No. 32-WD-l164 through the remainder of the Third Inservice Inspection Interval. |
| During the outage, NMPNS performed inservice examinations on the reactor recirculation system welds in accordance with the Alternate Risk-Informed Inservice Inspection Program and the ASME Section XI (1989 Edition no Addenda).Page 1 of 2 ATTACHMENT (1)REQUEST FOR APPROVAL TO USE LATER EDITION OF THE ASME CODE The automated ultrasonic (UT) examinations were performed by WesDyne, in accordance with ASME Section XI, Appendix VIII (1995 Edition thru 1996 Addenda) as modified by the Performance Demonstration Initiative
| | Page 2 of 2}} |
| -Dissimilar Metals (PDI). The examination results identified a surface planar flaw indication on nozzle-to-safe end weld 32-WD-164 located on the N2D recirculation nozzle. The results of the UT examination were compared against the acceptance standards of ASME Section XI, Table IWB-3514-2, "Allowable Planar Flaws" and were determined to exceed the acceptance criteria. | |
| Attachment (4) provides the documented results of the WesDyne automated UT weld examination. | |
| NMPNS, through its review of previous examination records and comparison of the flaw indication to the original fabrication radiographs and associated repair records, has determined that the indication is a fabrication type flaw (incomplete fusion). The flaw resulted from previous weld repairs performed during the recirculation piping and safe end replacement activity in 1982-1983. | |
| NMPNS also requested the Electric Power Research Institute's (EPRI)Nondestructive Examination (NDE) Program personnel to provide a technical and independent review of the reported flaw indication. | |
| Attachment 3 provides the results of the EPRI NDE Center evaluation. | |
| NMPNS, with assistance from Structural Integrity Associates, Inc., performed a flaw evaluation (Attachment | |
| : 2) in accordance with ASME Code, Section XI, TWB-3600, 1995 Edition. The evaluation results concluded that the flaw would meet the requirements of IWB-3640.VI. DURATION OF THE PROPOSED REOUEST NMP1 requests use of the 1995 ASME Code, Section XI, Subsubsection 3640, 1995 Edition for the analysis of the subject flaw in weld No. 32-WD-l164 through the remainder of the Third Inservice Inspection Interval.Page 2 of 2}}
| |
|
|---|
Category:Inservice/Preservice Inspection and Test Report
MONTHYEARNMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owners Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023
Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owners Activity Report for RFO-27 Inservice Examinations
NMP1L3517, Proposed Alternative Associated with a Weld Overlay Repair to the Torus2023-03-29029 March 2023
Proposed Alternative Associated with a Weld Overlay Repair to the Torus
NMP2L2811, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2022 Owners Activity Report for RFO-18 Inservice Examinations2022-05-13013 May 2022
Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2022 Owners Activity Report for RFO-18 Inservice Examinations
ML21189A0262021-06-28028 June 2021
Fifth Inservice Inspection Interval, First Inservice Inspection Period 2021 Owner'S Activity Report for RFO-26 Inservice Examinations
NMP1L3356, Relief Requests Associated with Pump Periodic Verification Tests for the Fifth Ten-Year Inservice Test Interval2020-10-0808 October 2020
Relief Requests Associated with Pump Periodic Verification Tests for the Fifth Ten-Year Inservice Test Interval
NMP2L2755, Fourth Inservice Inspection Interval, First Inservice Inspection Period, 2020 Owner'S Activity Report for RFO17 Inservice Examinations2020-01-0808 January 2020
Fourth Inservice Inspection Interval, First Inservice Inspection Period, 2020 Owner'S Activity Report for RFO17 Inservice Examinations
NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019
Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879
ML19267A0242019-09-24024 September 2019
End of Interval Relief Associated with the Third Ten-Year Inservice Inspection (ISI) Interval
NMP1L3309, Submittal of the Snubber IST Program Plan for the Unit 1 Fifth 10-Year Interval and the Unit 2 Fourth 10-Year Interval2019-09-0606 September 2019
Submittal of the Snubber IST Program Plan for the Unit 1 Fifth 10-Year Interval and the Unit 2 Fourth 10-Year Interval
NMP2L2700, Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants2019-04-30030 April 2019
Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants
ML18207A4062018-07-17017 July 2018
Third Inservice Inspection Interval, Third Iservice Inspection Period 2018 Owner'S Activity Report for RF0-16 Lnservice Examinations
ML18018A9622018-01-18018 January 2018
Preservice Inspection Plan - Preservice Testing - Component Supports
ML18018A9612018-01-18018 January 2018
Preservice Inspection Plan
ML17164A1812017-06-0606 June 2017
Fourth Inservice Inspection Interval, Third Inservice Inspection Period 2017 Owner'S Activity Report for RF0-24 Inservice Examinations
NMP2L2620, Submittal of Post Extended Power Uprate Steam Dryer Inspection Results and Long-term Steam Dryer Inspection Plan in Accordance with Operating License Conditions 2.C.(20)(f), 2.C.(20)(g) and 2.C.(20)(h)2016-08-0101 August 2016
Submittal of Post Extended Power Uprate Steam Dryer Inspection Results and Long-term Steam Dryer Inspection Plan in Accordance with Operating License Conditions 2.C.(20)(f), 2.C.(20)(g) and 2.C.(20)(h)
ML16216A1492016-07-25025 July 2016
Third Inservice Inspection Interval, Second Inservice Inspection Period 2016 Owner'S Activity Report for RFO-15 Inservice Examinations
ML15191A3852015-07-0909 July 2015
Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2015 Owner'S Activity Report for RFO-23 Inservice Examinations
ML15155A5912015-06-0303 June 2015
End of Interval Relief Request Associated with the Second 10- Year Risk Informed ISI Inspections
ML14203A0082014-07-16016 July 2014
Third Inservice Inspection Interval, Second Inservice Inspection Period 2014 Owner'S Activity Report for RFO14 Inservice Examinations
ML13261A2882013-09-0606 September 2013
Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for Implementation of a Risk-Informed, Safety-Based Inservice Inspection Program Based on ASME Code Case N-716 - Response to Nrc.
ML13231A1862013-08-0909 August 2013
Fourth Inservice Inspection Interval, Second Inservice Inspection Period, 2013 Owner'S Activity Report for RFO-22 Inservice Examinations
ML12335A2882012-11-20020 November 2012
Corrected Copy of 2012 Owner'S Activity Report for Refueling Outage 13 Inservice Examinations
ML12242A2362012-08-16016 August 2012
Owner'S Activity Report for Refueling Outage 13 Inservice Examinations
ML1012700232010-04-29029 April 2010
American Society of Mechanical Engineers Code, Section XI, Inservice Inspection Program for Third Ten-Year Inservice Inspection Interval - 10 CFR 50.55a Request Number ISI-25, Response to NRC Request for Additional Information
ML1003200522010-01-28028 January 2010
American Society of Mechanical Engineers Code, Section XI, Inservice Inspection Program for Fourth Ten-Year Inservice Inspection Interval & Associated 10 CFR 50.55a Requests - Additional Supplemental Information Relating to Relief Request 1
ML0933505232009-11-24024 November 2009
American Society of Mechanical Engineers Code, Section XI, Inservice Inspection Program for the Third Ten-Year Inservice Inspection Interval - 10 CFR 50.55a Request Number ISI-25
ML0924001492009-08-25025 August 2009
Third 10-Year Inservice Testing Program - Request for Alternative Number MSS-VR-02 Regarding Testing of Main Steam Safety Relief Valves
ML0919503072009-07-0606 July 2009
Third Inservice Inspection Interval Third Inservice Inspection Period 2009 Owner'S Activity Report for RFO-20 Inservice Examinations
ML0918300492009-06-25025 June 2009
Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair & Inservice Inspection of Control Rod Drive Stub Tubes for the License Renewal Period of Extended Operation - Response.
ML0908608602009-03-16016 March 2009
Submittal of American Society of Mechanical Engineers (ASME) Code, Section XI, Inservice Inspection Program for the Fourth Ten-Year Inservice Inspection Interval and Associated 10 CFR 50.55a Requests
ML0832305122008-11-13013 November 2008
Transmittal of Inservice Testing (IST) Program Update and Associated 10 CFR 50.55a Requests - Response to NRC Request for Additional Information
ML0826711202008-09-16016 September 2008
Extension of Permanent Relief from Inservice Inspection Requirements of 10 CFR 50.55a(g) for the Volumetric Examination of Reactor Pressure Vessel Shell Circumferential Welds for the License Renewal Period of Extended Operation
ML0819309652008-07-11011 July 2008
Second Inservice Inspection Interval 2008 Owners' Activity Report for Inservice Examinations
ML0818400222008-06-30030 June 2008
American Society of Mechanical Engineers Code, Section XI, Inservice Inspection Program for Third Ten-Year Inservice Inspection Interval & Associated 10 CFR 50.55a Requests - Response to NRC Requests for Additional Information
ML0819005682008-06-30030 June 2008
Inservice Testing Program Update and Associated 10 CFR 50.55a Requests for the Next Ten-Year IST Intervals
ML0802504102008-01-25025 January 2008
American Society of Mechanical Engineers (ASME) Code, Section XI, Inservice Inspection Program for the Third Ten-Year Inservice Inspection Interval and Associated 10 CFR 50.55a Requests - Replacement of Appendix H, Relief Requests / Alterna
ML0713702302007-05-10010 May 2007
Request for Use of Later Edition to ASME Code, Section XI for Inservice Inspection Program
ML0620101392006-07-13013 July 2006
Owner'S Activity Report for Inservice Examinations
ML0522104362005-07-26026 July 2005
Owner'S Activity Report for Inservice Examinations
ML0323104382003-08-0808 August 2003
Relief, Request for Relief from Qualification Requirements for Dissimilar Metal Piping Welds
ML0321101322003-07-23023 July 2003
Submittal of Inservice Inspection Owners Activity Reports
ML0307704482003-03-0606 March 2003
Inservice Inspection Relief Requests Regarding Inner Radius Examination of Class I Reactor Pressure Vessel Nozzles
ML0037349602000-07-18018 July 2000
Inservice Inspection (ISI) Summary Report
ML18018B0531999-10-15015 October 1999
Third Inservice Inspection Interval - Ten-Year Inservice Inspection Plan and Schedule
ML18018B0521999-09-27027 September 1999
Third Inservice Inspection Interval
ML18018B0131986-07-29029 July 1986
Preservice Inspection Plan for Nuclear Piping Systems and the Reactor Pressure Vessel Vol. 2
2023-07-14
[Table view]
Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024
Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3
RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024
Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024
Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)
ML24275A2442024-10-0303 October 2024
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing
IR 05000220/20243022024-10-0303 October 2024
Initial Operator Licensing Examination Report 05000220/2024302
ML24190A0012024-09-26026 September 2024
Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation
NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024
Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024
Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
ML24249A1362024-09-0404 September 2024
EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21
IR 05000220/20240052024-08-29029 August 2024
Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005)
IR 05000220/20240102024-08-22022 August 2024
Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024
Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan
ML24222A6772024-08-0909 August 2024
Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
IR 05000220/20240022024-08-0505 August 2024
Integrated Inspection Report 05000220/2024002 and 05000410/2024002
ML24215A3002024-08-0202 August 2024
Operator Licensing Examination Approval
NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024
Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
ML24213A1412024-07-31031 July 2024
Requalification Program Inspection
NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024
Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations
ML24198A0852024-07-16016 July 2024
Senior Reactor and Reactor Operator Initial License Examinations
RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024
Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions
RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024
License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling
IR 05000220/20244012024-05-30030 May 2024
Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only)
ML24079A0762024-05-23023 May 2024
Issuance of Amendments to Adopt TSTF 264
NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024
Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request
NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024
Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable
ML24158A2052024-05-15015 May 2024
Annual Radioactive Environmental Operating Report
NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024
2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2
IR 05000220/20240012024-05-10010 May 2024
Integrated Inspection Report 05000220/2024001 and 05000410/2024001
RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024
Updated Notice of Intent to Pursue Subsequent License Renewal Applications
RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024
Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024
Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum
RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024
Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024
Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report
NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024
2023 Annual Environmental Operating Report
NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024
Core Operating Limits Report
ML24103A2042024-04-12012 April 2024
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024
Constellation Energy Generation, LLC - Annual Property Insurance Status Report
ML24092A3352024-04-0101 April 2024
NRC Office of Investigations Case No. 1-2023-002
ML24074A2812024-03-14014 March 2024
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024
Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable
IR 05000220/20230062024-02-28028 February 2024
Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006)
IR 05000220/20230042024-02-0101 February 2024
Integrated Inspection Report 05000220/2023004 and 05000410/2023004
NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024
Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024
Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater
NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024
CFR 50.46 Annual Report
ML24004A2122024-01-0808 January 2024
Senior Reactor and Reactor Operator Initial License Examinations
ML23354A0012024-01-0404 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 122023-12-15015 December 2023
Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12
NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023
Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station
2024-09-04
[Table view] |
Text
P.O. Box 63 Lycoming, New York 13093 Constellation Nine Mile Point Nuclear Station Energy May 10, 2007 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 ATTENTION: Document Control Desk
SUBJECT:
Nine Mile Point Nuclear Station Unit No. 1; Docket No. 50-220 Request for Use of Later Edition to ASME Code,Section XI for the Nine Mile Point Unit 1 Inservice Inspection Program
REFERENCE:
Telecon Between Nine Mile Point Nuclear Station and NRR/NRC (D. Pickett, M. David, M. Mitchell, J. White, T. Bums, and B. Bickett),
on April 05, 2007, to "Discuss Inservice Inspection Results for Nine Mile Point Unit 1 Reactor Pressure Vessel Nozzle N2D."
Pursuant to 10 CFR 50.55a(g)(4)(iv), and as clarified in NRC Regulatory Issue Summary (RIS) 2004-12, "Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI," Nine Mile Point Nuclear Station, LLC (NMPNS) hereby requests NRC approval to use a later edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI at Nine Mile Point Unit 1.
This request is associated with an identified flaw indication discovered during the Alternate Risk-Informed Inservice Inspection (ISI) Program's automated ultrasonic examination of the reactor pressure vessel (RPV) nozzle N2D (reactor recirculation) to safe end weld 32-WD-164, during the recently completed refuel outage.
Attachment (1) provides NMPNS's request for approval to use a later Edition of the ASME Code, SectionXI; Attachment (2) provides the results of the analytical evaluation of the subject flaw for your review and approval; Attachment (3) contains the results of an independent review of the reported flaw indication (weld 32-WD-164) performed by the Electric Power Research Institute's (EPRI)
Document Control Desk May 10, 2007 Page 2 Nondestructive Examination (NDE) Program personnel; and Attachment (4) contains the automated ultrasonic examination summary report for weld 32-WD-164.
Should you have any questions regarding this matter, please contact M. H. Miller, Licensing Director, at (315) 349-5219.
Manager Engineering Services GJL/GB/
Attachments: (1) Request for Approval to Use Later Edition of the ASME Code.
(2) Flaw Evaluation of the Nine Mile Point Unit 1 Recirculation Inlet Nozzle-to-Safe End Weld (32-WD- 164) Indication and Allowable Flaw Size Calculation, Revision 1, dated April 4, 2007.
(3) Evaluation of Dissimilar Metal Weld Examinations Performed at Nine Mile Point Unit 1 During Refueling Outage 19 (N1R19).
(4) Automated Utrasonic Weld Examination Summary Report For Recirculation Inlet Nozzle-to-Safe End Weld No. 32-WD-164.
cc: S. J. Collins, NRC Regional Administrator, Region I L. M. Cline, NRC Senior Resident Inspector M. J. David, NRR Project Manager M. A. Mitchell, NRR J. R. White, NRC Region 1 T. F. Bums, NRC Region 1 B. Bickett, NRC Region 1
ATTACHMENT (1)
REQUEST FOR APPROVAL TO USE LATER EDITION OF THE ASME CODE Nine Mile Point Nuclear Station, LLC May 10, 2007
ATTACHMENT (1)
REQUEST FOR APPROVAL TO USE LATER EDITION OF THE ASME CODE ASME CODE COMPONENT(S) AFFECTED System: Reactor Recirculation System Weld Number: 32-WD-164
Description:
Nozzle-to-Safe End Weld Nozzle Location: RPV Inlet Nozzle N2D Nozzle Material: SA 336 Safe End Material: 316 NG Pipe Size & Thickness of weld: 28.0" Dia., 1.70" t II. APPLICABLE CODE EDITION AND ADDENDA The Code of Record for the Nine Mile Point Unit 1 (NMP1) Third Inservice Inspection Interval is the ASME Code,Section XI, 1989 Edition, no Addenda.
III. PROPOSED SUBSEOUENT CODE EDITION AND ADDENDA NMP1 proposes to use 1995 ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWB, "Class 1 Components," Article 3000, "Acceptance Standards," Subarticle 3600, "Analytical Evaluation of Flaws," Subsubarticle 3640, "Evaluation Procedures and Acceptance Criteria for Austenitic Piping" by reference in 10 CFR 50.55a(b)(2) with the following limitations. The request for use and application of Subsubarticle 3640 is specifically limited to the Reactor Recirculation System Nozzle-to-Safe End Weld No. 32-WD-164 and the evaluation of the associated planar flaw indication as detailed in "Flaw Evaluation of the Nine Mile Point Unit 1 Recirculation Inlet Nozzle-to-Safe End Weld (32-WD-164) Indication and Allowable Flaw Size Calculation" (Attachment 2).
IV. RELATED REOUIREMENTS The proposed use of the 1995 Edition of the Code does not affect other parts of the Code. All paragraphs, subparagraphs and related acceptance standards and requirements listed under Subsubarticle 3640 will be met with implementation of ASME Code,Section XI 1995 Edition.
Pursuant to 10 CFR 50.55a(g)(4)(iv), the use of a later Code edition is requested on the basis that the proposed alternative would provide an acceptable level of quality and safety.
V. BASIS FOR REOUEST NMP1 recently completed its first refuel outage of the Third Inspection Period of the Third Ten-Year Inservice Inspection Interval. During the outage, NMPNS performed inservice examinations on the reactor recirculation system welds in accordance with the Alternate Risk-Informed Inservice Inspection Program and the ASME Section XI (1989 Edition no Addenda).
Page 1 of 2
ATTACHMENT (1)
REQUEST FOR APPROVAL TO USE LATER EDITION OF THE ASME CODE The automated ultrasonic (UT) examinations were performed by WesDyne, in accordance with ASME Section XI, Appendix VIII (1995 Edition thru 1996 Addenda) as modified by the Performance Demonstration Initiative - Dissimilar Metals (PDI). The examination results identified a surface planar flaw indication on nozzle-to-safe end weld 32-WD-164 located on the N2D recirculation nozzle. The results of the UT examination were compared against the acceptance standards of ASME Section XI, Table IWB-3514-2, "Allowable Planar Flaws" and were determined to exceed the acceptance criteria. Attachment (4) provides the documented results of the WesDyne automated UT weld examination.
NMPNS, through its review of previous examination records and comparison of the flaw indication to the original fabrication radiographs and associated repair records, has determined that the indication is a fabrication type flaw (incomplete fusion). The flaw resulted from previous weld repairs performed during the recirculation piping and safe end replacement activity in 1982-1983. NMPNS also requested the Electric Power Research Institute's (EPRI)
Nondestructive Examination (NDE) Program personnel to provide a technical and independent review of the reported flaw indication. Attachment 3 provides the results of the EPRI NDE Center evaluation.
NMPNS, with assistance from Structural Integrity Associates, Inc., performed a flaw evaluation (Attachment 2) in accordance with ASME Code,Section XI, TWB-3600, 1995 Edition. The evaluation results concluded that the flaw would meet the requirements of IWB-3640.
VI. DURATION OF THE PROPOSED REOUEST NMP1 requests use of the 1995 ASME Code,Section XI, Subsubsection 3640, 1995 Edition for the analysis of the subject flaw in weld No. 32-WD-l164 through the remainder of the Third Inservice Inspection Interval.
Page 2 of 2
