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| | issue date = 09/30/2016 | | | issue date = 09/30/2016 |
| | title = PWR MSIP Analysis and Measurements | | | title = PWR MSIP Analysis and Measurements |
| | author name = Benson M L, Raynaud P A, Rudland D L | | | author name = Benson M, Raynaud P, Rudland D |
| | author affiliation = NRC/RES/DE | | | author affiliation = NRC/RES/DE |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:PWR MSIP Analysis and MeasurementsDavid L. Rudland, Mike Benson and Patrick RaynaudOffice of Nuclear Regulatory ResearchDivision of EngineeringU.S.NRCMeeting On Mechanical Stress Improvement Processes And The Calvert Cliffs ExperienceWednesday, September 28, 20162160578193 PWR MSIPIn 2007-8, RES responded to an NRR request to | | {{#Wiki_filter:PWR MSIP Analysis and Measurements 2160578193 David L. Rudland, Mike Benson and Patrick Raynaud Office of Nuclear Regulatory Research Division of Engineering U.S.NRC Meeting On Mechanical Stress Improvement Processes And The Calvert Cliffs Experience Wednesday, September 28, 2016 |
| -Develop criteria for evaluating the effectiveness of proposed Stress Improvement (MSIP) processes in producing compressive residual stresses and assistance in confirming appropriate changes in inspection frequency that may accompany application of effective Stress Improvementprocesses | | |
| .RES developed plan, conducted numerical analyses, and conducted experiments to meet the needRES confirmed the efficacy of the MSIP approach2 PWR MSIP Numerical StudiesResults summarized in
| | PWR MSIP |
| -Battelle report, "Evaluation of the mechanical stress improvement process (MSIP) as a mitigation strategy for primary water stress corrosion cracking in pressurized water reactors," ML092990638Investigated three geometries | | * In 2007-8, RES responded to an NRR request to |
| -Hot Leg-Pressurizer Surge | | - Develop criteria for evaluating the effectiveness of proposed Stress Improvement (MSIP) processes in producing compressive residual stresses and assistance in confirming appropriate changes in inspection frequency that may accompany application of effective Stress Improvement processes. |
| -Pressurizer Safety Nozzle3 PWR MSIP Numerical Studies 4All axi-symmetric analyses on pipeModelled both welds and MSIP Conducted a variety of sensitivity analysesConducted numerical flaw analyses PWR MSIP Sample Results 5Safety Nozzle GeometryHoop StressAxial Stress PWR MSIP Strain MeasurementsResults summarized in | | * RES developed plan, conducted numerical analyses, and conducted experiments to meet the need |
| -PNNL report, "Surge Nozzle NDE Specimen Mechanical Stress Improvement Analysis," ML111960318Pressurizer Surge NozzleSome difficulty was encountered in calculating stresses from strain due to plasticity | | * RES confirmed the efficacy of the MSIP approach 2 |
| -Predictions were reasonable 6 | | |
| PWR MSIP Strain Measurements 7Strain gage locationNumerical analysesComparison PWR MSIP UT MeasurementsResults Summarized in | | PWR MSIP Numerical Studies |
| -PNNL report, "Surge Nozzle NDE Specimen Mechanical Stress Improvement Analysis," ML113010152Ignalina(shop and field SS welds) and Pressurizer surge (from strain gage study)Service induced IGSCC and implanted flaws8 PWR MSIP UT Measurement 9The INPP data displayed a significant reduction in flaw length and amplitude after MSIP application and one flaw had become transparent to ultrasound The surge line specimen showed almost no change in length or depth after MSIP -attributed to initial stress state and implanted flaw misalignment1.5 MHz, Line Scan Data after MSIP PWR MSIP Summary ReportsAssessment of MSIP:-A PNNL Report, "Assessment of the Mechanical Stress Improvement Process for Mitigating Primary Water Stress Corrosion Cracking in Nickel Alloy Butt Welds in Piping Systems Approved for Leak-Before-Break," ML13330A972 | | * Results summarized in |
| -Uses previous work to draw conclusions on efficacy of MSIP and assesses inspection intervals per CC N770 PWSCC Mitigation | | - Battelle report, Evaluation of the mechanical stress improvement process (MSIP) as a mitigation strategy for primary water stress corrosion cracking in pressurized water reactors, ML092990638 |
| -NUREG/CR-7187 -Managing PWSCC in Butt Welds by Mitigation and Inspection10}} | | * Investigated three geometries |
| | - Hot Leg |
| | - Pressurizer Surge |
| | - Pressurizer Safety Nozzle 3 |
| | |
| | PWR MSIP Numerical Studies All axi-symmetric analyses on pipe Modelled both welds and MSIP Conducted numerical flaw analyses Conducted a variety of sensitivity analyses 4 |
| | |
| | PWR MSIP Sample Results Hoop Stress Axial Stress Safety Nozzle Geometry 5 |
| | |
| | PWR MSIP Strain Measurements |
| | * Results summarized in |
| | - PNNL report, Surge Nozzle NDE Specimen Mechanical Stress Improvement Analysis, ML111960318 |
| | * Pressurizer Surge Nozzle |
| | * Some difficulty was encountered in calculating stresses from strain due to plasticity - Predictions were reasonable 6 |
| | |
| | PWR MSIP Strain Measurements Strain gage location Comparison Numerical analyses 7 |
| | |
| | PWR MSIP UT Measurements |
| | * Results Summarized in |
| | - PNNL report, Surge Nozzle NDE Specimen Mechanical Stress Improvement Analysis, ML113010152 |
| | * Ignalina (shop and field SS welds) and Pressurizer surge (from strain gage study) |
| | * Service induced IGSCC and implanted flaws 8 |
| | |
| | PWR MSIP UT Measurement |
| | * The INPP data displayed a significant reduction in flaw length and amplitude after MSIP application and one flaw had become 1.5 MHz, Line Scan Data after MSIP transparent to ultrasound |
| | * The surge line specimen showed almost no change in length or depth after MSIP - attributed to initial stress state and implanted flaw misalignment 9 |
| | |
| | PWR MSIP Summary Reports |
| | * Assessment of MSIP: |
| | - A PNNL Report, Assessment of the Mechanical Stress Improvement Process for Mitigating Primary Water Stress Corrosion Cracking in Nickel Alloy Butt Welds in Piping Systems Approved for Leak-Before-Break, ML13330A972 |
| | - Uses previous work to draw conclusions on efficacy of MSIP and assesses inspection intervals per CC N770 |
| | * PWSCC Mitigation |
| | - NUREG/CR-7187 - Managing PWSCC in Butt Welds by Mitigation and Inspection 10}} |
|
---|
Category:Meeting Briefing Package/Handouts
MONTHYEARML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22013A3942022-01-13013 January 2022 Presentation Information for Pre-Submittal Meeting Regarding Relief Request to Use the Carbon Fiber Reinforced Polymer (Cfrp) Composite System ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21144A0172021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request Pre-Submittal Meeting ML21134A0162021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request - NRC Pre-submittal Meeting Telecon May 24, 2021 (EPID L-2021-LRM-0051) (Slides) ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20246G8772020-09-0303 September 2020 Licensee'S Presentation for September 3, 2020 Public Telephone Conference ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML19318F9512019-11-20020 November 2019 Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency ML19317C9952019-11-12012 November 2019 In-Service Testing Supplemental Position Indication Relief Request NRC Pre-Application Meeting November 18, 2019 ML19246B7162019-08-29029 August 2019 Meeting Between NRC and Exelon Regarding Calvert Cliffs-2 LAR to Use Framatome ATF LTAs ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19151A6602019-05-31031 May 2019 BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19022A2002019-01-23023 January 2019 Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18276A0712018-10-0404 October 2018 Exelon'S Presentation for October 4, 2018 Public Pre-Submittal Meeting on Planned Calvert Cliffs 10CFR50.69 LAR ML18171A0842018-06-21021 June 2018 GSI-191 Program Use of Risk Metrics for Containment Sump Tech Spec Operability Determination June 21, 2018 Public Meeting Slides (MF8521, MF8522; L-2016-LRM-0001) ML18190A3922018-06-14014 June 2018 Licensee Presentation Material for June 14, 2018 Public Meeting ML18136A4932018-05-16016 May 2018 Licensee'S Slides for Pre-Application Meeting W/Exelon Re Planned GSI-191 LAR for Calvert Cliffs (L-2016-LRM-0001) ML18096A0222018-04-0404 April 2018 Annual Assessment Meeting 04/04/2018 Handouts ML18096A9902018-03-12012 March 2018 NRC Pre-Submittal Call Briefing Notes, Calvert Cliffs Emergency Planning Future Licensing Actions ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML17143A1612017-05-23023 May 2017 Annual Assessment Meeting Handout and Sign in Sheet ML16274A0012016-09-30030 September 2016 PWR MSIP Analysis and Measurements ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML15321A3702015-12-0101 December 2015 GSI-191 Program Strainer Head Loss Testing and Option 2b Closure Approach ML15308A1072015-11-0505 November 2015 TSTF-505 LAR - NRC Pre-Submittal, November 5, 2015 Meeting Slides ML15282A0832015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application - Final ML15279A4992015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application ML15222A5472015-08-31031 August 2015 GSI 191 Program Chemical Effects Testing Update Option 2b Closure Approach ML15152A0822015-06-0404 June 2015 Presentation for the June 4, 2015 Public Meeting Regarding the National Fire Protection Association Standard 805 License Amendment Request ML14230A9132014-08-18018 August 2014 Enclosure - Fuel Performance and Cask Internals - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L ML14230A9112014-08-18018 August 2014 Enclosure - Example AMP - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 ML14230A9102014-08-18018 August 2014 Enclosure - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 2024-01-30
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides NEI 99-01, Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides2023-02-21021 February 2023 Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22124A1492022-05-10010 May 2022 (Ccnpp) Control Element Assembly (CEA) Recovery Time Improvement Project LAR Pre-Submittal Non-Proprietary (Public) ML22124A1482022-05-10010 May 2022 (Ccnpp) Control Element Assembly (CEA) Recovery Time Improvement Project LAR Pre-Submittal Redacted (Public) ML22013A3942022-01-13013 January 2022 Presentation Information for Pre-Submittal Meeting Regarding Relief Request to Use the Carbon Fiber Reinforced Polymer (Cfrp) Composite System ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML21144A0172021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request Pre-Submittal Meeting ML21134A0162021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request - NRC Pre-submittal Meeting Telecon May 24, 2021 (EPID L-2021-LRM-0051) (Slides) ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20246G8772020-09-0303 September 2020 Licensee'S Presentation for September 3, 2020 Public Telephone Conference ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20163A6542020-06-18018 June 2020 2020 NRC Annual Assessment Webinar Presentation - Pennsylvania and Maryland Facilities (Beaver Valley, Calvert Cliffs, Limerick, Peach Bottom, Susquehanna) ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML19246B7162019-08-29029 August 2019 Meeting Between NRC and Exelon Regarding Calvert Cliffs-2 LAR to Use Framatome ATF LTAs ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18276A0712018-10-0404 October 2018 Exelon'S Presentation for October 4, 2018 Public Pre-Submittal Meeting on Planned Calvert Cliffs 10CFR50.69 LAR ML18171A0842018-06-21021 June 2018 GSI-191 Program Use of Risk Metrics for Containment Sump Tech Spec Operability Determination June 21, 2018 Public Meeting Slides (MF8521, MF8522; L-2016-LRM-0001) ML18136A4932018-05-16016 May 2018 Licensee'S Slides for Pre-Application Meeting W/Exelon Re Planned GSI-191 LAR for Calvert Cliffs (L-2016-LRM-0001) ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML16328A2832016-11-18018 November 2016 Supplemental Presentation Slides for 10/25/2016 Public Meeting Via E-mail from K.Greene to R.Guzman Calvert Cliffs GSI-191 Resolution Update ML16307A4902016-10-25025 October 2016 Presentation Slides from Public Meeting Calvert Cliffs GSI-191 Resolution Update ML16274A0012016-09-30030 September 2016 PWR MSIP Analysis and Measurements ML16242A1782016-09-0101 September 2016 Presentation Slides from Public Meeting Regarding Calvert Cliffs GSI-191 Resolution Update ML16198A0012016-07-18018 July 2016 Presentation Slides from Public Meeting Regarding Calvert Cliffs GSI-191 Resolution Update ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML15321A3702015-12-0101 December 2015 GSI-191 Program Strainer Head Loss Testing and Option 2b Closure Approach ML15308A1072015-11-0505 November 2015 TSTF-505 LAR - NRC Pre-Submittal, November 5, 2015 Meeting Slides ML15279A4992015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application ML15282A0832015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application - Final ML15222A5472015-08-31031 August 2015 GSI 191 Program Chemical Effects Testing Update Option 2b Closure Approach ML15152A0822015-06-0404 June 2015 Presentation for the June 4, 2015 Public Meeting Regarding the National Fire Protection Association Standard 805 License Amendment Request ML14230A9132014-08-18018 August 2014 Enclosure - Fuel Performance and Cask Internals - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L ML14230A9112014-08-18018 August 2014 Enclosure - Example AMP - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 ML14230A9102014-08-18018 August 2014 Enclosure - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 ML14230A9092014-08-18018 August 2014 Enclosure - Generic Concrete AMP CC ISFSI - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 ML14230A9082014-08-18018 August 2014 Enclosure - Elements of an AMP CC ISFSI - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 2024-01-30
[Table view] |
Text
PWR MSIP Analysis and Measurements 2160578193 David L. Rudland, Mike Benson and Patrick Raynaud Office of Nuclear Regulatory Research Division of Engineering U.S.NRC Meeting On Mechanical Stress Improvement Processes And The Calvert Cliffs Experience Wednesday, September 28, 2016
PWR MSIP
- In 2007-8, RES responded to an NRR request to
- Develop criteria for evaluating the effectiveness of proposed Stress Improvement (MSIP) processes in producing compressive residual stresses and assistance in confirming appropriate changes in inspection frequency that may accompany application of effective Stress Improvement processes.
- RES developed plan, conducted numerical analyses, and conducted experiments to meet the need
- RES confirmed the efficacy of the MSIP approach 2
PWR MSIP Numerical Studies
- Battelle report, Evaluation of the mechanical stress improvement process (MSIP) as a mitigation strategy for primary water stress corrosion cracking in pressurized water reactors, ML092990638
- Investigated three geometries
- Hot Leg
- Pressurizer Surge
- Pressurizer Safety Nozzle 3
PWR MSIP Numerical Studies All axi-symmetric analyses on pipe Modelled both welds and MSIP Conducted numerical flaw analyses Conducted a variety of sensitivity analyses 4
PWR MSIP Sample Results Hoop Stress Axial Stress Safety Nozzle Geometry 5
PWR MSIP Strain Measurements
- PNNL report, Surge Nozzle NDE Specimen Mechanical Stress Improvement Analysis, ML111960318
- Some difficulty was encountered in calculating stresses from strain due to plasticity - Predictions were reasonable 6
PWR MSIP Strain Measurements Strain gage location Comparison Numerical analyses 7
PWR MSIP UT Measurements
- PNNL report, Surge Nozzle NDE Specimen Mechanical Stress Improvement Analysis, ML113010152
- Ignalina (shop and field SS welds) and Pressurizer surge (from strain gage study)
- Service induced IGSCC and implanted flaws 8
PWR MSIP UT Measurement
- The INPP data displayed a significant reduction in flaw length and amplitude after MSIP application and one flaw had become 1.5 MHz, Line Scan Data after MSIP transparent to ultrasound
- The surge line specimen showed almost no change in length or depth after MSIP - attributed to initial stress state and implanted flaw misalignment 9
PWR MSIP Summary Reports
- A PNNL Report, Assessment of the Mechanical Stress Improvement Process for Mitigating Primary Water Stress Corrosion Cracking in Nickel Alloy Butt Welds in Piping Systems Approved for Leak-Before-Break, ML13330A972
- Uses previous work to draw conclusions on efficacy of MSIP and assesses inspection intervals per CC N770
- NUREG/CR-7187 - Managing PWSCC in Butt Welds by Mitigation and Inspection 10