ML21217A259
| ML21217A259 | |
| Person / Time | |
|---|---|
| Issue date: | 08/09/2021 |
| From: | Boggs S NRC/NRR/DNRL |
| To: | |
| Hiser A | |
| Shared Package | |
| ML21217A247 | List: |
| References | |
| Download: ML21217A259 (18) | |
Text
Global Expertise
- One Voice 2021 Materials Programs Technical Information Exchange PWROG Materials Committee Update Scott Boggs - PWROG MSC Chair (NextEra)
- MSC PWROG Core/Planning Team Organization and Key Contacts 2021 Materials Programs Technical Information Exchange - PWROG Overview
PWROG MSC Key Focus Areas with NRC Interaction in 2021(1/3)
Transitioning RV Integrity to Direct Fracture Toughness
- The purpose of this ongoing program is to develop an acceptable method for any licensee to use irradiated fracture toughness data to improve or demonstrate margin in P-T curves (more detailed update to be provided in another presentation) o Concept presented to NRC in March 2016 o Pre-submittal meeting held in October 2020 (OG-20-239) o Topical Report PWROG-18068-NP, Revision 0, Use of Direct Fracture Toughness for Evaluation of RPV Integrity submitted for review and approval in July 2021 under OG-21-144 2021 Materials Programs Technical Information Exchange - PWROG Overview
PWROG MSC Key Focus Areas with NRC Interaction in 2021(2/3)
WCAP-17096-NP-A Interim Guidance and Document Update
- The purpose of this ongoing program is to update WCAP-17096-NP to be consistent with MRP-227, Rev. 1, include recent interim guidance and operating experience as appropriate. The TR also emphasizes the intended goal is to develop methodologies that will remain applicable to initial and subsequent license renewal.
o WCAP-17096-NP, Revision 3, Reactor Internals Acceptance Criteria Methodology and Data Requirements, was submitted to the NRC in July 2019 under OG-19-164 o The TR was accepted for the accelerated review process and a fee waiver was granted o NRC provided 14 RAIs for PWROG to address in October 2020 Teleconference held with NRC in November 2020 to discuss draft RAIs (OG-20-288)
Responses to RAIs 1-12 and 14 provided to the NRC in April 2021 under OG-21-81 Draft response to RAI 13 provided to the NRC in May 2021. NRC has requested additional dialogue on this response PWROG MSC working with EPRI on BWRVIP-100 Non-Conservatism. This issue is affecting the review of WCAP-17096-NP.
2021 Materials Programs Technical Information Exchange - PWROG Overview
PWROG MSC Key Focus Areas with NRC Interaction in 2021(3/3)
SLR Activities
- PWROG-19047-P/NP, Revision 0, North Anna Units 1 and 2 Reactor Vessels Low Upper-Shelf Fracture Toughness Equivalent Margin Analysis o The purpose of this topical report (TR) is to document the equivalent margins analysis (EMA) for the North Anna Units 1 and 2 reactor vessel (RV) inlet and outlet nozzle Rotterdam welds, nozzle forgings and nozzle belt forgings (a.k.a., upper shell forgings) o Topical Report was issued to the NRC for review and approval in May 2020 under OG 167 o RAIs received in November 2020 and responses provided in December 2020 under OG-20-284 o Draft SE received in May 2021 and final received in July 2021, PWROG working on issuing the Approved version by the end of August 2021 2021 Materials Programs Technical Information Exchange - PWROG Overview
PWROG MSC NEI 03-08 Guidance Documents - Mandatory & Needed (1/3)
Implementation Doc Number Rev Document Title Date Comments Level Documents Incorporated Within (i.e., issued prior to the initiative) or Under the Materials Initiative (i.e., issued since the initiative)
WCAP-12639-P 0 Westinghouse Owners Group Pressurizer Surge Line Thermal Jun 2008 Mandatory OG-08-203, 4/8/2003 Stratification Generic Detailed Analysis Program MUHP-1091 Summary Report WCAP-17451-P 2 Guidance: Reactor Internals Guide Tube Wear-Westinghouse November Needed OG-18-276, 11/9/2018 Domestic Fleet Operational Projections (WCAP-17451-P, 2018 Revision 2)
WCAP-14950 0 Mitigation and Evaluation of Pressurizer Insurge/Outsurge Jun 2008 Needed OG-08-203, 4/8/2003 Transients 51-5003700-01 1 CRDM Life Extension Action Plan Jan 2006 Needed OG-10-119, 3/29/2010 WCAP-16180-NP 0 Operability Assessment for Combustion Engineering Plants Dec 2003 Mandatory WOG-03-643, 12/23/2003 with Hypothetical Circumferential Flaw Indications in Pressurizer Heater Sleeves WCAP-15988-NP 2 Generic Guidance for an Effective Boric Acid Inspection Dec 2013 Mandatory OG-12-247, 6/20/12 Program for Pressurized Water Reactors WCAP-16423-NP 0 Standard Process and Methods for Calculating RCS Leak Rate Dec 2008 Needed OG-08-400, 11/19/2008 for Pressurized Water Reactors 2021 Materials Programs Technical Information Exchange - PWROG Overview
PWROG MSC NEI 03-08 Guidance Documents - Mandatory & Needed (2/3)
Implementation Doc Number Rev Document Title Date Comments Level Documents Incorporated Within (i.e., issued prior to the initiative) or Under the Materials Initiative (i.e., issued since the initiative)
WCAP-16465-NP 0 Standard RCS Leakage Action Levels and Response Dec 2008 Needed OG-08-400, 11/19/2008 Guidelines for Pressurized Water Reactors WCAP-16913-P 1 Operability Assessment and Plant Applicability Evaluation for Jan 2010 Needed OG-09-140, 4/6/2009 Pressurizer Heater Sleeve Leakage in Westinghouse Designed Pressurizers 51-5030027-01 1 Evaluation of RV Internals Bolting for the B&WOG (Note the May 2005 Needed OG-09-158, 4/17/2009 needed recommendations for inspection of the high- strength bolt location is now superseded by MRP-227-A)
OG-12-330 0 Generic Guidance for Valves that have Seal Encapsulation Aug 2012 Needed OG-12-330, 8/16/2012 Devices PWROG-16003-P 2 Evaluation of Potential Thermal Sleeve Flange Wear May 2019 Needed OG-19-101, 05/13/2019, Non-Proprietary Appendix incorporates the MRP 2018-027 inspection guidance as Needed OG-20-113 - NEI 03-08 Needed and Good Practice Guidance: Thermal July 2020 Needed OG-20-113, 4/13/2020 Sleeve Cross-Sectional Failure - Westinghouse Nuclear Safety Advisory Letter NSAL-20-1 2021 Materials Programs Technical Information Exchange - PWROG Overview
PWROG MSC NEI 03-08 Guidance Documents - Good Practice (3/3)
Doc Number Document Title Documents Incorporated Within (i.e., issued prior to the initiative) or Under the Materials Initiative (i.e., issued since the initiative)
WCAP-16423-NP and WCAP-16465-NP Recommendations for Implementation of Guidelines for PWROG RCS Leak Programs OG-12-330 Generic Guidance for Valves that have Seal Encapsulation Devices 51-1257700-000 Investigation of Sulfur Intrusions at Plants of the B&WOG 51-5030027-01 Evaluation of RV Internals Bolting for the B&WOG 51-5003700-01 CRDM Life Extension Action Plan 51-5000239-01 Interim B&WOG Report on HPI/MU Nozzle Cracking 51-5000239-00 Interim B&WOG Report on HPI/MU Nozzle Cracking 51-5001199-00 Evaluation of Oxygen Levels on Pressurizer PWROG-17067-NP Resource Guide for Selecting Weld Locations for Inspection to Address ID-Initiated Stress Corrosion Cracking of Stainless Steel Piping PWROG-17054-NP Long-term Strategy for Identifying ODSCC of Stainless Steel Piping OG-20-31 NEI 03-08 Good Practice Guidance: Westinghouse NSSS PWR Thermal Shield Degradation as per Westinghouse Technical Bulletin 19-5 OG-20-113 NEI 03-08 Needed and Good Practice Guidance: Thermal Sleeve Cross-Sectional Failure - Westinghouse Nuclear Safety Advisory Letter NSAL-20-1 OG-21-101 Guidance: Westinghouse NSSS PWR Thermal Shield Degradation - Westinghouse Technical Bulletin TB-19-5, Revision 1
2021 Materials Programs Technical Information Exchange - PWROG Overview
2020/2021 PWROG MSC Deviations 2021 Materials Programs Technical Information Exchange - PWROG Overview
Other Key PWROG MSC Programs in 2021(1/6)
Scale and Impact of Uncertainty in Fluence Determinations for Reactor Vessel Internals
- The purpose of this ongoing program revision is to; o Use the sensitivity studies completed under revision 0 of the program for the fluence input parameters to determine the range of the fast neutron fluence on the reactor vessel internals and, o The uncertainties associated with the fast neutron fluence will then be used to determine the impact on the downstream screening on RVI components o Framatome and W draft reports issued for review and comment in late June of 2021. Working to issue final Framatome report. Additional work associated with W report, so a second draft report will be issued to the members in November 2021 for review and comment.
Draft PWROG-21011-P, Rev 0-A, "Scale and Impact of Uncertainty in Fluence Determinations for Reactor Vessel Internals - Westinghouse and Combustion Engineering NSSS Plants Fast Neutron Fluence Analytical Uncertainty Analysis" Draft PWROG-21016-P, Rev 0, "Scale and Impact of Uncertainty in Fluence Determinations for Reactor Vessel Internals - Framatome Summary Report" 2021 Materials Programs Technical Information Exchange - PWROG Overview
Other Key PWROG MSC Programs in 2021(2/6)
Harvesting, Transport, and Laboratory Testing of Degraded Thermal Shield Flexures
- The purpose of this ongoing program revision is to; o For the fracture surface of the flexure(s) removed from Salem 1 to be examined to provide insight into the potential cause of the failure(s) o Collaborative effort with the EPRI MRP o Failed flexures are currently at the hot cell facility in Churchill. Scheduled work includes; Fractography Metallography Documentation Thermal Shield Flexure Susceptibility Study
- The purpose of this ongoing program revision is to; o Assess the relative risk between different TS flexure designs (i.e. 2-loop, 3-loop, and 4-loop) under generic (unit) loadings (Task 1 work approved at this time) o Draft PWROG-21015-P, Revision 0-A, "Thermal Shield Flexure Susceptibility Study issued to the members for review and comment in mid July 2021 2021 Materials Programs Technical Information Exchange - PWROG Overview
Other Key PWROG MSC Programs in 2021(3/6)
Management of Thermal Sleeve and Driveline Related Degradation and Interactions
- The purpose of this ongoing program revision is to; o To support the operation of a Thermal Sleeve and Driveline Degradation Focus Group. This Focus Group will coordinate industry activities relative to the following:
Understanding technical issues associated with recent thermal sleeve and drive line inspections and operating experiences Coordinate an agreed upon industry approach to resolving these issues o Deliverables issued to date:
PWROG-20046-NP, Rev 0, "Review of Framatome-Designed CRDM Thermal Sleeve Information for Applicability to Cracking Operating Experience" under OG-21-31 PWROG-20047-NP, Rev 0, "Results from the Examination of Four Cracked Thermal Sleeves from Kori Units 3 and 4 Nuclear Power Plants" under OG-21-43 PWROG-21010-P, Revision 0, Evaluation of Fractured Thermal Sleeve Remnant Wedging Scenario under OG-21-145 o A playbook that helps utility program owners understand how all of the thermal sleeve and driveline issues and documents tie together and how to navigate managing these issues is scheduled to be sent to the members for review in August 2021 o Additional work recently approved to revise NSAL-20-1 and the associated guidance in OG-20-113 to re-consider recommendations and to relax the re-inspection requirement consistent with the determination of no safety significance associated with this degradation 2021 Materials Programs Technical Information Exchange - PWROG Overview
Other Key PWROG MSC Programs in 2021(4/6)
Acceptance Criteria and Inspection Plan Guidance for Latch Assembly Visual Inspections
- The purpose of this ongoing program revision is to; o To develop generic inspection guidance, provide risk-based acceptance criteria and decision trees for the internal inspection of Westinghouse Style Control Rod Drive Mechanism (CRDM)
Latch Assemblies.
The tools created as part of this project will help plants perform internal CRDM inspections, flag for potential future issues and have the knowledge to draw initial conclusions from video reviews on their own o Draft PWROG-21020-P, Revision 0-A, "CRDM Latch Assembly Wear - Risk Factors" to be issued to the members for review and comment by mid August 2021 o Additional work planned to issue; A draft inspection plan and acceptance criteria A decision tree and mitigation options NEI 03-08 guidance 2021 Materials Programs Technical Information Exchange - PWROG Overview
Other Key PWROG MSC Programs in 2020(5/6)
Clevis Insert / Radial Key Wear Assessment
- The purpose of the work completed under revision 0 was to perform a technical assessment of lower radial key (LRK)/clevis insert wear in the industry o The work provided an assessment of the current state of wear in the lower radial support systems (LRSS) of operating nuclear power plants, and identified specific trends that allowed for the grouping or ranking of plants based on susceptibility o PWROG-19003-P/NP, Revision 0 Clevis Insert/Radial Key Wear Assessment, was issued to the PWROG in November 2019 under OG-19-209
- Under revision 1 of the program, the work documented in PWROG-19003-P was used to perform a generic safety assessment, with the intent of establishing a technical basis for safe operation with wear-related degradation of clevis inserts and radial keys o PWROG-19003-P/NP, Revision 1 Clevis Insert/Radial Key Wear Assessment, was issued to the PWROG in May 2021 under OG-21-103 (more detailed update to be provided in another presentation) 2021 Materials Programs Technical Information Exchange - PWROG Overview
Other Key PWROG MSC Programs in 2020(6/6)
Reactor Internals Guide Card Wear - Westinghouse Domestic Fleet Operational Projections Update to Incorporate Operating Experience from Inspections Assessment
- The purpose of this ongoing program is two-fold; o Revise the guidance contained in WCAP-17451-P, latest revision by considering the OE from several guide card wear measurement (GCWM) inspections performed to date o To support EPRI with the benchmarking evaluation of WCAP-17451-P, Rev. 2 against the Japanese guide card wear evaluation approach documented in JANSI-VIP-27, Fourth Edition
- WCAP-17451-P, Revision 2, "Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet -
Operational Projections submitted under OG-19-197 to the NRC for information only to support PWROG-17096-P, Revision 3, Reactor Internals Acceptance Criteria Methodology and Data Requirements. Minor comments received from the NRC.
- Next update to WCAp-14571 planned for 2022
- Work to support the benchmarking kicked off with the EPRI MRP in July 2021 2021 Materials Programs Technical Information Exchange - PWROG Overview
MSC PWROG Core/Planning Team Organization and Key Contacts Materials Committee Scott Boggs, FPL/NextEra (Chair)
Open (Vice Chair)
Reactor Internals Industry Planning Team Heather Malikowski, Exelon Jim Molkenthin PWROG PMO Reactor Vessel Integrity Core Team Chris Koehler, Xcel Energy Ray Stewart Framatome Pressure Boundary Core Team Open 2021 Materials Programs Technical Information Exchange - PWROG Overview
2021/2022 PWROG MSC Meeting Dates
- August 2022, TBD
Questions?
The Materials Committee is established to provide a forum for the identification and resolution of materials issues including their development, modification and implementation to enhance the safe, efficient operation of PWR plants.
2021 Materials Programs Technical Information Exchange - PWROG Overview