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Category:Meeting Summary
MONTHYEARML20083F1492020-07-0606 July 2020 Summary of Meeting to Discuss Digital Instrumentation and Control, Integrated Action Plan, Modernization Plan #3, Acceptance of Digital Equipment, Nuclear Energy Institute 17-06 ML20098F2472020-05-18018 May 2020 Summary of Meeting WCAP 18461, Common Q Platform and Component Interface Module System Elimination of Technical Specification Surveillance Requirements ML20069A7452020-05-14014 May 2020 Summary of Closed Pre-Submittal Meeting with Westinghouse Electric Company to Discuss WCAP-16097, Revision 5, Common Q Platform Topical Report ML19304A0932020-02-0505 February 2020 Summary of Closed Pre-Submittal Meeting with Westinghouse Electric Company to Discuss the Topical Report Related to Removing the Technical Specification Requirements for the Common Qualification System ML19247B4512020-02-0303 February 2020 Summary of the September 11, 2019, Meeting Between the U.S. Nuclear Regulatory Commission Staff and the Electric Power Research Institute to Discuss BWRVIP 315 ML19325C9242020-02-0303 February 2020 November 21, 2019, Summary of Closed Meeting on Hf Controls Amendment 4 Open Items ML19273A8942020-01-15015 January 2020 November 6, 2019, Summary of Meeting to Discuss Nuclear Energy Institute 17-06 ML19287A0052019-11-0808 November 2019 Summary of the October 24, 2019, Workshop on Topical Report Transform ML19247C0542019-10-0909 October 2019 20190911 Sep 18, 2019, Iassc Baffle Bolt Meeting Summary ML19253A0732019-10-0909 October 2019 Summary of Meeting Between the U.S. Nuclear Regulatory Commission Staff and the Electric Power Research Institute to Discuss BWRVIP-315 ML19226A1102019-09-0909 September 2019 Summary of August 21, 2019, Meeting to Discuss the Nuclear Procurement Issues Corporation Process and the Plans for Nuclear Energy Institute 17-06 ML19150A5572019-06-24024 June 2019 Summary of Closed Meeting with Westinghouse Electric Company to Discuss Common Qualified Platform Topic Report (WCAP-16097) Watchdog Timer Changes ML19094A3772019-06-19019 June 2019 Summary of Meeting Between the U.S. Nuclear Regulatory Commission Staff and the Electric Power Research Institute to Discuss BWRVIP-329 ML19038A4682019-02-13013 February 2019 Summary of Meeting to Discuss Draft Advanced Manufacturing Technologies Action Plan ML18302A0032019-01-15015 January 2019 Summary of Meeting to Discuss Operability Determination/Corrective Action Program Interface Definitions ML18305A7552019-01-15015 January 2019 Summary of Closed Teleconference on PWROG-15060, Pump Suction Gas Accumulation Operability Criteria Guidance. ML18204A0432018-11-28028 November 2018 Summary of Meeting to Discuss the Nuclear Regulatory Commission Staff Feedback on Entry Criteria for Operability Determination ML18220A7422018-10-29029 October 2018 Summary of the September 12, 2018, Meeting to Discuss Operating Experience and MRP-227, Revision 1 Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline. ML18206A1762018-10-22022 October 2018 09/26/2018 Summary of Meeting Between the U.S. Nuclear Regulatory Commission Staff and the Electric Power Research Institute to Discuss the Boiling Water Reactor Vessel and Internals Project Subsequent License Renewal Activities ML18267A0042018-10-0303 October 2018 Summary of Meeting to Discuss Digital Instrumentation and Control Integrated Action Plan, Modernization Plan #3 ML18204A0222018-10-0101 October 2018 August 30, 2018, Summary of Meeting to Discuss the Nuclear Energy Institute Introduction of Entry Criteria for Operability Determinations ML18232A1082018-09-26026 September 2018 Summary of 08/30/2018, Meeting to Discuss the Draft Safety Evaluation for PWROG-15060, Pump Suction Gas Accumulation Operability Criteria Guidance (CAC No. MF8075; EPID L-2016-TOP-0006) ML18193B1102018-08-0101 August 2018 Summary of Meeting with Representatives from the Nuclear Energy Institute (NEI) to Discuss Digital Instrumentation and Control Integrated Plan, Modernization Plan #3 ML18186A2002018-07-16016 July 2018 Summary of Closed Teleconference with Research and Production Corporation Radics, LLC ML18179A3622018-07-16016 July 2018 June 28, 2018, Operability Meeting Summary ML18155A0042018-07-0909 July 2018 Summary of May 24, 2018, Meeting to Discuss Digital Instrumentation and Control Common Cause Failure ML18136A5052018-05-30030 May 2018 Summary of Conference Call to Discuss the Use of Strategic Alliance for FLEX Emergency Response Resources to Support Exigent Situations ML18096A4482018-05-14014 May 2018 Summary of Conference Call to Discuss Clarification of MRP-277, Revision 1 Requests for Additional Information ML18082A0292018-04-23023 April 2018 March 29, 2018, Summary of Meeting to Discuss the Roadmap for Proposed Industry-Wide Monitoring Program and RAI Response Templates ML18009A6382018-04-0909 April 2018 Summary of Biweekly Conference Calls to Discuss Fleet-Wide Response to Draft Requests for Additional Information Related to Generic Letter 2016-01 ML18058A0082018-03-0808 March 2018 2/21/2018 Summary of Closed Meeting Held with Doosan Hf Controls to Discuss the Review Status of Amendments 2, 3, and 4 ML18025B4542018-02-28028 February 2018 Summary of February 13, 2018 - February 15, 2018, Meeting Between the U.S. Nuclear Regulatory Commission Staff and the Industry to Discuss MRP-175, Revision 1, MRP-211, Revision 1 and the Requests for Additional Information on MRP-227, Revi ML17335A4232018-01-22022 January 2018 Summary for 12/13/2017 NEI 16-16 Meeting ML17332A4452018-01-17017 January 2018 Summary of the December 12, 2017, Meeting with Westinghouse Regarding the AC160 Controller Watchdog Timer Issue Causal Analysis ML17331A4512017-12-22022 December 2017 Summary of November 29, 2017, Meeting to Discuss Staff Comments on NEI 16-16 (Draft 2) ML17331A4852017-12-22022 December 2017 Summary of 11/30/2017 Meeting on NEI 96-07, App D, Section 4.3.6 2020-07-06
[Table view]Some use of "" in your query was not closed by a matching "". Category:Memoranda
MONTHYEARML20083F1492020-07-0606 July 2020 Summary of Meeting to Discuss Digital Instrumentation and Control, Integrated Action Plan, Modernization Plan #3, Acceptance of Digital Equipment, Nuclear Energy Institute 17-06 ML20098F2472020-05-18018 May 2020 Summary of Meeting WCAP 18461, Common Q Platform and Component Interface Module System Elimination of Technical Specification Surveillance Requirements ML20069A7452020-05-14014 May 2020 Summary of Closed Pre-Submittal Meeting with Westinghouse Electric Company to Discuss WCAP-16097, Revision 5, Common Q Platform Topical Report ML19304A0932020-02-0505 February 2020 Summary of Closed Pre-Submittal Meeting with Westinghouse Electric Company to Discuss the Topical Report Related to Removing the Technical Specification Requirements for the Common Qualification System ML19247B4512020-02-0303 February 2020 Summary of the September 11, 2019, Meeting Between the U.S. Nuclear Regulatory Commission Staff and the Electric Power Research Institute to Discuss BWRVIP 315 ML19325C9242020-02-0303 February 2020 November 21, 2019, Summary of Closed Meeting on Hf Controls Amendment 4 Open Items ML19273A8942020-01-15015 January 2020 November 6, 2019, Summary of Meeting to Discuss Nuclear Energy Institute 17-06 ML19287A0052019-11-0808 November 2019 Summary of the October 24, 2019, Workshop on Topical Report Transform ML19247C0542019-10-0909 October 2019 20190911 Sep 18, 2019, Iassc Baffle Bolt Meeting Summary ML19253A0732019-10-0909 October 2019 Summary of Meeting Between the U.S. Nuclear Regulatory Commission Staff and the Electric Power Research Institute to Discuss BWRVIP-315 ML19226A1102019-09-0909 September 2019 Summary of August 21, 2019, Meeting to Discuss the Nuclear Procurement Issues Corporation Process and the Plans for Nuclear Energy Institute 17-06 ML19150A5572019-06-24024 June 2019 Summary of Closed Meeting with Westinghouse Electric Company to Discuss Common Qualified Platform Topic Report (WCAP-16097) Watchdog Timer Changes ML19094A3772019-06-19019 June 2019 Summary of Meeting Between the U.S. Nuclear Regulatory Commission Staff and the Electric Power Research Institute to Discuss BWRVIP-329 ML19038A4682019-02-13013 February 2019 Summary of Meeting to Discuss Draft Advanced Manufacturing Technologies Action Plan ML18302A0032019-01-15015 January 2019 Summary of Meeting to Discuss Operability Determination/Corrective Action Program Interface Definitions ML18305A7552019-01-15015 January 2019 Summary of Closed Teleconference on PWROG-15060, Pump Suction Gas Accumulation Operability Criteria Guidance. ML18204A0432018-11-28028 November 2018 Summary of Meeting to Discuss the Nuclear Regulatory Commission Staff Feedback on Entry Criteria for Operability Determination ML18220A7422018-10-29029 October 2018 Summary of the September 12, 2018, Meeting to Discuss Operating Experience and MRP-227, Revision 1 Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline. ML18206A1762018-10-22022 October 2018 09/26/2018 Summary of Meeting Between the U.S. Nuclear Regulatory Commission Staff and the Electric Power Research Institute to Discuss the Boiling Water Reactor Vessel and Internals Project Subsequent License Renewal Activities ML18267A0042018-10-0303 October 2018 Summary of Meeting to Discuss Digital Instrumentation and Control Integrated Action Plan, Modernization Plan #3 ML18204A0222018-10-0101 October 2018 August 30, 2018, Summary of Meeting to Discuss the Nuclear Energy Institute Introduction of Entry Criteria for Operability Determinations ML18232A1082018-09-26026 September 2018 Summary of 08/30/2018, Meeting to Discuss the Draft Safety Evaluation for PWROG-15060, Pump Suction Gas Accumulation Operability Criteria Guidance (CAC No. MF8075; EPID L-2016-TOP-0006) ML18262A0382018-09-21021 September 2018 Closed Sep 18, 2018, Telephonic Conference Summary Radic Defense in Depth Detailed Analysis ML18213A2852018-08-13013 August 2018 Aug. 1, 2018 Summary of Closed Meeting with Doosan Hf Controls to Discuss the Revision of Amendment 4 to the Doosan Hf Controls-6000 Safety System ML18193B1102018-08-0101 August 2018 Summary of Meeting with Representatives from the Nuclear Energy Institute (NEI) to Discuss Digital Instrumentation and Control Integrated Plan, Modernization Plan #3 ML18179A3622018-07-16016 July 2018 June 28, 2018, Operability Meeting Summary ML18186A2002018-07-16016 July 2018 Summary of Closed Teleconference with Research and Production Corporation Radics, LLC ML18155A0042018-07-0909 July 2018 Summary of May 24, 2018, Meeting to Discuss Digital Instrumentation and Control Common Cause Failure ML18096A4482018-05-14014 May 2018 Summary of Conference Call to Discuss Clarification of MRP-277, Revision 1 Requests for Additional Information ML18082A0292018-04-23023 April 2018 March 29, 2018, Summary of Meeting to Discuss the Roadmap for Proposed Industry-Wide Monitoring Program and RAI Response Templates ML18058A0082018-03-0808 March 2018 2/21/2018 Summary of Closed Meeting Held with Doosan Hf Controls to Discuss the Review Status of Amendments 2, 3, and 4 ML18025B4542018-02-28028 February 2018 Summary of February 13, 2018 - February 15, 2018, Meeting Between the U.S. Nuclear Regulatory Commission Staff and the Industry to Discuss MRP-175, Revision 1, MRP-211, Revision 1 and the Requests for Additional Information on MRP-227, Revi ML18036A0012018-02-0808 February 2018 Notice of Forthcoming Closed Meeting with Doosan Fh Controls to Discuss the Review Status and Schedule for Hf Controls Amendment 2 and 3 Submittal and Amendment 4 Submittal ML17335A4232018-01-22022 January 2018 Summary for 12/13/2017 NEI 16-16 Meeting ML0606901681984-08-15015 August 1984 Memo from J. Holonich, NRR, to H. Denton, Et Al., NRR, Daily Highlight ML0606901641984-08-13013 August 1984 Memo from J. Holonich, NRR, to B. Youngblood, NRR, Forthcoming Meeting W/Union Electric 2020-07-06
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October 29, 2018 MEMORANDUM TO: Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation FROM: Joseph J. Holonich, Senior Project Manager /RA/
Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF THE SEPTEMBER 12, 2018, MEETING TO DISCUSS OPERATING EXPERIENCE AND MRP-227, REVISION 1 MATERIALS RELIABILITY PROGRAM: PRESSURIZED WATER REACTOR INTERNALS INSPECTION AND EVALUATIONS GUIDELINE On September 12, 2018, U. S. Nuclear Regulatory Commission (NRC) staff met with representatives from the Electric Power Research Institute (EPRI), and the Pressurized Water Reactor Owners Group (PWROG). These organizations will be referred to collectively as the industry in this summary.
The purpose of the meeting was to discuss operating experience and Materials Reliability Program (MRP)-227, Revision 1 Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluations Guideline. The objective of the meeting was for EPRI to provide the NRC staff with information on the recent operating experience as it relates to the ongoing review of MRP-227, Revision 1. Information related to the meeting, including presentations, documents discussed in this summary, and the attendees list can be found in the Agencywide Document Access and Management System package ML18206A140.
At the opening of the meeting NRC staff stated that it was working on preparing the safety evaluation (SE) for MRP-227, Revision 1. Continuing, the NRC staff explained that it understood the industry desire to have a clean SE without any conditions. However, the NRC staff explained that it needed to understand if the industry wanted an SE on an accelerated schedule or wanted to wait for the SE until all the information could be evaluated. In response, the industry noted it would like an efficient SE with no conditions.
The NRC staff said that it would prepare the SE on a schedule that would allow it to review all the available information but that, if the staff found MRP-227, Revision 1 acceptable for use, the inclusion or exclusion of conditions in the SE would depend on what the NRC staff needed to document to protect safety.
CONTACT: Joseph J. Holonich, NRR/DLR/DLP 301-415-7297
D. Morey The NRC staff asked about the status of implementation of MRP-227, Rev. 1 by the plants. The industry indicated that most plants are governed by existing license-renewal commitments.
Therefore, the reactor vessel internal (RVI) aging management programs are in accordance with MRP-227-A.
EPRI explained that plants currently using MRP-227-A are implementing it along with guidance that was issued since the submittal of MRP-227-A. Industry noted that if MRP-227, Revision 1 was accepted for use, then its implementation would be analyzed using the methodology in Nuclear Energy Institute guidance 03-08, "Guideline for the Management of Materials Issues."
The NRC staff questioned if plants would have to come to the NRC for any changes coming out of the NEI 03-08 analysis. Industry said that it would conduct an evaluation under Title 10 of the Code of Federal Regulations (10 CFR), Section 50.59, "Changes, tests, and experiments." This analysis was the standard approach for handling changes at plants, and would determine if plants needed to come to the NRC.
Next, the recent EPRI guidance on control rod drive mechanism (CRDM) thermal sleeves was discussed. An NRC staff question dealt with whether impacts to the inside and outside diameters for CRDM thermal sleeves would be addressed in the responses to the Requests for Additional Information (RAIs). Industry responded that the PWROG was working on this topic and that the RAI response would discuss what is being done.
In addition, industry stated that PWROG-16003-P, Evaluation of Potential Thermal Sleeve Flange Wear, was being revised based on the work being done. Industry stated that PWROG-16003-P is intended to be the inspection and evaluation document for thermal sleeves. MRP-227 would then refer to this guidance, similar to the guide card guidance in WCAP-17451-P, "Reactor Internals Guide Tube Wear-Westinghouse Domestic Fleet Operational Projections."
Industry agreed to provide the PWROG-16003-P revision to the NRC staff for information when it is completed. Also, industry suggested that a pre-submittal meeting might be worth holding even if the revision was only being provided for information.
The NRC staff stated that it was conducting an assessment under LIC-504, "Integrated Risk-Informed Decision-Making Process for Emergent Issues." The NRC staff expected that the assessment would be done within approximately two weeks. Therefore, it was suggested that a meeting be held to discuss the NRC staff LIC-504 assessment and results in about a month from this meeting.
The industry indicated it does not plan to incorporate the interim guidance of CRDM thermal sleeves into MRP-227, Revision 1 due to the possibility of changes in this guidance in the near term. Industry does however, plan to issue thermal sleeve inspection and evaluation guidance under the revision to PWROG-16003-P by the first quarter of 2019. It would subsequently incorporate the PWROG guidance for CRDM thermal sleeves into MRP-227, Revision 2, expected to be submitted for NRC review in late 2020.
At the end of the discussions on this topic, industry explained that its overall process was to respond to the RAIs and look for the NRC staff to complete its evaluation of MRP-227, Revision 1. Plants would continue to follow guidance, such as that on the CRDM thermal sleeves, that was developed after the submittal of MRP-227, Revision 1. In addition, industry expected more information on the CRDM thermal sleeves in 2019.
D. Morey This information and the interim guidance would then be incorporated into MRP-227, Revision 2. Also, industry indicated that, although MRP-227, Revision 2 was originally intended for subsequent license renewal (SLR) work for 80 years, the goal is to have it apply to original license life and any life-extension period beyond the original operating license. The industry intent is that MRP-227 is applicable as a single NEI 03-08 inspection and evaluation guidance document for aging management of PWR reactor internals.
The next topic covered in the meeting was core-barrel welds. As part of the interactions on this topic, the NRC staff asked if industry was doing a root-cause analysis of the cracks found in core barrels. Industry responded that it was not doing a root-cause analysis but it was not known if the licensee of the plant was doing one. To respond to the RAI on core-barrel weld operating experience, EPRI would commit to increased coverage in MRP-227, Revision 1.
NRC staff had a presentation related to core-barrel welds. However, given the information provided in the industry presentations, the NRC staff presentation was not as relevant. The changes presented in the industry presentation was an increase in core-barrel weld inspections from the current 25% of the weld length to 100% of the accessible weld length, with 50%
minimum being required. The NRC staff presentation was based on the original inspection number of 25%.
The final industry presentation covered baffle-former bolts (BFBs). In its presentations on baffle bolts, industry said that the appropriate location for the guidance related to BFBs was in the acceptance criteria methodology in WCAP-17096-NP-A, Revision 2, "Reactor Internals Acceptance Criteria Methodology and Data Requirements." Industry reported that the plans were to revise WCAP-17096-NP in 2019. The issue would be addressed there, with guidance consistent with the recommendation from the NRC Staff Assessment of the BFB Interim Guidance.
A final topic covered at the meeting was the discussion of Action Item (AI) 8, "Submittal of Information for Staff Review and Approval," from the 2011 staff safety evaluation of MRP-227, Revision 0. The NRC staff explained that the AI was added as a reminder to include certain information related to RVI in the license renewal application. Now, the NRC staff explained, it has determined that the information required by AI 8 is already required by 10 CFR Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants."
The NRC staff also indicated that a requirement in AI 8 to address environmental effects of fatigue for RVIs is not needed because it is inconsistent with most plants current licensing basis and is not consistent with other guidance for license renewal, such as the Standard Review Plan. Because of that, the NRC staff stated that the AI was no longer needed and, if MRP-227, Revision 1 was found acceptable for use, the AI would not be included in the SE.
Docket No. 99902016
Package (ML18006A140); Summary (ML18220A742)
- concurrence via email NRC -001 OFFICE NRR/DLP/PLPB/PM* NRR/DE/EPNB* NRR/DLP/PLPB/BC NRR/DLP/PLPB/PM NAME JHolonich DAlley DMorey JHolonich DATE 10/24/2018 10/24/2018 10/25/2018 10/29/2018