ML18059A003
| ML18059A003 | |
| Person / Time | |
|---|---|
| Issue date: | 02/28/2018 |
| From: | Robert Wolfgang NRC/NRR/DE/EMIB |
| To: | |
| Wolfgang R, NRR/DE/EMIB 301-415-1624 | |
| References | |
| Download: ML18059A003 (10) | |
Text
1 Summary of ASME OM Code Meeting (December 2017)
On December 13 to 15, 2017, the American Society of Mechanical Engineers (ASME)
Operation and Maintenance of Nuclear Power Plants (OM Code) committees met in Clearwater Beach, FL. The NRC staff members who participated in the ASME OM Code committee meetings in December 2017 included Robert Wolfgang, Michael Farnan, and Gurjendra Bedi of the NRC Office of Nuclear Reactor Regulation (NRR); and Thomas Scarbrough and Yuken Wong of the NRC Office of New Reactors (NRO).
In addition, NRC staff members attended the winter meeting of the Inservice Testing Owners Group (ISTOG) on December 11 and 12, 2017, at the same location as the ASME OM Code committee meetings. For example, on December 11, Bob Wolfgang presented the NRC Liaison Report to the ISTOG, and on December 12, Gurjendra Bedi provided a slide presentation on Inservice Examination and Testing Issues. Also, on December 12, the NRC staff provided a slide presentation on the recent rulemaking to update 10 CFR 50.55a, Codes and standards, at the ISTOG meeting. The ISTOG appreciated the slide presentation and discussion of its member questions. The ISTOG members identified a typographical error in the recent 10 CFR 50.55a rulemaking that referenced an incorrect edition of the ASME OM Code in paragraph (b)(3)(iv) on check valve condition monitoring for the inservice testing (IST) program. The NRC staff has requested the NRR rulemaking staff to include this IST correction in an immediately effective rulemaking being prepared to correct a condition in 10 CFR 50.55a on inservice inspection provisions in Section XI of the ASME Boiler and Pressure Vessel Code (BPV Code).
New Reactor OM Code Subcommittee On December 13, 2017, Thomas Scarbrough participated at the meeting of the ASME OM Code Subcommittee on New Reactors (SC-NROMC) as the NRC representative. Chris Pendleton is the Chairman of SC-NROMC.
SC-NROMC discussed the draft OM standard for surveillance of non-safety related mechanical equipment in nuclear power plants with high safety significance. This standard is intended to provide guidance for the treatment of equipment within the scope of the Regulatory Treatment of Non-Safety Systems (RTNSS) in new nuclear power plants. SC-NROMC assigned the task group of Mark Holbrook, Joel Melito, and T. Scarbrough to update the draft standard to incorporate comments provided during the SC-NROMC meeting, and to prepare a Background Paper for the draft standard. SC-NROMC directed the task group to send the revised draft standard with its Background Paper to Oliver Martinez for ASME OM global review and comment.
SC-NROMC discussed draft Subsection ISTG, Preservice and Inservice Testing of Valves in Water-Cooled Reactor Nuclear Power Plants - Post-2000 Plants, for preservice testing (PST) and IST of valves in new reactors (post-2000 plants as defined in the OM Code) prepared by Steve Unikewicz and T. Scarbrough. The ASME OM Code defines a pre-2000 plant as a nuclear power plant that was issued its construction permit by the applicable regulatory authority prior to January 1, 2000; and a post-2000 plant as a nuclear power plant that was issued (or will be issued) its construction permit, or combined license for construction and operation, by the applicable regulatory authority on or following January 1, 2000. The draft Subsection ISTG is similar to the approach in Subsection ISTF, Inservice Testing of Pumps in Light-Water Reactor Nuclear Power Plants - Post-2000 Plants. SC-NROMC assigned a task group of Chris Pendleton, Natalie Rodgers, Tom Ruggiero, and T. Scarbrough to revise the draft Subsection ISTG to modify the valve categorization table to focus on valve function. SC-NROMC assigned
2 a task group of Willard Roit, Joel Melito, Brittany Shank, and T. Scarbrough to revise the squib valve provisions in the draft Subsection ISTG to reflect new passive reactor designs in addition to the AP1000 reactor. SC-NROMC specified that the task groups send their revisions to Steve Unikewicz by January 31, 2018, for his transmittal to Oliver Martinez for ASME OM global review and comment.
SC-NROMC discussed development for a new section for the ASME OM Code to provide function-based IST provisions for advanced reactors. SC-NROMC requested that Mark Holbrook send a list of contacts for advanced reactor design to Chris Pendleton for use in requesting assistance in the development of IST provisions for advanced reactors. SC-NROMC assigned a task group of Mark Holbrook, Tom Ruggiero, Joel Melito, and T. Scarbrough to initiate development of a function-based IST approach for advanced reactors.
SC-NROMC requested the task group updating the draft Subsection ISTG for squib valves to perform two additional task related to squib valve provisions in the ASME OM Code. First, the task group will prepare a proposed revision to Subsection ISTC to incorporate the squib valve provisions for passive reactor designs to be included in draft Subsection ISTG. Second, the task group will prepare a proposed revision to the squib valve provisions to clarify that the provision for remote internal inspection does not require complete disassembly of the squib valve.
T. Scarbrough presented the NRC Liaison Report prepared by Bob Wolfgang for the ASME OM Standards Committee. For example, the NRC staff has initiated the next 10 CFR 50.55a rulemaking to incorporate by reference the 2015 and 2017 Editions of the ASME OM Code with proposed conditions being considered to specify submittal of the IST program plan to the NRC, and relaxation of the 12-month schedule requirement for IST program implementation to 18 months. The proposed rule is planned to be issued for public comment in mid-2018 with final issuance in mid-2019. In addition, the NRC staff plans to re-consider issuance of a NUREG with the papers from the IST Symposium in July 2017 based on concerns raised by authors that they prepared their papers based on the NRC statement that a NUREG would be issued.
For squib valves in new reactors, SC-NROMC asked if the NRC staff would be receptive to a request to modify the ASME OM Code provisions or license conditions for squib valve surveillance based on lessons learned from experience during plant operation. T. Scarbrough noted that the ASME OM Code provisions and license conditions were based on the absence of operating experience with the first-of-a-kind squib valves in new reactors. Therefore, the staff would be receptive to a request to modify the Code provisions and license conditions for squib valve surveillance based on plant experience. SC-NROMC asked if the NRC staff could document its position.
Subcommittee on Pumps On December 13, 2017, Bob Wolfgang participated at the meeting of the ASME OM Code Subcommittee on Pumps (SC-Pumps) as the NRC representative. Tom Robinson is the Chairman of SC-Pumps.
SC-Pumps discussed the addition of a new Baseline Test definition. A new first consideration ballot will be sent out.
SC-Pumps discussed the proposed code case, Alternative for Range and Accuracy of Instrumentation Used in Pump Tests.
3 SC-Pumps discussed the proposed changes for smooth running pumps. Comments were made, and comments will be incorporated and then re-sent out to SC-Pumps members for review and comment.
SC-Pumps is reviewing code cases for applicability prior to the deadline of August 2018 for the 2018 Edition of the OM Code.
SC-Pumps is reviewing Section ISTB for the removal of the Group B variances (+2%/-1%).
Subcommittee on Risk Informed Activities On December 13, 2107, Bob Wolfgang participated at the meeting of the ASME OM Code Subcommittee on Risk Informed Activities (SC-Risk Informed Activities) as the NRC representative. Craig Sellers is the Chairman of SC-Risk Informed Activities.
SC-Risk Informed Activities reviewed the comments to Ballot 17-2281, which is the proposed revision to Subsection ISTE.
Subcommittee on Dynamic Restraints On December 13, 2017, Gurjendra Bedi participated at the meeting of the ASME OM Code Subcommittee on Dynamic Restraints (SC-Dynamic Restraints) as the NRC representative.
Glen Palmer is the Chairman of the SC-Dynamic Restraints.
Gurjendra Bedi presented the NRC Liaison Report prepared by Bob Wolfgang.
SC-Dynamic Restraints is working on the effectiveness of 10% snubber testing plan. Dave Brown is consulting the University of Rhode Island (URI) regarding 10% sample plan effectiveness.
SC-Dynamic Restraints member Russ Day would like to revisit Code Case OMN-10, Requirement for Safety Significance Categorization of Snubbers Using Risk Insights and Testing Strategies for Inservice Testing of LWR Power Plants, and will provide more detail at the next meeting.
SC-Dynamic Restraints discussed including the Compensating Strut as a mechanical snubber in Subsection ISTD without any clarification. G. Bedi considered that this might cause confusion if no explanation was included regarding this type of dynamic restraint. For example, compensating struts might be considered to be mechanical snubbers with some clarification.
The NRC staff is collecting additional information from vendors and licensees on compensating struts.
SC-Dynamic Restraints is studying service life monitoring for snubbers based on an industry survey by the Snubber Users Group (SNUG) with input by vendors.
ISTD-5240 states that snubber testing may begin no earlier than 60 days before scheduled refueling outage. SC-Snubbers is considering revising ISTD-5240 to change this 60-day window to 90 days to accommodate better scheduling. This change should align with the guidance in ASME OM Code Case OMN-20.
Subgroup on Air-Operated Valves
4 On December 13, 2017, Michael Farnan participated at the meeting of the ASME Subgroup on Air-Operated Valves (SG-AOVs) as the NRC representative. Fred Setzer is the Chairman of SG-AOVs. In the afternoon, T. Scarbrough attended the SG-AOV meeting.
SG-AOVs is preparing cross-references between Subsection ISTC and new Appendix IV with IST provisions for AOVs.
SG-AOVs discussed a proposal for a Code Case to provide an approach for implementing the new condition in 10 CFR 50.55a(b)(3)(xi) to supplement paragraph ISTC-3700, Position Verification Testing, to verify valve position indication every two years. SG-AOVs plans to draft a risk-informed Code Case to describe a graded approach for satisfying 10 CFR 50.55a(b)(3)(xi).
Subgroup on Pressure Relief Devices The NRC staff was unable to attend the meeting of the Subgroup on Pressure Relief Devices because of schedule conflicts.
Subgroup on Motor-Operated Valves On December 13, 2017, Michael Farnan participated at the meeting of the ASME OM Code Subgroup on Motor-Operated Valves (SG-MOVs) as the NRC representative. Chad Smith is the Chairman of SG-MOVs.
SG-MOVs discussed recent MOV failures in the industry. Of interest was the recent MOV failure with a Limitorque SMB-4T actuator at Browns Ferry. The valve did not pass its initial quarterly stroke time test. On the second attempt, the stroke time was within the ASME OM Code acceptance criteria. Over the years of collecting diagnostic data, MOV stroke time performance was determined to not be a good indicator of component degradation. Stroke times always remained stable. However, the Browns Ferry failure was identified via stroke time testing. The subgroup discussed this issue because stroke time testing had been removed with the incorporation of Mandatory Appendix III. SG-MOVs evaluated the failure and agreed that the failure occurred with a special actuator that represents a very small population of being in use. Because of the few actuators of this type, it was determined that a change to the Code was not necessary.
Subgroup on Check Valves On December 13, 2017, Michael Farnan participated at the meeting of the Subgroup on Check Valves (SG Check Valves) as the NRC representative.
SG Check Valves discussed ongoing updates to Appendix II of the ASME OM Code. During the course of the meeting, it was brought to NRC staff attention that the recent rulemaking that placed a condition on check valve testing had conflicting statements which created confusion.
The NRC staff reviewed the rulemaking and determined that the confusion was due to a typographical error. As discussed above, the NRC staff brought this to the attention of staff at headquarters in order to initiate an errata to correct the typo.
Subcommittee on Piping Systems On December 13, 2017, Yuken Wong participated at the meeting of the ASME OM Code Subcommittee on Piping Systems (SC-PS) as the NRC representative. Brian Voll is the Chairman of SC-PS.
5 In preparation for the OM Code 2017 Edition, SC-PS discussed the revision to OM Standard, Part 3, Vibration Testing of Piping Systems, Section 6.1, Modal Response Technique. SC-PS revised this section to be used for more general vibration analysis and not specific to modal response technique.
SC-PS updated Part 3, Nonmandatory Appendix A, Instrumentation and Measurement Guidelines. The revision includes adding a reference to a new Appendix J for high frequency vibration typically dominated by pipe shell modes and clarifying the frequency range limitation when using a remote charge converter for data collection.
SC-PS expanded Part 3, Nonmandatory Appendix B, Data Analysis Methods, to include discussions of time history domain and frequency domain analysis methods. A section on determination of results is added to discuss the vibration level results in the forms of root mean squared (RMS), zero-peak, or peak to peak.
Subcommittee on Valves On December 14, 2017, Michael Farnan participated at the meeting of the Subcommittee on Valves (SC-Valves) as the NRC representative. Mark Gowan is the Chairman of SC-Valves. T.
Scarbrough also attended the SC-Valves meeting.
SC-Valves discussed an action item to update paragraph ISTC-3700 in response to the new condition in 10 CFR 50.55a(b)(3)(xi) to supplement the ASME OM Code requirements to verify valve position indication. SC-Valves assigned Fred Setzer to help Bob Binz in preparing a proposed revision to ISTC-3700 with assistance from M. Farnan and T. Scarbrough. T.
Scarbrough stated that the condition in 10 CFR 50.55a(b)(3)(xi) allows a graded approach based on the safety significance of individual valves. M. Farnan noted that the SG-MOVs considers 10 CFR 50.55a(b)(3)(xi) to not apply to MOVs because ISTC-3700 refers to Mandatory Appendix III, Preservice and Inservice Testing of Active Electric Motor-Operated Valve Assemblies in Water-Cooled Reactor Nuclear Power Plants, for MOV valve position indication. T. Scarbrough stated that the development of ASME OM Code Case OMN-1 (upon which Appendix III is based) assumed that the periodic diagnostic testing would verify valve disc position such that ISTC-3700 was not necessary for MOVs. The NRC staff will determine if a clarification is necessary to 10 CFR 50.55a(b)(3)(xi) with respect to valve position indication for MOVs.
SC-Valves discussed the classification of valves as either active or passive. Subsection ISTA, General Requirements, defines valves as either active or passive while Table ISTC-3500-1, Inservice Test Requirements, in Subsection ISTC, Inservice Testing of Valves in Water-Cooled Reactor Nuclear Power Plants, classifies valve functions as active or passive. SC-Valves indicated that Interpretation 01-02 provided guidance on active or passive classification of valves. M. Farnan noted that the NRC staff does not concur with the guidance provided in Interpretation 01-02.
SC-Valves discussed the requirements in paragraph ISTC-5221, Valve Obturator Movement, regarding use of a mechanical exerciser when testing check valves. SC-Valves considers the use of a mechanical exerciser to be acceptable even where a flow test is practical. T.
Scarbrough stated that the NRC staff will review the Code language to confirm that the test using a mechanical exerciser would be equivalent to a flow test. For example, the mechanical exerciser should provide similar operating force as flow through the check valve.
Each subgroup provided a summary of their activities as follows:
6 Appendix I Relief Valve Subgroup: Shawn Comstock discussed the ongoing activities of the subgroup. For example, the subgroup is reviewing the requirement for 5-year replacement of rupture disks. The subgroup is also evaluating the timeliness of sample expansion for relief valve testing.
Appendix II Check Valve Subgroup: M. Farnan is preparing a draft guide for condition monitoring non-intrusive diagnostic testing. Tom Walker of the Electric Power Research Institute (EPRI) stated that EPRI is preparing to update its Check Valve Application Guide with completion planned for 2019.
Appendix III MOV Subgroup: Chad Smith discussed the ongoing activities of the subgroup.
For example, the subgroup is preparing several ballots related to Appendix III. The planned ballots address (1) obturator movement; (2) ISTC pointers to Appendix III; (3) MOV analysis provisions; (4) the mix of static and dynamic MOV testing; and (5) setup activities allowed for MOV testing.
Appendix IV Air-Operated Valve (AOV) Subgroup: Fred Setzer discussed the ongoing activities of the subgroup. For example, the subgroup is preparing proposed updates to Appendix IV, Preservice and Inservice Testing of Active Pneumatically Operated Valve Assemblies in Nuclear Power Plants, to clarify the AOV testing provisions. The subgroup is identifying portions of Appendix IV that are also included in Subsection ISTC. T.
Scarbrough noted that deleting significant portions of Appendix IV might cause confusion in applying Appendix IV, and result in some AOV testing being inadvertently omitted. The subgroup also reported that EPRI is developing guidance for the implementation of Appendix IV.
Subcommittee on Planning On December 14, 2017, Bob Wolfgang participated at the meeting of Subcommittee on Planning (SC-Planning) as the NRC representative.
The comments on the ballot for OM Part 11 transitioning from a guide to a standard have been resolved, and the ballot has been approved.
A draft of OM Part 14 has been developed. It has to be reviewed by SC-Pumps, then it will be issued for OM review and comment in the first quarter of 2018.
A new Subsection ISTG is being developed and will be ready for review by January 31.
The proposed standard for RTNSS pumps and valves will be out for ballot by January 31.
EPRI will develop an implementation guide for Appendix IV.
The majority of plants will submit license amendment requests by the end of 2018 to use 10 CFR 50.69.
SC-Planning discussed whether to request the NRC to endorse the Part 29 Standard in a Regulatory Guide rather than transitioning to an appendix in the OM Code.
Subcommittee on General Requirements
7 On December 14, 2017, T. Scarbrough participated at the meeting of the ASME OM Code Subcommittee on General Requirements (SC-GR) as the alternate for John Billerbeck. Shawn Comstock is the Chairman of SC-GR. Bob Wolfgang also attended the meeting.
SC-GR discussed a proposed revision to paragraph ISTA-3200, Administrative Requirements, to replace the specific 12-month schedule provisions for establishing the IST program with a reference to the regulatory authority. Mel McGaha is addressing comments on the recent ballot to allow incorporation of the change into the planned 2018 Edition of the ASME OM Code.
SC-GR discussed the ongoing work by John Billerbeck to update Table ISTA-1400-1, Referenced Standards and Specifications, for the applicable references in the ASME OM Code. SC-GR reassigned this task to Mel McGaha and Betsy Moenkedick to resolve concerns raised by members of other subcommittees with updating the reference table.
SC-GR discussed the ongoing work to clarify the scope requirements in paragraph ISTA-1100, Scope, of the ASME OM Code. The scope of Subsection ISTA, General Requirements, of the ASME OM Code is consistent with the NRC definition of safety-related components in 10 CFR 50.2, Definitions. However, some individuals have interpreted the scope to extend to any equipment used for fire protection beyond the safety-related definition. Previously, SC-GR had attempted to clarify the scope language in ISTA-1100, and to prepare a definition of accident to be consistent with design-basis events. However, a consensus could not be reached during the ballot process on the proposed language change or a proposed definition of accident. At this meeting, SC-GR prepared a proposed footnote to clarify the scope language in ISTA-1100 that will be distributed for ballot.
SC-GR discussed the ongoing effort to clarify the references to PST in the ASME OM Code.
Chris Pendleton reported that a ballot for Subsection ISTB, Inservice Testing of Pumps in Water-Cooled Reactor Nuclear Power Plants - Pre-2000 Plants, and Subsection ISTF, Inservice Testing of Pumps in Water-Cooled Reactor Nuclear Power Plants - Post-2000 Plants, had been issued to clarify that PST is conducted during the PST period prior to plant startup and, after plant startup, the pump repair, replacement, or modification will involve a baseline test (BST) rather than PST. C. Pendleton with work with the applicable subcommittees regarding clarification of PST and BST in the other subsections and appendices.
SC-GR discussed additional action items such as the following:
(1) The use of acronyms in the ASME OM Code with acronyms being spelled-out with their first use in the Code.
(2) Preparation of a comprehensive list of Interpretations of the ASME OM Code.
Executive Committee In the evening of December 14, 2017, the ASME OM Code Executive Committee met to discuss the overall OM Code committee activities. Bob Wolfgang is the NRC representative on the Executive Committee. T. Scarbrough also attended the meeting.
The Executive Committee stated that the 2017 IST Symposium was reported to be the best ever by the participants. The next IST Symposium is tentatively planned for 2020 with a final decision on the exact date to be reached during the summer of 2018.
The Executive Committee discussed a proposal to update ASME OM Part 29, Alternative Treatment Requirements for RISC-3 Pumps and Valves, to clarify its references to
8 considerations in developing alternate treatment for RISC-3 pumps and valves when implementing risk-informed programs in accordance with 10 CFR 50.69, Risk-informed categorization and treatment of structures, systems, and components for nuclear power reactors. T. Scarbrough stated that clarifying the ASME guidance in Part 29 would allow licensees to implement an approach that is generically acceptable to the NRC staff. Glen Schnizel noted that the Nuclear Energy Institute (NEI) is preparing industry guidance for implementing 10 CFR 50.69. The Executive Committee decided to propose updating Part 29 at the Standards Committee meeting.
Ron Lippy recommended that the ASME OM Code be reviewed to develop revisions to allow removal of conditions in 10 CFR 50.55a required by the NRC.
The Executive Committee discussed the need to correct the applicability dates for Code Cases.
Bob Wolfgang and T. Scarbrough indicated that the applicability dates in each Code Case control whether a licensee needs to request an alternative in accordance with 10 CFR 50.55a to apply the Code Case in lieu of the Code of record for the applicable nuclear power plant.
Bob Wolfgang noted that NRC Regulatory Guide (RG) 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code, applies to the date of issuance of Code Cases and does not establish the applicability of Code Cases.
Oliver Martinez indicated that proposed modifications to the ASME OM Code need to be provided to ASME by the end of May 2018 to be able to appear in the 2018 Edition of the ASME OM Code.
Oliver Martinez stated that ASME has not yet determined the week and location for the summer 2018 ASME OM Code meeting.
OM Code Standards Committee On December 15, 2017, Bob Wolfgang participated as the NRC representative at the meeting of the OM Code Standards Committee. Ron Lippy is the Chairman of the Standards Committee.
Thomas Scarbrough also attended the first half of the meeting.
The Standards Committee presented awards to several ASME committee members in support of the development of a proposed ASME OM Code Case on surveillance provisions for smooth running pumps. Bob Wolfgang and T. Scarbrough were among the committee members receiving certificates.
The Standards Committee discussed the preparation of a Code Case Applicability Table for the ASME OM Code. Shawn Comstock reported on the preparation of the applicability table. Bob Wolfgang and T. Scarbrough indicated that the specific language in each Code Case provides its applicability, and that RG 1.192 lists when the Code Case was published.
The Standards Committee discussed the fact that interpretations are no longer published with the ASME OM Code.
The Standards Committee discussed a proposal to update ASME OM Part 29 clarify its references to considerations in developing alternate treatment for RISC-3 pumps and valves when implementing 10 CFR 50.69 risk-informed programs. T. Scarbrough stated that clarifying the ASME guidance in Part 29 would allow licensees to implement an approach that is generically acceptable to the NRC staff. Glen Schnizel noted that NEI is preparing industry guidance for implementing 10 CFR 50.69. The Standards Committee voted to prepare an update Part 29 to resolve ambiguous language to allow its generic use at nuclear power plants.
9 The subcommittees provided reports on their activities including the following:
SC-NROMC: Chris Pendleton discussed (1) preparation of an OM standard for RTNSS equipment within the scope of the Regulatory Treatment of Non-Safety Systems (RTNSS) in reactors with passive core cooling systems; (2) development of a new Subsection ISTG in the OM Code for valves in post-2000 plants; (3) preparation of a new OM section to provide performance-based provisions for PST and IST in advanced reactors; and (4) the development of a Division 4 of the ASME OM Code for non-water cooled reactors.
SC-GR: Shawn Comstock discussed the proposed footnote for ISTA-1100.
SC-Valves: Mark Gowin discussed the EPRI development of an implementation guide for Appendix IV and the valve obturator movement issue.
SC-Pumps: Tom Robinson discussed the two ballots that are out for voting: (1) Baseline test definition, and (2) Systematic error ballot.
SC-Dynamic Restraints: Glen Palmer discussed (1) studying service life monitoring for snubbers based on an industry survey by the SNUG, (2) working on the effectiveness of the 10% snubber testing plan, and (3) including compensating struts as mechanical snubbers in ISTD without any clarification.
SC-Risk-Informed Activities: Craig Sellers discussed the status of the revision of Subsection ISTE.
SC-Piping Systems: Brian Voll discussed (1) revising OM-3, Vibration Testing of Piping Systems, and (2) the review of OM-7, Requirements for Thermal Expansion Testing of Nuclear Power Plant Piping Systems, in order to change it from a Guide to a Standard.
SC-Functional Systems: J.R. Hayes stated that ballots are out for OM-11, Vibration Testing and Assessment of Heat Exchangers, and OM-17, Performance Testing of Systems in Light-Water Reactor Power Plants.
China International Working Group (IWG): Ron Lippy asked for volunteers to work with the China IWG.
Liaison Reports were as follows:
Korea: Chang Seog Ko provided a status of the Korean nuclear plants.
Japan: Masao Honjin provided a status of the Japanese nuclear plants.
NRC: Bob Wolfgang discussed the information provided in the NRC Liaison Report (ADAMS Accession No. ML17320A616).
Nuclear Energy Institute (NEI): Stephen Geier will be replacing Jim Riley, who retired.
Inservice Testing Owners Group (ISTOG): Mark Gowin provided a summary of the meeting held earlier in the week.
10 ASME is currently working to determine the week and location of the next ASME OM Code meeting.