United States Nuclear Power

Federal Regulations, Codes, & Standards

Users Group ©


ASME OM Code Meeting Notes - September 2001

Site Updates


Introduction

Prepared By: Ron Lippy

Company: True North Consulting

Meeting Dates: September 10, 11, & 12, 2001

Meeting Location: Colorado Springs, Colorado

 

Meeting Notes

1. OM-1 Subgroup did not meet. Will meet again in January 2002.

2. ISTC Subgroup did not meet. Will meet again in January 2002.

3. Approximately 4-6 Utilities are either implementing Risk Informed IST either in full or part, or will be within the next couple of months.

4. The NRC is providing guidance on Risk Informing 10 CFR Part 50. Looking at pilot program at several plants.

5. NUREG 1482 is being revised and is expected to be issued within 18 months.

6. OM Code 1998 edition up to and including the 2000 addenda is expected to be approved by the NRC by the end of 2002.

7. In the future, the vehicle to approved Code Cases will be Appendix U of 10 CFR Part 50. The format will be similar to that used in RG 1.147 (Section XI) and DG-1089 (OM Code).

8. NRC has issued for public comment the Generic Aging Lessons Learned (GALL) report addressing aging management for license renewal along with the proposed standard review plan and regulatory guide.

9. A new Subgroup ISTE has been established to deal with generic IST Risk Informed implementation activities.

10. An inquiry was written addressing the inability to achieve reference values when testing pumps in the IST Program. It was determined that at present, the Code does not address what actions are required if the reference value for pumps previously established per OM Part 6 Paragraph 4.3, is unable to be achieved. The response from the ASME and NRC was to initiate an intent inquiry to determine if a Code change is needed to address the situation. It was clearly understood that, although the Code does not specifically address the actions required to be taken in the event of a facility’s inability to achieve the required reference value, other regulatory and Code requirements/guidance (e.g. 10 CFR 50, Appendix B, NUREG 1482 Section 5, GL 91-18, Section XI IWA-1400, etc., to name a few), would require the owner to take additional action, as appropriate, in order to determine the condition of the component. It should be noted that the majority of the committee members and the NRC would expect the licensee to take action appropriate to the safety significance of the component and in a timely manner commensurate with the plant condition and Technical Specifications.

11. A proposed Draft Standard, OM Part 24, for Reactor Coolant and Recirculation Pump Condition Monitoring was issued for comment.


Home Page

 

Copyright Disclosure