ML18144A996
| ML18144A996 | |
| Person / Time | |
|---|---|
| Issue date: | 05/24/2018 |
| From: | Robert Wolfgang NRC/NRR/DE/EMIB |
| To: | |
| Wolfgang R | |
| References | |
| Download: ML18144A996 (3) | |
Text
STATUS OF NRC ACTIVITIES OF POTENTIAL INTEREST TO OM STANDARDS COMMITTEE Robert Wolfgang, Senior Mechanical Engineer Mechanical Engineering and Inservice Testing Branch Division of Engineering NRC Office of Nuclear Reactor Regulation ASME OM Code Committee Meeting on June 20-22, 2018 At Vancouver, WA 10 CFR 50.55a Rulemaking Title 10 of the Code of Federal Regulations (10 CFR) in Section 50.55a, Codes and standards, currently incorporates by reference the 2012 Edition of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), the 2013 Edition of the ASME Boiler and Pressure Vessel Code (BPV Code),Section XI, and the 2013 Edition of the ASME BPV Code,Section III, with conditions. Section 50.55a also incorporates by reference selected previous editions and addenda of the ASME OM and BPV Codes, with conditions.
The scope of the next proposed rulemaking to amend 10 CFR 50.55a is currently planned to include:
2015 Edition to the ASME BPV Code,Section III, Division 1, and Section XI, Division 1, with conditions.
2017 Edition to the ASME BPV Code,Section III, Division 1, and Section XI, Division 1, with conditions.
2015 Edition to Division 1 of the ASME OM Code, with conditions.
2017 Edition to Division 1 of the ASME OM Code, with conditions.
Specific items of interest in the proposed rulemaking related to the OM Code being considered include:
- 1. Add NRC IST Plan submittal and reporting requirements consistent with current edition of OM Code.
- 2. Revise 10 CFR 50.55a(f)(4)(i) and (ii) and (g)(4)(i) and (ii) to relax the time schedule for complying with the latest edition and addenda of the ASME OM or BPV Codes for IST and ISI programs, respectively, from 12 months to 18 months before the applicable milestones in these paragraphs.
- 3. Streamline the references to editions of the ASME OM Code in each condition to simplify future 10 CFR 50.55a rulemaking, and to update specific conditions to reflect the latest ASME OM Code editions.
ASME requested that the NRC delay this rulemaking to incorporate by reference the 2017 Edition to the ASME BPV Code,Section III, Division 1 and Section XI, Division 1. The NRC Rulemaking Steering Committee agreed to accommodate ASMEs request. Therefore, this proposed rulemaking is now currently scheduled to be published for public comment in the fall of 2018, with a 75 day public comment period. The final rulemaking package is currently scheduled to be published in the fall of 2019.
Regulatory Guide (RG) Update - OM Code Case Acceptability Revision 2 of RG 1.192, Revision 37 of RG 1.84, and Revision 18 of RG 1.147 address the acceptability of code cases published in the 2009 Edition through the 2012 Edition of the ASME OM Code and the Sections III and XI code cases listed in Supplement 11 to the 2007 Edition and Supplements 0 through 10 to the 2010 Edition of the ASME BPV Code. The current regulations in 10 CFR 50.55a incorporate by reference these specific revisions to RGs 1.192, 1.84, and 1.147.
The NRC staff has completed a review of the new and revised code cases published in the 2015 Edition and 2017 Edition of the ASME OM Code. The proposed rulemaking and RGs for these code cases is currently scheduled to be published in July 2018, with a 75 day comment period.
The final rulemaking and RGs for these code cases is currently scheduled to be published in December 2018.
Valve Stem-Disc Connection Issues On June 15, 2017, the NRC issued Information Notice (IN) 2017-03, Anchor/Darling Double Disc Gate Valve Wedge Pin and Stem-Disc Separation Failures, to inform licensees and applicants of operating experience regarding Anchor/Darling (a subsidiary of Flowserve) double disc gate valve (DDGV) failures. IN 2017-03 provides a discussion of a recent LaSalle County Station Unit 2 Anchor/Darling DDGV failure, events at Browns Ferry that led to Part 21 reporting, and other operating experience that resulted in stem-disc separations. The IN contains information available to the NRC staff as of May 2017. The Nuclear Energy Institute (NEI) is coordinating the industry corrective action to address the potential valve stem-disc connection issues for Anchor/Darling DDGVs at operating nuclear power plants. The NRC staff is continuing its evaluation of this issue and plans to perform independent inspections beginning later this year. The NRC staff held a public meeting in May 2018 to discuss the draft inspection procedure and inspection plan.
ASME-Related Generic Communications ASME-related generic communications issued by (or in the process of being issued by)
NRR and NRO since the last report (December 2017) to the OM Standards Committee are listed below:
Bulletins (BLs)
None Generic Letters (GLs)
None Information Notices (INs)
IN-2018-02 (3/26/2018) Testing and Operations-Induced Degradation of 3-Stage Target Rock Safety Relief Valves IN-2018-04 (2/26/2018) Operating Experience Regarding Failure of Operators to Trip the Plant When Experiencing Unstable Conditions Regulatory Issue Summaries (RISs)
None The full text of any of these NRC generic communications can be accessed by visiting the NRCs public website at http://www.nrc.gov/reading-rm/doc-collections/gen-comm/index.html.