ML21175A113
| ML21175A113 | |
| Person / Time | |
|---|---|
| Issue date: | 06/24/2021 |
| From: | Thomas Scarbrough NRC/NRR/DEX/ESEB |
| To: | Ian Tseng NRC/NRR/DEX/EMIB |
| Thomas G. Scarbrough 301-415-2794 | |
| Shared Package | |
| ML21175A121 | List: |
| References | |
| Download: ML21175A113 (3) | |
Text
June 24, 2021 MEMORANDUM TO: Ian H. Tseng, Acting Chief Mechanical Engineering and Inservice Testing Branch Division of Engineering and External Hazards Office of Nuclear Reactor Regulation FROM: Thomas G. Scarbrough, Senior Mechanical Engineer /RA/
Mechanical Engineering and Inservice Testing Branch Division of Engineering and External Hazards Office of Nuclear Reactor Regulation
SUBJECT:
NRC PUBLIC MEETING ON JUNE 14, 2021, TO DISCUSS SUPPLEMENTAL VALVE POSITION INDICATION REQUIREMENTS On June 14, 2021, the staff of the U.S. Nuclear Regulatory Commission (NRC) held a public meeting to discuss the requirements for valve position indication in the American Society of Mechanical Engineers Operation and Maintenance of Nuclear Power Plants, Division 1, OM Code: Section IST (ASME OM Code) as supplemented by condition (b)(3)(xi) in Section 55a of Part 50 in Title 10 of the Code of Federal Regulations (10 CFR 50.55a(b)(3)(xi)). The NRC staff also discussed the regulatory process for alternative requests to the valve position indication requirements specified in 10 CFR 50.55a(z).
As stated in the meeting announcement, the public meeting on June 14, 2021, was an Information Meeting with a Question and Answer Session. The purpose of this meeting was for the NRC staff to meet directly with individuals to discuss regulatory and technical issues.
Attendees had an opportunity to ask questions of the NRC staff or make comments about the issues discussed throughout the meeting; however, the NRC staff did not actively solicit comments toward regulatory decisions at the meeting.
During its presentation, the NRC staff discussed the background of the supplemental valve position indication requirement specified in 10 CFR 50.55a(b)(3)(xi). The staff also discussed the risk insights related to the importance of accurate valve position verification provided by the remote indicating lights. The staff provided examples of alternative requests in accordance with 10 CFR 50.55a(z) to extend the initial implementation of the supplemental valve position indication requirements in 10 CFR 50.55a(b)(3)(xi). The staff also provided examples of alternative requests for extensions of the 2-year test interval required in ASME OM Code, Subsection ISTC, Inservice Testing of Valves in Water-Cooled Reactor Nuclear Power Plants, paragraph ISTC-3700, Position Verification Testing, for position verification testing of valves with remote position indicating lights.
CONTACT: Thomas G. Scarbrough, NRR/DEX/EMIB 301-415-2794
I.Tseng The staff discussed the specification of ASME OM Code Cases by licensees as part of alternative requests to help streamline the review process. For example, the staff noted that ASME has issued OM Code Case OMN-28, Alternative Valve Position Verification Approach to Satisfy ISTC-3700 for Valves Not Susceptible to Stem-Disk Separation, to provide an alternative approach for extending the 2-year test frequency specified in ASME OM Code, Subsection ISTC, paragraph ISTC-3700, for valves with a stem-disk connection that is not susceptible to separation. To improve the efficiency and effectiveness of the review process, the staff suggested that licensees explore submitting alternative requests related to the valve position indication requirements through the NRC Web-Based Relief Request (WRR) Portal. At the time of the meeting, the staff indicated that it was considering whether to review EPRI Technical Report 3002019621, Susceptibility of Valve Applications to Failure of the Stem-to-Disk Connection, for guidance in implementing Code Case OMN-28.
During the Question and Answer Session of the public meeting, the Nuclear Energy Institute (NEI) presented its views on the valve position indication requirements in the ASME OM Code and 10 CFR 50.55a(b)(3)(xi). Following the public meeting, the NRC staff provided the NEI suggestions to the applicable ASME OM Code committees for their consideration in updating ASME OM Code, Subsection ISTC, paragraph ISTC-3700.
Enclosed are the slides presented by the NRC staff during the public meeting. Also enclosed are the NEI slides presented at the meeting
Enclosures:
As stated
ML21175A121 - Package ML21175A113 - Meeting Summary ML21162A122 - NRC Slides ML21175A123 - NEI Slides
DATE 06/24/2021 06/24/2021