ML24331A067
| ML24331A067 | |
| Person / Time | |
|---|---|
| Issue date: | 12/31/2024 |
| From: | Nicholas Hansing NRC/NRR/DEX/EMIB |
| To: | |
| References | |
| Download: ML24331A067 (3) | |
Text
1 ADAMS Accession No. ML24331A067 STATUS OF NRC ACTIVITIES OF POTENTIAL INTEREST TO OM STANDARDS COMMITTEE Nicholas J. Hansing, Mechanical Engineer Mechanical Engineering and Inservice Testing Branch Division of Engineering and External Hazards NRC Office of Nuclear Reactor Regulation ASME OM Code Committee Meeting December 2024 Clearwater Beach, Florida 10 CFR 50.55a Code Edition Rulemaking Title 10 of the Code of Federal Regulations (10 CFR) in Section 50.55a, Codes and standards, incorporates by reference specific editions and addenda of the American Society of Mechanical Engineers (ASME) Operation and Maintenance of Nuclear Power Plants, Division 1, OM Code:
Section IST (OM Code), and the ASME Boiler and Pressure Vessel Code (BPV Code), Sections III and XI.
On August 30, 2024, the U.S. Nuclear Regulatory Commission (NRC) issued a final rulemaking to amend 10 CFR 50.55a to incorporate by reference the 2021 Edition to the ASME BPV Code,Section III, Division 1, and Section XI, Division 1, with conditions; and the 2022 Edition to Division 1 of the ASME OM Code, with conditions. See Federal Register Notice 89 FR 70449, dated August 30, 2024.
The NRC staff is preparing a proposed rule to incorporate by reference the 2023 Edition of the ASME BPV Code, Division 1, Sections III and XI with conditions as appropriate. ASME did not issue a new edition of the ASME OM Code in 2024.
10 CFR 50.55a Code Case Rulemaking In July 2024, the NRC issued a final rulemaking incorporating by reference into 10 CFR 50.55a revised NRC regulatory guides (RGs) that address the acceptability of ASME Code Cases in the Federal Register on July 17, 2024 (89 FR 58039) (corrected on July 29, 2024 (89 FR 60795)) with an effective date of August 16, 2024. In particular, Revision 5 of RG 1.192, Revision 40 of RG 1.84, and Revision 21 of RG 1.147 address the acceptability of ASME OM Code Cases published during the similar time period as the 2022 Edition of the ASME OM Code and available on the ASME Codes &
Standards (C&S) Connect Website; and specific ASME BPV Code Cases. RG 1.192, Revision 5, accepts new ASME OM Code Cases OMN-28 through OMN-30 without conditions, and OMN-31 with conditions. Other ASME OM Code Cases are accepted in the same manner in Revision 5 to RG 1.192 as the previous Revision 4 to RG 1.192.
In this rulemaking, the NRC established an option to extend of the Code of Record (COR) update requirement in 10 CFR 50.55a from 10 years to 20 or 24 years for those licensees that are implementing as their IST and Inservice Inspection (ISI) CORs the 2017 Edition of the ASME OM Code and 2019 Edition of the ASME BPV Code, or later editions and addenda, as incorporated by reference in 10 CFR 50.55a. For a licensee implementing this recent Code edition or later edition as its IST/ISI Program COR, the rule allows a 20-year or 24-year COR update interval depending on
2 whether the licensee is implementing a 10-year or 12-year OM Examination and Test interval and Section XI Inspection interval, as applicable, to the ASME OM and BPV Codes. For background information, see NRC Commission Paper SECY-21-0029 (March 15, 2021), Rulemaking Plan on Revision of Inservice Testing and Inservice Inspection Program Update Frequencies Required in 10 CFR 50.55a (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20273A286); Staff Requirements Memorandum SRM-SECY-21-0029 (November 8, 2021)
(Accession No. ML21312A490); and Commission Paper SECY-22-0075 (August 10, 2022), Staff Requirements SECY-21-0029 Inservice Testing and Inservice Inspection Program Rulemakings Update (Accession No. ML22124A178).
ASME OM-2-2024 Code, Component Testing Requirements at Nuclear Facilities ASME has issued the OM-2-2024 Code, Component Testing Requirements at Nuclear Facilities, for inservice testing of pumps, valves, and dynamic restraints (and other-named components that perform similar functions) that may be used in new and advanced nuclear facilities that will include water-cooled and non-water-cooled reactors. The NRC staff is preparing a new regulatory guide (DG-1424) to accept the ASME OM-2-2024 Code with applicable regulatory positions. Applicants for non-water-cooled reactors may reference ASME OM-2-2024 as accepted in the new regulatory guide in their licensing applications to meet the NRC regulatory requirements for component testing during plant operation.
Applicants or licensees of water-cooled reactors will need to submit a request for an exemption under 10 CFR 50.12 for prior review and approval by the NRC if desired to apply the ASME OM-2-2024 as conditioned in the new regulatory guide, in lieu of the ASME OM Code as incorporated by reference in 10 CFR 50.55a. The new regulatory guide should be issued for public comment soon.
Reformatted ASME Standard QME-1, Qualification of Active Mechanical Equipment Used in Nuclear Facilities ASME has prepared a reformatted version of ASME Standard QME-1 to provide qualification provisions for active mechanical equipment to be used in new and advanced nuclear facilities. The reformatted QME-1 Standard will allow its more effective use by applicants for the construction and licensing of non-water-cooled reactors. The NRC staff is preparing for public comment a proposed revision to RG 1.100, Seismic Qualification of Electrical and Active Mechanical Equipment and Functional Qualification of Active Mechanical Equipment for Nuclear Power Plants, to accept with applicable regulatory positions the ASME QME-1-2023 Standard and the reformatted QME-1 Standard. Staff will issue the draft RG when QME-1 is available as a public document.
NRC Staff Review of Technical Specification Task Force (TSTF) Proposals The NRC staff is continuing its review of several draft TSTF documents with coordination between the NRC IST staff and the Technical Specifications staff. For example, the NRC staff approved TSTF-576, Revise Safety/Relief Valve Requirements, that would allow the consideration of the safety relief valves in boiling water reactors as a group rather than individually for meeting Technical Specification requirements. The implementation of TSTF documents might result in the need for additional attention to ensure that both the ASME OM Code and the Technical Specifications continue to be met. Specific to TSTF-576, where the traveler identifies an instance where a licensee must request guidance, relief, or an alternative to the ASME OM Code - it may prove beneficial to consider a standardized approach for pursuing this option.
Extended Operating Cycles for Pressurized Water Reactor (PWR) Nuclear Power Plants Fuel enrichment improvements might allow PWR nuclear power plants to implement longer operating
3 cycles. In preparation for these extended operating cycles, PWR licensees should ensure that performance data are available for IST components to provide confidence in extending the test intervals for those components. In addition, PWR licensees should ensure that the plant-specific IST Program is updated to reflect this interval change for the applicable components.
Proposed Revision to NUREG-1482 The NRC staff is preparing the next revision to NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants, Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants. A public meeting was held on May 7, 2024, to discuss possible improvements to the guidance in NUREG-1482 as suggested by the Inservice Testing Owners Group (available at ML24124A000). A draft of the proposed revision to NUREG-1482 should be made publicly available soon.
10 CFR 50.36, Technical specifications, and 10 CFR 50.55a, Codes and standards The NRC regulations in 10 CFR 50.36 and 10 CFR 50.55a specify separate requirements for a licensee of a nuclear power plant. For example, if the ASME OM Code as incorporated by reference in 10 CFR 50.55a requires specific actions to be taken by a licensee (such as actions to be taken following an IST failure), the licensee is required to take those actions or must submit a relief or alternative request in accordance with the regulatory process specified in 10 CFR 50.55a. In addition, many surveillance requirements in technical specifications refer to the IST Program under 10 CFR 50.55a(f) for the specific frequency in performing the surveillance requirement. Therefore, it is important to consider the potential impact on the surveillance requirement frequency in technical specifications when revising the testing requirements in the ASME OM Code as incorporated by reference in 10 CFR 50.55a.
NRC/ASME O&M Code and IST Symposium The NRC/ASME OM Fifteenth Symposium is being planned for July 28 and 29, 2025, at the North Bethesda Marriott, Rockville, MD, across the street from the NRC White Flint offices. The Symposium will include an informal question and answer session with the NRC IST staff on a variety of IST topics.
The ASME OM Code committee meetings will be held at the same hotel on July 30 and 31, and August 1, 2025.
ASME-Related Generic Communications and Regulatory Guides No ASME-related generic communications or regulatory guides have been issued by the NRC since the last report (June 2024) to the ASME OM Standards Committee.