ML23241A949
| ML23241A949 | |
| Person / Time | |
|---|---|
| Issue date: | 09/06/2023 |
| From: | Hammock T Office of Nuclear Material Safety and Safeguards |
| To: | |
| References | |
| Download: ML23241A949 (41) | |
Text
ADAMS Accession No. ML Proposed Rule to Incorporate by Reference the 2021 and 2022 Editions of ASME Codes into 10 CFR 50.55a September 6, 2023
NRC Speakers & Agenda Presenter Topic Tyler Hammock Purpose and Overview Kamal Manoly ASME BPV Code,Section III Yamir Diaz-Castillo ASME BPV Code,Section III (Quality Assurance)
Mike Benson ASME BPV Code,Section XI Thomas Scarbrough ASME OM Code Tyler Hammock Specific Requests for Comment All Question and Answer 2
Purpose and Overview Tyler Hammock Division of Rulemaking, Environmental, and Financial Support Office of Nuclear Material Safety and Safeguards 3
Purpose of Meeting
- Status of the ongoing rulemaking
- Discuss the NRC staffs position regarding incorporation by reference of the ASME 2021 and 2022 Code Editions
- NRC will consider information and perspectives discussed today when developing the final rule, but comments must be submitted in writing through the methods described in the Federal Register notice to receive formal consideration in the rulemaking 4
Timeline -
ASME Rulemakings Publication Year ASME BPV Code ASME OM NRC Proposed Rule NRC Final Rule 2005 2005 Addenda 2006 Addenda 2006 2006 Addenda 2007 2007 Edition 2008 2008 Addenda 2009 2009 Addenda 2009 Edition 2010 2010 Edition 75 FR 24324 (5/4/2010) 2011 2011 Addenda 2011 Addenda 76 FR 36232 (6/21/2011) 2012 2012 Edition 2013 2013 Edition 2014 2015 2015 Edition 2015 Edition 80 FR 56820 (9/18/2015) 2016 2017 2017 Edition 2017 Edition 82 FR 32934 (7/18/2017) 2018 83 FR 56156 (11/9/2018) 2019 2019 Edition 2020 2020 Edition 86 FR 16087 (3/26/2021)** 85 FR 26540 (5/4/2020)*
2021 2021 Edition 2022 2022 Edition 87 FR 65128 (10/27/22) 2023 88 FR 53384 (8/8/2023) 2024 Target: January 2025
- Correction Notice was published in 85 FR 34087 (6/3/2020)
- Correction Notice was published in 86 FR 25977 (5/12/21) 9
Rulemaking Process IBR 2021 -
2022 Editions Identify Proposed Final Rule need for Rule rulemaking It is NRCs
- Draft rule text *Final rule text practice to use ASME codes to
- Public meeting establish
- 75-day public requirements for comment period nuclear power plants.
Opportunities for public participation 6
ASME 2021-2022 Editions RulemakingSchedule
- Proposed rule published in the Federal Register on August 8, 2023 (88 FR 53384) day public comment period ends on
[October 23, 2023]
- NRC will consider public comments submitted on the docket
- Docket ID: NRC-2018-0289
- Target date to publish final rule in the Federal Register: January 10, 2025 7
Submitting Comments
- Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2018-0289.
- Email comments to:
Rulemaking.Comments@nrc.gov. If you do not receive an automatic email reply confirming receipt, then contact us at 301-415-1677.
8
Scope of ASME 2021-2022 Editions Rulemaking
- Two* new conditions being considered
- Three revised existing conditions being considered
- Seven new conditions being considered
- Three revised existing conditions being considered
- One condition is being considered for removal
- Updated Augmented ISI requirements in §50.55a(g)(6)(ii)
- Includes revisions to Quality Assurance conditions 9
Scope of ASME 2021-2022 Editions Rulemaking
- Two new conditions being considered
- Five conditions being are being considered for removal 10
ASME BPV Code,Section III, Conditions under Consideration Kamal Manoly Division of Engineering and External Hazards Office of Nuclear Reactor Regulation 11
Section III New Condition
- Section 50.55a(b)(1)(xiv)Section III Condition: Repairs to Stamped Components.
- If using Nonmandatory Appendix NN for elimination of surface defects and repairs of stamped components, all requirements of Nonmandatory Appendix NN must be met 12
Section III Revised Conditions
- Section 50.55a(b)(1)(vi): Section III Condition: Subsection NH
- Revision to change word "sleeves" to "sheaths"
- Not applicable to 2015 Edition and later Editions
- Section 50.55a(b)(1)(xi): Section III, Condition: Mandatory Appendix XXVI
- When applying the 2015 and 2017 Editions, applicants/licensees must meet the first provision
- When applying the 2015 through 2021 Editions, applicants/licensees must meet the second provision
- When applying the 2017 Edition, applicants/licensees must meet the third provision 13
Section III Revised Conditions
- Section 50.55a(b)(1)(xiii): Section III, Condition:
Preservice Inspection of Steam Generator Tubes
- Proposal to revise the first and second provisions to extend applicability of the condition through the latest ASME BPV Code Section III that is incorporated into 50.55a(a)(1)(i) 14
ASME BPV Code,Section III Conditions under Consideration (Quality Assurance)
Yamir Diaz-Castillo Division of Reactor Oversight Office of Nuclear Reactor Regulation 15
Section III New Condition
- Revise §50.55a(b)(1)(iv)Section III Condition: Quality Assurance
- The NRC is proposing to add a condition to prohibit the use of Subpart 2.19 in NQA-1-2017, NQA-1-2019, and NQA-1-2022.
- The NRC has endorsed NEI 14-05A Rev. 1 in lieu of Subpart 2.19 in NQA-1-2017, NQA-1-2019 and NQA-1-2022.
- The NRC published a correction notice in the Federal Register (88 FR 56780, August 21, 2023) to include NQA-1-2019 and NQA-1-2022 as these provisions were missing in a sentence in the preamble.
16
ASME BPV Code,Section XI, Conditions under Consideration Michael Benson Division of New and Renewed Licenses Office of Nuclear Reactor Regulation 17
Section XI Revised Conditions
- Section 50.55a(b)(2)(viii)Section XI condition: Concrete containment examinations:
- Proposes that the existing conditions in eight and ninth provisions for concrete examinations do not apply to the 2021 Edition
- Section 50.55a(b)(2)(ix)Section XI condition: Metal containment examinations:
- Proposes that the first provision for metal containment examinations not apply to the 2021 Edition 18 25
Section XI Revised Conditions
- Section 50.55a(b)(2)(xxxiv)Section XI Condition:
Nonmandatory Appendix U
- Proposes to prohibit the use of Nonmandatory Appendix U, Supplement U-S1 in the 2021 Edition
- Code Case N-513 provides the same rules and is more frequently updated
- Section 50.55a(b)(2)(xliv)Section XI Condition:
Nonmandatory Appendix Y
- Proposes to prohibit the use of Y-2200, Y-2420 and Y-3200 in the 2021 Edition
- Code Cases N-809, N-889 and N-643 provide the same crack growth laws and are more frequently updated 19 25
Section XI New Condition
- Section 50.55a(b)(2)(xlv)Section XI condition: Pressure testing of containment penetration piping after repair/replacement activities.
- Requires a VT-2 examination of the affected area be performed when applying provisions of IWA-4540(a) and (e)
- Incorporation of Code Case N-751 into the 2021 Edition did not fully address the NRC condition
- Section 50.55a(b)(2)(xlvi)Section XI Condition:
Contracted repair/replacement organization fabricating items offsite of the Owners facilities:
- Proposes to prohibit a contracted Repair/Replacement Organization from fabricating an item off-site of the Owners facility without an ASME Certificate of Authorization and without applying an ASME Certification Mark when applying IWA-4143 20
Section XI New Condition
- Section 50.55a(b)(2)(xlvii)Section XI condition: Weld Overlay Design Crack Growth Analysis:
- Proposes to require stress corrosion crack growth analysis of the weld overlay material in Nonmandatory Appendix Q
- Section 50.55a(b)(2)(xlviii)Section XI Condition:
Analytical Evaluations of Degradation
- Proposes to require analytical evaluations performed in accordance with IWB-3132.3 and IWC-3132.3 be submitted to the NRC for review
- Consistent with the 2019 Edition requirements in IWB-3134 and IWC-3125 21
Section XI New Condition
- Section 50.55a(b)(2)(xlix)Section XI condition: Analytical evaluations of flaws in cladding
- Proposes to prohibit the use of IWB-3600(b)(1) for the inlay and onlay subjected to (g)(6)(ii)(F) augmented inspection requirements
- Section 50.55a(b)(2)(xv)Section XI condition: Appendix VIII specimen set and qualification requirements:
- This condition is no longer applicable to any licensee.
22
Augmented ISI Requirements
- Section 50.55a(g)(6)(ii)(D)(9) Augmented ISI requirements: Reactor vessel head inspections
- Proposes to allow licensees the option to utilize Supplement 15 of Mandatory Appendix VIII for volumetric qualifications required by Table 1 of ASME Code Case N-729-6.
23 27
Augmented ISI Requirements
- Section 50.55a(g)(6)(ii)(F) Augmented ISI requirements:
Examination requirements for Class 1 piping and nozzle dissimilar-metal butt welds
- Proposes to update the requirements for augmented inspections of dissimilar-metal butt welds from Code Case N-770-5 to N-770-7 with an implementation date of one year after the effective date of the final rule.
- Updating the condition on N-770-5 in 50.55a(g)(6)(ii)(F)(8) to require examination of 100% of welds with an optimized weld overlay once each interval.
Note: The OFR mistakenly published that this requirement was in effect on September 7, 2023. A correction notice was published (88 FR 59471, August 29, 2023) by the OFR to correct the dates to say [DATE 30 DAYS AFTER DATE OF PUBLICATION OF THE FINAL RULE IN THE FEDERAL REGISTER].
24 27
ASME OM Code Conditions under Consideration Thomas G. Scarbrough Division of Engineering and External Hazards Office of Nuclear Reactor Regulation 25
OM Code New Conditions
- Proposes to clarify that when implementing ASME OM Code, Subsection ISTD, paragraph ISTD-4253, and Note 7 of Table ISTD-4252-1 in the 2022 Edition of the OM Code, licensees are prohibited from applying Code Case OMN-15, Revision 2 or Revision 3, to extend snubber test interval because Section 3.4 of Code Case OMN-15 specifies that OMN-15 shall not be used in conjunction with Code Case OMN-13, which has been incorporated into the 2022 Edition of the ASME OM Code, Subsection ISTD.
26
OM Code New Conditions
- Section 50.55a(b)(3)(x) OM Condition: Class 1 pressure relief valve sample expansion
- Proposes to clarify that for each Class 1 Pressure Relief Valve tested per ASME OM Code, Mandatory Appendix I, paragraph I-1320(c)(1), for which the as-found set-pressure exceeds the plus/minus tolerance limit of the Owner-established design set-pressure acceptance criteria of paragraph I-1310(e) or +/- 3% of the nameplate set-pressure if the Owner has not established design set-pressure acceptance criteria, two additional valves shall be tested from the same valve group.
27
OM Code Conditions Proposed to be Removed
- Proposes to remove conditions (A), (B) and (C) when implementing the 2022 Edition of the ASME OM Code because these conditions have been incorporated into the 2022 Edition
- Condition (D) was not incorporated into the 2022 Edition and continues to apply to all editions 28
OM Code Conditions Proposed to be Removed
- Section 50.55a(b)(3)(iii)(B) New Reactors OM Condition: Check valves
- Proposes to remove condition (B) that requires bi-directional testing of check valves within the IST program for new reactors
- New reactors are applying recent editions of the ASME OM Code that require bi-directional testing without the need for condition (B) in 10 CFR 50.55a 29
OM Code Conditions Proposed to be Removed
- Section 50.55a(b)(3)(iii)(C) New Reactors OM Condition:
Flow-induced vibration
- Proposes to remove condition (C) for new reactors that requires licensees to monitor flow-induced vibration from hydrodynamic loads and acoustic resonance during preservice and inservice testing to identify potential adverse flow effects on components within the scope of the IST program
- NRC considers flow-induced vibration from hydrodynamic loads and acoustic resonance to be adequately addressed by other regulatory requirements during licensing and the initial testing program at each new reactor power plant without the need for condition (C) in 10 CFR 50.55a 30
Specific Requests for Comment Tyler Hammock Division of Rulemaking, Environmental, and Financial Support Office of Nuclear Material Safety and Safeguards 31
Specific Requests for Comment
- The NRC is proposing to add 50.55a(b)(2)(xlviii) to require analytical evaluations performed in accordance with IWB-3132.3 and IWC-3132.3 be submitted to the NRC. The NRC is seeking advice/recommendations from the public on the proposed condition and other related reporting requirements to determine their perceived value.
- (1) What alternative means are there for the NRC to accomplish the goal of monitoring degradation trends such that the NRC could remove the condition?
- (2) How can the NRC effectively leverage the information provided in flaw evaluations and associated component degradation in a way that is transparent to stakeholders and ensures structural integrity of nuclear components without incurring excessive administrative burden for plant owners?
32
Questions & Answers 33
How to get involved?
To find information about Search for docket ID ASME 2021-2022 rulemaking NRC-2018-0289 34
Questions & Comments ASME 2021-2022 Rulemaking Tyler Hammock, Project Manager Division of Rulemaking, Environmental, and Financial Support Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Email: Tyler.Hammock@nrc.gov Phone: 301-415-1381 Proposed Rule published August 8, 2023 (88 FR 53384)
Public Comment Period Ends October 23, 2023 Docket ID: NRC-2018-0289 (www.regulations.gov) 35
Acronyms ADAMS Agencywide Documents Access and Management System ASME American Society of Mechanical Engineers BPV Boiler and Pressure Vessel CFR Code of Federal Regulations FR Federal Register IBR Incorporation by Reference ISI Inservice Inspection IST Inservice Testing NDE Non-destructive Evaluation NRC Nuclear Regulatory Commission OM Operation and Maintenance RIN Regulation Identifier Number 36
Backup Slides 37
Section 50.55a(b)(1)(xi): Section III, Condition: Mandatory Appendix XXVI Provisions 38
First Provision. When performing fusing procedure qualification testing in accordance with XXVI-2300 and XXVI-4330 the following essential variables must be used for the performance qualification tests of butt fusion joints:
- (1) Joint Type: A change in the type of joint from that qualified, except that a square butt joint qualifies as a mitered joint.
- (2) Pipe Surface Alignment: A change in the pipe outside diameter (O.D.) surface misalignment of more than 10 percent of the wall thickness of the thinner member to be fused.
- (3) PE Material: Each lot of polyethylene source material to be used in production (XXVI-2310(c)).
- (4) Wall Thickness: Each thickness to be fused in production (XXVI-2310(c)).
- (5) Diameter: Each diameter to be fused in production (XXVI-2310(c)).
- (6) Cross-sectional Area: Each combination of thickness and diameter (XXVI-2310(c)).
- (7) Position: Maximum machine carriage slope when greater than 20 degrees from horizontal (XXVI-4321(c)).
- (8) Heater Surface Temperature: A change in the heater surface temperature to a value beyond the range tested (XXVI-2321).
- (9) Ambient Temperature: A change in ambient temperature to less than 50 °F (10 °C) or greater than 125 °F (52 °C) (XXVI-4412(b)).
- (10) Interfacial Pressure: A change in interfacial pressure to a value beyond the range tested (XXVI-2321).
- (11) Decrease in Melt Bead Width: A decrease in melt bead size from that qualified.
- (12) Increase in Heater Removal Time: An increase in heater plate removal time from that qualified.
- (13) Decrease in Cool-down Time: A decrease in the cooling time at pressure from that qualified.
- (14) Fusing Machine Carriage Model: A change in the fusing machine carriage model from that tested 39 (XXVI-2310(d)).
Second Provision: When performing procedure qualification for high speed tensile impact testing of butt fusion joints in accordance with XXVI-2300 or XXVI-4330, breaks in the specimen that are away from the fusion zone must be retested. When performing fusing operator qualification bend tests of butt fusion joints in accordance with XXVI-4342, guided side bend testing must be used for all thicknesses greater than 1.25 inches.
40
Third provision. When performing fusing procedure qualification tests in accordance with 2017 Edition of BPV Code Section III XXVI-2300 and XXVI-4330, the following essential variables must be used for the testing of electrofusion joints:
- 1) Joint Design: A change in the design of an electrofusion joint.
- (2) Fit-up Gap: An increase in the maximum radial fit-up gap qualified.
- (3) Pipe PE Material: A change in the PE designation or cell classification of the pipe from that tested (XXVI-2322(a)).
- (4) Fitting PE Material: A change in the manufacturing facility or production lot from that tested (XXVI-2322(b)).
- (5) Pipe Wall Thickness: Each thickness to be fused in production (XXVI-2310(c)).
- (6) Fitting Manufacturer: A change in fitting manufacturer.
- (7) Pipe Diameter: Each diameter to be fused in production (XXVI-2310(c)).
- (8) Cool-down Time: A decrease in the cool time at pressure from that qualified.
- (9) Fusion Voltage: A change in fusion voltage.
- (10) Nominal Fusion Time: A change in the nominal fusion time.
- (11) Material Temperature Range: A change in material fusing temperature beyond the range qualified.
- (12) Power Supply: A change in the make or model of electrofusion control box (XXVI-2310(f)).
- (13) Power Cord: A change in power cord material, length, or diameter that reduces current at the coil to below the minimum qualified.
- (14) Processor: A change in the manufacturer or model number of the processor. (XXVI-2310(f)).
- (15) Saddle Clamp: A change in the type of saddle clamp.
- (16) Scraping Device: A change from a clean peeling scraping tool to any other type of tool. 41