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ASME Section III Users Group Bulletin Board

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Welcome to the ASME Section III Users Group Bulletin Board for the United States Nuclear Power Federal Regulations, Codes, & Standards Users Group. This bulletin board is for the use and benefit of all individuals and organizations that wish to post specific questions and replies that are relevant to the implementation and use of ASME Section III. Questions and replies are posted below as they are received, and only identify the subject, date, and signature as provided, if any, to maintain individual privacy. Advertising and irrelevant material will not be posted. Please limit your postings to 100 words or less and do not include attachments. Send your questions and replies to bulletinboard@tech-tel.com.

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Bulletin Board Postings:

Date:  Wednesday, 27 August 2008

Subject:  New Construction Per 10 CFR Part 52

Dear Group:  Which ASME BPVC edition / addenda will apply to new nuclear plants constructed in accordance with 10 CFR Part 52?  Is the applicability determined by the referenced reactor's standard design certification approval date, the combined license application date, the combined license approval date, or some construction milestone date?

 

Thank you, Eric

 

 

Date:  Friday, 29 August 2008

Subject:  New Construction Per 10 CFR Part 52

Dear Eric:  The applicable Code Edition and Addenda for each component will be the one listed in the design certification document.  These dates may be modified by the COL, but I believe that it is unlikely that anyone will use the COL to modify the dates in the DCD.  The NRC will allow use of later editions and addenda for individual components or systems, but it is unclear at this point how the COL applicant will be able to request or obtain NRC approval for such changes.  The NRC has not yet figured out how they are going to handle this.  We are all laying new track immediately ahead of the train, with only an idea of where we want to be but no certainty on how we are going to get there.

 

By the way, this approach violates NCA-1140, but we are currently processing a revision and a Case to align NCA-1140 with the above approach.

 

Rick Swayne

 

 

Date:  Thursday, 26 June 2008

Subject:  ASME Section III Inquiries

Dear Group:  Can you please tell me where to send a technical inquiry for ASME Section III?  Pete

 

 

Date:  Sunday, 29 June 2008

Subject:  ASME Section III Inquiries

Dear Pete:  You should send the technical inquiry to the Secretary of the ASME Section III Committee as indicated on this page http://cstools.asme.org/csconnect/CommitteePages.cfm?Committee=N20070000.

 

 

Date:  Tuesday, 6 March 2007

Subject:  NRC Enforcement Positions for ASME Codes

Dear Group:  I understand that the ASME has been working with the NRC to help clarify the NRC’s endorsement positions for Nonmandatory Appendices, references in Codes to other Codes, certain Subsections in Section III and Code Cases related to certain Codes.  Can you tell me what the status is?  Thanks, George

 

 

Date:  Sunday, 11 March 2007

Subject:  NRC Enforcement Positions for ASME Codes

Dear George:  On January 11.2007, the NRC presented their draft positions as follows:

 

1.  All Nonmandatory Appendices are considered approved for use for the currently endorsed ASME Code Editions and Addenda of Section III (Division I), Section XI (Division I) and the OM Code as listed in 10 CFR 55a.

 

2.  All references in these Codes to supporting Codes such as Section II, Section V and Section IX are implicitly approved for use, up to the latest published versions available.

 

3.  The current endorsement of ASME Section III (Division I) Subsections NE for containments, NF for supports and NG for core support structures are implicitly approved for use, but are not mandatory.

 

4.  Code Cases published for Sections II, V and IX are also implicitly approved.

 

The NRC is expected to publish their final positions soon, but the publication media is unknown at this time.

 

 

Date: Tue, 18 July 2006

Subject:  Welding Certification and Qualification

Dear Group:  Where can I find a discussion on Welding Certification and Qualification?  Kim

 

 

Date: Sun, 30 July 2006

Subject:  Welding Certification and Qualification

Dear Kim:  Take a look at the American Welding Society (AWS) Bulletin Board – BBS Grand Central under Welding Certification and Qualification, as well as some of the other links on the Online Forums and Conferences page.

 

 

Date: Tue, 3 January 2006

Subject:  Summary of ASME Code Changes

Dear Group:  Does anyone provide a summary of ASME Code changes?  Thanks, Pete

 

 

Date:  Sun, 8 January 2006

Subject:  Summary of ASME Code Changes

Dear Pete:  Take a look at: http://cstools.asme.org/csconnect/public/index.cfm?SummaryOfChanges=yes for the Boiler and Pressure Vessel Code 2005 Addenda.  This is the beginning of a new service by ASME.

 

 

Date: Mon, 14 March 2005

Subject: Historical Section III Editions and Addenda

Dear Group:

 

Where can I find an historical listing of all issued ASME Section III Code editions and addenda?

 

Regards…Gordon

 

 

Date: Wed, 23 March 2005

Subject: Historical Section III Editions and Addenda

Dear Gordon:

 

We are not aware of a public listing providing that information.

 

However, Rick Swayne of Reedy Engineering has offered the following:

 

Reedy Engineering has all of those Editions and Addenda.  Gordon is welcome to drop by our office and make a list of them.  Or he can pay us a modest fee to do that for him.  He might also be able to get that information from the Linda Hall Library in Kansas City.  They might or might not charge for such a list.

 

Rick Swayne can be reached on (408) 558-0330.

The Linda Hall Library can be reached on (800) 662-1545.

 

 

Date: Mon, 10 January 2005

Subject: Standard Welding Procedure Specifications

Dear Group:

 

I want to know whether ASME Section III, Division 1, prohibits the use of a Standard Welding Procedure Specification (SWPS) in ASME Section IX.

 

Thank you, Song

 

 

Date: Wed, 12 January 2005

Subject: Standard Welding Procedure Specifications

Dear Song:

 

ASME Section III does not prohibit or limit the use of ASME Section IX SWPSs.  Therefore, they may be used in Section III construction.

 

Rick Swayne

 

 

Date: Tue, 2 November 2004

Subject: Component Support Load-Bearing and Non-Load-Bearing Members

Dear Group:

Do you know of the existence of a Code Case (like N-62 for valves, or N-119 for pumps), or some other industry recognized guideline document, which provides drawings and/or lists of support components and their descriptions as load-bearing or non-load-bearing members? This would be something in addition to, or other than, the drawings and listings in ASME Section III, Subsection NF, and definitions such as in NF-1215.

If so, can you please give me a hint as to where to find this document?

Thanks, Richard

 

 

Date: Tue, 2 November 2004

Subject: Component Support Load-Bearing and Non-Load-Bearing Members

Dear Richard: I’m sorry to say that we have never seen such a listing. So, I don’t know where you would find such. Not to complicate matters, but it may be possible for a specific support item to be load bearing in one design application and non-load bearing in another. So it may be design specific.

 

 

Date: Tue, 25 May 2004

Subject: NRC Approval of Latest ASME Section III, Section XI, and OM Code

Dear Group: What are the latest versions of the ASME Boiler and Pressure Vessel Codes to be approved by the NRC for Sections III, XI, and OM, and when will they be indicated as approved in 10 CFR 50.55a? Thank you, Alice

 

 

Date: Thur, 27 May 2004

Subject: NRC Approval of Latest ASME Section III, Section XI, and OM Code

Dear Alice: The latest versions of the ASME Boiler and Pressure Vessel Codes to be approved by the NRC for Sections III, XI, and OM will be the 2001 Edition through the 2003 Addenda, and per the May 2004 NRC Section XI Report, http://www.sectionxi.com/Meeting-Notes-and-Reports/NRC-Section-XI-Report(May-2004)W-Norris.html on the Meeting Notes and Reports Page http://www.sectionxi.com/Meeting-Notes-and-Reports/Meeting-Notes-and-Reports.html, they are to be indicated as approved in 10 CFR 50.55a in September 2004.

 

 

Date: Mon, 2 February 2004

Subject: Documentation For Repair/Replacements

Dear Group: Sizewell B is performing a Class 2 repair/replacement on the Reactor Building Spray System piping and supports. The original construction code is the 1983 Edition with the Winter 1985 Addenda of Section III and the current Section XI Code is the 1989 Edition with the Winter 1990 Addenda.

What are the requirements regarding the Section III A-Forms, N-Forms, design specification, revision of original forms, Section XI NIS-2 Form, etc.? Ron

 

 

Date: Thur, 5 February 2004

Subject: Documentation For Repair/Replacements

Dear Ron: The short answer is that any components, parts, or appurtenances to be N or NPT stamped must be furnished in accordance with a Certified Design Specification and supplied with the applicable Section III Code Data Reports.  N-stamped components must be furnished with a Certified Design Report, when that is required by Section III.  The A-Forms are nonmandatory sample statements.  The N-Forms are mandatory.  Revision of original Forms is not required.  See IWA-4300 in the 2003 Addenda for requirements for updating design documentation.  An NIS-2 must be completed for all Repair/Replacement Activities.

Rick Swayne

 

 

Date: Mon, 19 January 2004

Subject: Latest NRC Concerns Regarding ASME Section III

Dear Group: Where can I find the latest NRC concerns regarding ASME Section III. Thanks, Ben

 

 

Date: Sat, 24 January 2004

Subject: Latest NRC Concerns Regarding ASME Section III

Dear Ben: For the latest NRC concerns regarding ASME Section III (proposed modifications and limitations), take a look at the NRC Federal Register, Vol. 69, No. 4, dated Wednesday, January 7, 2004, Pages 879 through 892.

 

 

Date: Mon, 3 November 2003

Subject: ASME Section III Standard and Code

Dear Group: What is it about the ASME Section III Standard that makes it a Code? William

 

 

Date: Sun, 9 November 2003

Subject: ASME Section III Standard and Code

Dear William: The ASME Section III Standard is a Code because the Standard has been adopted by one or more governmental bodies and has the force of law.

 

 

Date: Mon, 21 July 2003

Subject: Class 1 Ellipsoidal Head Design

Dear Group: Section III in ND-3133.4(c) of the 2001 Edition provides guidance for design of Class 3 ellipsoidal heads. However, no such guidance is provided in NB-3133.4 for the design of Class 1 ellipsoidal heads.

Does this mean that Class 1 ellipsoidal heads are not permitted, or does this just mean that there are no code requirements for Class 1 ellipsoidal heads? And if the latter is true, how does one proceed to design a Class 1 ellipsoidal head? Sincerely yours, A. Nikkhah

 

 

Date: Wed, 23 July 2003

Subject: Class 1 Ellipsoidal Head Design

Dear A. Anikkhah: The formulas for Class 2 and 3 are taken from Section VIII, Division 1, and are based on the maximum stress theory. For Class 1 and Section VIII, Division 2, there are no simple formulas because the maximum shear stress theory is used which complicates things a great deal. With the latter, you must subtract the compressive stress from the tensile stress and this value changes at each point. A Class 1 ellipsoidal head will require more thickness than a Class 2 or 3 head, even with the higher allowable stresses of Class 1. But, there is no easy formula. As they say, the Code is not a handbook!

The bottom line is, if you perform a complete stress analysis, using shear stress theory, Class 1 allows an ellipsoidal head, or any head of any shape as long as the correct stress theory is used!

I didn't know of any Class 1 ellipsoidal heads. Same for Div. 2. Hope this answers the question. Roger Reedy

 

 

Date: Tue, 8 April 2003

Subject: Nuclear Vessel Classification

Dear Group: Does the 1968 Edition of ASME Section III use different terminology for Nuclear Class 1, 2 and 3 vessels? Specifically, was Class 1 referred to as Class A? Matt

 

 

Date: Thur, 10 April 2003

Subject: Nuclear Vessel Classification

Dear Matt: Although not always, Quality Group A per 10 CFR 50 is usually recognized and identified as Class 1. Quality Group B and Quality Group C per NRC Regulatory Guide 1.26 is usually recognized and identified as Class 2 and 3 respectively.

 

 

Date: Mon, 10 March 2003

Subject: ASME Code Interpretations

Dear Group: I have copies of several ASME Section XI, Section III, and OM Code Interpretations, but the copies have been retyped and don't indicate which editions and/or addenda they apply to. How can I determine their applicability? Thank you, Fernando

 

 

Date: Thur, 13 March 2003

Subject: ASME Code Interpretations

Dear Fernando: When ASME Section XI, Section III, and OM Code Interpretations are published by ASME, the applicability is indicated in the subject line of each interpretation. Since your copies have been retyped and don't indicate which editions and/or addenda they apply to, you will have to obtain the original versions so that each applicability can be determined.

 

 

Date: Wed, 2 October 2002

Subject: ASME Code Case Applicability

Dear Group: I have copies of many ASME Code Cases but it is not clear how you determine which code editions and addenda they are applicable to. Are code cases applicable to all editions and addenda of the code? Kurt

 

 

Date: Sat, 5 October 2002

Subject: ASME Code Case Applicability

Dear Kurt: No, code cases are only applicable to those editions and addenda of the code as either indicated in the code case or as indicated in the "Applicability Index" located in the front of the official volume of ASME Code Cases.

 

 

Date: Mon, 17 June 2002

Subject: ASME Section III Public Review and Comment Process

Dear Group: Our organization is unable to attend ASME Section III Code Committee meetings, but we would like to participate in the public review and comment process. Can you please tell me how to do that? Bob

 

 

Date: Thur, 20 June 2002

Subject: ASME Section III Public Review and Comment Process

Dear Bob: You can participate in the ASME Section III public review and comment process electronically. If you go to the Libraries and Reference Sources page under "Reference Links" you will find the link your looking for entitled "ASME Codes and Standards - Public Review and Comment".

 

 

Date: Wed, 6 March 2002

Subject: NRC Approval and Disapproval of ASME Section III Code Cases

Dear Group: I understand the NRC has issued new draft regulatory guides proposing the approval and disapproval of ASME Section III code cases. Can you please direct me to where I may find them? Thank you, Cindy

 

 

Date: Fri, 8 March 2002

Subject: NRC Approval and Disapproval of ASME Section III Code Cases

Dear Cindy: The new NRC draft regulatory guides proposing the approval and disapproval of ASME Section III code cases can be found as follows. Go to the Libraries and Reference Sources page and then scroll down under "Reference Links" and click on NRC Draft NUREGS and Draft Regulatory Guides. Click on "Rulemaking Text and Other Documents" and then scroll down to the bottom of the list to file 123-0143.pdf entitled "Draft Regulatory Guide DG-1090 - Design, Fabrication, and Materials Code Case Acceptability, ASME Section III. Also see file 123-0145.pdf entitled "Draft Regulatory Guide DG-1112 - ASME Code Cases Not Approved for Use".

 

 

Date: Mon, 3 December 2001

Subject: ASME Section III Design Requirements

Dear Group: I do not have access to a copy of ASME Section III, therefore can you please tell me what subsections contain the design requirements for Class 1, 2, and 3 Components? Thanks, Brian

 

 

Date: Mon, 3 December 2001

Subject: ASME Section III Design Requirements

Dear Brian: The design requirements for Class 1, 2, and 3 Components are contained in Subsections NB, NC, and ND respectively.

 

 

Date: Tue, 16 October 2001

Subject: ASME Section III and XI Inquiries

Dear Group: Where can I find guidance on the web for submitting inquiries to ASME Section III and Section XI? Thank you, Fred

 

 

Date: Sun, 21 October 2001

Subject: ASME Section III and XI Inquiries

Dear Fred: Take a look at the ASME Guide entitled "Guide to Submittal of Technical Inquiries to an ASME Committee" located at http://www.asme.org/cns/departments/PTCS/Public/InquirySubmittal.html.

 

 

Date: Thur, 16 August 2001

Subject: USNRC Limitations and Modifications of ASME Section III

Dear Group: How can I determine what the USNRC Limitations and Modifications are for implementing ASME Section III in the United States? We appreciate your help, Liu Win

 

 

Date: Tue, 21 August 2001

Subject: USNRC Limitations and Modifications of ASME Section III

Dear Liu: The USNRC Limitations and Modifications for implementing ASME Section III in the United States are published in the United States Code of Federal Regulations 10 CFR 50.55a in Paragraphs (b)(1)(i) through (b)(1)(v).

 

 

Date: Sat, 9 June 2001

Subject: Alloy-600 Weld Cracking Problems

Dear Group: Where can I find information on the Alloy-600 weld cracking problems recently identified at the Summer and Oconee nuclear power plants? Thank you, Dave

 

 

Date: Tue, 12 June 2001

Subject: Alloy-600 Weld Cracking Problems

Dear Dave: Take a look at the U.S. Nuclear Regulatory Commission web site, specifically at http://www.nrc.gov/NRC/REACTOR/ALLOY-600/index.html.

 

 

Date: Fri, 30 March 2001

Subject: Use of ASME Section III with ASME Section II

Dear Group: When applying the 1992 Edition of ASME Section III, is it permissible to use the 1992 Edition of ASME Section II? Steve Roberts

 

 

Date: Sun, 1 April 2001

Subject: Use of ASME Section III with ASME Section II

Dear Steve: No. When applying the 1992 Edition of ASME Section III, it is required by the NRC in 10 CFR 50.55a(b)(1)(i) to use the 1992 Edition with the 1992 Addenda of ASME Section II.

 

 

Date: Thur, 4 January 2001

Subject: Sensitized Stainless Steel

Dear Group: Where does the United States Nuclear Regulatory Commission discuss the use of sensitized stainless steel? Raul

 

 

Date: Sun, 7 January 2001

Subject: Sensitized Stainless Steel

Dear Raul: The United States Nuclear Regulatory Commission (NRC) discusses the use of sensitized stainless steel in the NRC Regulatory Guide 1.44 entitled "Control of the Use of Sensitized Stainless Steel". You may also want to do a search of the "NRC Generic Communications" that are linked on the Libraries and Reference Sources page under "Reference Links".

 

 

Date: Thur, 16 March 2000

Subject: Seismic Design Classification

Dear Group: Can someone please tell me what standard is generally followed in the United States for seismic design classification of ASME Section III nuclear power plant systems and components? Dajun

 

 

Date: Sun, 19 March 2000

Subject: Seismic Design Classification

Dear Dajun: Most nuclear power plants in the United States were seismically classified in accordance with NRC Regulatory Guide 1.29, entitled "Seismic Design Classification". Robert

 

 

Date: Wed, 10 November 1999

Subject: NRC Approval of 1996 Addenda for ASME Section III

Dear Group: I understand that the NRC has placed limitations on their approval of the 1996 Addenda of ASME Section III. Is this true, and if so where is this discussed? Shawn

 

 

Date: Fri, 12 November 1999

Subject: NRC Approval of 1996 Addenda for ASME Section III

Dear Shawn: The NRC did place five limitations and modifications on the implementation of the 1996 Addenda of ASME Section III. You will find this discussed in the September 22, 1999 Federal Register as referenced below in the response dated Wed, 29 September 1999.

 

 

Date: Mon, 27 September 1999

Subject: NRC Approval of 1996 Addenda for ASME Section III, Section XI, and Operations and Maintenance Code

Dear Group: Where can I find a copy of the NRC final rule for their acceptance of the 1996 Addenda of the ASME Boiler and Pressure Vessel Code, for Section III, Section XI, and the Operations and Maintenance Code? Charlie

 

 

Date: Wed, 29 September 1999

Subject: NRC Approval of 1996 Addenda for ASME Section III, Section XI, and Operations and Maintenance Code

Dear Charlie: The approval was issued in the Federal Register on Wednesday, September 22, 1999. The document is available from the "Federal Register: 1999 Issues" link provided on this site on the Libraries and Reference Sources page, under "Reference Links". Scroll down the Federal Register page to Nuclear Regulatory Commission, RULES, [FR Doc.99-24256]. Dennis

 

 

Date: Thur, 14 Jan 1999

Subject: Classification of Containment Piping Penetration Flued Heads

Hello Group: I would appreciate a little help from anyone. What guidance is available for classifying the flued head with its integral attachment to piping at containment penetrations? Should the flued head be considered a component support, recognizing that the pipe stress analyst may have treated it as an anchor point in the analysis, or should it be considered an integral part of the piping that performs a containment boundary function? Any response will be helpful. Thank you. Jose

 

 

Date: Tue, 2 Feb 1999

Subject: Classification of Containment Piping Penetration Flued Heads

Dear Jose: The 1989 Edition of ASME Section III, Rules for Class 1 Components in Paragraph NB-1132.2(a), entitled "Jurisdictional Boundary" states "Attachments cast or forged with the component and weld buildup on the component surface shall be considered part of the component." Since piping systems are considered to be components, an argument can be made that the flued head is part of the piping system, and therefore is not a component support. Further classification guidance is provided in ASME Section III for containment penetrations in Figure NE-1120-1 entitled "Typical Containment Penetrations". Hope this helps. Dennis

 

 

Date: Tue, 27 Oct 1999

Subject: Classification of Service Water Systems

Dear Group: Can someone please point me to specific reference sources that discuss the classification of Service Water Systems in Nuclear Power Plants? Thanks in advance. Jeff

 

 

Date: Sat, 7 Nov 1998

Subject: Classification of Service Water Systems

Dear Jeff: You will find plenty to read on classifying Service Water Systems and Class 3 Essential Systems in NRC Generic Letter 89-13 (including Supplement 1), NRC Information Notice 94-03, NRC IE Manual/Instruction -2515/118, and NUREG-0800 Sections 9.2.1, 9.2.2, 9.2.6, 9.3.4, 9.5.4, 9.5.8, 10.4.9. Don

 

 

Date: Mon, 14 Sep 1998

Subject: Classification of U.S. Diesel Generator Fuel Oil Systems

Dear User Group: What guidance is available for the classification of diesel generator fuel oil systems in the United States? Thanks again. Hin Liu

 

 

Date: Thur, 17 Sep 1998

Subject: Classification of U.S. Diesel Generator Fuel Oil Systems

Dear Hin: Take a look at NRC Regulatory Guide 1.137 and NRC Standard Review Plan, Sections 9.5.4 and 9.5.8. Jeromy

 

 

Date: Fri, 11 Sep 1998

Subject: Classification of U.S. Nuclear Systems

Dear User Group: What federal regulations are generally followed in the United States when classifying mechanical safety related nuclear power plant systems? Thank you. Hin Liu

 

 

Date: Mon, 14 Sep 1998

Subject: Classification of U.S. Nuclear Systems

Dear Hin: The classification of the reactor coolant pressure boundary is generally Class 1 (Quality Group A) in accordance with the Code of Federal Regulations 10CFR50.2. The classification of the safety related systems is generally Class 2 and 3 (Quality Group B and C) in accordance with NRC Regulatory Guide 1.26. Also see the NRC Standard Review Plan, NUREG-0800, Section 3.2.2, "System Quality Group Classification". Richard

 

 

Date: Tue, 8 Sep 1998

Subject: Design Criteria for Future Inspections

Dear User Group: What design criteria is mandated in the United States to ensure adequate access for future inspection and testing? Ho Lin

 

 

Date: Thur, 10 Sep 1998

Subject: Design Criteria for Future Inspections

Dear Ho: The basic criteria is contained in 10CFR50, Appendix A, entitled "General Design Criteria". See Criterion No. 32, 36, 37, 39, 40, 42, 43, 45, 46, 54, and 55 for guidance on various systems and equipment.