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Federal Regulations, Codes, &
Standards Users Group © |
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Federal Regulations, Codes, & Standards Bulletin Board - General |
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Welcome to the General 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 general questions and replies that are relevant to the implementation and use of nuclear power federal regulations, codes, and standards. 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. To search this bulletin board for key words and phrases, click on "Edit" on your web browser tool bar and then click "Find ... ". In the resulting dialog box, insert the desired key word or phrase and then click "Find ... ", repeatedly as necessary to locate multiple entries as you proceed through the page. |
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Note: All information provided on this bulletin board is provided "as is", without warranty of any kind, as stipulated in the Disclaimer and Conditions of Use for this web site. |
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Bulletin Board Postings: |
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Date: Tuesday, 24 June 2008 Subject: Dear
Group: Where can I find technical information on
the |
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Date: Friday, 27 June 2008 Subject: Dear
Jeanie: Please take a look at http://www.pbmr.co.za/index.asp?Content=182. |
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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 |
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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. |
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Date: Tuesday, 31 October 2006 Subject: NUREG-0492 Fault Tree Handbook Dear
Group: I am looking to purchasing the "fault
tree analysis" NUREG-0492. Can
you assist? Thank you, Gooliver |
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Date: Wednesday, 1 November 2006 Subject: NUREG-0492 Fault Tree Handbook Dear
Gooliver: You
will find a path for a free copy of NUREG-0492 “Fault Tree Handbook” on the
page http://www.usnrc.com/Libraries-and-References.html
, under Reference Links entitled NRC NUREG-Series Publications. Once you have clicked on the NRC
NUREG-Series Publications link, click on Publications Prepared by NRC
Staff, and scroll down to the link for a free copy of NUREG-0492. |
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Date: Friday, 29 September 2006 Subject: Spent Fuel Transport Package Dear
Group: in 10cfr 71.43(g), the accessible surface
of a spent fuel transport package should not be exceeded 85°C (185°F); for
the exclusive use shipment. the problem is i can identify the definition of
the accessible surface of package from the description of code, and if there
is personal barrier, is the surface of the barrier be defined as accessible
surface or not? yours sincerely, liu
zhenling |
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Date: Wednesday, 4 October 2006 Subject: Spent Fuel Transport Package Dear Liu: It would be reasonable to assume that if the “personal
barrier” is part of the package, then the accessible surface of the personal
barrier would also be included and governed by the requirements of 10 CFR 71.43(g). For additional information, you
could ask your same question on the U.S. NRC Web Site at http://www.nrc.gov/site-help/feedback.html
. |
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Date: Monday, 24 July 2006 Subject: Storage of Nuclear Fuel Dear
Group: Can you direct me to a good
reference source on U.S regulations for storage of nuclear fuel? Thank you, Gail |
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Date: Sunday, 30 July 2006 Subject: Storage of Nuclear Fuel Dear
Gail: The U.S. Nuclear Regulatory
Commission offers an extensive reference source on storage of nuclear fuel at
http://www.nrc.gov/waste/spent-fuel-storage.html. |
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Date: Tue, 3 January 2006 Subject: Summary of ASME Code Changes Dear
Group: Does anyone provide a summary
of ASME Code changes? Thanks, Pete |
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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. |
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Date: Fri, 5
November 2004 Subject:
Procurement of ASME Codes and Standards that are Out of Print Dear Group: Where
does one purchase ASME Codes and Standards when they are out of print and no
longer offered by ASME? Thank you, Don |
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Date: Sun, 7
November 2004 Subject:
Procurement of ASME Codes and Standards that are Out of Print Dear Don: ASME
recommends purchasing ASME Codes and Standards that are out of print and no
longer offered by ASME through the Linda Hall Library of Science, Engineering
& Technology. A link to the Linda Hall Library and order form has been
placed on the Libraries and Reference
Sources page under Reference Links. |
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Date: Mon, 24 May
2004 Subject: NRC
Exceptions to Mandatory Codes and Standards Dear Group: Where
does the NRC publish their exceptions to mandatory codes and standards? Thank
you, Martin |
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Date: Thur, 27
May 2004 Subject: NRC
Exceptions to Mandatory Codes and Standards Dear Martin: The
NRC publishes their exceptions to mandatory codes and standards in the Code
of Federal Regulations 10 CFR 50.55a, which is available on the Libraries and
Reference Sources Page http://www.sectionxi.com/Libraries-and-References.html. |
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Date: Tues, 20
January 2003 Subject: Plant
License Renewal Dear Group: I
would like to educate myself on the subject of plant license renewal. What documents
do you recommend I read and where can I find them? Thank you,
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Date: Sat, 24
January 2004 Subject: Plant
License Renewal Dear Gary: Take a
look at the following. 1. 10 CFR Part 54
"Requirements for Renewal of Operating Licenses for Nuclear Power
Plants" 2. NEI 95-10
"Industry Guideline for Implementing the Requirements of 10 CFR Part 54
- The License Renewal Rule" 3. NUREG-1800
"Standard Review Plan for Review of License Renewal Applications for
Nuclear Power Plants" 4. NUREG-1801
"Generic Aging Lessons Learned (GALL) Report These documents
and others are available on the NRC website located at http://www.nrc.gov/reactors/operating/licensing/renewal.html.
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Date: Tues, 4
November 2003 Subject: Errata Dear Group: If
the errata process can not to be used for technical changes in an addenda to
a Code, why is it we periodically see errata referenced for a technical
change in an addenda to the Code? Bill
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Date: Wed, 5
November 2003 Subject: Errata Dear Bill: If a
technical change is properly voted on by the appropriate committees and then
the technical change in the addenda is inadvertently omitted during printing
or contains errors inadvertently created during printing, then the technical
change is corrected in a subsequent addenda by errata and so noted.
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Date: Tue, 5
August 2003 Subject:
ANSI/ASME NQA-3 Dear Group: The standard
ANSI/ASME NQA-3 that dealt with quality assurance requirements for high level
waste was withdrawn several years ago. Are you aware of another (current)
standard that deals with this subject to be used by an organization that
wishes to develop a QA program for working with nuclear waste (other than 10
CFR 71, 72, etc.)? Martin
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Date: Fri, 8
August 2003 Subject:
ANSI/ASME NQA-3 Dear Martin:
Apparently NQA-3 has been incorporated into NQA-1. As indicated in the
forward of the 1997 Edition of NQA-1, guidance regarding the application of
NQA-3 was to be included in Part III or Part IV of NQA-1.
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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
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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.
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Date: Wed, 2
October 2002 Subject: ASME
Code Changes Dear Group: If I
can't attend ASME Code Meetings, what's the best way to keep somewhat informed
with the latest code changes for nuclear power? Willis
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Date: Sat, 5
October 2002 Subject: ASME
Code Changes Dear Willis: Some
of the information is available at the ASME web site located at http://www.asme.org. Also, take a look at our Meeting Notes
and Reports page
located on our site.
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Date: Mon, 17
June 2002 Subject: ASME
Code Cases Not Approved For Use Dear Group: Where
can I find a list of ASME Code Cases that are not approved for use by the
USNRC? Jenny
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Date: Wed, 19
June 2002 Subject: ASME
Code Cases Not Approved For Use Dear Jenny: For ASME
Code Cases pertaining to Section III, XI, and the OM Code, take a look at the
following: 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 123-0145.pdf entitled "Draft Regulatory Guide
DG-1112 - ASME Code Cases Not Approved for Use".
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Date: Wed, 17
April 2002 Subject: Best
Current Informational Source Document Dear Group: Can
you please recommend a good informational source document that discusses the
current status of
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Date: Fri, 19
April 2002 Subject: Best
Current Informational Source Document Dear Bernard: The
best informational source document that discusses the current status of
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Date: Wed, 5
March 2002 Subject: Public
Review and Comment on ASME Codes and Standards Dear Group: Where
can the public review and comment on ASME Codes and Standards? Thanks, Bill
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Date: Fri, 8
March 2002 Subject: Public
Review and Comment on ASME Codes and Standards Dear Bill: The public
can review and comment on ASME Codes and Standards by going to the Libraries and Reference Sources page and clicking on the
link entitled "ASME Codes & Standards - Public Review and
Comment" under Reference Links.
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Date: Wed, 16
January 2002 Subject: US
Reactors - Ownership and Management Changes Dear Group: Where
can I find some historical information on the changes of ownership and
management of nuclear power plants in the
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Date: Fri, 18
January 2002 Subject: US
Reactors - Ownership and Management Changes Dear Willis: You
will find some historical information on the changes of ownership and
management of nuclear power plants on the Nuclear Energy Institute (NEI) web
site at http://www.nei.org/doc.asp?catnum=3&catid=18.
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Date: Sat, 1
December 2001 Subject: List of
Decommissioned Nuclear Power Plants Dear Group: Where
can I find a list of decommissioned nuclear power plants? Thanks for your
help, John
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Date: Sun, 2
December 2001 Subject: List of
Decommissioned Nuclear Power Plants Dear John: You
will find a list of decommissioned nuclear power plants at http://www.nei.org/doc.asp?catnum=3&catid=19.
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Date: Thur, 18
October 2001 Subject:
Distinction of a Code Versus a Standard Dear Group: Can you
please tell me what is the distinction between a Code versus a Standard?
Thanks,
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Date: Sun, 21
October 2001 Subject:
Distinction of a Code Versus a Standard Dear Virginia:
According to ASME, a Code is a Standard that has been adopted by one or more
governmental bodies and has the force of law.
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Date: Thur, 16
August 2001 Subject: NRC
Proposed Amendment to Revise 10 CFR 50.55a Dear Group: I
understand that the NRC recently issued a proposed amendment to revise 10 CFR
50.55a to adopt ASME Section III, XI, and the OM Code up to and including the
2000 Addenda. Can you please direct me to where I may find it? Thank you,
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Date: Tue, 21
August 2001 Subject: NRC
Proposed Amendment to Revise 10 CFR 50.55a Dear Wayne: The
proposed amendment to revise 10 CFR 50.55a to adopt ASME Section III, XI, and
the OM Code up to and including the 2000 Addenda was published in the Federal
Register on Friday August 3, 2001. You will find it available from the Libraries and Reference Sources page under
"Reference Links" by using the link provided for the Federal
Register: 2001 Issues, then
scroll down to "Nuclear Regulatory Commission/Proposed Rules".
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Date: Fri, 15
June 2001 Subject:
Extension of Nuclear Power Plant Operating Licenses Dear Group: Where
is the best place to find general information on extending a nuclear power plant
operating license beyond the typical 40 years? Gina
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Date: Fri, 15
June 2001 Subject:
Extension of Nuclear Power Plant Operating Licenses Dear Gina: The
best place we know of is on the U.S. Nuclear Regulatory Commission web site,
specifically at http://www.nrc.gov/NRC/REACTOR/LR/index.html.
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Date: Thur, 29
March 2001 Subject: Purchase
of ASME Codes Dear Group: Where
can I purchase ASME Codes? Opbhatia General Manager Everest Transmission,
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Date: Fri, 30
March 2001 Subject: Purchase
of ASME Codes Dear Opbhatia:
You can purchase copies of ASME Codes directly from ASME in
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Date: Wed, 3
January 2001 Subject: V. C.
Summer Event Dear Group: Where
can I find information regarding the event that was discovered at the V. C.
Summer Nuclear Power Plant on October 7, 2000? Thanks for your help. Sara
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Date: Sat, 6
January 2001 Subject: V. C.
Summer Event Dear Sara: You
will be able find information regarding the event that was discovered at the V.
C. Summer plant on October 7, 2000 by using the NRC V. C. Summer Event link
provided on the Quick Links page.
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Date: Wed, 13
September 2000 Subject: NRC
Review of Updated Final Safety Analysis Reports (UFSAR's) Dear Group: What
document provides the NRC general guidelines for reviewing and evaluating
Updated Final Safety Analysis Reports for nuclear power plants? Peter
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Date: Fri, 15
September 2000 Subject: NRC Review
of Updated Final Safety Analysis Reports (UFSAR's) Dear Peter: The
NRC Standard Review Plan NUREG-0800 provides the NRC general guidelines for
reviewing and evaluating Updated Final Safety Analysis Reports for nuclear
power plants. A few sections of NUREG-0800 are available from the Libraries and Reference Sources page under Reference
Links using the NRC NUREG links.
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Date: Fri, 20
July 2000 Subject: NRC
Generic Communications Dear Group: Can
someone please tell me where I might find an NRC publication that describes
the purpose of each of the NRC Generic Communication documents such as
Bulletins, Generic Letters, Information Notices, etc.? Thanks to all, Marsha
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Date: Fri, 20
July 2000 Subject: NRC
Generic Communications Dear Marsha: You
will find the purpose of each of the NRC Generic Communication documents
described in the NRC Regulatory Issue Summary 99-01, entitled "Revisions
to the Generic Communications Program". The NRC Regulatory Issue Summary
99-01 can be accessed from the Libraries
and Reference Sources
page under Reference Links as a NRC Generic Communication.
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Date: Mon, 26
June 2000 Subject:
Common-Cause Failures Dear Group: I am
trying to educate myself on the subject of Common-Cause Failures in nuclear
power plants. Can someone please suggest some NRC applicable reading
materials? Thank you, Jay
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Date: Wed, 28
June 2000 Subject:
Common-Cause Failures Dear Jay: For NRC
Common-Cause Failure reading materials, you could start with the following:
NRC Administrative Letter 98-04, "Availability of Common-Cause Failure
Database"; NUREG/CR-5497, "Common-Cause Failure Parameter
Estimations", NUREG/CR-6268; "Common-Cause Failure Database and
Analysis System; and NRC Regulatory Issue Summary 99-03. The NRC
Administrative Letter and the Regulatory Issue Summary are both available
from the "NRC Generic Communications" link provided at this site on
the Libraries and Reference
Sources page
under "References Links". Dennis
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Date: Thur, 23
March 2000 Subject: United
Nations Organization Dear Group: Could
you please tell me what United Nations Organization oversees and coordinates
nuclear power information for its participating countries and where I might
find their web site? Ronald J.
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Date: Fri, 24
March 2000 Subject: United
Nations Organization Dear Ronald: The
United Nations Organization that oversees and coordinates nuclear power
information for its participating countries is the International Atomic
Energy Agency (IAEA) located in
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Date: Mon, 8
November 1999 Subject: NRC
Federal Register Dear Group: Would
someone please indicate where I can find copies of the Federal Register as published
by the Nuclear Regulatory Commission in the
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Date: Fri, 12
November 1999 Subject: NRC
Federal Register Dear Debbie: You
will find several links to the NRC Federal Register on the Libraries and Reference Sources page under
"Reference Links".
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Date: Thur, 16
September 1999 Subject: Code of
Federal Regulations - 10 CFR 30.35 Dear Group: I would
like to know what statutory authority NRC has to impose financial assurance
requirements pursuant 10 CFR 30.35 upon entities operating under a 42 USC
2014(e)(1) classification (Cobalt-60). JDAL
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Date: Tue, 28
September 1999 Subject: Code of Federal
Regulations - 10 CFR 30.35 Dear JDAL: The
referenced 10CFR section states that licensees must provide evidence of
financial assurance before they can utilize licensed radioactive sources. I
believe the answer to this question is twofold. First, If the license was
issued through the NRC, then the NRC has the authority to invoke this
requirement. Second, If this requirement is providing an undue financial
hardship, then relief can always be sought. If it is a matter of excessive
paperwork, then nothing short of a congressional mandate can help. One final
thought, ask the NRC. The region would be happy to provide an answer...(no
joke here). It might save some problems in the long run. Russ Day
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Date: Tue, 29
June 1999 Subject: Relief
Requests - Code of Federal Regulations Dear Group: Where
are relief requests discussed in the Code of Federal Regulations? Thanks in
advance. Jim
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Date: Fri, 16
July 1999 Subject: Relief
Requests - Code of Federal Regulations Dear Jim: For discussion
on relief requests in the Code of Federal Regulations, take a look at 10 CFR
50.55a(a)(3), 10 CFR 50.55a(g)(5)(iii), (iv), and (6i). Sara
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Date: Thur, 24
Sep 1998 Subject: Nuclear
Plant Configuration Management Dear Group: Can
someone please suggest some
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Date: Sun, 4 Oct
1998 Subject: Nuclear Plant
Configuration Management Dear Warren: For
NRC requirements regarding unreviewed safety questions, plant changes,
maintenance of records, and submittal of reports see 10CFR50.59 and
10CFR50.71. Also see NRC Inspection Procedure 37001 "10CFR50.59 Safety
Evaluation Program" and NUREG-1397 "An Assessment of Design Control
Practices and Design Reconstitution Programs in the Nuclear Industry".
Jerry
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Date: Tue, 4 Aug
1998 Subject: NRC
Regulatory Guides Hello Everyone: I
was trying to check the status of three NRC Regulatory Guides in the link
provided at this site under Libraries and Reference Sources and found that
all three have been withdrawn by the NRC. The guides in question are 1.58
"Qualification of Nuclear Power Plant Inspection, Examination, and
Testing Personnel (Rev. 1)", 1.88 "Collection, Storage, and
Maintenance of Nuclear Power Plant Quality Assurance Records (Rev. 2)",
and 1.123 Quality Assurance Requirements for Control of Procurement of Items
and Services for Nuclear Power Plants (Rev. 1)". Can anyone tell me what
the basis was for withdrawing these guides? Thanks in advance. Larry Barten
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Date: Fri, 7 Aug
1998 Subject: NRC
Regulatory Guides Hi Larry:
According to NRC letter dated June 17, 1991, all three regulatory guides in
question were withdrawn, along with three others (1.64, 1.144, and 1.146),
because they had become obsolete and incorporated into ANSI/ASME NQA-1-1983
entitled "Quality Assurance Program Requirements for Nuclear
Facilities". However as indicated in the letter, the withdrawal of these
regulatory guides does not alter any prior or existing licensing commitments
based on their use". Hope this helpful. Frank
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Date: Wed, 22 Jul
1998 Subject:
10CFR50.55a Public Comments Dear Group: Where
can I find the public comments for the NRC recently proposed new rules in
10CFR50.55a? Thanks, Don
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Date: Thur, 23
Jul 1998 Subject: 10 CFR
50.55a Public Comments Dear Don: For the
recent 10CFR50.55a public comments, go the Users Group Quick Links page and select "NRC Current
Rulemakings", then select "Proposed Rulemaking-Industry Codes and
Standards; Amended Requirements", then select "Public
Comments". Dennis
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Date: Tue, 21 Jul
1998 Subject: Plant
Description Documents Dear User Group:
Where can I find design and technical information on various nuclear plants
in the
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Date: Tue, 21 Jul
1998 Subject: Plant
Description Documents For design and
technical information on various nuclear plants in the
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Date: Mon, 20 Jul
1998 Subject: Code of Federal
Regulations 10CFR50.55a Dear User Group:
Where do I find links in the Users Group web page to 10CFR50.55a and NRC SECY
Papers? Thank you. Katie
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Date: Mon, 20 Jul
1998 Subject: Code of
Federal Regulations 10CFR50.55a Hi Katie: You
will find links to 10CRF50.55a and NRC SECY Papers on the Users Group web
page at Libraries and
Reference Sources
under "Reference Links".
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