Limit of Error Concepts and Principles of Calculation in Nuclear Materials Control, 12142-12143 [2017-03891]
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Federal Register / Vol. 82, No. 38 / Tuesday, February 28, 2017 / Notices
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are listed in the Safety Evaluation
enclosed with the amendments.
Renewed Facility Operating License
Nos. NPF–57, DPR–70, and DPR–75: The
amendments revised the Renewed
Facility Operating Licenses and the TSs.
Date of initial notice in Federal
Register: November 22, 2016 (81 FR
83877). The supplemental letter dated
December 19, 2016, provided additional
information that clarified the
application, did not expand the scope of
the application as originally noticed,
and did not change the staff’s original
proposed no significant hazards
consideration determination as
published in the Federal Register.
The Commission’s related evaluation
of the amendments is contained in a
Safety Evaluation dated February 6,
2017.
No significant hazards consideration
comments received: No.
Southern Nuclear Operating Company,
Docket No. 52–025, Vogtle Electric
Generating Plant (VEGP), Unit 3, Burke
County, Georgia
Date of amendment request:
September 13, 2016.
Description of amendment: The
amendment authorizes changes to the
VEGP Units 3 and 4 Updated Final
Safety Analysis Report in the form of
departures from the incorporated plant
specific Design Control Document Tier
2* information. The departures change
the provided minimum reinforcement
area in the VEGP Unit 3 column line 7.3
wall from elevation 82′-6″ to elevation
100′-0″.
Date of issuance: January 30, 2017.
Effective date: As of the date of
issuance and shall be implemented
within 30 days of issuance.
Amendment No.: 68. A publiclyavailable version is in ADAMS under
Accession No. ML16350A060;
documents related to this amendment
are listed in the Safety Evaluation
enclosed with the amendment.
Facility Combined Licenses No. NPF–
91: Amendment revised the Facility
Combined License.
Date of initial notice in Federal
Register: October 11, 2016 (81 FR
70175).
The Commission’s related evaluation
of the amendment is contained in the
Safety Evaluation dated January 30,
2017.
No significant hazards consideration
comments received: No.
Southern Nuclear Operating Company,
Docket Nos. 52–025 and 52–026, Vogtle
Electric Generating Plant (VEGP), Units
3 and 4, Burke County, Georgia
Date of amendment request: May 27,
2016.
VerDate Sep<11>2014
18:46 Feb 27, 2017
Jkt 241001
Description of amendment: The
amendment authorizes changes to the
VEGP Units 3 and 4 Updated Final
Safety Analysis Report in the form of
departures from the incorporated plant
specific Design Control Document Tier
2 information and involves changes to
COL Appendix A Technical
Specifications and associated Bases. The
changes add reactor coolant density
compensation to the reactor coolant
flow input signal to the Reactor Trip
System instrumentation for the low
reactor coolant flow reactor trip
function and add Technical
Specification Surveillance Requirement
3.3.1.3 to the surveillances required for
the Reactor Coolant Flow-Low reactor
trip.
Date of issuance: January 13, 2017.
Effective date: As of the date of
issuance and shall be implemented
within 30 days of issuance.
Amendment No.: 65. A publiclyavailable version is in ADAMS under
Accession No. ML16348A073;
documents related to this amendment
are listed in the Safety Evaluation
enclosed with the amendment.
Facility Combined Licenses Nos. NPF–
91 and NPF–92: Amendment revised the
Facility Combined License.
Date of initial notice in Federal
Register: August 2, 2016 (81 FR 50729).
The Commission’s related evaluation
of the amendment is contained in the
Safety Evaluation dated January 13,
2017.
No significant hazards consideration
comments received: No.
Dated at Rockville, Maryland, this 17th day
of February 2017.
For the Nuclear Regulatory Commission.
Kathryn M. Brock,
Deputy Director, Division of Operating
Reactor Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2017–03806 Filed 2–27–17; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2017–0059]
Limit of Error Concepts and Principles
of Calculation in Nuclear Materials
Control
Nuclear Regulatory
Commission.
ACTION: Regulatory guide: withdrawal.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is withdrawing
Regulatory Guide (RG) 5.18, ‘‘Limit of
Error Concepts and Principles of
Calculation in Nuclear Materials
SUMMARY:
PO 00000
Frm 00064
Fmt 4703
Sfmt 4703
Control.’’ This RG is being withdrawn
because the term ‘‘limit of error’’ is no
longer used in the material control and
accounting (MC&A) requirements in
NRC’s regulations, and therefore the RG
5.18 guidance is no longer needed. The
MC&A requirements now include the
term ‘‘standard error’’ in place of the
term ‘‘limit of error.’’ The ‘‘standard
error’’ term is used in evaluating the
significance of an inventory difference
(ID). The NRC has issued guidance
separately for the term ‘‘standard error.’’
DATES: The effective date of the
withdrawal of RG 5.18 is February 28,
2017.
ADDRESSES: Please refer to Docket ID
NRC–2017–0059 when contacting the
NRC about the availability of
information regarding this document.
You may obtain publically-available
information related to this document,
using the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2017–0059. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–415–3463;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individuals listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publiclyavailable documents online in the
ADAMS Public Document collection at
https://www.nrc.gov/reading-rm/
adams.html. To begin the search, select
‘‘ADAMS Public Documents’’ and then
select ‘‘Begin Web-based ADAMS
Search.’’ For problems with ADAMS,
please contact the NRC’s Public
Document Room (PDR) reference staff at
1–800–397–4209, 301–415–4737, or by
email to pdr.resource@nrc.gov. The
ADAMS accession number for each
document referenced (if it is available in
ADAMS) is provided the first time that
it is mentioned in this document. The
basis for the withdrawal of this guide is
in ADAMS under Accession No.
ML16244A672.
• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, Room O1–F21, One
White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
Regulatory guides are not
copyrighted, and NRC approval is not
required to reproduce them.
FOR FURTHER INFORMATION CONTACT:
Glenn Tuttle, Office of Nuclear
Materials Safety and Safeguards,
telephone: 301–415–7230, email:
Glenn.Tuttle@nrc.gov; and Harriet
Karagiannis, Office of Nuclear
E:\FR\FM\28FEN1.SGM
28FEN1
12143
mstockstill on DSK3G9T082PROD with NOTICES
Federal Register / Vol. 82, No. 38 / Tuesday, February 28, 2017 / Notices
Regulatory Research, telephone: 301–
415–2493, email: Harriet.Karagiannis@
nrc.gov. Both are staff members of the
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001.
SUPPLEMENTARY INFORMATION: The NRC
staff issued RG 5.18 in January 1974 to
provide guidance on meeting the
material control and accounting (MC&A)
requirements in part 70 of title 10 the
Code of Federal Regulations (10 CFR),
‘‘Domestic Licensing of Special Nuclear
Material.’’ Part 70 then contained MC&A
requirements, including those in 10 CFR
70.51, ‘‘Material Balance, Inventory, and
Records Requirements’’ that were
established in 1973. Specifically, 10
CFR 70.51(a)(5) defined the term ‘‘Limit
of error,’’ and 10 CFR 70.51(e) required
licensees to calculate statistical limits of
error for any material unaccounted for
as part of their MC&A procedures. Part
70 regulations no longer contain any
MC&A requirements, and licensees are
no longer required to calculate
statistical limits of error for any material
unaccounted for. In 1985, 10 CFR part
74, ‘‘Material Control and Accounting of
Special Nuclear Material,’’ was
established, and in 2002, the 10 CFR
70.51 requirements were transferred to
10 CFR part 74 which now includes the
current MC&A requirements. As part of
the 2002 MC&A revisions, the term
‘‘limit of error’’ was replaced by the
term ‘‘standard error,’’ and licensees are
now required to calculate the
‘‘inventory difference’’ (as defined in 10
CFR 74.4) rather than determining the
amounts of material that are
‘‘unaccounted for.’’ The ‘‘standard
error’’ is used in evaluating the
significance of an inventory difference
(ID).
Guidance for calculating the
‘‘standard error’’ of the ID is found in
NUREG–1065, ‘‘Acceptable Standard
Format and Content for the
Fundamental Nuclear Material Control
(FNMC) Plan Required for LowEnriched Uranium Facilities’’ (ADAMS
Accession No. ML031340288), NUREG–
1280, ‘‘Standard Format and Content
Acceptance Criteria for the Material
Control and Accounting (MC&A) Reform
Amendment’’ (ADAMS Accession No.
ML13253A308), and NUREG/CR–5734,
‘‘Recommendations to the NRC on
Acceptable Standard Format and
Content for the Fundamental Nuclear
Material Control (FNMC) Plan Required
for Low-Enriched Uranium Enrichment
Facilities’’ (ADAMS Accession No.
ML15120A354).
In addition, RG 5.18 endorsed the
American National Standards Institute
Standard N15.16–1974, ‘‘Limit of Error
Concepts and Principles of Calculation
VerDate Sep<11>2014
18:46 Feb 27, 2017
Jkt 241001
in Nuclear Materials Control,’’ to
provide guidance on the ‘‘limit of error’’
concept. However, this standard has
been withdrawn from active status with
no replacement.
The NRC is withdrawing RG 5.18
because it is no longer needed.
Withdrawal of an RG means that the
guide no longer provides useful
information or has been superseded by
other guidance, technological
innovations, congressional actions, or
other events. The withdrawal of RG 5.18
does not alter any prior or existing NRC
licensing approval or the acceptability
of licensee commitments to RG 5.18.
Although RG 5.18 is withdrawn, current
licensees may continue to use it, and
withdrawal does not affect any existing
licenses or agreements. However, 5.18
should not be used in future requests or
applications for NRC licensing actions.
Dated at Rockville, Maryland, this 21st day
of February 2017.
For the Nuclear Regulatory Commission.
Harriet Karagiannis,
Acting Chief, Regulatory Guidance and
Generic Issues Branch, Division of
Engineering, Office of Nuclear Regulatory
Research.
[FR Doc. 2017–03891 Filed 2–27–17; 8:45 am]
BILLING CODE 7590–01–P
PEACE CORPS
Information Collection Request;
Submission for OMB Review
Peace Corps.
60-day notice and request for
comments.
AGENCY:
ACTION:
The Peace Corps will be
submitting the following information
collection request to the Office of
Management and Budget (OMB) for
review and approval. The purpose of
this notice is to allow 60 days for public
comment in the Federal Register
preceding submission to OMB. We are
conducting this process in accordance
with the Paperwork Reduction Act of
1995 (44 U.S.C. Chapter 35).
DATES: Submit comments on or before
May 1, 2017.
ADDRESSES: Comments should be
addressed to Denora Miller, FOIA/
Privacy Act Officer. Denora Miller can
be contacted by telephone at 202–692–
1236 or email at pcfr@peacecorps.gov.
Email comments must be made in text
and not in attachments.
FOR FURTHER INFORMATION CONTACT:
Denora Miller at Peace Corps address
above.
SUPPLEMENTARY INFORMATION:
Title: Confidential Reference Form.
SUMMARY:
PO 00000
Frm 00065
Fmt 4703
Sfmt 4703
OMB Control Number: 0420–0006.
Type of Request: Revision.
Affected Public: Individuals.
Respondents Obligation to Reply:
Voluntary.
Respondents: Individuals.
Burden to the Public:
Estimated burden (hours) of the
collection of information:
a. Number of respondents ..
b. Frequency of response ...
c. Completion time .............
d. Annual burden hours ....
18,000.
one time.
10 minutes.
3,000 hours.
General Description of Collection: The
reference form is a tool that the Peace
Corps employs to ensure a standardized
suitability review of applicants. The
Assessment and Placement Officer
requests the completion of the reference
form and uses the information therein to
assist in determining the suitability and
competitiveness of the applicant.
Request for Comment: Peace Corps
invites comments on whether the
proposed collections of information are
necessary for proper performance of the
functions of the Peace Corps, including
whether the information will have
practical use; the accuracy of the
agency’s estimate of the burden of the
proposed collection of information,
including the validity of the information
to be collected; and, ways to minimize
the burden of the collection of
information on those who are to
respond, including through the use of
automated collection techniques, when
appropriate, and other forms of
information technology.
This notice is issued in Washington, DC,
on February 23, 2017.
Denora Miller,
FOIA/Privacy Act Officer, Management.
[FR Doc. 2017–03862 Filed 2–27–17; 8:45 am]
BILLING CODE 6051–01–P
OFFICE OF PERSONNEL
MANAGEMENT
Comment Request for Review of a
Revised Information Collection: MultiState Plan Program External Review
Case Intake Form, OPM Form 1840
Office of Personnel
Management.
ACTION: Notice.
AGENCY:
The Office of Personnel
Management (OPM) intends to submit to
the Office of Management and Budget
(OMB) a request for review of a revision
of a currently approved collection, the
Multi-State Plan Program External
Review Intake Form, OPM Form 1840.
Approval of the revised Multi-State Plan
SUMMARY:
E:\FR\FM\28FEN1.SGM
28FEN1
Agencies
[Federal Register Volume 82, Number 38 (Tuesday, February 28, 2017)]
[Notices]
[Pages 12142-12143]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2017-03891]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2017-0059]
Limit of Error Concepts and Principles of Calculation in Nuclear
Materials Control
AGENCY: Nuclear Regulatory Commission.
ACTION: Regulatory guide: withdrawal.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is withdrawing
Regulatory Guide (RG) 5.18, ``Limit of Error Concepts and Principles of
Calculation in Nuclear Materials Control.'' This RG is being withdrawn
because the term ``limit of error'' is no longer used in the material
control and accounting (MC&A) requirements in NRC's regulations, and
therefore the RG 5.18 guidance is no longer needed. The MC&A
requirements now include the term ``standard error'' in place of the
term ``limit of error.'' The ``standard error'' term is used in
evaluating the significance of an inventory difference (ID). The NRC
has issued guidance separately for the term ``standard error.''
DATES: The effective date of the withdrawal of RG 5.18 is February 28,
2017.
ADDRESSES: Please refer to Docket ID NRC-2017-0059 when contacting the
NRC about the availability of information regarding this document. You
may obtain publically-available information related to this document,
using the following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2017-0059. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: Carol.Gallagher@nrc.gov. For technical questions, contact
the individuals listed in the FOR FURTHER INFORMATION CONTACT section
of this document.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly-available documents online in the
ADAMS Public Document collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS,
please contact the NRC's Public Document Room (PDR) reference staff at
1-800-397-4209, 301-415-4737, or by email to pdr.resource@nrc.gov. The
ADAMS accession number for each document referenced (if it is available
in ADAMS) is provided the first time that it is mentioned in this
document. The basis for the withdrawal of this guide is in ADAMS under
Accession No. ML16244A672.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
Regulatory guides are not copyrighted, and NRC approval is not
required to reproduce them.
FOR FURTHER INFORMATION CONTACT: Glenn Tuttle, Office of Nuclear
Materials Safety and Safeguards, telephone: 301-415-7230, email:
Glenn.Tuttle@nrc.gov; and Harriet Karagiannis, Office of Nuclear
[[Page 12143]]
Regulatory Research, telephone: 301-415-2493, email:
Harriet.Karagiannis@nrc.gov. Both are staff members of the U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001.
SUPPLEMENTARY INFORMATION: The NRC staff issued RG 5.18 in January 1974
to provide guidance on meeting the material control and accounting
(MC&A) requirements in part 70 of title 10 the Code of Federal
Regulations (10 CFR), ``Domestic Licensing of Special Nuclear
Material.'' Part 70 then contained MC&A requirements, including those
in 10 CFR 70.51, ``Material Balance, Inventory, and Records
Requirements'' that were established in 1973. Specifically, 10 CFR
70.51(a)(5) defined the term ``Limit of error,'' and 10 CFR 70.51(e)
required licensees to calculate statistical limits of error for any
material unaccounted for as part of their MC&A procedures. Part 70
regulations no longer contain any MC&A requirements, and licensees are
no longer required to calculate statistical limits of error for any
material unaccounted for. In 1985, 10 CFR part 74, ``Material Control
and Accounting of Special Nuclear Material,'' was established, and in
2002, the 10 CFR 70.51 requirements were transferred to 10 CFR part 74
which now includes the current MC&A requirements. As part of the 2002
MC&A revisions, the term ``limit of error'' was replaced by the term
``standard error,'' and licensees are now required to calculate the
``inventory difference'' (as defined in 10 CFR 74.4) rather than
determining the amounts of material that are ``unaccounted for.'' The
``standard error'' is used in evaluating the significance of an
inventory difference (ID).
Guidance for calculating the ``standard error'' of the ID is found
in NUREG-1065, ``Acceptable Standard Format and Content for the
Fundamental Nuclear Material Control (FNMC) Plan Required for Low-
Enriched Uranium Facilities'' (ADAMS Accession No. ML031340288), NUREG-
1280, ``Standard Format and Content Acceptance Criteria for the
Material Control and Accounting (MC&A) Reform Amendment'' (ADAMS
Accession No. ML13253A308), and NUREG/CR-5734, ``Recommendations to the
NRC on Acceptable Standard Format and Content for the Fundamental
Nuclear Material Control (FNMC) Plan Required for Low-Enriched Uranium
Enrichment Facilities'' (ADAMS Accession No. ML15120A354).
In addition, RG 5.18 endorsed the American National Standards
Institute Standard N15.16-1974, ``Limit of Error Concepts and
Principles of Calculation in Nuclear Materials Control,'' to provide
guidance on the ``limit of error'' concept. However, this standard has
been withdrawn from active status with no replacement.
The NRC is withdrawing RG 5.18 because it is no longer needed.
Withdrawal of an RG means that the guide no longer provides useful
information or has been superseded by other guidance, technological
innovations, congressional actions, or other events. The withdrawal of
RG 5.18 does not alter any prior or existing NRC licensing approval or
the acceptability of licensee commitments to RG 5.18. Although RG 5.18
is withdrawn, current licensees may continue to use it, and withdrawal
does not affect any existing licenses or agreements. However, 5.18
should not be used in future requests or applications for NRC licensing
actions.
Dated at Rockville, Maryland, this 21st day of February 2017.
For the Nuclear Regulatory Commission.
Harriet Karagiannis,
Acting Chief, Regulatory Guidance and Generic Issues Branch, Division
of Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2017-03891 Filed 2-27-17; 8:45 am]
BILLING CODE 7590-01-P