Corrective Action Programs for Fuel Cycle Facilities, 41315-41316 [2014-16513]
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Federal Register / Vol. 79, No. 135 / Tuesday, July 15, 2014 / Notices
material reference temperatures of the
Linde 80 weld materials present in the
RPV beltline region will not result in
changes in operation or configuration of
the facility. The change does not impose
any new or different requirements or
eliminate any existing requirements.
The change is consistent with the
current safety analysis assumptions and
current plant operating practice. No new
accident scenarios, transient precursors,
failure mechanisms, or limiting single
failures are introduced as a result of the
proposed change. Equipment important
to safety will continue to operate as
designed. The change does not result in
any event previously deemed incredible
being more credible. The change does
not result in any adverse conditions or
result in any increase in the challenges
to safety systems.
Therefore, the proposed exemption
does not create the possibility of a new
or different kind of accident from any
previously evaluated.
mstockstill on DSK4VPTVN1PROD with NOTICES
3. Does the proposed exemption involve
a significant reduction in a margin of
safety?
Response: No.
The proposed exemption does not
alter safety limits, limiting safety system
settings, or limiting conditions for
operation. The setpoints at which
protective actions are initiated are not
altered by the change. There are no new
or significant changes to initial
conditions contributing to accident
severity or consequences. The
exemption will not otherwise affect
plant protective boundaries, will not
cause a release of fission products to the
public, nor will it degrade the
performance of any other structures,
systems or components important to
safety.
Therefore, the proposed exemption
does not involve a significant reduction
in a margin of safety.
Based on the above evaluation of the
standards set forth in 10 CFR 50.92(c),
the NRC staff concludes that the
proposed exemption involves no
significant hazards consideration.
Accordingly, the requirements of 10
CFR 51.22(c)(9)(i) are met.
Requirements in 10 CFR 51.22(c)(9)(ii)
The proposed exemption would allow
use of an alternate method for
determining the initial, unirradiated
material reference temperatures of the
Linde 80 weld materials present in the
RPV beltline region. The proposed
change in reactor vessel material initial
properties will continue to satisfy the
intent of 10 CFR part 50, Appendix G,
and 10 CFR 50.61. Thus, the use of this
alternate methodology will not
VerDate Mar<15>2010
17:46 Jul 14, 2014
Jkt 232001
significantly change the types of
effluents that may be released offsite, or
significantly increase the amount of
effluents that may be released offsite.
Therefore, the requirements of 10 CFR
51.22(c)(9)(ii) are met.
Requirements in 10 CFR 51.22(c)(9)(iii)
The proposed exemption would allow
use of an alternate method for
determining the initial, unirradiated
material reference temperatures of the
Linde 80 weld materials present in the
RPV beltline region. The proposed
change in reactor vessel material initial
properties will continue to satisfy the
intent of 10 CFR part 50, Appendix G,
and 10 CFR 50.61. Thus, the use of this
alternate methodology will not
significantly increase individual
occupational radiation exposure, or
significantly increase cumulative
occupational radiation exposure.
Therefore, the requirements of 10 CFR
51.22(c)(9)(iii) are met.
Conclusion
Based on the above, the NRC staff
concludes that the proposed exemption
meets the eligibility criteria for the
categorical exclusion set forth in 10 CFR
51.22(c)(9). Therefore, in accordance
with 10 CFR 51.22(b), no environmental
impact statement or environmental
assessment need be prepared in
connection with the NRC’s proposed
issuance of this exemption.
IV. Conclusions
Accordingly, the Commission has
determined that, pursuant to 10 CFR
50.12, the exemption is authorized by
law, will not present an undue risk to
the public health and safety, and is
consistent with the common defense
and security. Also, special
circumstances pursuant to 10 CFR
50.12(a)(2)(ii) are present. Therefore, the
Commission hereby grants NextEra
Energy Point Beach an exemption from
the requirements of Appendix G to 10
CFR part 50 and 10 CFR 50.61, to allow
an alternative methodology as described
in BAW–2308, Revisions 1–A and 2–A,
that is based on using fracture toughness
test data to determine initial,
unirradiated properties for evaluating
the integrity of the RPV beltline welds
at the Point Beach Nuclear Plant, Units
1 and 2.
This exemption is effective upon
issuance.
Dated at Rockville, Maryland, this 30th day
of June 2014.
PO 00000
Frm 00070
Fmt 4703
Sfmt 4703
41315
For The Nuclear Regulatory Commission.
Michele G. Evans,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2014–16415 Filed 7–14–14; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2014–0021]
Corrective Action Programs for Fuel
Cycle Facilities
Nuclear Regulatory
Commission.
ACTION: Regulatory guide; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing a new
regulatory guide (RG) 3.75, ‘‘Corrective
Action Programs for Fuel Cycle
Facilities.’’ This RG describes
programmatic elements that the staff of
the NRC considers acceptable when
developing corrective action programs
for fuel cycle facilities that are licensed
under the NRC’s regulations.
ADDRESSES: Please refer to Docket ID
NRC–2014–0021 when contacting the
NRC about the availability of
information regarding this document.
You may obtain publicly-available
information related to this document
using any of the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2014–0021. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–287–3422;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individual(s) listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may access publicly
available documents online in the NRC
Library at https://www.nrc.gov/readingrm/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 in this notice (if
that document is available in ADAMS)
is provided the first time that a
document is referenced. Revision 0 of
RG 3.75 is available in ADAMS under
Accession No. ML14139A321. The
regulatory analysis may be found in
SUMMARY:
E:\FR\FM\15JYN1.SGM
15JYN1
41316
Federal Register / Vol. 79, No. 135 / Tuesday, July 15, 2014 / Notices
ADAMS under Accession No.
ML14139A316.
• 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:
Sabrina Atack, Office of Nuclear
Material Safety and Safeguards;
telephone: 301–287–9075, email:
Sabrina.Atack@nrc.gov; and Steve
Burton, Office of Nuclear Regulatory
Research; telephone: 301–415–7000,
Stephen.Burton@nrc.gov. Both are staff
of the U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
SUPPLEMENTARY INFORMATION:
mstockstill on DSK4VPTVN1PROD with NOTICES
I. Introduction
The NRC is issuing a new guide in the
NRC’s ‘‘Regulatory Guide’’ series. This
series was developed to describe and
make available to the public information
such as methods that are acceptable to
the NRC staff for implementing specific
parts of the agency’s regulations,
techniques that the staff uses in
evaluating specific problems or
postulated accidents, and data that the
staff needs in its review of applications
for permits and licenses.
Regulatory Guide 3.75 describes
programmatic elements that the staff of
the NRC considers acceptable when
developing corrective action programs
for fuel cycle facilities that are licensed
under part 40 of Title 10 of the Code of
Federal Regulations (10 CFR),
‘‘Domestic Licensing of Source
Material’’ or 10 CFR part 70, ‘‘Domestic
Licensing of Special Nuclear Material’’
or holders of certificates of compliance
or approvals of a compliance plan for
gaseous diffusion plants under 10 CFR
part 76, ‘‘Certification of Gaseous
Diffusion Plants.’’
II. Additional Information
Regulatory Guide 3.75 was issued
with a temporary identification as draft
regulatory guide (DG), DG–3044. Draft
regulatory guide, DG–3044, was
published in the Federal Register on
February 12, 2014 (79 FR 8511), for a
30-day public comment period. The
public comment period closed on March
14, 2014. Public comments on DG–3044
and the staff’s responses to the public
comments are available in ADAMS
under Accession No. ML14139A318.
III. Congressional Review Act
This RG is a rule as defined in the
Congressional Review Act (5 U.S.C.
VerDate Mar<15>2010
17:46 Jul 14, 2014
Jkt 232001
801–808). However, the Office of
Management and Budget has not found
it to be a major rule as defined in the
Congressional Review Act.
IV. Backfitting and Issue Finality
This RG describes programmatic
elements that the staff considers
acceptable for corrective action
programs (CAPs) for fuel cycle facilities
licensed under 10 CFR parts 40, or 70,
and gaseous diffusion plants holding
certificates of compliance under 10 CFR
part 76. Applicants for such facilities
and certificates of compliance, as well
as existing licensees and holders of
certificate of compliance, may use the
guidance in developing, implementing
or revising CAPs. Licensees may choose
to develop and implement CAPs that
meet the guidance in this RG for the
purpose of applying Section 2.3.2 of the
NRC Enforcement Policy. The NRC staff
may find methods or solutions that
differ from those described in this RG
acceptable for the purpose of applying
Section 2.3.2 of the NRC Enforcement
Policy if those methods or solutions
effectively implement controls to
identify, document, and correct
conditions adverse to safety and
security.
Applicants for, and holders of fuel
cycle licenses under part 40 are not
subject to backfitting protection,
inasmuch as the NRC’s regulations do
not provide backfitting protection to
part 40 applicants or licensees.
This RG does not constitute
backfitting for any fuel cycle facility
applicants or licensees subject to
backfitting protection under part 70, or
applicants for or holders of certificates
of compliance for gaseous diffusion
plants under part 76. No part 70
licensee or holder of a part 76
certificates of compliance is required to
comply with the guidance, and a
licensee or holder of a certificate of
compliance is free to demonstrate that
its corrective action program is effective
in identifying, documenting, and
correcting conditions adverse to safety
and security in order to be within the
purview of Section 2.3.2 of the NRC
Enforcement Policy. With respect to
applicants or potential applicants for
part 70 licenses and part 76 certificates
of compliance, such entities are not
protected by the backfitting provisions
in parts 70 and 76. Backfitting is
intended to protect the reasonable
expectations of certain entities who
have received NRC regulatory approvals
(e.g., a license), and was not intended to
apply to NRC actions which
substantially change the expectations of
current and future applicants.
PO 00000
Frm 00071
Fmt 4703
Sfmt 4703
This RG does not apply to any nuclear
power reactors subject to 10 CFR parts
50 or 52. Therefore, backfitting
considerations under 10 CFR 50.109 or
issue finality considerations under 10
CFR part 52 are not applicable to this
RG.
Dated at Rockville, Maryland, this 9 day of
July, 2014.
For the Nuclear Regulatory Commission.
Thomas H. Boyce,
Chief, Regulatory Guidance and Generic
Issues Branch, Division of Engineering, Office
of Nuclear Regulatory Research.
[FR Doc. 2014–16513 Filed 7–14–14; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Advisory Committee on the Medical
Uses of Isotopes: Meeting Notice
U.S. Nuclear Regulatory
Commission.
ACTION: Notice of Meeting.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) will convene a
meeting of the Advisory Committee on
the Medical Uses of Isotopes (ACMUI)
on September 29–30, 2014. A sample of
agenda items to be discussed during the
public session includes: (1) A
discussion on the physical presence
requirements for the Leksell Gamma
Knife ® Perfexion TM; (2) a discussion on
why and how certain emerging medical
technologies are licensed under 10 CFR
35.1000; (3) a presentation on FDA’s
role regarding the global molybdenum99 shortage; (4) an update on the NRC
staff’s efforts related to the release of
patients administered radioactive
material; (5) a discussion on the various
mechanisms in use or proposed for
reporting medical incidents; and (6) a
discussion on the recommendations
regarding the current medical event
reporting criteria for yttrium-90
microspheres. The agenda is subject to
change. The current agenda and any
updates will be available at https://
www.nrc.gov/reading-rm/doccollections/acmui/meetings/2014.html
or by emailing Ms. Sophie Holiday at
the contact information below.
Purpose: Discuss issues related to 10
CFR Part 35 Medical Use of Byproduct
Material.
Date and Time for Closed Sessions:
September 30, 2014, from 1:30 p.m. to
3:00 p.m. The session on September 30,
2014 will be closed for ACMUI training.
Date and Time for Open Sessions:
September 29, 2014, from 8:30 a.m. to
5:00 p.m. and September 30, 2014, from
8:00 a.m. to 1:30 p.m.
SUMMARY:
E:\FR\FM\15JYN1.SGM
15JYN1
Agencies
[Federal Register Volume 79, Number 135 (Tuesday, July 15, 2014)]
[Notices]
[Pages 41315-41316]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2014-16513]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2014-0021]
Corrective Action Programs for Fuel Cycle Facilities
AGENCY: Nuclear Regulatory Commission.
ACTION: Regulatory guide; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing a new
regulatory guide (RG) 3.75, ``Corrective Action Programs for Fuel Cycle
Facilities.'' This RG describes programmatic elements that the staff of
the NRC considers acceptable when developing corrective action programs
for fuel cycle facilities that are licensed under the NRC's
regulations.
ADDRESSES: Please refer to Docket ID NRC-2014-0021 when contacting the
NRC about the availability of information regarding this document. You
may obtain publicly-available information related to this document
using any of the following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2014-0021. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: Carol.Gallagher@nrc.gov. For technical questions, contact
the individual(s) listed in the FOR FURTHER INFORMATION CONTACT section
of this document.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may access publicly available documents online in the NRC
Library 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 in this notice (if that document is
available in ADAMS) is provided the first time that a document is
referenced. Revision 0 of RG 3.75 is available in ADAMS under Accession
No. ML14139A321. The regulatory analysis may be found in
[[Page 41316]]
ADAMS under Accession No. ML14139A316.
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: Sabrina Atack, Office of Nuclear
Material Safety and Safeguards; telephone: 301-287-9075, email:
Sabrina.Atack@nrc.gov; and Steve Burton, Office of Nuclear Regulatory
Research; telephone: 301-415-7000, Stephen.Burton@nrc.gov. Both are
staff of the U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is issuing a new guide in the NRC's ``Regulatory Guide''
series. This series was developed to describe and make available to the
public information such as methods that are acceptable to the NRC staff
for implementing specific parts of the agency's regulations, techniques
that the staff uses in evaluating specific problems or postulated
accidents, and data that the staff needs in its review of applications
for permits and licenses.
Regulatory Guide 3.75 describes programmatic elements that the
staff of the NRC considers acceptable when developing corrective action
programs for fuel cycle facilities that are licensed under part 40 of
Title 10 of the Code of Federal Regulations (10 CFR), ``Domestic
Licensing of Source Material'' or 10 CFR part 70, ``Domestic Licensing
of Special Nuclear Material'' or holders of certificates of compliance
or approvals of a compliance plan for gaseous diffusion plants under 10
CFR part 76, ``Certification of Gaseous Diffusion Plants.''
II. Additional Information
Regulatory Guide 3.75 was issued with a temporary identification as
draft regulatory guide (DG), DG-3044. Draft regulatory guide, DG-3044,
was published in the Federal Register on February 12, 2014 (79 FR
8511), for a 30-day public comment period. The public comment period
closed on March 14, 2014. Public comments on DG-3044 and the staff's
responses to the public comments are available in ADAMS under Accession
No. ML14139A318.
III. Congressional Review Act
This RG is a rule as defined in the Congressional Review Act (5
U.S.C. 801-808). However, the Office of Management and Budget has not
found it to be a major rule as defined in the Congressional Review Act.
IV. Backfitting and Issue Finality
This RG describes programmatic elements that the staff considers
acceptable for corrective action programs (CAPs) for fuel cycle
facilities licensed under 10 CFR parts 40, or 70, and gaseous diffusion
plants holding certificates of compliance under 10 CFR part 76.
Applicants for such facilities and certificates of compliance, as well
as existing licensees and holders of certificate of compliance, may use
the guidance in developing, implementing or revising CAPs. Licensees
may choose to develop and implement CAPs that meet the guidance in this
RG for the purpose of applying Section 2.3.2 of the NRC Enforcement
Policy. The NRC staff may find methods or solutions that differ from
those described in this RG acceptable for the purpose of applying
Section 2.3.2 of the NRC Enforcement Policy if those methods or
solutions effectively implement controls to identify, document, and
correct conditions adverse to safety and security.
Applicants for, and holders of fuel cycle licenses under part 40
are not subject to backfitting protection, inasmuch as the NRC's
regulations do not provide backfitting protection to part 40 applicants
or licensees.
This RG does not constitute backfitting for any fuel cycle facility
applicants or licensees subject to backfitting protection under part
70, or applicants for or holders of certificates of compliance for
gaseous diffusion plants under part 76. No part 70 licensee or holder
of a part 76 certificates of compliance is required to comply with the
guidance, and a licensee or holder of a certificate of compliance is
free to demonstrate that its corrective action program is effective in
identifying, documenting, and correcting conditions adverse to safety
and security in order to be within the purview of Section 2.3.2 of the
NRC Enforcement Policy. With respect to applicants or potential
applicants for part 70 licenses and part 76 certificates of compliance,
such entities are not protected by the backfitting provisions in parts
70 and 76. Backfitting is intended to protect the reasonable
expectations of certain entities who have received NRC regulatory
approvals (e.g., a license), and was not intended to apply to NRC
actions which substantially change the expectations of current and
future applicants.
This RG does not apply to any nuclear power reactors subject to 10
CFR parts 50 or 52. Therefore, backfitting considerations under 10 CFR
50.109 or issue finality considerations under 10 CFR part 52 are not
applicable to this RG.
Dated at Rockville, Maryland, this 9 day of July, 2014.
For the Nuclear Regulatory Commission.
Thomas H. Boyce,
Chief, Regulatory Guidance and Generic Issues Branch, Division of
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2014-16513 Filed 7-14-14; 8:45 am]
BILLING CODE 7590-01-P