Light Load Handling System and Refueling Cavity Design, 45496-45497 [2014-18507]
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45496
Federal Register / Vol. 79, No. 150 / Tuesday, August 5, 2014 / Notices
are met; and (3) any inspections for the
ITAAC have been completed and any
ITAAC findings associated with the
ITAAC have been closed.
The NRC staff’s determination of the
successful completion of this ITAAC is
based on information available at this
time and is subject to the licensee’s
ability to maintain the condition that
the acceptance criteria are met. If new
information disputes the NRC staff’s
determination, this ITAAC will be
reopened as necessary. The NRC staff’s
determination will be used to support a
subsequent finding, pursuant to 10 CFR
52.103(g), at the end of construction that
all acceptance criteria in the combined
license are met. The ITAAC closure
process is not finalized for this ITAAC
until the NRC makes an affirmative
finding under 10 CFR 52.103(g). Any
future updates to the status of this
ITAAC will be reflected on the NRC’s
Web site at https://www.nrc.gov/reactors/
new-reactors/oversight/itaac.html.
Dated at Rockville, Maryland, this 28th day
of July 2014.
For the Nuclear Regulatory Commission.
Denise McGovern,
Senior Project Manager, Licensing Branch 4,
Division of New Reactor Licensing, Office of
New Reactors.
[FR Doc. 2014–18510 Filed 8–4–14; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2013–0148]
Light Load Handling System and
Refueling Cavity Design
Nuclear Regulatory
Commission.
ACTION: Standard review plan-final
section revision; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing a final
revision to NUREG–0800, ‘‘Standard
Review Plan (SRP) for the Review of
Safety Analysis Reports for Nuclear
Power Plants: LWR Edition,’’ Section
9.1.4, ‘‘Light Load Handling System and
Refueling Cavity Design.’’
DATES: The effective date of this
Standard Review Plan (SRP) update is
September 4, 2014.
ADDRESSES: Please refer to Docket ID
NRC–2013–0148 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
mstockstill on DSK4VPTVN1PROD with NOTICES
SUMMARY:
VerDate Mar<15>2010
18:16 Aug 04, 2014
Jkt 232001
for Docket ID NRC–2013–0148. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–287–3422;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individual listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may access publiclyavailable 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 at 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. The final
revision for the SRP Section 9.1.4,
‘‘Light Load Handling System and
Refueling Cavity Design,’’ is available in
ADAMS under Accession No.
ML13318A923. A redline strikeout
comparing the proposed revision to the
final revision can be found in ADAMS
under Accession No. ML13318A954.
The responses to public comments can
be found in ADAMS under Accession
No. ML13318A795.
• 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.
• The NRC posts its issued staff
guidance on the NRC’s external Web
page (https://www.nrc.gov/reading-rm/
doc-collections/nuregs/staff/sr0800/).
FOR FURTHER INFORMATION CONTACT:
Jonathan DeGange, Office of New
Reactors, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, telephone: 301–415–6992, email:
Jonathan.DeGange@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Background
On July 11, 2013 (78 FR 41810), the
NRC published for public comment the
proposed revisions to this section of the
SRP. The staff made changes to the
proposed revision after consideration of
comments received. A summary of the
comments and the staff’s disposition of
the comments are available in a separate
document, ‘‘Response to Public
Comments on Draft SRP Section 9.1.4’’
(ADAMS Accession No. ML13318A795).
The changes to this SRP chapter
reflect current staff review methods and
PO 00000
Frm 00075
Fmt 4703
Sfmt 4703
practices based on lessons learned from
NRC’s reviews of design certification
and combined license applications
completed since the last revision of this
chapter. This chapter has been updated
primarily to reflect operating experience
associated with IE Bulletin 84–03,
‘‘Refueling Cavity Water Seal’’ (ADAMS
Accession No. ML082700127).
II. Backfitting and Issue Finality
Issuance of this final SRP section does
not constitute backfitting as defined in
§ 50.109 of Title 10 of the Code of
Federal Regulations (10 CFR) (the
Backfit Rule) and is not otherwise
inconsistent with the issue finality
provisions in 10 CFR part 52. The staff’s
position is based upon the following
considerations:
1. The SRP positions do not constitute
backfitting, inasmuch as the SRP is
internal guidance directed at the NRC
staff with respect to their regulatory
responsibilities.
The SRP provides guidance to the
staff on how to review an application for
NRC regulatory approval in the form of
licensing. Changes in internal staff
guidance are not matters for which
either nuclear power plant applicants or
licensees are protected under either the
Backfit Rule or the issue finality
provisions of 10 CFR part 52.
2. The NRC staff has no intention to
impose the SRP positions on current
licensees and regulatory approvals
either now or in the future.
The staff does not intend to impose or
apply the positions described in the SRP
to existing (already issued) licenses and
regulatory approvals. Hence, the
issuance of a final SRP—even if
considered guidance which is within
the purview of the issue finality
provisions in 10 CFR part 52—need not
be evaluated as if it were a backfit or as
being inconsistent with issue finality
provisions. If, in the future, the staff
seeks to impose a position in the SRP on
holders of already issued holders of
licenses SRP in a manner which does
not provide issue finality as described
in the applicable issue finality
provision, then the staff must make the
showing as set forth in the Backfit Rule
or address the criteria for avoiding issue
finality as described applicable issue
finality provision.
3. Backfitting and issue finality do
not—with limited exceptions not
applicable here—protect current or
future applicants.
Applicants and potential applicants
are not, with certain exceptions,
protected by either the Backfit Rule or
any issue finality provisions under 10
CFR part 52. This is because neither the
Backfit Rule nor the issue finality
E:\FR\FM\05AUN1.SGM
05AUN1
Federal Register / Vol. 79, No. 150 / Tuesday, August 5, 2014 / Notices
provisions under 10 CFR part 52—with
certain exclusions discussed below—
were intended to apply to every NRC
action which substantially changes the
expectations of current and future
applicants.
The exceptions to the general
principle are applicable whenever an
applicant references a 10 CFR part 52
license (e.g., an early site permit) and/
or NRC regulatory approval (e.g., a
design certification rule) with specified
issue finality provisions. The staff does
not, at this time, intend to impose the
positions represented in the SRP in a
manner that is inconsistent with any
issue finality provisions. If, in the
future, the staff seeks to impose a
position in the SRP in a manner which
does not provide issue finality as
described in the applicable issue finality
provision, then the staff must address
the criteria for avoiding issue finality as
described in the applicable issue finality
provision.
III. Congressional Review Act
This action 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.
Dated at Rockville, Maryland, this 24th day
of July, 2014.
For the Nuclear Regulatory Commission.
Joseph Colaccino,
Chief, New Reactor Rulemaking and
Guidance Branch, Division of Advanced
Reactors and Rulemaking, Office of New
Reactors.
[FR Doc. 2014–18507 Filed 8–4–14; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2013–0179]
Maintenance Rule
Nuclear Regulatory
Commission.
ACTION: Standard review plan—final
section; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing a final
revision to Section 17.6, ‘‘Maintenance
Rule,’’ of NUREG–0800, ‘‘Standard
Review Plan for the Review of Safety
Analysis Reports for Nuclear Power
Plants: LWR Edition.’’
DATES: The effective date of this
Standard Review Plan (SRP) update is
September 4, 2014.
ADDRESSES: Please refer to Docket ID
NRC–2013–0179 when contacting the
mstockstill on DSK4VPTVN1PROD with NOTICES
SUMMARY:
VerDate Mar<15>2010
18:16 Aug 04, 2014
Jkt 232001
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–2013–0179. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–287–3422;
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 access publiclyavailable 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. The final
revision for Standard Review Plan (SRP)
Section17.6, ‘‘Maintenance Rule,’’ is
available under ADAMS Accession No.
ML14099A044. A redline strikeout
comparing the proposed and final
revision of the document can be found
in ADAMS under Accession No.
ML14099A053.
• 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.
• The NRC posts its issued staff
guidance on the NRC’s external Web
page (https://www.nrc.gov/reading-rm/
doc-collections/nuregs/staff/sr0800/).
FOR FURTHER INFORMATION CONTACT: Mr.
Jonathan DeGange, Office of New
Reactors, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, telephone: 301–415–6992, email:
Jonathan.DeGange@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Background
On August 8, 2013 (78 FR 48504), the
NRC published for public comment the
proposed SRP Section 17.6,
‘‘Maintenance Rule,’’ in Chapter 17,
‘‘Quality Assurance,’’ of NUREG–0800.
The staff received a total of six
comments on the draft section. A
summary of the comments and the
staff’s disposition of the comments are
PO 00000
Frm 00076
Fmt 4703
Sfmt 4703
45497
available in a separate document,
‘‘Response to Public Comments on Draft
Standard Review Plan, Section 17.6,
Maintenance Rule’’ (ADAMS Accession
No. ML14099A033).
II. Backfitting and Issue Finality
SRP Section 17.6 provides guidance
to the staff for reviewing applications
for a construction permit and an
operating license under part 50 of Title
10 of the Code of Federal Regulations
(10 CFR) with respect to compliance
with the Maintenance Rule, 10 CFR
50.65 and the guidance in Nuclear
Management and Resources Council 93–
01 as approved for use by the NRC in
Regulatory Guide 1.160. SRP Section
17.6 also provides guidance for
reviewing an application for a standard
design approval, a standard design
certification, a combined license, and a
manufacturing license under 10 CFR
part 52 with respect to those same
subject matters.
Issuance of this SRP section revision
does not constitute backfitting as
defined in 10 CFR 50.109 (the Backfit
Rule) nor is it inconsistent with the
issue finality provisions in 10 CFR part
52. The NRC’s position is based upon
the following considerations.
1. The SRP positions would not
constitute backfitting, inasmuch as the
SRP is internal guidance to NRC staff.
The SRP provides internal guidance
to the NRC staff on how to review an
application for NRC regulatory approval
in the form of licensing. Changes in
internal staff guidance are not matters
for which either nuclear power plant
applicants or licensees are protected
under either the Backfit Rule or the
issue finality provisions of 10 CFR part
52.
2. The NRC staff has no intention to
impose the SRP positions on existing
licensees either now or in the future.
The NRC staff does not intend to
impose or apply the positions described
in the SRP to existing licenses and
regulatory approvals. Hence, the
issuance of this SRP—even if
considered guidance within the purview
of the issue finality provisions in 10
CFR part 52—does not need to be
evaluated as if it were a backfit or as
being inconsistent with issue finality
provisions. If, in the future, the NRC
staff seeks to impose a position in the
SRP on holders of already issued
licenses in a manner that does not
provide issue finality as described in the
applicable issue finality provision, then
the staff must make the showing as set
forth in the Backfit Rule or address the
criteria for avoiding issue finality as
described in the applicable issue finality
provision.
E:\FR\FM\05AUN1.SGM
05AUN1
Agencies
[Federal Register Volume 79, Number 150 (Tuesday, August 5, 2014)]
[Notices]
[Pages 45496-45497]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2014-18507]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2013-0148]
Light Load Handling System and Refueling Cavity Design
AGENCY: Nuclear Regulatory Commission.
ACTION: Standard review plan-final section revision; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing a
final revision to NUREG-0800, ``Standard Review Plan (SRP) for the
Review of Safety Analysis Reports for Nuclear Power Plants: LWR
Edition,'' Section 9.1.4, ``Light Load Handling System and Refueling
Cavity Design.''
DATES: The effective date of this Standard Review Plan (SRP) update is
September 4, 2014.
ADDRESSES: Please refer to Docket ID NRC-2013-0148 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-2013-0148. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: Carol.Gallagher@nrc.gov. For technical questions, contact
the individual 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 at 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. The final revision for the SRP Section 9.1.4, ``Light Load
Handling System and Refueling Cavity Design,'' is available in ADAMS
under Accession No. ML13318A923. A redline strikeout comparing the
proposed revision to the final revision can be found in ADAMS under
Accession No. ML13318A954. The responses to public comments can be
found in ADAMS under Accession No. ML13318A795.
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.
The NRC posts its issued staff guidance on the NRC's
external Web page (https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr0800/).
FOR FURTHER INFORMATION CONTACT: Jonathan DeGange, Office of New
Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, telephone: 301-415-6992, email: Jonathan.DeGange@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Background
On July 11, 2013 (78 FR 41810), the NRC published for public
comment the proposed revisions to this section of the SRP. The staff
made changes to the proposed revision after consideration of comments
received. A summary of the comments and the staff's disposition of the
comments are available in a separate document, ``Response to Public
Comments on Draft SRP Section 9.1.4'' (ADAMS Accession No.
ML13318A795).
The changes to this SRP chapter reflect current staff review
methods and practices based on lessons learned from NRC's reviews of
design certification and combined license applications completed since
the last revision of this chapter. This chapter has been updated
primarily to reflect operating experience associated with IE Bulletin
84-03, ``Refueling Cavity Water Seal'' (ADAMS Accession No.
ML082700127).
II. Backfitting and Issue Finality
Issuance of this final SRP section does not constitute backfitting
as defined in Sec. 50.109 of Title 10 of the Code of Federal
Regulations (10 CFR) (the Backfit Rule) and is not otherwise
inconsistent with the issue finality provisions in 10 CFR part 52. The
staff's position is based upon the following considerations:
1. The SRP positions do not constitute backfitting, inasmuch as the
SRP is internal guidance directed at the NRC staff with respect to
their regulatory responsibilities.
The SRP provides guidance to the staff on how to review an
application for NRC regulatory approval in the form of licensing.
Changes in internal staff guidance are not matters for which either
nuclear power plant applicants or licensees are protected under either
the Backfit Rule or the issue finality provisions of 10 CFR part 52.
2. The NRC staff has no intention to impose the SRP positions on
current licensees and regulatory approvals either now or in the future.
The staff does not intend to impose or apply the positions
described in the SRP to existing (already issued) licenses and
regulatory approvals. Hence, the issuance of a final SRP--even if
considered guidance which is within the purview of the issue finality
provisions in 10 CFR part 52--need not be evaluated as if it were a
backfit or as being inconsistent with issue finality provisions. If, in
the future, the staff seeks to impose a position in the SRP on holders
of already issued holders of licenses SRP in a manner which does not
provide issue finality as described in the applicable issue finality
provision, then the staff must make the showing as set forth in the
Backfit Rule or address the criteria for avoiding issue finality as
described applicable issue finality provision.
3. Backfitting and issue finality do not--with limited exceptions
not applicable here--protect current or future applicants.
Applicants and potential applicants are not, with certain
exceptions, protected by either the Backfit Rule or any issue finality
provisions under 10 CFR part 52. This is because neither the Backfit
Rule nor the issue finality
[[Page 45497]]
provisions under 10 CFR part 52--with certain exclusions discussed
below--were intended to apply to every NRC action which substantially
changes the expectations of current and future applicants.
The exceptions to the general principle are applicable whenever an
applicant references a 10 CFR part 52 license (e.g., an early site
permit) and/or NRC regulatory approval (e.g., a design certification
rule) with specified issue finality provisions. The staff does not, at
this time, intend to impose the positions represented in the SRP in a
manner that is inconsistent with any issue finality provisions. If, in
the future, the staff seeks to impose a position in the SRP in a manner
which does not provide issue finality as described in the applicable
issue finality provision, then the staff must address the criteria for
avoiding issue finality as described in the applicable issue finality
provision.
III. Congressional Review Act
This action 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.
Dated at Rockville, Maryland, this 24th day of July, 2014.
For the Nuclear Regulatory Commission.
Joseph Colaccino,
Chief, New Reactor Rulemaking and Guidance Branch, Division of Advanced
Reactors and Rulemaking, Office of New Reactors.
[FR Doc. 2014-18507 Filed 8-4-14; 8:45 am]
BILLING CODE 7590-01-P