Southern Nuclear Operating Company, Inc., Vogtle Electric Generating Plant, Units 3 and 4; Debris Screen Related Dimensions, 4425-4426 [2017-00683]
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Federal Register / Vol. 82, No. 9 / Friday, January 13, 2017 / Notices
contribute to any significant increase in
occupational or public radiation
exposure.
(iv) There is no significant
construction impact;
The proposed action involves only a
schedule change which is
administrative in nature; the application
review is suspended until further
notice, and there is no consideration of
any construction at this time, and hence
the proposed action does not involve
any construction impact.
(v) There is no significant increase in
the potential for or consequences from
radiological accidents;
The proposed action involves only a
schedule change which is
administrative in nature, and does not
impact the probability or consequences
of accidents.
(vi) The requirements from which an
exemption is sought involve:
(B) Reporting requirements;
The exemption request involves
submitting an updated COL application
by DEP
and
(G) Scheduling requirements;
The proposed exemption relates to the
schedule for submitting a COL
application update to the NRC.
asabaliauskas on DSK3SPTVN1PROD with NOTICES
IV. Conclusion
Accordingly, the Commission has
determined that, pursuant to 10 CFR
50.12(a), 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
are present. Therefore, the Commission
hereby grants DEP a one-time exemption
from the requirements of 10 CFR part 50
Appendix E, Section I.5 pertaining to
the Harris Units 2 and 3 COL
application to allow submittal of the
revised COL application that complies
with the enhancements to the EP rules
prior to any request to the NRC to
resume the review, and in any event, no
later than December 31, 2019.
Pursuant to 10 CFR 51.22, the
Commission has determined that the
exemption request meets the applicable
categorical exclusion criteria set forth in
10 CFR 51.22(c)(25), and the granting of
this exemption will not have a
significant effect on the quality of the
human environment.
This exemption is effective upon
issuance.
Dated at Rockville, Maryland, this 4th day
of January 2017.
VerDate Sep<11>2014
19:06 Jan 12, 2017
Jkt 241001
For The Nuclear Regulatory Commission.
Francis M. Akstulewicz,
Director, Division of New Reactor Licensing,
Office of New Reactors.
[FR Doc. 2017–00685 Filed 1–12–17; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 52–025 and 52–026; NRC–
2008–0252]
Southern Nuclear Operating Company,
Inc., Vogtle Electric Generating Plant,
Units 3 and 4; Debris Screen Related
Dimensions
Nuclear Regulatory
Commission.
ACTION: Exemption and combined
license amendment; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is granting an
exemption to allow a departure from the
certification information of Tier 1 of the
generic design control document (DCD)
and is issuing License Amendment No.
63 to Combined Licenses (COL), NPF–
91 and NPF–92. The COLs were issued
to Southern Nuclear Operating
Company, Inc., and Georgia Power
Company, Oglethorpe Power
Corporation, MEAG Power SPVM, LLC,
MEAG Power SPVJ, LLC, MEAG Power
SPVP, LLC, Authority of Georgia, and
the City of Dalton, Georgia (the
licensee); for construction and operation
of the Vogtle Electric Generating Plant
(VEGP) Units 3 and 4, located in Burke
County, Georgia.
The granting of the exemption allows
the changes to Tier 1 information asked
for in the amendment. Because the
acceptability of the exemption was
determined in part by the acceptability
of the amendment, the exemption and
amendment are being issued
concurrently.
DATES: The exemption and amendment
were issued on December 29, 2016.
ADDRESSES: Please refer to Docket ID
NRC–2008–0252 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–2008–0252. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–415–3463;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individual listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
SUMMARY:
PO 00000
Frm 00147
Fmt 4703
Sfmt 4703
4425
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publiclyavailable documents online in the
ADAMS Public Documents 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
request for the amendment and
exemption was submitted by letter
dated August 11, 2016 (ADAMS
Accession No. ML16224B122).
• 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.
FOR FURTHER INFORMATION CONTACT:
Ruth Reyes, Office of New Reactors,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001; telephone:
301–415–3249; email: Ruth.Reyes@
nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is granting an exemption
from Paragraph B of Section III, ‘‘Scope
and Contents,’’ of appendix D, ‘‘Design
Certification Rule for the AP1000,’’ to
part 52 of title 10 of the Code of Federal
Regulations (10 CFR), and issuing
License Amendment No. 63 to COLs,
NP–91 and NPF–92, to the licensee. The
exemption is required by Paragraph A.4
of Section VIII, ‘‘Processes for Changes
and Departures,’’ appendix D, to 10 CFR
part 52 to allow the licensee to depart
from Tier 1 information. With the
requested amendment, the licensee
sought proposed changes that would
revise the Updated Final Safety
Analysis Report in the form of
departures from the incorporated plantspecific DCD Tier 2 information. The
proposed amendment also involves
related changes to plant-specific Tier 1
information, with corresponding
changes to the associated COL
Appendix C information. The proposed
changes are to information identifying
the frontal face area and screen surface
area for the In-Containment Refueling
Water Storage Tank (IRWST) screens,
the location and dimensions of the
protective plate located above the
containment recirculation (CR) screens,
and increasing the maximum Normal
E:\FR\FM\13JAN1.SGM
13JAN1
4426
Federal Register / Vol. 82, No. 9 / Friday, January 13, 2017 / Notices
asabaliauskas on DSK3SPTVN1PROD with NOTICES
Residual Heat Removal System flowrate
through the IRWST and CR screens.
Part of the justification for granting
the exemption was provided by the
review of the amendment. Because the
exemption is necessary in order to issue
the requested license amendment, the
NRC granted the exemption and issued
the amendment concurrently, rather
than in sequence. This included issuing
a combined safety evaluation containing
the NRC staff’s review of both the
exemption request and the license
amendment. The exemption met all
applicable regulatory criteria set forth in
10 CFR 50.12, 10 CFR 52.7, and Section
VIII.A.4 of appendix D to 10 CFR part
52. The license amendment was found
to be acceptable as well. The combined
safety evaluation is available in ADAMS
under Accession No. ML16307A355.
Identical exemption documents
(except for referenced unit numbers and
license numbers) were issued to the
licensee for VEGP Units 3 and 4 (COLs
NPF–91 and NPF–92). The exemption
documents for VEGP Units 3 and 4 can
be found in ADAMS under Accession
Nos. ML16307A281 and ML16307A302,
respectively. The exemption is
reproduced (with the exception of
abbreviated titles and additional
citations) in Section II of this document.
The amendment documents for COLs
NPF–91 and NPF–92 are available in
ADAMS under Accession Nos.
ML16307A274 and ML16307A276,
respectively. A summary of the
amendment documents is provided in
Section III of this document.
II. Exemption
Reproduced below is the exemption
document issued to Vogtle Unit 3 and
Unit 4. It makes reference to the
combined safety evaluation that
provides the reasoning for the findings
made by the NRC (and listed under Item
1) in order to grant the exemption:
1. In a letter dated August 11, 2016,
the licensee requested from the
Commission an exemption to allow
departures from Tier 1 information in
the certified DCD incorporated by
reference in 10 CFR part 52, appendix
D, as part of License Amendment
Request 16–013, ‘‘Debris Screen Related
Dimensions.’’
For the reasons set forth in Section 3.1
of the NRC staff’s Safety Evaluation,
which can be found at ADAMS
Accession No. ML16307A355, the
Commission finds that:
A. The exemption is authorized by
law;
B. the exemption presents no undue
risk to public health and safety;
C. the exemption is consistent with
the common defense and security;
VerDate Sep<11>2014
19:06 Jan 12, 2017
Jkt 241001
D. special circumstances are present
in that the application of the rule in this
circumstance is not necessary to serve
the underlying purpose of the rule;
E. the special circumstances outweigh
any decrease in safety that may result
from the reduction in standardization
caused by the exemption; and
F. the exemption will not result in a
significant decrease in the level of safety
otherwise provided by the design.
2. Accordingly, the licensee is granted
an exemption from the certified DCD
Tier 1 information, with corresponding
changes to Appendix C of the Facility
COLs as described in the licensee’s
request dated August 11, 2016. This
exemption is related to, and necessary
for, the granting of License Amendment
No. 63, which is being issued
concurrently with this exemption.
3. As explained in Section 5.0 of the
NRC staff’s Safety Evaluation this
exemption meets the eligibility criteria
for categorical exclusion set forth in 10
CFR 51.22(c)(9). Therefore, pursuant to
10 CFR 51.22(b), no environmental
impact statement or environmental
assessment needs to be prepared in
connection with the issuance of the
exemption.
4. This exemption is effective as of the
date of its issuance.
III. License Amendment Request
By letter dated August 11, 2016, the
licensee requested that the NRC amend
the COLs for VEGP, Units 3 and 4, COLs
NPF–91 and NPF–92. The proposed
amendment is described in Section I of
this Federal Register notice.
The Commission has determined for
these amendments that the application
complies with the standards and
requirements of the Atomic Energy Act
of 1954, as amended (the Act), and the
Commission’s rules and regulations.
The Commission has made appropriate
findings as required by the Act and the
Commission’s rules and regulations in
10 CFR chapter I, which are set forth in
the license amendment.
A notice of consideration of issuance
of amendment to facility operating
license or combined license, as
applicable, proposed no significant
hazards consideration determination,
and opportunity for a hearing in
connection with these actions, was
published in the Federal Register on
September 27, 2016 (81 FR 66308). No
comments were received during the 30day comment period.
The Commission has determined that
these amendments satisfy the criteria for
categorical exclusion in accordance
with 10 CFR 51.22. Therefore, pursuant
to 10 CFR 51.22(b), no environmental
impact statement or environmental
PO 00000
Frm 00148
Fmt 4703
Sfmt 4703
assessment need be prepared for these
amendments.
IV. Conclusion
Using the reasons set forth in the
combined safety evaluation, the staff
granted the exemption and issued the
amendment that the licensee requested
on August 11, 2016.
The exemption and amendment were
issued on December 29, 2016, as part of
a combined package to the licensee
(ADAMS Accession No. ML16307A260).
Dated at Rockville, Maryland, this 3rd day
of January 2017.
For the Nuclear Regulatory Commission.
Jennifer Dixon-Herrity,
Chief, Licensing Branch 4, Division of New
Reactor Licensing, Office of New Reactors.
[FR Doc. 2017–00683 Filed 1–12–17; 8:45 am]
BILLING CODE 7590–01–P
SECURITIES AND EXCHANGE
COMMISSION
[Release No. 34–79763; File No. SR–DTC–
2016–802]
Self-Regulatory Organizations; The
Depository Trust Company; Notice of
No Objection To Advance Notice Filing
Relating To Processing of
Transactions in Money Market
Instruments
January 9, 2017.
The Depository Trust Company
(‘‘DTC’’) filed with the Securities and
Exchange Commission (‘‘Commission’’)
on September 23, 2016 advance notice
SR–DTC–2016–802 (‘‘Advance Notice’’)
pursuant to Section 806(e)(1) of the
Payment, Clearing, and Settlement
Supervision Act of 2010 (‘‘Payment,
Clearing and Settlement Supervision
Act’’) 1 and Rule 19b–4(n)(1)(i) 2 under
the Securities Exchange Act of 1934
(‘‘Exchange Act’’) to establish a change
in the processing of transactions in
money market instruments (‘‘MMI’’).3
1 12 U.S.C. 5465(e)(1). The Financial Stability
Oversight Council designated DTC a systemically
important financial market utility on July 18, 2012.
See Financial Stability Oversight Council 2012
Annual Report, Appendix A, https://
www.treasury.gov/initiatives/fsoc/Documents/
2012%20Annual%20Report.pdf. Therefore, DTC is
required to comply with the Payment, Clearing and
Settlement Supervision Act and file advance
notices with the Commission. See 12 U.S.C.
5465(e).
2 17 CFR 240.19b–4(n)(1)(i).
3 MMI are short-term debt securities issued by
financial institutions, large corporations, or state
and local governments that generally mature 1 to
270 days from their original issuance date, and
include, but are not limited to, commercial paper,
banker’s acceptances, and short-term bank notes.
Most MMI trade in large denominations (typically,
$250,000 to $50 million) and are purchased by
institutional investors.
E:\FR\FM\13JAN1.SGM
13JAN1
Agencies
[Federal Register Volume 82, Number 9 (Friday, January 13, 2017)]
[Notices]
[Pages 4425-4426]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2017-00683]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 52-025 and 52-026; NRC-2008-0252]
Southern Nuclear Operating Company, Inc., Vogtle Electric
Generating Plant, Units 3 and 4; Debris Screen Related Dimensions
AGENCY: Nuclear Regulatory Commission.
ACTION: Exemption and combined license amendment; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is granting an
exemption to allow a departure from the certification information of
Tier 1 of the generic design control document (DCD) and is issuing
License Amendment No. 63 to Combined Licenses (COL), NPF-91 and NPF-92.
The COLs were issued to Southern Nuclear Operating Company, Inc., and
Georgia Power Company, Oglethorpe Power Corporation, MEAG Power SPVM,
LLC, MEAG Power SPVJ, LLC, MEAG Power SPVP, LLC, Authority of Georgia,
and the City of Dalton, Georgia (the licensee); for construction and
operation of the Vogtle Electric Generating Plant (VEGP) Units 3 and 4,
located in Burke County, Georgia.
The granting of the exemption allows the changes to Tier 1
information asked for in the amendment. Because the acceptability of
the exemption was determined in part by the acceptability of the
amendment, the exemption and amendment are being issued concurrently.
DATES: The exemption and amendment were issued on December 29, 2016.
ADDRESSES: Please refer to Docket ID NRC-2008-0252 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-2008-0252. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; 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 obtain publicly-available documents online in the
ADAMS Public Documents 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 request for the amendment and exemption was submitted by
letter dated August 11, 2016 (ADAMS Accession No. ML16224B122).
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.
FOR FURTHER INFORMATION CONTACT: Ruth Reyes, Office of New Reactors,
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001;
telephone: 301-415-3249; email: Ruth.Reyes@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is granting an exemption from Paragraph B of Section III,
``Scope and Contents,'' of appendix D, ``Design Certification Rule for
the AP1000,'' to part 52 of title 10 of the Code of Federal Regulations
(10 CFR), and issuing License Amendment No. 63 to COLs, NP-91 and NPF-
92, to the licensee. The exemption is required by Paragraph A.4 of
Section VIII, ``Processes for Changes and Departures,'' appendix D, to
10 CFR part 52 to allow the licensee to depart from Tier 1 information.
With the requested amendment, the licensee sought proposed changes that
would revise the Updated Final Safety Analysis Report in the form of
departures from the incorporated plant-specific DCD Tier 2 information.
The proposed amendment also involves related changes to plant-specific
Tier 1 information, with corresponding changes to the associated COL
Appendix C information. The proposed changes are to information
identifying the frontal face area and screen surface area for the In-
Containment Refueling Water Storage Tank (IRWST) screens, the location
and dimensions of the protective plate located above the containment
recirculation (CR) screens, and increasing the maximum Normal
[[Page 4426]]
Residual Heat Removal System flowrate through the IRWST and CR screens.
Part of the justification for granting the exemption was provided
by the review of the amendment. Because the exemption is necessary in
order to issue the requested license amendment, the NRC granted the
exemption and issued the amendment concurrently, rather than in
sequence. This included issuing a combined safety evaluation containing
the NRC staff's review of both the exemption request and the license
amendment. The exemption met all applicable regulatory criteria set
forth in 10 CFR 50.12, 10 CFR 52.7, and Section VIII.A.4 of appendix D
to 10 CFR part 52. The license amendment was found to be acceptable as
well. The combined safety evaluation is available in ADAMS under
Accession No. ML16307A355.
Identical exemption documents (except for referenced unit numbers
and license numbers) were issued to the licensee for VEGP Units 3 and 4
(COLs NPF-91 and NPF-92). The exemption documents for VEGP Units 3 and
4 can be found in ADAMS under Accession Nos. ML16307A281 and
ML16307A302, respectively. The exemption is reproduced (with the
exception of abbreviated titles and additional citations) in Section II
of this document. The amendment documents for COLs NPF-91 and NPF-92
are available in ADAMS under Accession Nos. ML16307A274 and
ML16307A276, respectively. A summary of the amendment documents is
provided in Section III of this document.
II. Exemption
Reproduced below is the exemption document issued to Vogtle Unit 3
and Unit 4. It makes reference to the combined safety evaluation that
provides the reasoning for the findings made by the NRC (and listed
under Item 1) in order to grant the exemption:
1. In a letter dated August 11, 2016, the licensee requested from
the Commission an exemption to allow departures from Tier 1 information
in the certified DCD incorporated by reference in 10 CFR part 52,
appendix D, as part of License Amendment Request 16-013, ``Debris
Screen Related Dimensions.''
For the reasons set forth in Section 3.1 of the NRC staff's Safety
Evaluation, which can be found at ADAMS Accession No. ML16307A355, the
Commission finds that:
A. The exemption is authorized by law;
B. the exemption presents no undue risk to public health and
safety;
C. the exemption is consistent with the common defense and
security;
D. special circumstances are present in that the application of the
rule in this circumstance is not necessary to serve the underlying
purpose of the rule;
E. the special circumstances outweigh any decrease in safety that
may result from the reduction in standardization caused by the
exemption; and
F. the exemption will not result in a significant decrease in the
level of safety otherwise provided by the design.
2. Accordingly, the licensee is granted an exemption from the
certified DCD Tier 1 information, with corresponding changes to
Appendix C of the Facility COLs as described in the licensee's request
dated August 11, 2016. This exemption is related to, and necessary for,
the granting of License Amendment No. 63, which is being issued
concurrently with this exemption.
3. As explained in Section 5.0 of the NRC staff's Safety Evaluation
this exemption meets the eligibility criteria for categorical exclusion
set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR
51.22(b), no environmental impact statement or environmental assessment
needs to be prepared in connection with the issuance of the exemption.
4. This exemption is effective as of the date of its issuance.
III. License Amendment Request
By letter dated August 11, 2016, the licensee requested that the
NRC amend the COLs for VEGP, Units 3 and 4, COLs NPF-91 and NPF-92. The
proposed amendment is described in Section I of this Federal Register
notice.
The Commission has determined for these amendments that the
application complies with the standards and requirements of the Atomic
Energy Act of 1954, as amended (the Act), and the Commission's rules
and regulations. The Commission has made appropriate findings as
required by the Act and the Commission's rules and regulations in 10
CFR chapter I, which are set forth in the license amendment.
A notice of consideration of issuance of amendment to facility
operating license or combined license, as applicable, proposed no
significant hazards consideration determination, and opportunity for a
hearing in connection with these actions, was published in the Federal
Register on September 27, 2016 (81 FR 66308). No comments were received
during the 30-day comment period.
The Commission has determined that these amendments satisfy the
criteria for categorical exclusion in accordance with 10 CFR 51.22.
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact
statement or environmental assessment need be prepared for these
amendments.
IV. Conclusion
Using the reasons set forth in the combined safety evaluation, the
staff granted the exemption and issued the amendment that the licensee
requested on August 11, 2016.
The exemption and amendment were issued on December 29, 2016, as
part of a combined package to the licensee (ADAMS Accession No.
ML16307A260).
Dated at Rockville, Maryland, this 3rd day of January 2017.
For the Nuclear Regulatory Commission.
Jennifer Dixon-Herrity,
Chief, Licensing Branch 4, Division of New Reactor Licensing, Office of
New Reactors.
[FR Doc. 2017-00683 Filed 1-12-17; 8:45 am]
BILLING CODE 7590-01-P