Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3, 53483-53484 [2013-21094]
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Federal Register / Vol. 78, No. 168 / Thursday, August 29, 2013 / Notices
(2) the pressure spike is also localized
to the wetwell area which makes up
roughly 10 percent of containment,
(3) the number of containment
penetrations in this area is limited.
Therefore, the current Pa value of 7.6
psig meets the intent of 10 CFR part 50,
appendix J by bounding the peak bulk
containment pressure (3.6 psig) and
assuring that leakage through the
primary containment does not exceed
allowable leakage rate values,
(4) the calculated peak bulk
containment pressure is 3.6 psig so the
Technical Specification (TS) value of
7.6 is conservative for the use of
determining containment leakage, and
(5) this request is consistent with the
determination that the NRC staff has
reached for other licensees under
similar conditions based on the same
considerations.
The application for exemption may be
examined, and/or copied for a fee, at the
NRC’s Public Document Room, located
at One White Flint North, 11555
Rockville Pike (first floor), Rockville,
Maryland 20852. Publicly available
records will be accessible electronically
from the ADAMS Public Library
component on the NRC’s Web site,
https://www.nrc.gov (the Electronic
Reading Room).
Therefore, the NRC staff concludes
that requesting exemption under the
special circumstances of 10 CFR
50.12(a)(2)(ii) is appropriate and that the
alternate definition of Pa may be used
for the appendix J testing.
sroberts on DSK5SPTVN1PROD with NOTICES
Authorized by Law
This exemption would allow Entergy
to use a Pa value of 7.6 psig for appendix
J testing at the RBS as discussed above.
As stated above, 10 CFR 50.12 allows
the NRC to grant exemptions from the
requirements of 10 CFR part 50,
appendix J. The NRC staff has
determined that granting of the
licensee’s proposed exemption is in
accordance with the Atomic Energy Act
of 1954, as amended, or the
Commission’s regulations. Therefore,
the exemption is authorized by law.
No Undue Risk to Public Health and
Safety
The underlying purposes of 10 CFR
part 50, appendix J are stated in section
(I) ‘‘Introduction.’’ The purpose is to
conduct tests to assure that a) leakage
through the primary reactor
containment does not exceed allowable
leakage rate values and b) to conduct
periodic surveillance of reactor
containment penetrations to support
proper maintenance. No new accident
precursors are created because the
testing is conducted at a Pa value
VerDate Mar<15>2010
18:34 Aug 28, 2013
Jkt 229001
calculated to be representative of peak
conditions throughout containment
during a design basis accident. No new
accident precursors are created by use of
a Pa of 7.6 psig instead of 9.3 psig, thus,
the probability of postulated accidents
is not increased. Therefore, there is no
undue risk to public health and safety.
Consistent With Common Defense and
Security
The exemption would permit
exclusion of the short duration spike in
wetwell pressure as Pa for Appendix J
testing purposes. This change to the
interpretation of Pa as defined in
Appendix J has no relation to security
issues. Therefore, the common defense
and security is not impacted by this
exemption.
4.0 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 Entergy
Operations, Inc., an exemption from the
definition for Pa in 10 CFR part 50,
appendix J for River Bend Station, Unit
1 and alternatively to continue to use a
Pa value of 7.6 psig.
Pursuant to 10 CFR 51.32, the
Commission has determined that the
granting of this exemption will not have
a significant effect on the quality of the
human environment (78 FR 50454;
August 19, 2013).
This exemption is effective upon
issuance.
Dated at Rockville, Maryland, this 20th day
of August 2013.
For the Nuclear Regulatory Commission.
Michele G. Evans,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2013–21103 Filed 8–28–13; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 052–00025; NRC–2008–0252]
Inspections, Tests, Analyses, and
Acceptance Criteria; Vogtle Electric
Generating Plant, Unit 3
Nuclear Regulatory
Commission.
ACTION: Determination of inspections,
tests, analyses, and acceptance criteria
(ITAAC) completion.
AGENCY:
PO 00000
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Fmt 4703
Sfmt 4703
53483
The U.S. Nuclear Regulatory
Commission (NRC) staff has determined
that the inspections, tests, and analyses
have been successfully completed, and
that the specified acceptance criteria are
met for ITAAC E.2.5.04.05.05.02, for the
Vogtle Electric Generating Plant, Unit 3.
ADDRESSES: Please refer to Docket ID
NRC–2008–0252 when contacting the
NRC about the availability of
information regarding this document.
You may access publicly-available
information related to this action by 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: 301–287–3422;
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 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 document
(if that document is available in
ADAMS) is provided the first time that
a document is referenced.
• 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:
Ravindra Joshi, Office of New Reactors,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001; telephone:
301–415–6191, email: Ravindra.Joshi@
nrc.gov.
SUPPLEMENTARY INFORMATION:
SUMMARY:
Licensee Notification of Completion of
ITAAC
On May 31, 2013, Southern Nuclear
Operating Company, Inc. (the licensee)
submitted an ITAAC closure
notification (ICN) under § 52.99(c)(1) of
Title 10 of the Code of Federal
Regulations (10 CFR), informing the
NRC that the licensee has successfully
performed the required inspections,
tests, and analyses for ITAAC
E.2.5.04.05.05.02, and that the specified
acceptance criteria are met for Vogtle
E:\FR\FM\29AUN1.SGM
29AUN1
53484
Federal Register / Vol. 78, No. 168 / Thursday, August 29, 2013 / Notices
Electric Generating Plant, Unit 3
(ADAMS Accession No. ML13154A033).
This ITAAC was approved as part of the
issuance of the combined license, NPF–
91, for this facility.
sroberts on DSK5SPTVN1PROD with NOTICES
NRC Staff Determination of Completion
of ITAAC
The NRC staff has determined that the
inspections, tests, and analyses have
been successfully completed, and that
the specified acceptance criteria are met
for Vogtle Electric Generating Plant,
Unit 3, ITAAC E.2.5.04.05.05.02. This
notice fulfills the staff’s obligations
under 10 CFR 52.99(c)(1) to publish a
notice in the Federal Register of the
NRC staff’s determination of the
successful completion of inspections,
tests and analyses.
The documentation of the NRC staff’s
determination is in the ITAAC Closure
Verification Evaluation Form (VEF),
dated July 10, 2013 (ADAMS Accession
No. ML13191A249). The VEF is a form
that represents the NRC staff’s
structured process for reviewing ICNs.
The ICN presents a narrative description
of how the ITAAC was completed, and
the NRC’s ICN review process involves
a determination on whether, among
other things, (1) The ICN provides
sufficient information, including a
summary of the methodology used to
perform the ITAAC, to demonstrate that
the inspections, tests, and analyses have
been successfully completed; (2) the
ICN provides sufficient information to
demonstrate that the acceptance criteria
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 22nd
day of August 2013.
VerDate Mar<15>2010
18:34 Aug 28, 2013
Jkt 229001
For the Nuclear Regulatory Commission.
Denise McGovern,
Senior Project Manager, Licensing Branch 4,
Division of New Reactor Licensing, Office of
New Reactors.
[FR Doc. 2013–21094 Filed 8–28–13; 8:45 am]
BILLING CODE 7590–01–P
SUPPLEMENTARY INFORMATION:
NUCLEAR REGULATORY
COMMISSION
[Docket No. 052–00026; NRC–2008–0252]
Inspections, Tests, Analyses, and
Acceptance Criteria; Vogtle Electric
Generating Plant, Unit 4
Nuclear Regulatory
Commission.
ACTION: Determination of inspections,
tests, analyses, and acceptance criteria
(ITAAC) completion.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) staff has determined
that the inspections, tests, and analyses
have been successfully completed, and
that the specified acceptance criteria are
met for ITAAC E.2.5.04.05.05.02, for the
Vogtle Electric Generating Plant, Unit 4.
ADDRESSES: Please refer to Docket ID
NRC–2008–0252 when contacting the
NRC about the availability of
information regarding this document.
You may access publicly-available
information related to this action by 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: 301–287–3442;
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 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 document
(if that document is available in
ADAMS) is provided the first time that
a document is referenced.
• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, Room O1–F21, One
SUMMARY:
PO 00000
Frm 00063
Fmt 4703
Sfmt 4703
White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT:
Ravindra Joshi, Office of New Reactors,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001; telephone:
301–415–6191, email: Ravindra.Joshi@
nrc.gov.
Licensee Notification of Completion of
ITAAC
On May 31, 2013, Southern Nuclear
Operating Company, Inc. (the licensee)
submitted an ITAAC closure
notification (ICN) under § 52.99(c)(1) of
Title 10 of the Code of Federal
Regulations (10 CFR), informing the
NRC that the licensee has successfully
performed the required inspections,
tests, and analyses for ITAAC
E.2.5.04.05.05.02, and that the specified
acceptance criteria are met for Vogtle
Electric Generating Plant, Unit 4
(ADAMS Accession No. ML13154A032).
This ITAAC was approved as part of the
issuance of the combined license, NPF–
92, for this facility.
NRC Staff Determination of Completion
of ITAAC
The NRC staff has determined that the
inspections, tests, and analyses have
been successfully completed, and that
the specified acceptance criteria are met
for Vogtle Electric Generating Plant,
Unit 4, ITAAC E.2.5.04.05.05.02. This
notice fulfills the staff’s obligations
under 10 CFR 52.99(e)(1) to publish a
notice in the Federal Register of the
NRC staff’s determination of the
successful completion of inspections,
tests and analyses.
The documentation of the NRC staff’s
determination is in the ITAAC Closure
Verification Evaluation Form (VEF),
dated July 10, 2013 (ADAMS Accession
No. ML13191A333). The VEF is a form
that represents the NRC staff’s
structured process for reviewing ICNs.
The ICN presents a narrative description
of how the ITAAC was completed, and
the NRC’s ICN review process involves
a determination on whether, among
other things, (1) the ICN provides
sufficient information, including a
summary of the methodology used to
perform the ITAAC, to demonstrate that
the inspections, tests, and analyses have
been successfully completed; (2) the
ICN provides sufficient information to
demonstrate that the acceptance criteria
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
E:\FR\FM\29AUN1.SGM
29AUN1
Agencies
[Federal Register Volume 78, Number 168 (Thursday, August 29, 2013)]
[Notices]
[Pages 53483-53484]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2013-21094]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 052-00025; NRC-2008-0252]
Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle
Electric Generating Plant, Unit 3
AGENCY: Nuclear Regulatory Commission.
ACTION: Determination of inspections, tests, analyses, and acceptance
criteria (ITAAC) completion.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) staff has
determined that the inspections, tests, and analyses have been
successfully completed, and that the specified acceptance criteria are
met for ITAAC E.2.5.04.05.05.02, for the Vogtle Electric Generating
Plant, Unit 3.
ADDRESSES: Please refer to Docket ID NRC-2008-0252 when contacting the
NRC about the availability of information regarding this document. You
may access publicly-available information related to this action by 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: 301-287-
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 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 document (if that document is
available in ADAMS) is provided the first time that a document is
referenced.
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: Ravindra Joshi, Office of New
Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone: 301-415-6191, email: Ravindra.Joshi@nrc.gov.
SUPPLEMENTARY INFORMATION:
Licensee Notification of Completion of ITAAC
On May 31, 2013, Southern Nuclear Operating Company, Inc. (the
licensee) submitted an ITAAC closure notification (ICN) under Sec.
52.99(c)(1) of Title 10 of the Code of Federal Regulations (10 CFR),
informing the NRC that the licensee has successfully performed the
required inspections, tests, and analyses for ITAAC E.2.5.04.05.05.02,
and that the specified acceptance criteria are met for Vogtle
[[Page 53484]]
Electric Generating Plant, Unit 3 (ADAMS Accession No. ML13154A033).
This ITAAC was approved as part of the issuance of the combined
license, NPF-91, for this facility.
NRC Staff Determination of Completion of ITAAC
The NRC staff has determined that the inspections, tests, and
analyses have been successfully completed, and that the specified
acceptance criteria are met for Vogtle Electric Generating Plant, Unit
3, ITAAC E.2.5.04.05.05.02. This notice fulfills the staff's
obligations under 10 CFR 52.99(c)(1) to publish a notice in the Federal
Register of the NRC staff's determination of the successful completion
of inspections, tests and analyses.
The documentation of the NRC staff's determination is in the ITAAC
Closure Verification Evaluation Form (VEF), dated July 10, 2013 (ADAMS
Accession No. ML13191A249). The VEF is a form that represents the NRC
staff's structured process for reviewing ICNs. The ICN presents a
narrative description of how the ITAAC was completed, and the NRC's ICN
review process involves a determination on whether, among other things,
(1) The ICN provides sufficient information, including a summary of the
methodology used to perform the ITAAC, to demonstrate that the
inspections, tests, and analyses have been successfully completed; (2)
the ICN provides sufficient information to demonstrate that the
acceptance criteria 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 22nd day of August 2013.
For the Nuclear Regulatory Commission.
Denise McGovern,
Senior Project Manager, Licensing Branch 4, Division of New Reactor
Licensing, Office of New Reactors.
[FR Doc. 2013-21094 Filed 8-28-13; 8:45 am]
BILLING CODE 7590-01-P