[Federal Register Volume 84, Number 195 (Tuesday, October 8, 2019)]
[Notices]
[Pages 53767-53776]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-21447]
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NUCLEAR REGULATORY COMMISSION
[NRC-2019-0196]
Biweekly Notice; Applications and Amendments to Facility
Operating Licenses and Combined Licenses Involving No Significant
Hazards Considerations
AGENCY: Nuclear Regulatory Commission.
ACTION: Biweekly notice.
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SUMMARY: Pursuant to the Atomic Energy Act of 1954, as amended (the
Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this
regular biweekly notice. The Act requires the Commission to publish
notice of any amendments issued, or proposed to be issued, and grants
the Commission the authority to issue and make immediately effective
any amendment to an operating license or combined license, as
applicable, upon a determination by the Commission that such amendment
involves no significant hazards consideration, notwithstanding the
pendency before the Commission of a request for a hearing from any
person. This biweekly notice includes all notices of amendments issued,
or proposed to be issued, from September 10, 2019, to September 23,
2019. The last biweekly notice was published on September 24, 2019.
DATES: Comments must be filed by November 7, 2019. A request for a
hearing must be filed by December 9, 2019.
ADDRESSES: You may submit comments by any of the following methods:
Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2019-0196. Address
questions about NRC docket IDs in Regulations.gov to Jennifer Borges;
telephone: 301-287-9127; email: [email protected]. For technical
questions, contact the individual listed in the FOR FURTHER INFORMATION
CONTACT section of this document.
Mail comments to: Office of Administration, Mail Stop:
TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, ATTN: Program Management, Announcements and Editing Staff.
For additional direction on obtaining information and submitting
comments, see ``Obtaining Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
FOR FURTHER INFORMATION CONTACT: Janet Burkhardt, Office of Nuclear
Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone: 301-415-1384, email: [email protected].
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2019-0196, facility name, unit
number(s), plant docket number, application date, and subject when
contacting the NRC about the availability of information for this
action. You may obtain publicly-available information related to this
action by any of the following methods:
Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2019-0196.
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 ``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 [email protected]. 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.
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.
B. Submitting Comments
Please include Docket ID NRC-2019-0196, facility name, unit
number(s), plant docket number, application date, and subject in your
comment submission.
The NRC cautions you not to include identifying or contact
information that you do not want to be publicly disclosed in your
comment submission. The NRC will post all comment submissions at
https://www.regulations.gov as well as enter the comment submissions
into ADAMS. The NRC does not routinely edit comment submissions to
remove identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, then you should inform those persons not to
include identifying or contact information that they do not want to be
publicly disclosed in their comment submission. Your request should
state that the NRC does not routinely edit comment submissions to
remove such information before making the comment submissions available
to the public or entering the comment into ADAMS.
II. Background
Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954, as
amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is
publishing this regular biweekly notice. The Act requires the
Commission to publish notice of any amendments issued, or proposed to
be issued, and grants the Commission the authority to issue and make
immediately effective any amendment to an operating license or combined
license, as applicable, upon a determination by the Commission that
such amendment involves no significant hazards consideration,
notwithstanding the pendency before the Commission of a request for a
hearing from any person.
III. Notice of Consideration of Issuance of Amendments to Facility
Operating Licenses and Combined Licenses and Proposed No Significant
Hazards Consideration Determination
The Commission has made a proposed determination that the following
amendment requests involve no significant hazards consideration. Under
the Commission's regulations in Sec. 50.92 of title 10 of the Code of
Federal Regulations (10 CFR), this means that operation of the facility
in accordance with the proposed amendment would not (1) involve a
significant increase in the probability or consequences of an accident
previously evaluated; or (2) create the possibility of a new or
different kind of accident from any accident previously evaluated; or
(3) involve a significant reduction in a margin of safety. The basis
for this
[[Page 53768]]
proposed determination for each amendment request is shown below.
The Commission is seeking public comments on this proposed
determination. Any comments received within 30 days after the date of
publication of this notice will be considered in making any final
determination.
Normally, the Commission will not issue the amendment until the
expiration of 60 days after the date of publication of this notice. The
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment
involves no significant hazards consideration. In addition, the
Commission may issue the amendment prior to the expiration of the 30-
day comment period if circumstances change during the 30-day comment
period such that failure to act in a timely way would result, for
example in derating or shutdown of the facility. If the Commission
takes action prior to the expiration of either the comment period or
the notice period, it will publish in the Federal Register a notice of
issuance. If the Commission makes a final no significant hazards
consideration determination, any hearing will take place after
issuance. The Commission expects that the need to take this action will
occur very infrequently.
A. Opportunity To Request a Hearing and Petition for Leave To Intervene
Within 60 days after the date of publication of this notice, any
persons (petitioner) whose interest may be affected by this action may
file a request for a hearing and petition for leave to intervene
(petition) with respect to the action. Petitions shall be filed in
accordance with the Commission's ``Agency Rules of Practice and
Procedure'' in 10 CFR part 2. Interested persons should consult a
current copy of 10 CFR 2.309. The NRC's regulations are accessible
electronically from the NRC Library on the NRC's website at https://www.nrc.gov/reading-rm/doc-collections/cfr/. Alternatively, a copy of
the regulations is available at the NRC's Public Document Room, located
at One White Flint North, Room O1-F21, 11555 Rockville Pike (first
floor), Rockville, Maryland 20852. If a petition is filed, the
Commission or a presiding officer will rule on the petition and, if
appropriate, a notice of a hearing will be issued.
As required by 10 CFR 2.309(d) the petition should specifically
explain the reasons why intervention should be permitted with
particular reference to the following general requirements for
standing: (1) The name, address, and telephone number of the
petitioner; (2) the nature of the petitioner's right under the Act to
be made a party to the proceeding; (3) the nature and extent of the
petitioner's property, financial, or other interest in the proceeding;
and (4) the possible effect of any decision or order which may be
entered in the proceeding on the petitioner's interest.
In accordance with 10 CFR 2.309(f), the petition must also set
forth the specific contentions which the petitioner seeks to have
litigated in the proceeding. Each contention must consist of a specific
statement of the issue of law or fact to be raised or controverted. In
addition, the petitioner must provide a brief explanation of the bases
for the contention and a concise statement of the alleged facts or
expert opinion which support the contention and on which the petitioner
intends to rely in proving the contention at the hearing. The
petitioner must also provide references to the specific sources and
documents on which the petitioner intends to rely to support its
position on the issue. The petition must include sufficient information
to show that a genuine dispute exists with the applicant or licensee on
a material issue of law or fact. Contentions must be limited to matters
within the scope of the proceeding. The contention must be one which,
if proven, would entitle the petitioner to relief. A petitioner who
fails to satisfy the requirements at 10 CFR 2.309(f) with respect to at
least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene.
Parties have the opportunity to participate fully in the conduct of the
hearing with respect to resolution of that party's admitted
contentions, including the opportunity to present evidence, consistent
with the NRC's regulations, policies, and procedures.
Petitions must be filed no later than 60 days from the date of
publication of this notice. Petitions and motions for leave to file new
or amended contentions that are filed after the deadline will not be
entertained absent a determination by the presiding officer that the
filing demonstrates good cause by satisfying the three factors in 10
CFR 2.309(c)(1)(i) through (iii). The petition must be filed in
accordance with the filing instructions in the ``Electronic Submissions
(E-Filing)'' section of this document.
If a hearing is requested, and the Commission has not made a final
determination on the issue of no significant hazards consideration, the
Commission will make a final determination on the issue of no
significant hazards consideration. The final determination will serve
to establish when the hearing is held. If the final determination is
that the amendment request involves no significant hazards
consideration, the Commission may issue the amendment and make it
immediately effective, notwithstanding the request for a hearing. Any
hearing would take place after issuance of the amendment. If the final
determination is that the amendment request involves a significant
hazards consideration, then any hearing held would take place before
the issuance of the amendment unless the Commission finds an imminent
danger to the health or safety of the public, in which case it will
issue an appropriate order or rule under 10 CFR part 2.
A State, local governmental body, Federally-recognized Indian
Tribe, or agency thereof, may submit a petition to the Commission to
participate as a party under 10 CFR 2.309(h)(1). The petition should
state the nature and extent of the petitioner's interest in the
proceeding. The petition should be submitted to the Commission no later
than 60 days from the date of publication of this notice. The petition
must be filed in accordance with the filing instructions in the
``Electronic Submissions (E-Filing)'' section of this document, and
should meet the requirements for petitions set forth in this section,
except that under 10 CFR 2.309(h)(2) a State, local governmental body,
or Federally-recognized Indian Tribe, or agency thereof does not need
to address the standing requirements in 10 CFR 2.309(d) if the facility
is located within its boundaries. Alternatively, a State, local
governmental body, Federally-recognized Indian Tribe, or agency thereof
may participate as a non-party under 10 CFR 2.315(c).
If a hearing is granted, any person who is not a party to the
proceeding and is not affiliated with or represented by a party may, at
the discretion of the presiding officer, be permitted to make a limited
appearance pursuant to the provisions of 10 CFR 2.315(a). A person
making a limited appearance may make an oral or written statement of
his or her position on the issues but may not otherwise participate in
the proceeding. A limited appearance may be made at any session of the
hearing or at any prehearing conference, subject to the limits and
conditions as may be imposed by the presiding officer. Details
regarding the opportunity to make a limited appearance will be provided
by
[[Page 53769]]
the presiding officer if such sessions are scheduled.
B. Electronic Submissions (E-Filing)
All documents filed in NRC adjudicatory proceedings, including a
request for hearing and petition for leave to intervene (petition), any
motion or other document filed in the proceeding prior to the
submission of a request for hearing or petition to intervene, and
documents filed by interested governmental entities that request to
participate under 10 CFR 2.315(c), must be filed in accordance with the
NRC's E-Filing rule (72 FR 49139; August 28, 2007, as amended at 77 FR
46562; August 3, 2012). The E-Filing process requires participants to
submit and serve all adjudicatory documents over the internet, or in
some cases to mail copies on electronic storage media. Detailed
guidance on making electronic submissions may be found in the Guidance
for Electronic Submissions to the NRC and on the NRC website at https://www.nrc.gov/site-help/e-submittals.html. Participants may not submit
paper copies of their filings unless they seek an exemption in
accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least 10
days prior to the filing deadline, the participant should contact the
Office of the Secretary by email at [email protected], or by
telephone at 301-415-1677, to (1) request a digital identification (ID)
certificate, which allows the participant (or its counsel or
representative) to digitally sign submissions and access the E-Filing
system for any proceeding in which it is participating; and (2) advise
the Secretary that the participant will be submitting a petition or
other adjudicatory document (even in instances in which the
participant, or its counsel or representative, already holds an NRC-
issued digital ID certificate). Based upon this information, the
Secretary will establish an electronic docket for the hearing in this
proceeding if the Secretary has not already established an electronic
docket.
Information about applying for a digital ID certificate is
available on the NRC's public website at https://www.nrc.gov/site-help/e-submittals/getting-started.html. Once a participant has obtained a
digital ID certificate and a docket has been created, the participant
can then submit adjudicatory documents. Submissions must be in Portable
Document Format (PDF). Additional guidance on PDF submissions is
available on the NRC's public website at https://www.nrc.gov/site-help/electronic-sub-ref-mat.html. A filing is considered complete at the
time the document is submitted through the NRC's E-Filing system. To be
timely, an electronic filing must be submitted to the E-Filing system
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of
a transmission, the E-Filing system time-stamps the document and sends
the submitter an email notice confirming receipt of the document. The
E-Filing system also distributes an email notice that provides access
to the document to the NRC's Office of the General Counsel and any
others who have advised the Office of the Secretary that they wish to
participate in the proceeding, so that the filer need not serve the
document on those participants separately. Therefore, applicants and
other participants (or their counsel or representative) must apply for
and receive a digital ID certificate before adjudicatory documents are
filed so that they can obtain access to the documents via the E-Filing
system.
A person filing electronically using the NRC's adjudicatory E-
Filing system may seek assistance by contacting the NRC's Electronic
Filing Help Desk through the ``Contact Us'' link located on the NRC's
public website at https://www.nrc.gov/site-help/e-submittals.html, by
email to [email protected], or by a toll-free call at 1-866-672-
7640. The NRC Electronic Filing Help Desk is available between 9 a.m.
and 6 p.m., Eastern Time, Monday through Friday, excluding government
holidays.
Participants who believe that they have a good cause for not
submitting documents electronically must file an exemption request, in
accordance with 10 CFR 2.302(g), with their initial paper filing
stating why there is good cause for not filing electronically and
requesting authorization to continue to submit documents in paper
format. Such filings must be submitted by: (1) First class mail
addressed to the Office of the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or
expedited delivery service to the Office of the Secretary, 11555
Rockville Pike, Rockville, Maryland 20852, Attention: Rulemaking and
Adjudications Staff. Participants filing adjudicatory documents in this
manner are responsible for serving the document on all other
participants. Filing is considered complete by first-class mail as of
the time of deposit in the mail, or by courier, express mail, or
expedited delivery service upon depositing the document with the
provider of the service. A presiding officer, having granted an
exemption request from using E-Filing, may require a participant or
party to use E-Filing if the presiding officer subsequently determines
that the reason for granting the exemption from use of E-Filing no
longer exists.
Documents submitted in adjudicatory proceedings will appear in the
NRC's electronic hearing docket which is available to the public at
https://adams.nrc.gov/ehd, unless excluded pursuant to an order of the
Commission or the presiding officer. If you do not have an NRC-issued
digital ID certificate as described above, click ``cancel'' when the
link requests certificates and you will be automatically directed to
the NRC's electronic hearing dockets where you will be able to access
any publicly-available documents in a particular hearing docket.
Participants are requested not to include personal privacy information,
such as social security numbers, home addresses, or personal phone
numbers in their filings, unless an NRC regulation or other law
requires submission of such information. For example, in some
instances, individuals provide home addresses in order to demonstrate
proximity to a facility or site. With respect to copyrighted works,
except for limited excerpts that serve the purpose of the adjudicatory
filings and would constitute a Fair Use application, participants are
requested not to include copyrighted materials in their submission.
For further details with respect to these license amendment
applications, see the application for amendment which is available for
public inspection in ADAMS and at the NRC's PDR. For additional
direction on accessing information related to this document, see the
``Obtaining Information and Submitting Comments'' section of this
document.
Dominion Energy Nuclear Connecticut, Inc., Docket No. 50-336, Millstone
Power Station, Unit No. 2 (Millstone 2), New London County, Connecticut
Date of amendment request: July 30, 2019. A publicly-available
version is in ADAMS under Accession No. ML19218A177.
Description of amendment request: The amendment would reduce the
Millstone 2 technical specification (TS) reactor coolant system (RCS)
and secondary side-specific activity by 50 percent. The proposed
changes are based on evaluations that were conducted to assess the
radiological consequences following postulated design-basis main steam
line break
[[Page 53770]]
(MSLB) and steam generator tube rupture (SGTR) accidents to address
analysis deficiencies documented in the Millstone 2 corrective action
program. A reduction in the TS RCS and secondary side-specific activity
is necessary to meet the control room dose regulatory limit and would
also provide inherent source term margin.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
RCS and secondary side specific activity are not initiators for
any accident previously evaluated. Reanalyzing the MSLB and SGTR
events does not require changes to any plant structures, systems, or
components (SSCs) and therefore does not affect accident initiators.
As a result, the proposed changes do not significantly increase the
probability of an accident. The proposed TS change will limit
primary coolant activity to concentrations consistent with the
accident analyses. The proposed MSLB and SGTR design basis accident
analyses demonstrate that the Exclusion Area Boundary, Low
Population Zone, and Control Room doses are within the limits of 10
CFR 50.67, SRP [Standard Review Plan]-15.0.1, and RG [Regulatory
Guide] 1.183. Therefore, the proposed changes do not involve a
significant increase in the probability or consequences of any
accident previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed TS change in specific activity limits and the
reanalyzed MSLB and SGTR events do not alter any physical part of
the plant, (i.e., no new or different type of equipment will be
installed), nor do they affect any plant operating parameter or
create new accident precursors. Therefore, the proposed changes do
not create the possibility of a new or different kind of accident
from any accident previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed TS change in specific activity limits is consistent
with the assumptions in the safety analyses and will ensure the
monitored values protect the initial assumptions in the safety
analyses. The proposed changes for radiological events related to
the computer code used to calculate radiological dose consequences
have been analyzed and result in acceptable consequences, meeting
the criteria as specified in 10 CFR 50.67, SRP-15.0.1, and RG 1.183.
The proposed changes will not result in plant operation in a
configuration outside the analyses or design bases and do not
adversely affect systems that are required to respond for safe
shutdown of the plant and to maintain the plant in a safe operating
condition. Therefore, the proposed changes do not involve a
significant reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Lillian M. Cuoco, Senior Counsel, Dominion
Resources Services, Inc., 120 Tredegar Street, RS-2, Richmond, VA
23219.
NRC Branch Chief: James G. Danna.
Dominion Energy Nuclear Connecticut, Inc. (DENC), Docket No. 50-423,
Millstone Power Station, Unit No. 3 (Millstone 3), New London County,
Connecticut
Date of amendment request: July 30, 2019. A publicly-available
version is in ADAMS under Accession No. ML19217A208.
Description of amendment request: The amendment would revise the
Millstone 3 Technical Specification (TS) 6.8.4.f, ``Containment Leakage
Rate Testing Program,'' by replacing the reference to Regulatory Guide
(RG) 1.163 with a reference to Nuclear Energy Institute (NEI) Topical
Report NEI 94-01, Revision 3-A, and the limitations and conditions
specified in NEI 94-01, Revision 2-A, as the implementing documents
used to develop the Millstone 3 performance-based leakage testing
program in accordance with option B of 10 CFR part 50, appendix J,
``Primary Reactor Containment Leakage Testing for Water-Cooled Power
Reactors.'' The amendment would allow Dominion Energy Nuclear
Connecticut, Inc. (DENC) to extend the primary containment integrated
leak rate test (ILRT) interval for Millstone 3 to 15 years and Type C
local leak rate test interval to 75 months, and incorporate the
regulatory positions stated in RG 1.163.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed change involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed amendment involves changes to the MPS3 [Millstone
3] Containment Leakage Rate Testing Program. The proposed amendment
does not involve a physical change to the plant or a change in the
manner in which the plant is operated or controlled. The primary
containment function is to provide an essentially leak tight barrier
against the uncontrolled release of radioactivity to the environment
for postulated accidents. As such, the containment and the testing
requirements to periodically demonstrate the integrity of the
containment exist to ensure the plant's ability to mitigate the
consequences of an accident, and do not involve any accident
precursors or initiators.
Therefore, the probability of occurrence of an accident
previously evaluated is not significantly increased by the proposed
amendment.
The proposed amendment adopts the NRC-accepted guidelines of NEI
94-01, Revision 3-A, and the limitations and conditions specified in
NEI 94-01, Rev. 2-A, for development of the MPS3 performance-based
leakage testing program. Implementation of these guidelines
continues to provide adequate assurance that during design basis
accidents, the primary containment and its components will limit
leakage rates to less than the values assumed in the plant safety
analyses. The potential consequences of extending the ILRT interval
to 15 years have been evaluated by analyzing the resulting changes
in risk. The increase in risk in terms of person-rem per year within
50 miles resulting from design basis accidents was estimated to be
acceptably small and determined to be within the guidelines
published in RG 1.17. Additionally, the proposed change maintains
defense-in-depth by preserving a reasonable balance among prevention
of core damage, prevention of containment failure, and consequence
mitigation. DENC has determined that the increase in Conditional
Containment Failure Probability due to the proposed change is very
small.
Therefore, it is concluded that the proposed amendment does not
significantly increase the consequences of an accident previously
evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The proposed amendment adopts the NRC-accepted guidelines of NEI
94-01, Revision 3-A, and the limitations and conditions specified in
NEI 94-01, Rev. 2-A, for development of the MPS3 performance-based
leakage testing program, and establishes a 15-year interval for Type
A testing and an interval of 75 months for Type C testing. The
containment and the testing requirements to periodically demonstrate
the integrity of the containment exist to ensure the plant's ability
to mitigate the consequences of an accident; and do not involve any
accident precursors or initiators. The proposed change does not
involve a physical change to the plant (i.e., no new or different
type of equipment will be installed) or a change to the manner in
which the plant is operated or controlled.
[[Page 53771]]
Therefore, the proposed change does not create the possibility
of a new or different kind of accident from any previously
evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The proposed amendment adopts the NRC-accepted guidelines of NEI
94-01, Revision 3-A, and the limitations and conditions specified in
NEI 94-01, Rev. 2-A, for the development of the MPS3 performance-
based leakage testing program, and establishes a 15-year interval
for Type A testing and an interval of 75 months for Type C testing.
This amendment does not alter the manner in which safety limits,
limiting safety system setpoints, or limiting conditions for
operation are determined. The specific requirements and conditions
of the Containment Leakage Rate Testing Program, as defined in the
TS, ensure that the degree of primary containment structural
integrity and leak-tightness that is considered in the plant's
safety analysis is maintained. The overall containment leakage rate
limit specified by the TS is maintained, and the Type A, Type B, and
Type C containment leakage tests will be performed at the
frequencies established in accordance with the NRC-accepted
guidelines of NEI 94-01, Revision 3-A, and the limitations and
conditions specified in NEI 94-01, Rev. 2-A.
Containment inspections performed in accordance with other plant
programs serve to provide a high degree of assurance that the
containment will not degrade in a manner that is not detectable by
an ILRT. A risk assessment using the current MPS3 PRA [probabilistic
risk assessment] model concluded that extending the ILRT test
interval from 10 years to 15 years results in a small change to the
MPS3 risk profile.
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Lillian M. Cuoco, Senior Counsel, Dominion
Resource Services, Inc., 120 Tredegar Street, RS-2, Richmond, VA 23219.
NRC Branch Chief: James G. Danna.
Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457,
Braidwood Station, Units 1 and 2, Will County, Illinois
Exelon Generation Company, LLC, Docket Nos. STN 50-454 and STN 50-455,
Byron Station, Unit Nos. 1 and 2, Ogle County, Illinois
Exelon Generation Company, LLC, Docket No. 50-461, Clinton Power
Station, Unit No. 1, DeWitt County, Illinois
Exelon Generation Company, LLC, Docket Nos. 50-010, 50-237, and 50-249,
Dresden Nuclear Power Station, Units 1, 2, and 3, Grundy County,
Illinois
Exelon Generation Company, LLC and Exelon FitzPatrick, LLC, Docket No.
50-333, James A. FitzPatrick Nuclear Power Plant, Oswego County, New
York
Exelon Generation Company, LLC, Docket Nos. 50-373 and 50-374, LaSalle
County Station, Units 1 and 2, LaSalle County, Illinois
Exelon Generation Company, LLC, Docket Nos. 50-352 and 50-353, Limerick
Generating Station, Units 1 and 2, Montgomery County, Pennsylvania
Exelon Generation Company, LLC, Docket Nos. 50-220 and 50-410, Nine
Mile Point Nuclear Station, Units 1 and 2, Oswego County, New York
Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket Nos. 50-
171, 50-277 and 50-278, Peach Bottom Atomic Power Station, Units 1, 2,
and 3, York and Lancaster Counties, Pennsylvania
Exelon Generation Company, LLC, Docket Nos. 50-254 and 50-265, Quad
Cities Nuclear Power Station, Units 1 and 2, Rock Island County,
Illinois
Exelon Generation Company, LLC, Docket No. 50-244, R.E. Ginna Nuclear
Power Plant, Wayne County, New York
Date of amendment request: August 28, 2019. A publicly-available
version is in ADAMS under Accession No. ML19240B609.
Description of amendment request: The amendments would delete
certain facility operating license (FOL) conditions that specify
requirements for decommissioning trust agreements for these facilities.
The amendments would also delete some obsolete license conditions
associated with completed license transfers for these facilities. The
decommissioning trust fund requirements in 10 CFR 50.75(h) would become
applicable to these facilities if the amendments are approved.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The requested changes delete license conditions pertaining to
Decommissioning Trust Agreements currently in the FOL. The requested
changes are consistent with the types of license amendments
permitted in 10 CFR 50.75(h)(4).
The regulations of 10 CFR 50.75(h)(4) state: ``Unless otherwise
determined by the Commission with regard to a specific application,
the Commission has determined that any amendment to the license of a
utilization facility that does no more than delete specific license
conditions relating to the terms and conditions of decommissioning
trust agreements involves ``no significant hazard considerations.''
This request involves changes that are administrative in nature.
No actual plant equipment or accident analyses will be affected by
the proposed changes.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
This request involves administrative changes to the license that
will be consistent with the 10 CFR 50.75(h). No actual plant
equipment or accident analyses will be affected by the proposed
change and no failure modes not bounded by previously evaluated
accidents will be created.
Therefore, the proposed change does not create the possibility
of a new or different kind of accident from any previously
evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
This request involves administrative changes to the license that
will be consistent with the 10 CFR 50.75(h). No actual plant
equipment or accident analyses will be affected by the proposed
change. Additionally, the proposed changes will not relax any
criteria used to establish safety limits, will not relax any safety
systems settings, or will not relax the bases for any limiting
conditions of operation.
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
[[Page 53772]]
requested amendments involve no significant hazards consideration.
Attorney for licensee: Tamra Domeyer, Associate General Counsel,
Exelon Generation Company, LLC, 4300 Winfield Road, Warrenville, IL
60555.
NRC Acting Branch Chief: Lisa M. Regner.
Indiana Michigan Power Company, Docket Nos. 50-315 and 50-316, Donald
C. Cook Nuclear Plant, Unit Nos. 1 and 2, Berrien County, Michigan
Date of amendment request: August 27, 2019. A publicly-available
version is in ADAMS under Accession No. ML19241A242.
Description of amendment request: The amendment would revise the
reactor coolant pump (RCP) motor flywheel examination frequency from
the currently approved 10-year inspection interval to an interval not
to exceed 20 years. The changes are consistent with Technical
Specifications Task Force (TSTF) Standard Technical Specification
Change Traveler, TSTF-421, ``Revision to RCP Flywheel Inspection
Program (WCAP-15666).''
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided (via incorporation by reference) its analysis of the issue of
no significant hazards consideration, which is presented below:
Criterion 1--The Proposed Change Does Not Involve a Significant
Increase in the Probability of Consequences of an Accident Previously
Evaluated
The proposed change to the RCP flywheel examination frequency
does not change the response of the plant to any accidents. The RCP
will remain highly reliable and the proposed change will not result
in a significant increase in the risk of plant operation. Given the
extremely low failure probabilities for the RCP motor flywheel
during normal and accident conditions, the extremely low probability
of a loss-of-coolant accident with loss of offsite power, and
assuming a conditional core damage probability of 1.0 (complete
failure of safety systems), the core damage frequency and change in
risk would still not exceed the NRC's acceptance guidelines
contained in RG [Regulatory Guide] 1.174 (<1.0E-6 per year).
Moreover, considering the uncertainties involved in this evaluation,
the risk associated with the postulated failure of an RCP motor
flywheel is significantly low. Even if all four RCP motor flywheels
are considered in the bounding plant configuration case, the risk is
still acceptably low.
The proposed change does not adversely affect accident
initiators or precursors, nor alter the design assumptions,
conditions, or configuration of the facility, or the manner in which
the plant is operated and maintained; alter or prevent the ability
of structures, systems, components (SSCs) from performing their
intended function to mitigate the consequences of an initiating
event within the assumed acceptance limits; or affect the source
term, containment isolation, or radiological release assumptions
used in evaluating the radiological consequences of an accident
previously evaluated. Further, the proposed change does not increase
the type or amount of radioactive effluent that may be released
offsite, nor significantly increase individual or cumulative
occupational/public radiation exposure. The proposed change is
consistent with the safety analysis assumptions and resultant
consequences. Therefore, the proposed change does not involve a
significant increase in the probability or consequences of an
accident previously evaluated.
Criterion 2--The Proposed Change Does Not Create the Possibility of a
New or Different Kind of Accident From Any Accident Previously
Evaluated
The proposed change in flywheel inspection frequency does not
involve any change in the design or operation of the RCP. Nor does
the change to examination frequency affect any existing accident
scenarios, or create any new or different accident scenarios.
Further, the change does not involve a physical alteration of the
plant (i.e., no new or different type of equipment will be
installed) or alter the methods governing normal plant operation. In
addition, the change does not impose any new or different
requirements or eliminate any existing requirements, and does not
alter any assumptions made in the safety analysis. The proposed
change is consistent with the safety analysis assumptions and
current plant operating practice. Therefore, the proposed change
does not create the possibility of a new or different kind of
accident from any accident previously evaluated.
Criterion 3--The Proposed Change Does Not Involve a Significant
Reduction in a Margin of Safety
The proposed change does not alter the manner in which safety
limits, limiting safety system settings, or limiting conditions for
operation are determined. The safety analysis acceptance criteria
are not impacted by this change. The proposed change will not result
in plant operation in a configuration outside of the design basis.
The calculated impact on risk is insignificant and meets the
acceptance criteria contained in RG 1.174. There are no significant
mechanisms for inservice degradation of the RCP flywheel. Therefore,
the proposed change does not involve a significant reduction in a
margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Robert B. Haemer, Senior Nuclear Counsel,
One Cook Place, Bridgman, MI 49106.
NRC Acting Branch Chief: Lisa M. Regner.
Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026,
Vogtle Electric Generating Plant, Units 3 and 4, Burke County, Georgia
Date of amendment request: August 9, 2019. A publicly-available
version is in ADAMS under Accession No. ML19221B669.
Description of amendment request: The amendment proposes to depart
from Updated Final Safety Analysis Report Tier 2 information (which
includes the plant-specific Design Control Document (DCD) Tier 2
information) and involves related changes to plant-specific Tier 1
information, with corresponding changes to the associated Combined
License (COL) Appendix C information. Pursuant to the provisions of 10
CFR 52.63(b)(1), an exemption from elements of the design as certified
in the 10 CFR part 52, appendix D, Design Certification Rule is also
requested for the plant-specific DCD Tier 1 material departures.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed changes would revise the COL and licensing basis
documents to add Onsite Standby Diesel Generator loads identified as
required for orderly plant shutdown, defense-in-depth, and
prevention of automatic passive safety-related system actuation
following anticipated operational occurrences, to prevent
duplication of testing by deleting [Inspections, Tests, Analyses and
Acceptance Criteria] ITAAC 2.6.01.04c for the function of Onsite
Standby Diesel Generator breaker closing and combining with ITAAC
2.6.04.02a, and to provide editorial updates.
The proposed non-technical change to COL Appendix C consolidates
ITAAC to improve efficiency of the ITAAC completion and closure
process. No structure, system, or component (SSC) design or function
is affected. No design or safety analysis is affected. The proposed
changes do not affect any accident initiating event or component
failure, thus the probabilities of the accidents previously
evaluated are not affected. No function used to mitigate a
radioactive material release and no radioactive material release
source term is involved, thus the radiological releases in the
accident analyses are not affected.
Therefore, the proposed amendment does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
[[Page 53773]]
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed changes would revise the COL and licensing basis
documents to add Onsite Standby Diesel Generator loads identified as
required for orderly plant shutdown, defense-in-depth, and
prevention of automatic passive safety-related system actuation
following anticipated operational occurrences, to prevent
duplication of testing by deleting ITAAC 2.6.01.04c for the function
of Onsite Standby Diesel Generator breaker closing and combining
with ITAAC 2.6.04.02a, and to provide editorial updates.
The proposed change to COL Appendix C does not affect the design
or function of any SSC but consolidates ITAAC to improve efficiency
of the ITAAC completion and closure process. The proposed changes
would not introduce a new failure mode, fault or sequence of events
that could result in a radioactive material release.
Therefore, the proposed amendment does not create the
possibility of a new or different kind of accident from any accident
previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed changes would revise the COL and licensing basis
documents to add Onsite Standby Diesel Generator loads identified as
required for orderly plant shutdown, defense-in-depth, and
prevention of automatic passive safety-related system actuation
following anticipated operational occurrences, to prevent
duplication of testing by deleting ITAAC 2.6.01.04c for the function
of Onsite Standby Diesel Generator breaker closing and combining
with ITAAC 2.6.04.02a, and to provide editorial updates.
The proposed change to COL Appendix C to consolidate ITAAC to
improve efficiency of the ITAAC completion and closure process is
considered non-technical and would not affect any design parameter,
function or analysis.
There would be no change to an existing design basis, design
function, regulatory criterion, or analysis. No safety analysis or
design basis acceptance limit/criterion is involved.
Therefore, the proposed amendment does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: M. Stanford Blanton, Balch & Bingham LLP,
1710 Sixth Avenue North, Birmingham, AL 35203-2015.
NRC Branch Chief: Jennifer L. Dixon-Herrity.
IV. Previously Published Notice of Consideration of Issuance of
Amendments to Facility Operating Licenses and Combined Licenses,
Proposed No Significant Hazards Consideration Determination, and
Opportunity for a Hearing
The following notice was previously published as a separate
individual notice. The notice content was the same as above. It was
published as an individual notice either because time did not allow the
Commission to wait for this biweekly notice or because the action
involved exigent circumstances. It is repeated here because the
biweekly notice lists all amendments issued or proposed to be issued
involving no significant hazards consideration.
For details, see the individual notice in the Federal Register on
the day and page cited. This notice does not extend the notice period
of the original notice.
Entergy Operations, Inc., Docket Nos. 50-313 and 50-368, Arkansas
Nuclear One (ANO), Units 1 and 2, Pope County, Arkansas
Date of amendment request: September 5, 2019. A publicly-available
version is in ADAMS under Accession No. ML19248C601.
Brief description of amendment request: The proposed amendments
would extend the implementation dates for License Amendment Nos. 263
and 314 for ANO, Units 1 and 2, respectively, from October 30, 2019, to
January 14, 2020. These amendments, which were issued on January 17,
2019, approved an update to the ANO Emergency Plan to adopt a revised
Emergency Action Level scheme.
Date of publication of individual notice in Federal Register:
September 19, 2019 (84 FR 49349).
Expiration date of individual notice: October 21, 2019 (public
comments); November 18, 2019 (hearing requests).
V. Notice of Issuance of Amendments to Facility Operating Licenses and
Combined Licenses
During the period since publication of the last biweekly notice,
the Commission has issued the following amendments. The Commission has
determined for each of 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 as indicated.
Unless otherwise indicated, 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. If the Commission has prepared an
environmental assessment under the special circumstances provision in
10 CFR 51.22(b) and has made a determination based on that assessment,
it is so indicated.
For further details with respect to the action see (1) the
applications for amendment, (2) the amendment, and (3) the Commission's
related letter, Safety Evaluation and/or Environmental Assessment as
indicated. All of these items can be accessed as described in the
``Obtaining Information and Submitting Comments'' section of this
document.
Duke Energy Progress, LLC, Docket Nos. 50-325 and 50-324, Brunswick
Steam Electric Plant, Units 1 and 2, Brunswick County, North Carolina
Date of amendment request: January 10, 2018, as supplemented by
letters dated November 2, 2018, February 13, 2019, and April 8, 2019.
Brief description of amendments: The amendments revised the
licensing basis by the addition of a license condition, to allow for
the implementation of the provisions of 10 CFR 50.69, ``Risk-Informed
Categorization and Treatment of Structures, Systems, and Components for
Nuclear Power Reactors.''
Date of issuance: September 17, 2019.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment Nos.: Unit 1--292; Unit 2--320. A publicly-available
version is in ADAMS under Accession No. ML19149A471; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. DPR-71 and DPR-62: The
amendments revised the renewed facility operating licenses.
Date of initial notice in Federal Register: May 22, 2018 (83 FR
23731). The supplemental letters dated November 2, 2018, February 13,
2019,
[[Page 53774]]
and April 8, 2019, 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 September 17, 2019.
No significant hazards consideration comments received: No.
Duke Energy Progress, LLC, Docket No. 50-400, Shearon Harris Nuclear
Power Plant, Unit 1, Wake and Chatham Counties, North Carolina
Date of amendment request: February 1, 2018, as supplemented by
letters dated October 18, 2018, and April 23, 2019.
Brief description of amendment: The amendment revised the licensing
basis of Shearon Harris Nuclear Power Plant, Unit 1, by voluntarily
adopting 10 CFR 50.69, ``Risk-informed categorization and treatment of
structures, systems and components.''
Date of issuance: September 17, 2019.
Effective date: As of the date of issuance and shall be implemented
within 60 days.
Amendment No: 174. A publicly-available version is in ADAMS under
Accession No. ML19192A012; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-63: The amendment
revised the renewed facility operating license.
Date of initial notice in Federal Register: May 22, 2018 (83 FR
23731). The supplemental letters dated October 18, 2018, and April 23,
2019, provided additional information that clarified the application,
did not expand the scope of the application as originally noticed, and
did not change the NRC staff's original proposed no significant hazards
consideration determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated September 17, 2019.
No significant hazards consideration comments received: No.
Duke Energy Progress, LLC, Docket No. 50-400, Shearon Harris Nuclear
Power Plant, Unit 1, Wake and Chatham Counties, North Carolina
Date of amendment request: July 30, 2019, as supplemented by
letters dated September 24, 2018, and December 27, 2018.
Brief description of amendment: The amendment revised Technical
Specification (TS) Table 2.2-1, ``Reactor Trip System Instrumentation
Trip Setpoints,'' and TS Table 3.3-4, ``Engineered Safety Features
Actuation System Instrumentation Trip Setpoints,'' to optimize safety
analysis margin in the Final Safety Analysis Report Chapter 15
transient analyses. It also removed the high-power range high negative
neutron flux rate trip from the TSs.
Date of issuance: September 19, 2019.
Effective date: As of the date of issuance and shall be implemented
prior to the startup of Cycle 23.
Amendment No.: 175. A publicly-available version is in ADAMS under
Accession No. ML19225C069; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-63: The amendment
revised the renewed facility operating license and TSs.
Date of initial notice in Federal Register: February 12, 2019 (84
FR 3508). The supplemental letters dated September 24, 2018, and
December 27, 2018, 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 initial proposed no significant
hazards consideration determination as published in the Federal
Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated September 19, 2019.
No significant hazards consideration comments received: No.
Entergy Operations, Inc., Docket Nos. 50-313 and 50-368, Arkansas
Nuclear One (ANO), Units 1 and 2, Pope County, Arkansas
Entergy Operations, Inc.; System Energy Resources, Inc.; Cooperative
Energy, A Mississippi Electric Cooperative; and Entergy Mississippi,
LLC, Docket No. 50-416, Grand Gulf Nuclear Station, Unit 1 (Grand
Gulf), Claiborne County, Mississippi
Entergy Nuclear Operations, Inc., Docket Nos. 50-247 and 50-286, Indian
Point Nuclear Generating (Indian Point) Unit Nos. 2 and 3, Westchester
County, New York
Entergy Nuclear Operations, Inc., Docket No. 50-255, Palisades Nuclear
Plant (Palisades), Van Buren County, Michigan
Entergy Louisiana, LLC, and Entergy Operations, Inc., Docket No. 50-
458, River Bend Station, Unit 1 (River Bend), West Feliciana Parish,
Louisiana
Entergy Operations, Inc., Docket No. 50-382, Waterford Steam Electric
Station, Unit 3 (Waterford 3), St. Charles Parish, Louisiana
Date of amendment request: January 31, 2019, as supplemented by
letter dated May 23, 2019.
Brief description of amendments: The amendments revised the
technical specifications (TSs) for each of these facilities based on
Technical Specifications Task Force (TSTF) Traveler TSTF-529, Revision
4, ``Clarify Use and Application Rules.'' Specifically, the changes
revised and clarified the TS usage rules for completion times, limiting
conditions for operation, and surveillance requirements.
Date of issuance: September 11, 2019.
Effective date: As of the date of issuance and shall be implemented
within 90 days of issuance.
Amendment Nos.: 265 (ANO-1); 316 (ANO-2); 221 (Grand Gulf); 291
(Indian Point 2), 266 (Indian Point 3); 270 (Palisades); 199 (River
Bend); and 255 (Waterford 3). A publicly-available version is in ADAMS
under Accession No. ML19175A042; documents related to these amendments
are listed in the Safety Evaluation enclosed with the amendments.
Renewed Facility Operating License No. NPF-29: The amendments
revised the renewed facility operating licenses and TSs.
Date of initial notice in Federal Register: April 9, 2019 (84 FR
14145). The supplemental letter dated May 23, 2019, provided additional
information that clarified the application, did not
[[Page 53775]]
expand the scope of the application as originally noticed, and did not
change the NRC staff's original proposed no significant hazards
consideration determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated September 11, 2019.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket Nos. 50-317 and 50-318, Calvert
Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Calvert County, Maryland
Exelon Generation Company, LLC and Exelon FitzPatrick, LLC, Docket No.
50-333, James A. FitzPatrick Nuclear Power Plant, Oswego County, New
York
Exelon Generation Company, LLC, Docket Nos. 50-220 and 50-410, Nine
Mile Point Nuclear Station, Units 1 and 2, Oswego County, New York
Date of amendment request: August 31, 2018, as supplemented by
letter dated February 22, 2019.
Brief description of amendments: The amendments revised the
emergency response organization positions identified in the emergency
plan for each site.
Date of issuance: September 13, 2019.
Effective date: As of the date of issuance and shall be implemented
on or before December 31, 2019.
Amendment Nos.: Calvert Cliffs--331/309; FitzPatrick--328; and Nine
Mile Point--238/177. A publicly-available version is in ADAMS under
Accession No. ML19204A063. Documents related to these amendments are
listed in the Safety Evaluation enclosed with the amendments.
Facility Operating License Nos. DPR-53, DPR-69, DPR-59, DPR-63, and
NPF-69: The amendments revised the emergency plans.
Date of initial notice in Federal Register: October 9, 2018 (83 FR
50696). The supplemental letter provided additional information that
clarified the application, did not expand the scope of the application
as originally noticed, and did not change the NRC 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 September 13, 2019.
No significant hazards consideration comments received: No.
Oyster Creek Environmental Protection, LLC and Holtec Decommissioning
International, LLC, Docket No. 50-219, Oyster Creek Nuclear Generating
Station (Oyster Creek), Ocean County, New Jersey
Date of application for amendment: November 12, 2018, as
supplemented by letter dated March 7, 2019.
Brief description of amendment: The amendment removed the existing
Cyber Security Plan (CSP) requirements contained in License Condition
2.C.(4) of the Oyster Creek Renewed Facility Operating License and the
commitment to fully implement the CSP by the Milestone 8 commitment
date of August 31, 2021 (ADAMS Accession No. ML17289A222).
Date of issuance: September 18, 2019.
Effective date: As of the date the licensee notifies the NRC in
writing that all spent nuclear fuel assemblies have been transferred
out of the spent fuel pool and have been placed in dry storage within
the independent spent fuel storage installation, and shall be
implemented within 60 days of the effective date.
Amendment No.: 298. A publicly-available version is in ADAMS under
Package Accession No. ML19179A202; documents related to this amendment
are referenced in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-16: This amendment
revised the renewed facility operating license.
Date of initial notice in Federal Register: December 18, 2018 (83
FR 64892).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated September 18, 2019.
No significant hazards consideration comments received: No.
PSEG Nuclear LLC, Docket No. 50-354, Hope Creek Generating Station,
Salem County, New Jersey
Date of amendment request: April 22, 2019.
Brief description of amendment: The amendment adopted Technical
Specifications Task Force (TSTF) Traveler TSTF-564, Revision 2,
``Safety Limit MCPR [Minimum Critical Power Ratio],'' which revises the
Hope Creek Generating Station technical specification (TS) safety limit
on MCPR to reduce the need for cycle-specific changes to the value,
while still meeting the regulatory requirement for a safety limit.
Date of issuance: September 19, 2019.
Effective date: As of the date of issuance and shall be implemented
prior to restart following Refueling Outage H1R22.
Amendment No.: 219. A publicly-available version is in ADAMS under
Accession No. ML19218A305; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-57: The amendment
revised the renewed facility operating license and TSs.
Date of initial notice in Federal Register: May 21, 2019 (84 FR
23074).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated September 19, 2019.
No significant hazards consideration comments received: No.
Southern Nuclear Operating Company, Inc., Georgia Power Company,
Oglethorpe Power Corporation, Municipal Electric Authority of Georgia,
City of Dalton, Georgia, Docket Nos. 50-321 and 50-366, Edwin I. Hatch
Nuclear Plant, Unit Nos. 1 and 2, Appling County, Georgia
Date of amendment request: April 23, 2019.
Brief description of amendments: The amendments revised the
technical specification (TS) safety limit (SL) on minimum critical
power ratio (MCPR) to reduce the need for cycle-specific changes to the
value, while still meeting the regulatory requirement for an SL, by
adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-
564, ``Safety Limit MCPR,'' Revision 2, which is an approved change to
the Improved Standard Technical Specifications, into the Hatch Nuclear
Power Plant, Units 1 and 2 TS.
Date of issuance: September 20, 2019.
Effective date: As of the date of issuance and shall be implemented
prior to reaching Mode 4 following Refueling Outage 1 R29 (spring 2020)
or within 270 days from the date of issuance, whichever is later.
Amendment Nos.: 299--Unit 1; 244--Unit 2. A publicly-available
version is in ADAMS under Accession No. ML19212A054; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. DPR-57 and NPF-5: The
amendments revised the renewed facility operating licenses and TSs.
Date of initial notice in Federal Register: July 2, 2019 (84 FR
31637).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated September 20, 2019.
[[Page 53776]]
No significant hazards consideration comments received: No.
Tennessee Valley Authority, Docket Nos. 50-327 and 50-328, Sequoyah
Nuclear Plant, Units 1 and 2, Hamilton County, Tennessee
Date of amendment request: March 16, 2018, as supplemented by
letter dated March 21, 2019.
Brief description of amendments: The amendments added a license
condition to allow for the adoption of 10 CFR 50.69, ``Risk-informed
categorization and treatment of structures, systems, and components for
nuclear power reactors.'' The provisions of 10 CFR 50.69 allow improved
focus on equipment that has safety significance, resulting in improved
plant safety.
Date of issuance: September 18, 2019.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment Nos.: 346--Unit 1; 340--Unit 2. A publicly-available
version is in ADAMS under Accession No. ML19179A135; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. DPR-77 and DPR-79: The
amendments revised the renewed facility operating licenses.
Date of initial notice in Federal Register: August 28, 2018 (83 FR
43908). The supplemental letter dated March 21, 2019, 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 September 18, 2019.
No significant hazards consideration comments received: No.
Virginia Electric and Power Company, Docket Nos. 50-338 and 50-339,
North Anna Power Station (North Anna), Units No. 1 and No. 2, Louisa
County, Virginia
Date of amendment request: April 30, 2018, as supplemented by
letters dated May 24 and August 8, 2019.
Brief description of amendments: The amendments revised the North
Anna Unit Nos. 1 and 2 technical specifications (TSs) to add
operability requirements, required actions, and surveillance
requirements for the new 4160-volt emergency bus voltage unbalance
protection system.
Date of issuance: September 12, 2019.
Effective date: As of the date of issuance and shall be implemented
by the completion of the fall 2019 refueling outage for North Anna Unit
1 and the fall 2020 refueling outage for North Anna Unit 2.
Amendment Nos.: 282--Unit 1; 265--Unit 2. A publicly-available
version is in ADAMS under Accession No. ML19238A127; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License No. NPF-4 and NPF-7: The
amendments revised the renewed facility operating licenses and TSs.
Date of initial notice in Federal Register: September 11, 2018 (83
FR 45989). The supplemental letters dated May 24, 2019, and August 8,
2019, 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 amendment is contained
in a Safety Evaluation dated September 12, 2019.
No significant hazards consideration comments received: No.
Dated at Rockville, Maryland, this 27th day of September 2019.
For the Nuclear Regulatory Commission.
Jamie M. Heisserer,
Acting Deputy Director, Division of Operating Reactor Licensing, Office
of Nuclear Reactor Regulation.
[FR Doc. 2019-21447 Filed 10-7-19; 8:45 am]
BILLING CODE 7590-01-P