Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
| Published date | 24 September 2019 |
| Citation | 84 FR 50078 |
| Record Number | 2019-20507 |
| Section | Notices |
| Court | Nuclear Regulatory Commission |
Federal Register, Volume 84 Issue 185 (Tuesday, September 24, 2019)
[Federal Register Volume 84, Number 185 (Tuesday, September 24, 2019)]
[Notices]
[Pages 50078-50087]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-20507]
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NUCLEAR REGULATORY COMMISSION
[NRC-2019-0187]
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 August 27, 2019 to September 9, 2019. The
last biweekly notice was published on September 10, 2019.
DATES: Comments must be filed by October 24, 2019. A request for a
hearing must be filed by November 25, 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-2019-0187. Address
questions about NRC dockets 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: Shirley Rohrer, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001; telephone: 301-415-5411, email: [email protected].
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2019-0187, 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-2019-0187.
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/
[[Page 50079]]
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-2019-0187, 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 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 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 http://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
[[Page 50080]]
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 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
[[Page 50081]]
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.
Exelon Generation Company, LLC, Docket Nos. 50-352 and 50-353, Limerick
Generating Station (Limerick), Units 1 and 2, Montgomery County,
Pennsylvania
Date of amendment request: August 1, 2019. A publicly-available
version is in ADAMS under Accession No. ML19213A246.
Description of amendment request: The amendments would relocate the
following operability and surveillance requirements from the Limerick
Technical Specifications (TSs) to the Limerick Technical Requirements
Manual: TS Section 3.3.7.8.1, ``Chlorine Detection System,'' and TS
Section 3.3.7.8.2, ``Toxic Gas Detection System.''
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. Do the proposed changes involve a significant increase in the
probability or consequences of an accident previously evaluated?
Response: No.
The proposed changes do not alter the physical design of any
plant structure, system, or component; therefore, the proposed
changes have no adverse effect on plant operation, or the
availability or operation of any accident mitigation equipment. The
plant response to the design basis accidents does not change.
Operation or failure of the Chlorine Detection System and the Toxic
Gas Detection System are not assumed to be initiators of any
analyzed event in the Updated Final Safety Analysis Report (UFSAR)
and cannot cause an accident. Whether the requirements for the
Chlorine Detection System and the Toxic Gas Detection System are in
TS or another licensee-controlled document has no effect on the
probability or consequences of any accident previously evaluated.
Therefore, the proposed changes do not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Do the proposed changes create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The proposed changes do not alter the plant configuration (no
new or different type of equipment is being installed) or require
any new or unusual operator actions. The proposed changes do not
alter the safety limits or safety analysis assumptions associated
with the operation of the plant. The proposed changes do not
introduce any new failure modes that could result in a new accident.
The proposed changes do not reduce or adversely affect the
capabilities of any plant structure, system, or component in the
performance of their safety function. Also, the response of the
plant and the operators following the design basis accidents is
unaffected by the proposed changes.
Therefore, the proposed changes do not create the possibility of
a new or different kind of accident from any accident previously
evaluated.
3. Do the proposed changes involve a significant reduction in a
margin of safety?
Response: No.
The proposed changes have no adverse effect on plant operation,
or the availability or operation of any accident mitigation
equipment. The plant response to the design basis accidents does not
change. The proposed changes do not adversely affect existing plant
safety margins or the reliability of the equipment assumed to
operate in the safety analyses. There is no change being made to
safety analysis assumptions, safety limits or limiting safety system
settings that would adversely affect plant safety as a result of the
proposed changes.
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: Tamra Domeyer, Associate General Counsel,
Exelon Generation Company, LLC, 4300 Winfield Road, Warrenville, IL
60555.
NRC Branch Chief: James G. Danna.
[[Page 50082]]
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 NuclearPower Station, Units 1, 2, and 3, Grundy County,
Illinois
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. 50-254 and 50-265, Quad
Cities Nuclear Power Station, Units 1 and 2, Rock Island County,
Illinois
Date of amendment request: August 23, 2019. A publicly-available
version is in ADAMS under Accession No. ML19239A006.
Description of amendment request: The amendments would revise the
emergency plans for each of these facilities by removing specific
references to radiation monitoring instrumentation in emergency action
level (EAL) RA3.
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 for each site, 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 change to EAL RA3.1 for the Exelon facilities noted
meets the guidance established in NEI 99-01, Revision 6, as endorsed
by the NRC and does not reduce the capability to meet the emergency
planning requirements established in 10 CFR 50.47 and 10 CFR 50,
Appendix E. The proposed change does not reduce the functionality,
performance, or capability of Exelon's ERO [emergency response
organization] to respond in mitigating the consequences of any
design basis accident.
The probability of a reactor accident requiring implementation
of Emergency Plan EALs has no relevance in determining whether the
proposed change to EAL RA3.1 will reduce the effectiveness of the
Emergency Plans. As discussed in Section D, ``Planning Basis,'' of
NUREG-0654, Revision 1, ``Criteria for Preparation and Evaluation of
Radiological Emergency Response Plans and Preparedness in Support of
Nuclear Power Plants'':
``. . . The overall objective of emergency response plans is to
provide dose savings (and in some cases immediate life saving) for a
spectrum of accidents that could produce offsite doses in excess of
Protective Action Guides (PAGs). No single specific accident
sequence should be isolated as the one for which to plan because
each accident could have different consequences, both in nature and
degree. Further, the range of possible selection for a planning
basis is very large, starting with a zero point of requiring no
planning at all because significant offsite radiological accident
consequences are unlikely to occur, to planning for the worst
possible accident, regardless of its extremely low likelihood. . .
.''
Therefore, Exelon did not consider the risk insights regarding
any specific accident initiation or progression in evaluating the
proposed change involving EAL RA3.
The proposed change to EAL RA3.1 does not involve any physical
changes to plant equipment or systems, nor does the proposed change
alter the assumptions of any accident analyses. The proposed change
does not adversely affect accident initiators or precursors nor does
the proposed change alter the design assumptions, conditions, and
configuration or the manner in which the plants are operated and
maintained. The proposed change does not adversely affect the
ability of Structures, Systems, or Components (SSCs) to perform
their intended safety functions in mitigating the consequences of an
initiating event within the assumed acceptance limits.
Therefore, the proposed change to EAL RA3.1 for the affected
sites 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.
The proposed change to EAL RA3.1 for the Exelon facilities noted
meets the guidance established in NEI 99-01, Revision 6, as endorsed
by the NRC and does not involve any physical changes to plant
systems or equipment. The proposed change does not involve the
addition of any new plant equipment. The proposed change will not
alter the design configuration, or method of operation of plant
equipment beyond its normal functional capabilities. Exelon ERO
functions will continue to be performed as required. The proposed
change does not create any new credible failure mechanisms,
malfunctions, or accident initiators.
Therefore, the proposed change to EAL RA3.1 for the affected
sites does not create the possibility of a new or different kind of
accident from those that have been previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed change to EAL RA3.1 for the Exelon facilities noted
meets the guidance established in the guidance in NEI 99-01,
Revision 6, as endorsed by the NRC and does not alter or exceed a
design basis or safety limit. There is no change being made to
safety analysis assumptions, safety limits, or limiting safety
system settings that would adversely affect plant safety as a result
of the proposed change. There are no changes to setpoints or
environmental conditions of any SSC or the manner in which any SSC
is operated. Margins of safety are unaffected by the proposed change
to EAL RA3. The applicable requirements of 10 CFR 50.47 and 10 CFR
50, Appendix E will continue to be met.
Therefore, the proposed change to EAL RA3.1 for the affected
sites does not involve any reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis for each site
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 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.
Southern Nuclear Operating Company, Docket No. 52-026, Vogtle Electric
Generating Plant (VEGP), Unit 4, Burke County, Georgia
Date of amendment request: August 22, 2019. A publicly-available
version is in ADAMS under Accession No. ML19234A327.
Description of amendment request: The amendment proposes to depart
from AP1000 Design Control Document Tier 2* material that has been
incorporated into the Updated Final Safety Analysis Report (UFSAR). The
proposed departure consists of changes to Tier 2* information in the
UFSAR to change the provided area of horizontal reinforcement for VEGP
Unit 4 Wall L and Wall 7.3 from elevation 117'-6'' to 135'-3''.
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.
As described in UFSAR Subsections 3H.5.1.2 and 3H.5.1.3,
interior Wall 7.3 and Wall L are located in the auxiliary building.
UFSAR, Section 3H.5 classifies Interior Wall on Column Line 7.3,
from elevation (EL) 66'-6'' to 160'-6'' as a ``Critical Section.''
UFSAR, Section 3H.5 classifies Interior Wall
[[Page 50083]]
on Column Line L, from EL 117'-6'' to 153-0'' as a Critical
Section.'' Deviations were identified in the constructed walls from
the design requirements. The proposed changes modify the provided
area of steel horizontal reinforcement for VEGP Unit 4 Wall L and
Wall 7.3 from elevation 117'-6'' to 135'-3''. These changes maintain
conformance to American Concrete Institute (ACI) 349-01 and have no
adverse impact on the seismic response of Wall L and Wall 7.3 Wall L
and Wall 7.3 continue to withstand the design basis loads without
loss of structural integrity or the safety-related functions. The
proposed changes do not affect the operation of any system or
equipment that initiates an analyzed accident or alter any
structures, systems, and components (SSC) accident initiator or
initiating sequence of events.
This change does not adversely affect the design function of
VEGP Unit 4 Wall L and Wall 7.3, or the SSCs contained within the
auxiliary building. This change does not involve any accident
initiating components or events, thus leaving the probabilities of
an accident unaltered.
Therefore, the proposed amendment does not involve a significant
increase in the probability or consequences of a previously
evaluated accident.
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 change modifies the provided area of steel
horizontal reinforcement for VEGP Unit 4 Wall L and Wall 7.3 from
elevation 117'-6'' to 135-3''. As demonstrated by the continued
conformance to the applicable codes and standards governing the
design of the structures, the walls withstand the same effects as
previously evaluated. The proposed change does not affect the
operation of any systems or equipment that may initiate a new of
different kind of accident or alter any SSC such that a new accident
initiator or initiating sequence of events is created. The proposed
change does not adversely affect the design function of auxiliary
building Wall L and Wall 7.3, or any other SSC design functions or
methods of operation in a manner that results in a new failure mode,
malfunction, or sequence of events that affect safety-related or
non-safety-related equipment. This change does not allow for a new
fission product release path, result in a new fission product
barrier failure mode, or create a new sequence of events that result
in significant fuel cladding failures.
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 change modifies the provided area of steel
horizontal reinforcement for VEGP Unit 4 Wall L and Wall 7.3 from
elevation 117'-6'' to 135'-3''. This change maintains conformance to
ACI 349-01. The changes to Wall L and Wall 7.3 horizontal
reinforcement from elevation 117'-6'' to 135'-3'' do not change the
performance of the affected portion of the auxiliary building for
postulated loads. The criteria and requirements of ACI 349-01
provide a margin of safety to structural failure. The design of the
auxiliary building structure conforms to criteria and requirements
in ACI 349-01 and therefore, maintains the margin of safety. The
change does not alter any design function, design analysis, or
safety analysis input or result, and sufficient margin exists to
justify departure from the Tier 2* requirements for the walls. As
such, because the system continues to respond to design basis
accidents in the same manner as before without any changes to the
expected response of the structure, no safety analysis or design
basis acceptance limit/criterion is challenged or exceeded by the
proposed changes. Accordingly, no significant safety margin is
reduced by the change.
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.
Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026,
Vogtle Electric Generating Plant (VEGP), Units 3 and 4, Burke County,
Georgia
Date of amendment request: July 26, 2019. A publicly-available
version is in ADAMS under Accession No. ML19207A727.
Description of amendment request: The amendment request proposes
changes to the Combined License (COL) Numbers NPF-91 and NPF-92 for
VEGP, Units 3 and 4, and Updated Final Safety Analysis Report (UFSAR).
Specifically, the requested amendment would eliminate COL condition
2.D.(2)(a)1 which describes a first plant Pressurizer Surge Line
Stratification Evaluation and make related revisions to the UFSAR Tier
2 information.
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 change does not affect the operation of any systems
or equipment that initiates an analyzed accident or alter any
structures, systems, or components [SSC] accident initiator or
initiating sequence of events. The proposed changes remove the
requirement to perform the Pressurizer Surge Line Stratification
Evaluation first plant tests based on a number of factors that
render the testing unnecessary. The changes do not adversely affect
any methodology which would increase the probability or consequences
of a previously evaluated accident.
The change does not impact the support, design, or operation of
mechanical or fluid systems. There is no change to plant systems or
the response of systems to postulated accident conditions. There is
no change to predicted radioactive releases due to normal operation
or postulated accident conditions. The plant response to previously
evaluated accidents or external events is not adversely affected,
nor does the proposed change create any new accident precursors.
The proposed changes do not involve a change to any mitigation
sequence or the predicted radiological releases due to postulated
accident conditions, thus, the consequences of the accidents
evaluated in the UFSAR are not affected.
Therefore, the proposed amendment does not involve a significant
increase in the probability or consequences of a previously
evaluated accident.
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 remove the requirement to perform the
Pressurizer Surge Line Stratification Evaluation first plant tests
based on a number of factors that render the testing unnecessary.
The proposed changes do not adversely affect any design function of
any SSC design functions or methods of operation in a manner that
results in a new failure mode, malfunction, or sequence of events
that affect safety-related or non-safety-related equipment. This
proposed change does not allow for a new fission product release
path, result in a new fission product barrier failure mode, or
create a new sequence of events that result in significant fuel
cladding failures.
These proposed changes do not adversely affect any other SSC
design functions or methods of operation in a manner that results in
a new failure mode, malfunction, or sequence of events that affect
safety-related or non-safety-related equipment. Therefore, this
proposed change does not allow for a new fission product release
path, result in a new fission product barrier failure mode, or
create a new sequence of events that results in significant fuel
cladding failures.
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 change maintains existing safety margin and
provides adequate protection through continued application of the
existing design requirements in the
[[Page 50084]]
UFSAR. The proposed change satisfies the same design functions in
accordance with the same codes and standards as stated in the UFSAR.
This change does not adversely affect any design code, function,
design analysis, safety analysis input or result, or design/safety
margin.
No safety analysis or design basis acceptance limit/criterion is
challenged or exceeded by this change, and no significant margin of
safety is reduced.
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: M. Stanford Blanton, Balch & Bingham LLP,
1710 Sixth Avenue North, Birmingham, AL 35203-2015.
NRC Branch Chief: Jennifer Dixon-Herrity.
IV. 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 Carolinas, LLC, Docket Nos. 50-413 and 50-414, Catawba
Nuclear Station, Units 1 and 2, York County, South Carolina
Date of amendment requests: May 2, 2017, as supplemented by letters
dated July 20 and November 21, 2017; December 3, 2018; and March 7,
April 8, July 10, and August 1, 2019.
Brief description of amendments: The amendments modified Catawba's
Technical Specifications (TSs) to extend the Completion Time (CT) of TS
3.8.1, ``AC Sources--Operating,'' Required Action B.6 (existing
Required Action B.4, numbered as B.6) for an inoperable emergency
diesel generator (EDG) from 72 hours to 14 days. To support this
request, the licensee will add a supplemental power source (i.e., two
supplemental diesel generators (SDGs) per station) with the capability
to power any emergency bus.
The SDGs will have the capacity to bring the affected unit to cold
shutdown. Additionally, the amendments would modify TS 3.8.1 to add new
two limiting conditions for operation (LCOs), TS LCO 3.8.1.c and TS LCO
3.8.1.d, to ensure that at least one train of shared components has an
operable emergency power supply. Corresponding Conditions, Required
Actions and CTs of TS 3.8.1 are revised to account for the new
supplemental AC power source.
Date of issuance: August 27, 2019.
Effective date: These license amendments are effective as of its
date of issuance and shall be implemented within 120 days of issuance.
Amendment Nos.: 304 (Unit 1) and 300 (Unit 2). A publicly-available
version is in ADAMS under Accession No. ML19212A655; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. NPF-35 and NPF-52:
Amendments revised the Renewed Licenses and TSs.
Date of initial notice in Federal Register: February 27, 2018 (83
FR 8512). The supplemental letters dated July 20 and November 21, 2017;
December 3, 2018; and March 7, April 8, July 10, and August 1, 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 August 27, 2019.
No significant hazards consideration comments received: No.
Entergy Nuclear Operations, Inc., Docket No. 50-247, Indian Point
Nuclear Generating Unit No. 2, Westchester County, New York
Date of amendment request: December 11, 2017, as supplemented by
letter dated June 6, 2019.
Brief description of amendment: The amendment revised Technical
Specification (TS) Limiting Condition for Operation 3.7.13, ``Spent
Fuel Pit Storage,'' and TS 4.0, ``Design Features,'' Section 4.3,
``Fuel Storage.'' The amendment resolves a non-conservative TS
associated with TS Limiting Condition for Operation 3.7.13 and negates
the need for the associated compensatory measures, while taking no
credit for installed Boraflex panels.
Date of issuance: September 4, 2019.
Effective date: As of the date of issuance and shall be implemented
within 120 days.
Amendment No.: 290. A publicly-available version is in ADAMS under
Accession No. ML19209C966; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Facility Operating License No. DPR-26: The amendment revised the
Renewed Facility Operating License and TSs.
Date of initial notice in Federal Register: March 13, 2018 (83 FR
10916). The supplemental letter dated June 6, 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 4, 2019.
No significant hazards consideration comments received: No.
[[Page 50085]]
Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket Nos. 50-
277 and 50-278, Peach Bottom Atomic Power Station (Peach Bottom), Units
2 and 3, York and Lancaster Counties, Pennsylvania
Date of amendment request: September 28, 2018, as supplemented by
letters dated February 15, 2019; March 26, 2019; and May 23, 2019.
Brief description of amendments: The amendments revised the design
and licensing basis described in the Peach Bottom Updated Final Safety
Analysis Report to reduce the design pressure rating of the high-
pressure service water (HPSW) system. This change provides additional
corrosion margin in the HPSW system pipe wall thickness, thereby
increasing the margin of safety for the existing piping. In addition,
this change also temporarily revises certain Technical Specifications
(TSs) to allow sufficient time to perform modifications of the HPSW
system to support the proposed reduction of the HPSW design pressure
and to allow for timely repairs of a heat exchanger on Peach Bottom,
Unit 3.
Date of issuance: August 28, 2019.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendments Nos.: 327 (Unit 2) and 330 (Unit 3). A publicly-
available version is in ADAMS under Accession No. ML19182A006;
documents related to these amendments are listed in the Safety
Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-44 and DPR-56: The
amendments revised TSs 3.6.2.3, 3.6.2.4, 3.6.2.5, and 3.7.1.
Date of initial notice in: November 6, 2018 (83 FR 55566).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated August 28, 2019.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket No. 50-461, Clinton Power
Station (CPS), Unit No. 1, DeWitt County, Illinois
Exelon Generation Company, LLC and Exelon FitzPatrick, LLC, Docket No.
50-333, James A. FitzPatrick Nuclear Power Plant (JAF), Oswego County,
New York
Exelon Generation Company, LLC, Docket Nos. 50-373 and 50-374, LaSalle
County Station (LCS), Units 1 and 2, LaSalle County, Illinois
Exelon Generation Company, LLC, Docket Nos. 50-352 and 50-353, Limerick
Generating Station (LGS), Units 1 and 2, Montgomery County,
Pennsylvania
Exelon Generation Company, LLC, Docket No. 50-410, Nine Mile Point
Nuclear Station (NMP), Unit 2, Oswego County, New York
Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket Nos. 50-
277 and 50-278, Peach Bottom Atomic Power Station (PBAPS), Units 2 and
3, York and Lancaster Counties, Pennsylvania
Date of amendment request: February 1, 2019, as supplemented by
letter dated March 7, 2019.
Brief description of amendments: The amendments revise the
Technical Specification (TS) requirements for these facilities related
to the safety limit minimum critical power ratio (MCPR) and the core
operating limits report. The amendments are based on Technical
Specification Task Force (TSTF) Traveler TSTF-564, Revision 2, ``Safety
Limit MCPR'' (ADAMS Accession No. ML18297A361). The amendments for LGS
and JAF also make changes to these requirements that are outside the
scope of TSTF-564, Revision 2.
Date of issuance: August 28, 2019.
Effective date: As of the date of issuance and shall be implemented
as shown in the following table.
------------------------------------------------------------------------
Implementation
Facility requirement
------------------------------------------------------------------------
CPS Unit 1........................................ prior to entering
Mode 4 following
refueling outage
C1R19.
JAF............................................... prior to entering
Mode 4 following
refueling outage
FPR24.
LCS Unit 1........................................ prior to entering
Mode 4 following
refueling outage
L1R18.
LCS Unit 2........................................ prior to LCS Unit 1
entering Mode 4
following refueling
outage L1R18.
LGS Unit 1........................................ prior to entering
Operational
Condition 4
following refueling
outage Li1R18.
LGS Unit 2........................................ prior to entering
Operational
Condition 4
following refueling
outage Li2R16.
NMP Unit 2........................................ prior to entering
Mode 4 following
refueling outage
N2R17.
PBAPS Unit 2...................................... prior to entering
Mode 4 following
refueling outage
P2R23
PBAPS Unit 3...................................... prior to entering
Mode 4 following
refueling outage
P3R22.
------------------------------------------------------------------------
Amendment Nos.: CPS-225, JAF-327, LCS-238/224, LGS-236/199, NMP2-
176, and PBAPS-326/329. A publicly-available version is in ADAMS under
Accession No. ML19176A033. Documents related to these amendments are
listed in the Safety Evaluation enclosed with the amendments.
Facility Operating License Nos. NPF-62, DPR-59, NPF-11, NPF-18,
NPF-39, NPF-85, NPF-69, DPR-44, and DPR-56: Amendments revised the
Facility Operating Licenses and TSs.
Date of initial notice in: April 9, 2019 (84 FR 14146).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated August 28, 2019.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457,
Braidwood Station, Units 1 and 2, Will County, Illinois and Docket Nos.
STN 50-454 and STN 50-455, Byron Station, Unit Nos. 1 and 2, Ogle
County, Illinois
Date of amendment request: January 31, 2019, as supplemented by
letter dated August 9, 2019.
[[Page 50086]]
Brief description of amendments: The amendments revised Technical
Specifications (TSs) for inoperable snubbers by adding limiting
condition for operation (LCO) 3.0.9. The change is consistent with the
NRC-approved Technical Specification Task Force (TSTF) Standard
Technical Specifications Change Traveler, TSTF-372, ``Addition of LCO
3.0.8, lnoperability of Snubbers.''
Date of issuance: August 28, 2019.
Effective date: As of the date of issuance and shall be implemented
within 30 days from the date of issuance.
Amendment Nos.: 202/208 (Braidwood, Units 1 and 2), and 208/208
(Byron, Unit Nos. 1 and 2). A publicly-available version is in ADAMS
under Accession No. ML19190A081; documents related to these amendments
are listed in the related Safety Evaluation enclosed with the
amendments.
Renewed Facility Operating License Nos. NPF-72, NPF-77, NPF-37, and
NPF-66: The amendments revised the TSs and the Renewed Facility
Operating Licenses.
Date of initial notice in: May 7, 2019 (84 FR 19970).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated August 28, 2019.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket No. 50-289, Three Mile Island
Nuclear Station, Unit 1 (TMI-1), Dauphin County, Pennsylvania
Date of amendment request: July 25, 2018, as supplemented by letter
dated March 6, 2019.
Brief description of amendment: The amendment revised the TMI-1
Renewed Facility Operating License and the associated Technical
Specifications (TSs) to permanently defueled TSs, consistent with the
permanent cessation of reactor operation and permanent defueling of the
reactor. The amendment also changed the current licensing basis
mitigation strategies for flood mitigation and aircraft impact
protection in the air intake tunnel.
Date of issuance: August 29, 2019.
Effective date: The amendment is effective following the docketing
of the certifications required by 10 CFR 50.82(a)(1)(i) and (ii) that
TMI-1 has been permanently shut down and defueled. The amendment shall
be implemented within 30 days of the effective date of the amendment,
but will not exceed December 31, 2019.
Amendment No.: 297. A publicly-available version is in ADAMS under
Accession No. ML19211D317; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-50: The amendment
revised the Renewed Facility Operating License and TSs.
Date of initial notice in: November 20, 2018 (83 FR 58611). The
supplemental letter dated March 6, 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 August 29, 2019.
No significant hazards consideration comments received: No.
Holtec Pilgrim, LLC and Holtec Decommissioning International, LLC,
Docket No. 50-293, Pilgrim Nuclear Power Station (Pilgrim), Plymouth
County, Massachusetts
Date of amendment request: November 16, 2018, as supplemented by
letters dated November 16, 2018; April 17, 2019; and July 29, 2019.
Brief description of amendment: The amendment revised Renewed
Facility Operating License No. DPR-35 to reflect the indirect transfer
of Pilgrim Renewed Facility Operating License No. DPR-35 and the
general license for the Pilgrim Independent Spent Fuel Storage
Installation from Entergy Nuclear Operations, Inc. (ENOI) to Holtec
International; the name change for Entergy Nuclear Generation Company
to Holtec Pilgrim, LLC; and the direct transfer of ENOI's operating
authority to Holtec Decommissioning International, LLC.
Date of issuance: August 27, 2019.
Effective date: As of the date of issuance and shall be implemented
within 30 days of issuance.
Amendment No.: 249. A publicly-available version is in ADAMS under
Accession No. ML19235A050; documents related to this amendment are
listed in the Safety Evaluation referenced in the letter dated August
22, 2019 (ADAMS Accession No. ML19170A101).
Renewed Facility Operating License No. DPR-35: The amendment
revised the Renewed Facility Operating License and Technical
Specifications.
Date of initial notice in: January 31, 2019 (84 FR 816).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated August 27, 2019.
Northern States Power Company--Minnesota, Docket No. 50-263, Monticello
Nuclear Generating Plant (MNGP), Wright County, Minnesota
Date of amendment request: March 28, 2018, as supplemented by
letters dated March 13, 2019, and May 15, 2019.
Brief description of amendment: The amendment added a condition to
the MNGP renewed facility operating license to allow the implementation
of 10 CFR 50.69, ``Risk-informed categorization and treatment of
structures, systems and components for nuclear power reactors.''
Date of issuance: August 29, 2019.
Effective date: As of the date of issuance and shall be implemented
within 90 days of issuance.
Amendment No.: 203. A publicly-available version is in ADAMS under
Accession No. ML19176A421; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-22: Amendment revised
the Facility Operating License and Technical Specifications.
Date of initial notice in: May 22, 2018 (83 FR 23735). The
supplemental letters dated March 13, 2019, and May 15, 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 August 29, 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 18, 2019.
Brief description of amendment: The amendment revised Hope Creek
Generating Station Technical Specification (TS) 3.6.5.1, ``Secondary
Containment Integrity,'' Surveillance Requirements (SRs) 4.6.5.1.a and
4.6.5.1.b.2.a. SR 4.6.5.1.a is revised to address conditions during
which the secondary containment pressure may not meet the SR pressure
requirements. SR 4.6.5.1.b.2.a is modified to
[[Page 50087]]
acknowledge that both secondary containment access openings may be
simultaneously open for entry and exit. Additionally, TS Definitions
1.39.d and 1.39.g are revised to conform to the changes to these two
SRs.
Date of issuance: September 6, 2019.
Effective date: As of the date of issuance and shall be implemented
within 60 days of the date of issuance.
Amendment No.: 218. A publicly-available version is in ADAMS under
Accession No. ML19205A306; 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: June 4, 2019 (84 FR
25839).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated September 6, 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 (Hatch), Unit Nos. 1 and 2, Appling County, Georgia
Date of amendment request: October 17, 2018.
Brief description of amendments: The amendments modified the
required actions associated with the Hatch, Unit Nos. 1 and 2,
Technical Specification (TS) 3.6.4.1, ``Secondary Containment,'' to
allow up to 7 days to determine and correct the cause of secondary
containment degradation when at least one combination of standby gas
treatment subsystems can maintain adequate secondary containment
vacuum.
Date of issuance: September 4, 2019.
Effective date: As of the date of issuance and shall be implemented
within 90 days of issuance.
Amendment Nos.: 298 (Unit 1) and 243 (Unit 2). A publicly-available
version is in ADAMS under Accession No. ML19198A104; 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:
Amendments revised the Renewed Facility Operating Licenses and TSs.
Date of initial notice in Federal Register: March 26, 2019 (84 FR
11342).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated September 4, 2019.
No significant hazards consideration comments received: No.
Tennessee Valley Authority (TVA) Docket Nos. 50-259, 50-260, and 50-
296, Browns Ferry Nuclear Plant (Browns Ferry), Units 1, 2, and 3,
Limestone County, Alabama
TVA Docket Nos. 50-327 and 50-328, Sequoyah Nuclear Plant (Sequoyah),
Units 1 and 2, Hamilton County, Tennessee
TVA Docket Nos. 50-390 and 50-391, Watts Bar Nuclear Plant (Watts Bar),
Units 1 and 2, Rhea County, Tennessee
Date of amendment request: November 17, 2017, as supplemented by
letter dated June 18, 2018, and as subsequently revised by letter dated
November 19, 2018, and supplemented by letter dated January 25, 2019.
Brief description of amendments: The amendments added a new level
of protection regarding ``unbalanced voltage'' to the Technical
Specifications (TSs) for the loss of power instrumentation.
Implementation of these amendments provides for equipment protection
from the effects of an unbalanced voltage in a similar fashion to the
existing degraded and loss of voltage protection schemes. Specifically,
the amendments added a new condition to TS 3.3.8.1 and revised TS Table
3.3.8.1-1 for Browns Ferry, and added a new condition to TS 3.3.5 and
revised TS Table 3.3.5-1 for Sequoyah and Watts Bar to reflect the
implementation of the Class 1E ``unbalanced voltage'' relays for Browns
Ferry, Sequoyah, and Watts Bar TSs loss of power instrumentation.
Date of issuance: August 27, 2019.
Effective date: As of the date of issuance and shall be implemented
within 120 days of issuance.
Amendment Nos.: 309, 332, and 292 (Browns Ferry, Units 1, 2, and 3
respectively); 345 and 339 (Sequoyah, Units 1 and 2, respectively); and
128 and 31 (Watts Bar, Units 1 and 2, respectively). A publicly-
available version is in ADAMS under Accession No. ML18277A110;
documents related to these amendments are listed in the Safety
Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-33, DPR-52, DPR-68,
DPR-77, and DPR-79, and Facility Operating License Nos. NPF-90 and NPF-
96: The amendments revised the Facility Operating Licenses and TSs.
Date of initial notice in Federal Register: January 16, 2018 (83 FR
2231). The supplemental letter dated June 18, 2018, and as subsequently
revised by letter dated November 19, 2018, and supplemented by letter
dated January 25, 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 amendments is contained
in a Safety Evaluation dated August 27, 2019.
No significant hazards consideration comments received: No.
Dated at Rockville, Maryland, this 18th day of September 2019.
For the Nuclear Regulatory Commission.
Jessica A. Bielecki,
Acting Deputy Director, Division of Operating Reactor Licensing, Office
of Nuclear Reactor Regulation.
[FR Doc. 2019-20507 Filed 9-23-19; 8:45 am]
BILLING CODE 7590-01-P
