Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations, 53767-53776 [2019-21447]

Agencies

• NUCLEAR REGULATORY COMMISSION

[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]


=======================================================================
-----------------------------------------------------------------------

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.

-----------------------------------------------------------------------

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 pdr.resour[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