[Federal Register Volume 84, Number 29 (Tuesday, February 12, 2019)]
[Notices]
[Pages 3504-3514]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-01215]


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NUCLEAR REGULATORY COMMISSION

[NRC-2019-0040]


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 January 15, 2019 to January 28, 2019. The 
last biweekly notice was published on January 31, 2019.

DATES: Comments must be filed by March 14, 2019. A request for a 
hearing must be filed by April 15, 2019. Comments received after this 
date will be considered if it is practical to do so, but the Commission 
is able to ensure consideration only for comments received before this 
date.

ADDRESSES: You may submit comments by any of the following methods:
     Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2019-0040. Address 
questions about Docket IDs in Regulations.gov to Krupskaya Castellon; 
telephone: 301-287-9221; 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 
Reactor 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-2019-0040, 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 http://www.regulations.gov and search for Docket ID NRC-2019-0040.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``Begin Web-based ADAMS 
Search.'' For problems with ADAMS, please contact the NRC's Public 
Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or 
by email to [email protected]. The ADAMS accession number for each 
document referenced (if it is available in ADAMS) is provided the first 
time that it is mentioned in this document.
     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.

B. Submitting Comments

    Please include Docket ID NRC-2019-0040, 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 http://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

[[Page 3505]]

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 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

[[Page 3506]]

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 http://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 http://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 http://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 http://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.

Arizona Public Service Company, et al., Docket Nos. STN 50-528, STN 50-
529, and STN 50-530, Palo Verde Nuclear Generating Station, Units 1, 2, 
and 3 (PVNGS), Maricopa County, Arizona

    Date of amendment request: December 27, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18361A845.
    Description of amendment request: The amendments would modify the 
Technical Specification (TS) requirements in Section 1.3 and Section

[[Page 3507]]

3.0 regarding limiting condition for operation (LCO) and surveillance 
requirement (SR) usage for PVNGS. These changes are consistent with 
NRC-approved Technical Specifications Task Force (TSTF) Traveler TSTF-
529, ``Clarify Use and Application Rules,'' Revision 4.
    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 to Section 1.3 and LCO 3.0.4 have no effect 
on the requirement for systems to be Operable and have no effect on 
the application of TS actions. The proposed change to SR 3.0.3 
states that the allowance may only be used when there is a 
reasonable expectation the surveillance will be met when performed. 
Since the proposed change does not significantly affect system 
Operability, the proposed change, will have no significant effect on 
the initiating events for accidents previously evaluated and will 
have no significant effect on the ability of the systems to mitigate 
accidents previously evaluated.
    Therefore, it is concluded that this 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.
    The proposed changes to the TS usage rules do not affect the 
design or function of any plant systems. The proposed change does 
not change the Operability requirements for plant systems or the 
actions taken when plant systems are not operable.
    Therefore, it is concluded that this change 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 clarifies the application of Section 1.3 and 
LCO 3.0.4 and does not result in changes in plant operation. SR 
3.0.3 is revised to allow application of SR 3.0.3 when an SR has not 
been previously performed and there is reasonable expectation that 
the SR will be met when performed. This expands the use of SR 3.0.3 
while ensuring the affected system is capable of performing its 
safety function. As a result, plant safety is either improved or 
unaffected.
    Therefore, it is concluded that this change does not involve a 
significant reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
that 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: Michael G. Green, Associate General Counsel, 
Nuclear and Environmental, Pinnacle West Capital Corporation, P.O. Box 
52034, Mail Station 7602, Phoenix, Arizona 85072-2034.
    NRC Branch Chief: Robert J. Pascarelli.

Duke Energy Florida, LLC (DEF), Docket No. 50-302, Crystal River Unit 3 
Nuclear Generating Plant (CR-3), Citrus County, Florida

    Date of amendment request: January 16, 2019. A publicly-available 
version is in ADAMS under Accession No. ML19016A496.
    Description of amendment request: The amendment would revise the 
CR-3 Independent Spent Fuel Storage Installation (ISFSI)-Only Emergency 
Plan (IOEP). The amendment would make several editorial changes and 
revise the IOEP to replace the Emergency Response Coordinator position.
    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 amendment would modify the CR-3 facility operating 
license by revising the emergency plan. CR-3 has permanently ceased 
operation and is permanently defueled.
    Occurrence of postulated accidents associated with spent fuel 
stored in a spent fuel pool is no longer credible in a spent fuel 
pool devoid of such fuel. The UFSAR [Updated Final Safety Analysis 
Report] for NUHOMS Certificate of Compliance (CoC) 1004 states most 
accidents are not credible and the accident analysis demonstrates 
that none of the hypothetical accidents analyzed has any 
consequential effect on the public. Many of the analyzed events, 
like a fire at the ISFSI, have no radiological release. The proposed 
amendment has no effect on the capability of any plant or ISFSI 
System, Structure, or Components (SSC) to perform its design 
function. The proposed amendment would not increase the likelihood 
of the malfunction of any ISFSI SSC as there are no hardware or 
software modifications associated with this change. The proposed 
amendment would have no effect on any of the previously evaluated 
accidents in the ISFSI UFSAR for CoC 1004.
    The specific non-editorial changes of the emergency plan 
revision only reassign the medical and fire response 
responsibilities from one individual title, the Emergency Response 
Coordinator, to plant specific personnel.
    A medical emergency may be the result of some event within the 
plant or ISFSI protected area. However, the qualification or 
response time of the individuals providing basic first aid or 
contacting offsite responders for additional medical assistance 
would have no impact on any accident or event scenario and will not 
change the bounding accident or event consequences to the onsite 
personnel or the general public.
    Likewise, a fire emergency may be the result of an onsite event, 
but a calculation performed by DEF demonstrates that the design 
basis fire analyzed in the UFSAR for CoC 1004 is bounding and would 
not create a release. The CR-3 Fire Protection Program allows for 
plant personnel to attempt to put out small fires with fire 
extinguishers but requires offsite fire response organization to be 
called for assistance. The person who makes the call for this 
assistance does not need to be highly trained in firefighting 
techniques, and being able to make the call more rapidly can only be 
considered a beneficial change.
    The proposed amendment would not increase the likelihood of the 
malfunction of any ISFSI SSC. The proposed amendment would have no 
effect on any of the previously evaluated accidents in the UFSAR for 
CoC 1004.

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 constitutes a revision of the emergency 
planning function commensurate with the ongoing and anticipated 
reduction in staff at CR-3.
    The proposed amendment does not involve a physical alteration of 
the ISFSI. No new or different types of equipment will be installed 
and there are no physical modifications to existing equipment as a 
result of the proposed amendment. Similarly, the proposed amendment 
would not physically change any SSC utilized in the mitigation of 
any postulated accidents (such as fire protection equipment). Thus, 
no new initiators or precursors of a new or different kind of 
accident are created. Furthermore, the proposed amendment does not 
create the possibility of a new failure mode associated with any 
equipment or personnel failures. The credible events for the ISFSI 
remain unchanged and the resultant consequences are unchanged.
    Therefore, the proposed amendment 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.
    Because the 10 CFR part 50 license for CR-3 no longer authorizes 
operation of the

[[Page 3508]]

reactor or emplacement or retention of fuel into the reactor vessel, 
as specified in 10 CFR 50.82(a)(2), the occurrence of postulated 
accidents associated with reactor operation is no longer credible. 
With all spent nuclear fuel transferred out of wet storage from the 
spent fuel pools and placed in dry storage within the ISFSI, a fuel 
handling accident is no longer credible. The accident analyses 
presented in the ISFSI UFSAR for CoC 1004 demonstrates that there 
are no accidents or events that will result in any type of 
significant release, with most accidents having no radiological 
release.
    The proposed amendment does not involve a change in the ISFSI's 
design, configuration, or operation. The proposed amendment does not 
affect either the way in which the ISFSI structures, systems, and 
components perform their safety function or their design margins.
    Because there is no change to the physical design of the ISFSI, 
there is no change to these margins. 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: Lara S. Nichols, 550 South Tryon Street, 
Charlotte, North Carolina 28202.
    NRC Branch Chief: Bruce A. Watson.

Duke Energy Progress, LLC, Docket No. 50-400, Shearon Harris Nuclear 
Power Plant (HNP), Unit 1, Wake and Chatham Counties, North Carolina

    Date of amendment request: July 30, 2018, as supplemented by 
letters dated September 24, 2018, and December 27, 2018. Publicly-
available versions are in ADAMS under Accession Nos. ML18211A546, 
ML18267A102, and ML18362A415, respectively.
    Description of amendment request: The amendment would revise 
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 
(FSAR) Chapter 15 transient analyses. It would also remove the high 
power range high negative neutron flux rate trip from the TSs.
    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 Reactor Trip System (RTS) and Engineered Safety Feature 
Actuation System (ESFAS) provide plant protection and are part of 
the accident mitigation response. The RTS and ESFAS functions do not 
themselves act as a precursor or an initiator for any transient or 
design basis accident. Therefore, the proposed change does not 
significantly increase the probability of any accident previously 
evaluated.
    The proposed change does not alter the design assumptions, 
conditions, or configuration of the facility. The structural and 
functional integrity of the RTS and ESFAS, or any other plant 
system, is unaffected. The proposed change does not alter or prevent 
the ability of structures, systems, and components from performing 
their intended function to mitigate the consequences of an 
initiating event within the assumed acceptance limits. The proposed 
changes will not alter any assumptions or change any mitigation 
actions in the radiological consequence evaluations in the FSAR.
    The proposed changes do 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. The proposed changes do not alter or 
prevent the ability of structures, systems, and components from 
performing their intended function to mitigate the consequences of 
an initiating event within the assumed acceptance limits. The 
proposed changes do not affect the source term, containment 
isolation, or radiological release assumptions used in evaluating 
the radiological consequences of any accident previously evaluated. 
The proposed changes are consistent with safety analysis assumptions 
and resultant consequences. The methods used to calculate the 
parameter uncertainties and the setpoints remain unchanged. Changes 
to the setpoints are primarily due to updated component uncertainty 
values and harvesting excess calculational margin (CM) in the 
setpoint total allowance (TA).
    The removal of the high power range negative neutron flux rate 
trip function from the HNP Technical Specifications does not involve 
a significant increase in the probability or consequences of 
accidents resulting from dropped RCCA [rod cluster control assembly] 
events analyzed utilizing the NRC-approved Duke Energy methodology 
for FSAR Chapter 15 transient analyses, DPC-NE-3009, ``FSAR/UFSAR 
Chapter 15 Transient Analysis Methodology.'' As demonstrated in the 
response to SRXB RAI #2, the results of the dropped rod analysis 
without crediting the high power range negative neutron flux rate 
trip meet the applicable Chapter 15 accident analysis acceptance 
criteria. The safety functions of other safety-related systems and 
components, which are related to mitigation of these events, have 
not been altered by this change. All other reactor trip system 
protection functions are not impacted by the deletion of the trip 
function. The dropped RCCA accident analysis does not rely on the 
high power range negative neutron flux rate trip to safely shut down 
the plant. The safety analysis of the plant is unaffected by the 
proposed change. Since the safety analysis is unaffected, the 
calculated radiological releases associated with the analysis are 
not affected.
    Therefore, the proposed change does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.

2. Does the proposed change create the possibility of a new or 
different kind of accident from any previously evaluated?

    Response: No.
    There are no hardware changes nor are there any changes in the 
method by which any safety-related plant system performs its safety 
function. The proposed changes will not affect the normal method of 
plant operation. No performance requirements will be affected or 
eliminated. The proposed changes will not result in physical 
alteration to any plant system nor will there be any change in the 
method by which any safety-related plant system performs its safety 
function. The proposed changes do not alter assumptions made in the 
safety analysis but ensures that the instruments behave as assumed 
in the accident analysis. The proposed change is consistent with the 
safety analysis assumptions. The methods used to calculate the 
parameter uncertainties and the setpoints remain unchanged. Changes 
to the setpoints are primarily due to updated component uncertainty 
values and harvesting excess CM in the setpoint TA.
    No new accident scenarios, transient precursors, failure 
mechanisms, or limiting single failures are introduced as a result 
of these changes. There will be no adverse effect or challenges 
imposed on any safety-related system as a result of these changes.
    The proposed change does not adversely alter the design 
assumptions, conditions, or configuration of the facility or the 
manner in which the plant is operated. No new accident scenarios, 
failure mechanisms, or limiting single failures are introduced as a 
result of deleting the high power range negative neutron flux rate 
trip function. The proposed change does not challenge the 
performance or integrity of any safety-related systems or 
components.
    Therefore, the proposed change does not create the possibility 
of a new or different kind of accident from any accident previously 
evaluated.

3. Does the proposed change involve a significant reduction in a margin 
of safety?

    Response: No.
    The proposed changes do 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 negatively impacted by these changes. Redundant RTS and 
ESFAS trains are maintained, and diversity with regard to the 
signals that provide reactor trip and engineered safety features 
actuation is also maintained. All signals credited as primary or 
secondary, and all operator actions credited in the accident

[[Page 3509]]

analyses will remain the same. The proposed changes will not result 
in plant operation in a configuration outside the design basis. The 
methods used to calculate the parameter uncertainties and the 
setpoints remain unchanged. Changes to the setpoints are primarily 
due to updated component uncertainty values and harvesting excess CM 
in the setpoint TA.
    The margin of safety associated with the acceptance criteria of 
any accident is unchanged. It has been demonstrated that the high 
power range negative neutron flux rate trip function can be deleted 
by the NRC-approved methodology described in WCAP-11394-P-A. In 
utilizing the NRC-approved Duke Energy methodology for FSAR Chapter 
15 transient analyses, DPC-NE-3009, it has been demonstrated that 
the removal of the high power range negative neutron flux rate trip 
function does not result in exceeding the limits on DNB [departure 
from nucleate boiling] for dropped RCCA events. The proposed change 
will have no effect on the availability, operability, or performance 
of safety-related systems and components.
    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: David Cummings, Associate General Counsel, 
Duke Energy Corporation, 550 South Tryon St., M/C DEC45A, Charlotte, NC 
28202.
    NRC Branch Chief: Undine Shoop.

Southern Nuclear Operating Company, Inc. (SNC), Docket Nos. 52-025 and 
52-026, Vogtle Electric Generating Plant (VEGP), Units 3 and 4, Burke 
County, Georgia

    Date of amendment request: December 13, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18347B484.
    Description of amendment request: The requested amendment proposes 
changes to Updated Final Safety Analysis Report (UFSAR) 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. Specifically, the amendment 
proposes changes that revise the COL and licensing basis documents to 
identify passive residual heat removal (PRHR) heat exchanger (HX) inlet 
isolation valve status and PRHR HX control valve status as requiring 
main control room (MCR) and remote shutdown workstation (RSW) display 
and alert indications. Additionally, a change is proposed to remove 
duplicate Tier 2 information from a document that is incorporated by 
reference into the UFSAR. The licensee is submitting technical 
specification base changes to reflect the changes in the license 
amendment request.
    SNC has also requested an exemption from the provisions of 10 CFR 
part 52, Appendix D, Section III.B, ``Design Certification Rule for the 
AP1000 Design, Scope and Contents,'' to allow a departure from the 
elements of the certification information in Tier 1 of the generic 
Design Control Document.
    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 Updated Final Safety 
Analysis Report (UFSAR) Tier 2 information, which involves a change 
to the COL Appendix C and corresponding plant-specific Tier 1 
information in Tables 2.5.2-5 and 2.5.4-1 to identify passive 
residual heat removal (PRHR) heat exchanger (HX) inlet isolation 
valve status and PRHR HX control valve status as requiring main 
control room (MCR) and remote shutdown workstation (RSW) display and 
alert indications. Corresponding changes are made to remove reliance 
upon the use of PRHR HX outlet temperature (RCS-TE161) as the 
diverse measurement to PRHR HX flow, and to make other changes to 
consistently describe the post-accident monitoring system (PAMS) 
``PRHR Outlet Temperature'' and ``PRHR HX Outlet Temperature'' 
variables to be consistent with the description provided in UFSAR 
Table 7.5-1. Additionally, a change is proposed to remove duplicate 
Tier 2 information from a document that is incorporated by reference 
(IBR) into the UFSAR.
    The proposed changes to the post-accident monitoring system 
(PAMS) PRHR heat removal function, including changes to the 
classification of the PRHR HX outlet temperature variable, and the 
Minimum Inventory Tables for PRHR HX Valve Status do not constitute 
a modification, addition to, or removal of a structure, system, or 
component (SSC) such that a PXS or PAMS design function as described 
in the UFSAR is adversely affected. The instrumentation affected by 
this activity is not an initiator of an accident condition or of any 
accident analyzed in Chapter 15 of the UFSAR. The changes do not 
involve an interface with any SSC accident initiator or initiating 
sequence of events, and thus, the probabilities of the accidents 
evaluated in the UFSAR are not affected. 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. The deletion of IBR information from the UFSAR is an 
administrative change that removes unnecessary duplicate information 
from the licensing basis.
    Therefore, the proposed amendment 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 will continue to maintain required 
functional capability of the safety systems for previously evaluated 
accidents, including those involving a loss of the normal core decay 
heat removal path. The instrumentation affected by this activity is 
not an initiator of an accident condition or of any accident 
analyzed in Chapter 15 of the UFSAR. The changes do not involve an 
interface with any SSC accident initiator or initiating sequence of 
events, and thus, the probabilities of the accidents evaluated in 
the UFSAR are not affected. The changes do not introduce a new 
interface with any SSC accident initiator or initiating sequence of 
events, and thus, the possibility of a new accident is not created. 
The proposed changes do not change the function of the related 
systems, and thus, the changes do not introduce a new failure mode, 
malfunction or sequence of events that could adversely affect safety 
or safety-related equipment.
    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 to the PAMS PRHR heat removal function and 
Minimum Inventory Tables for PRHR HX Valve Status continue to comply 
with the applicable design criteria addressing instrumentation and 
controls, protection system functions, and protection system 
independence. The addition of these variables under the same type/
category as the current PRHR outlet temperature variable will ensure 
the heat sink maintenance function will be satisfied. The proposed 
changes do not change the function of the related systems or affect 
the margins provided by the systems, and thus, the changes do not 
affect any safety-related design code, function, design analysis, 
safety analysis input or result, or existing design/safety margin. 
No safety analysis or design basis acceptance limit/criterion is 
challenged or exceeded by the requested changes.
    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

[[Page 3510]]

proposes to determine that the amendment request involves no 
significant hazards consideration.
    Attorney for licensee: Mr. M. Stanford Blanton, Balch & Bingham 
LLP, 1710 Sixth Avenue North, Birmingham, AL 35203-2015.
    NRC Branch Chief: Jennifer Dixon-Herrity.

Southern Nuclear Operating Company, Inc., Docket Nos. 50-348 and 50-
364, Joseph M. Farley Nuclear Plant, Units 1 and 2, Houston County, 
Alabama,

    Date of amendment request: December 14, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18348A733.
    Description of amendment request: The proposed amendments would 
modify the plant operating licenses to allow, as a performance-based 
method, use of thermal insulation materials in limited applications 
subject to appropriate engineering reviews and controls, as a deviation 
from National Fire Protection Association (NFPA) Standard 805 Chapter 
3, Section 3.3, Prevention.
    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 change does not affect accident initiators or 
precursors, nor alter the design assumptions, conditions and 
configuration of the facility or the manner in which the plant is 
operated and maintained.
    The proposed change is administrative in nature and does not 
affect the ability of structures, systems and components (SSCs) to 
perform their intended safety function to mitigate the consequences 
of an initiating event within the assumed acceptance limits.
    The proposed amendment does not involve a physical change to the 
containment or spent fuel area systems, nor does it change the 
safety function of the containment, containment purge and exhaust 
ventilation system, penetration room filtration system, or 
associated instrumentation.
    Therefore, it is concluded that these proposed changes do not 
involve a significant increase in the probability of 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.
    There is no risk impact to Core Damage Frequency (CDF) or Large 
Early Release Frequency (LERF) because this is an administrative 
change. Plant secondary combustibles, including insulating 
materials, are considered in the fire modeling input to the Fire PRA 
[Probabilistic Risk Assessment].
    With respect to a new or different kind of accident, there are 
no proposed design changes to the safety related plant SSCs nor are 
there any changes in the method by which safety related plant SSCs 
perform their safety functions. The proposed change does not result 
in any new or different kinds of accidents from those previously 
evaluated because it does not change any precursors or equipment 
that is previously credited for accident mitigation.
    The proposed amendment will not affect the normal method of 
plant operation or revise any operating parameters. No new accident 
scenarios, transient precursors, failure mechanisms, or limiting 
single failures will be introduced as a result of this proposed 
change and the failure modes and effects analyses of SSCs important 
to safety are not altered as a result of this proposed change. The 
proposed amendment does not alter the design or performance of the 
related SSCs, and, therefore, does not constitute a new type of 
test.
    No changes are being proposed to the procedures that operate the 
plant equipment and the change does not have a detrimental impact on 
the manner in which plant equipment operates or responds to an 
actuation signal.
    Therefore, the proposed change will not create the possibility 
of a new or different accident than previously evaluated.

3. Does the proposed change involve a significant reduction in a margin 
of safety?

    Response: No.
    The margin of safety is related to the ability of the fission 
product barriers to perform their design functions during and 
following an accident. These barriers include the fuel cladding, the 
reactor coolant system, and the containment.
    Instrumentation safety margin is established by ensuring the 
limiting safety system settings (LSSSs) automatically actuate the 
applicable design function to correct an abnormal situation before a 
safety limit is exceeded. Safety analysis limits are established for 
reactor trip system and ESF [engineered safety feature] actuation 
system instrumentation functions related to those variables having 
significant safety functions. The proposed change does not alter the 
design of these protection systems; nor are there any changes in the 
method by which safety related plant SSCs perform their specified 
safety functions.
    The limited installations of the insulation materials do not 
compromise post-fire safe shutdown capability as previously 
designed, reviewed and considered. Essential fire protection safety 
functions are maintained and are capable of being performed. Because 
the insulation materials do not compromise post-fire safe shutdown 
capability as previously designed, reviewed and considered, it is 
concluded that this 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: Ms. Millicent Ronnlund, Vice President and 
General Counsel, Southern Nuclear Operating Company, Inc., P.O. Box 
1295, Bin 038, Birmingham, AL 35201-1295.
    NRC Branch Chief: Michael T. Markley.

Tennessee Valley Authority, Docket Nos. 50-390 and 50-391, Watts Bar 
Nuclear Plant, Units 1 and 2, Rhea County, Tennessee

    Date of amendment request: August 1, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18213A120.
    Description of amendment request: The amendments would revise the 
Technical Specifications (TSs) to adopt, with minor administrative 
variation, Technical Specification Task Force (TSTF) Traveler 266-A, 
Revision 3, ``Eliminate the Remote Shutdown System Table of 
Instrumentation and Controls.'' TSTF-266-A relocates TS Table 3.3.4-1, 
``Remote Shutdown System Instrumentation and Controls,'' to the TS 
Bases, where changes can be administered under the provisions of TS 
5.6, ``TS Bases Control Program.''
    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 consequence of an accident previously evaluated?

    Response: No.
    The proposed change removes the list of Remote Shutdown System 
(RSS) instrumentation and controls from the TS and places them in 
the TS Bases. The TS continue to require that the instrumentation 
and controls be operable. The location of the list of Remote 
Shutdown System instrumentation and controls is not an initiator to 
any accident previously evaluated. The proposed change will have no 
effect on the mitigation of any accident previously evaluated 
because the instrumentation and controls continue to be required to 
be operable.
    Therefore, the proposed change does not involve a significant 
increase in the probability or consequences of any accident 
previously evaluated.

[[Page 3511]]

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 does not involve a physical alteration to 
the plant (i.e., no new or different type of equipment will be 
installed) or a change to the methods governing normal plant 
operation. The changes do not alter the assumptions made in the 
safety analysis.
    Therefore, the proposed change 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 removes the list of RSS instrumentation and 
controls from the TS and places it in the TS Bases. The review 
performed by the Nuclear Regulatory Commission when the list of RSS 
instrumentation and controls is revised will no longer be needed 
unless the criteria of 10 CFR 50.59 are not met such that prior 
Nuclear Regulatory Commission (NRC) review is required. The TS 
requirement that the RSS be operable, the definition of operability, 
the requirements of 10 CFR 50.59, and the TS Bases Control Program 
are sufficient to ensure that revision of the list without prior NRC 
review and approval does not introduce a significant safety risk.
    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: General Counsel, Tennessee Valley Authority, 
400 West Summit Hill Drive, 6A West Tower, Knoxville, TN 37902.
    NRC Branch Chief: Undine Shoop.

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. 50-369 and 50-370, McGuire 
Nuclear Station, Units 1 and 2, Mecklenburg County, North Carolina

    Date of amendment request: February 26, 2018, as supplemented by 
letter dated September 13, 2018.
    Brief description of amendments: The amendments modified Technical 
Specification (TS) 3.4.11, ``Pressurizer Power Operated Relief Valves 
(PORVs),'' to resolve non-conservative Required Actions. TS 3.4.11, 
Condition B, for one or two PORVs inoperable and not capable of being 
manually cycled is revised and split into three separate Conditions: 
(1) One Train B PORV inoperable and not capable of being manually 
cycled, (2) one Train A PORV inoperable and not capable of being 
manually cycled, and (3) two Train B PORVs inoperable and not capable 
of being manually cycled. TS 3.4.11, Condition C, for one block valve 
inoperable is revised and split into two separate Conditions: (1) One 
Train B block valve inoperable and (2) one Train A block valve 
inoperable. TS 3.4.11, Condition F for two block valves inoperable is 
revised to be new Condition I for two Train B block valves inoperable. 
A new condition, Condition J, is added for one Train B PORV and the 
other Train B block valve inoperable. Current Condition G for three 
block valves inoperable is revised to be new Condition K. Current 
Condition D is revised and renamed as Condition E, current Condition E 
is revised and renamed as Condition F, and current Condition H is 
revised and renamed as new Condition L. The Surveillance Requirement 
(SR) 3.4.11.1 note is revised to include additional Conditions C and D, 
when performing this SR is not required for inoperable block valves in 
these conditions.
    Date of issuance: January 16, 2019.
    Effective date: These amendments are effective as of the date of 
issuance and shall be implemented within 60 days of issuance.
    Amendment Nos.: 311 (Unit 1) and 290 (Unit 2). A publicly-available 
version is in ADAMS under Accession No. ML18318A358; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Renewed Facility Operating License Nos. NPF-9 and NPF-17: The 
amendments revised the Renewed Facility Operating Licenses and TSs.
    Date of initial notice in Federal Register: July 31, 2018 (83 FR 
36974). The supplemental letter dated September 13, 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 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 January 16, 2019.
    No significant hazards consideration comments received: No.

Duke Energy Carolinas, LLC, Docket Nos. 50-369 and 50-370, McGuire 
Nuclear Station, Units 1 and 2, Mecklenburg County, North Carolina

    Date of amendment request: December 8, 2017, as supplemented by 
letters dated July 3 and November 1, 2018.
    Brief description of amendments: The amendments modified McGuire 
Nuclear Station's, Units 1 and 2, Updated Final Safety Analysis Report 
(UFSAR) to describe the methodology and results of the analyses 
performed to evaluate the protection of the plant's structures, 
systems, and components from tornado-generated missiles.
    Date of issuance: January 25, 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.: 312 (Unit 1) and 291 (Unit 2). A publicly-available 
version is in ADAMS under Accession

[[Page 3512]]

No. ML18355A610; documents related to these amendments are listed in 
the Safety Evaluation enclosed with the amendments.
    Renewed Facility Operating License Nos. NPF-9 and NPF-17: 
Amendments revised the UFSAR.
    Date of initial notice in Federal Register: June 5, 2018 (83 FR 
26100). The supplemental letters dated July 3 and November 1, 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 original proposed no significant hazards 
consideration determination as published in the Federal Register.
    No significant hazards consideration comments received: Yes. One 
comment from a member of the public was received; however, it was not 
related to the proposed no significant hazards consideration 
determination or to the proposed license amendment request.
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated January 25, 2019.

Entergy Louisiana, LLC, and Entergy Operations, Inc., Docket No. 50-
458, River Bend Station, Unit 1 (River Bend), West Feliciana Parish, 
Louisiana

    Date of amendment request: April 2, 2018, as supplemented by letter 
dated October 4, 2018.
    Brief description of amendment: The amendment revised the River 
Bend Technical Specification Figure 3.4.11-1, ``Minimum Temperature 
Required vs. RCS [Reactor Coolant System] Pressure,'' for reactor 
heatup, cooldown, and critical operations as well as for inservice leak 
tests and hydrostatic tests. The change also replaced the non-
conservative curve, which is for 32 Effective Full Power Years (EFPY), 
with a new curve that is for 54 EFPY.
    Date of issuance: January 17, 2019.
    Effective date: As of the date of issuance and shall be implemented 
30 days from the date of issuance.
    Amendment No.: 195. A publicly-available version is in ADAMS under 
Accession No. ML18360A025; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-47: The amendment 
revised the Renewed Facility Operating License and Technical 
Specifications.
    Date of initial notice in Federal Register: June 5, 2018 (83 FR 
26115). The supplemental letter dated October 4, 2018, 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 January 17, 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

    Date of amendment request: March 29, 2018, as supplemented by 
letter dated September 17, 2018.
    Brief description of amendment: The amendments revised the ANO 
Emergency Plan by changing the emergency action level scheme to one 
based on the Nuclear Energy Institute's (NEI's) guidance in NEI 99-01, 
Revision 6, ``Development of Emergency Action Levels for Non-Passive 
Reactors,'' dated November 2012, which was endorsed by the NRC by 
letter dated March 28, 2013.
    Date of issuance: January 17, 2019.
    Effective date: As of the date of issuance and shall be implemented 
on or before October 30, 2019.
    Amendment Nos.: Unit 1--263; Unit 2--314. A publicly-available 
version is in ADAMS under Accession No. ML18337A247; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Renewed Facility Operating License Nos. DPR-51 and NPF-6: The 
amendments revised the ANO Emergency Plan.
    Date of initial notice in Federal Register: May 22, 2018 (83 FR 
23733). The supplemental letter dated September 17, 2018, 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 January 17, 2019.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket No. 50-461, Clinton Power 
Station, Unit No. 1, DeWitt County, Illinois

Exelon Generation Company, LLC, Docket Nos. 50-237 and 50-249, Dresden 
Nuclear Power Station, Units 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 No. 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-
277 and 50-278, Peach Bottom Atomic Power Station, Units 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

    Date of amendment request: June 15, 2018.
    Brief description of amendments: The amendments revised the 
technical specification requirements associated with the average power 
range monitors.
    Date of issuance: January 16, 2019.
    Effective date: As of the date of issuance and shall be implemented 
within 150 days from the date of issuance.
    Amendment Nos.: Clinton Unit 1 (222); Dresden Units 1 (260) and 2 
(253); FitzPatrick (324); LaSalle Units 1 (234) and 2 (220); Limerick 
Units 1 (233) and 2 (196); Nine Mile Point Units 1 (235) and 2 (175); 
Peach Bottom Units 1 (322) and 2 (325); and Quad Cities Units 1 (272) 
and 2 (267). A publicly-available version is in ADAMS under Accession 
No. ML18304A365; documents related to these amendments are listed in 
the Safety Evaluation enclosed with the amendments.
    Facility Operating License Nos. NPF-62, DPR-19, DPR-25, DPR-59, 
NPF-11, NPF-18, NPF-39, NPF-85, DPR-63, NPF-69, DPR-44, DPR-56, DPR-29, 
and DPR-30: Amendments revised the Facility Operating Licenses and 
Technical Specifications.

[[Page 3513]]

    Date of initial notice in Federal Register: August 14, 2018 (83 FR 
40348).
    The Commission's related evaluation of the amendments is contained 
in a safety evaluation dated January 16, 2019.
    No significant hazards consideration comments received: No.

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: February 26, 2018, as supplemented by 
letter dated September 27, 2018.
    Brief description of amendments: The amendments added, deleted, 
modified, and replaced numerous technical specification requirements 
related to operations with a potential for draining the reactor vessel 
with new requirements for reactor pressure vessel water inventory 
control to protect Safety Limit 2.1.1.3.
    Date of issuance: January 28, 2019.
    Effective date: As of the date of issuance and shall be implemented 
prior to initial entry into Mode 4 for Quad Cities Nuclear Power 
Station, Unit 1 refueling outage, Q1R25.
    Amendment Nos.: Unit 1--273; Unit 2--268. A publicly-available 
version is in ADAMS under Accession No. ML18353A229; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Renewed Facility Operating License Nos. DPR-29 and DPR-30: 
Amendments revised the Technical Specifications and Licenses.
    Date of initial notice in Federal Register: April 24, 2018 (83 FR 
17861). The supplemental letter dated September 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 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 January 28, 2019.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket No. 50-220, Nine Mile Point 
Nuclear Station (Nine Mile Point), Unit 1, Oswego County, New York

    Date of amendment request: December 15, 2017, as supplemented by 
letters dated October 1 and November 2, 2018.
    Brief description of amendment: The amendment revised the Nine Mile 
Point, Unit 1, Technical Specifications by replacing requirements 
related to ``operations with a potential for draining the reactor 
vessel'' with new requirements on reactor pressure vessel water 
inventory control. The changes are based on Technical Specifications 
Task Force Improved Standard Technical Specifications Change Traveler 
TSTF-542, Revision 2, ``Reactor Pressure Vessel Water Inventory 
Control'' (ADAMS Accession No. ML16074A448).
    Date of issuance: January 22, 2019.
    Effective date: As of the date of issuance and shall be implemented 
no later than the start of the Nine Mile Point, Unit 1, Spring 2019 
refueling outage.
    Amendment No.: 236. A publicly-available version is in ADAMS under 
Accession No. ML19008A454; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-63: The amendment 
revised the Renewed Facility Operating License and Technical 
Specifications.
    Date of initial notice in Federal Register: February 13, 2018 (83 
FR 6224). The supplemental letters dated October 1 and November 2, 
2018, 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 January 22, 2019.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket Nos. 50-317 and 50-318, Calvert 
Cliffs Nuclear Power Plant, Units 1 and 2 (Calvert Cliffs), Calvert 
County, Maryland

    Date of amendment request: August 23, 2018, as supplemented by 
letters dated November 12 and November 30, 2018.
    Brief description of amendments: The amendments revised the Calvert 
Cliffs Technical Specifications to permit one-time extensions to the 
completion times for a required action in Technical Specification 
3.8.1, ``AC [Alternating Current] Sources-Operating.'' The one-time 
extension up to 14 days would apply to Required Action D.3.
    Date of issuance: January 22, 2019.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment Nos.: 328 (Unit 1) and 306 (Unit 2). A publicly-available 
version is in ADAMS under Accession No. ML18365A373; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Renewed Facility Operating License Nos. DPR-53 and DPR-69: The 
amendments revised the Renewed Facility Operating Licenses and 
Technical Specifications.
    Date of initial notice in Federal Register: October 23, 2018 (83 FR 
53513). The supplemental letters dated November 12 and November 30, 
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 original proposed no significant hazards 
consideration determination as published in the Federal Register. The 
letter dated November 30, 2018, reduced the scope of the application.
    The Commission's related evaluation of the amendments is contained 
in a safety evaluation dated January 22, 2019.
    No significant hazards consideration comments received: No.

Northern States Power Company--Minnesota, Docket No. 50-263, Monticello 
Nuclear Generating Plant (MNGP), Wright County, Minnesota

    Date of amendment request: December 19, 2017, as supplemented by 
letters dated April 24, October 23, and November 20, 2018.
    Brief description of amendment: The amendment revised the MNGP 
technical specification to adopt Technical Specification Task Force 
(TSTF) Travel 425, ``Relocate Surveillance Frequencies to Licensee 
Control--RITSTF Initiative 5B.''
    Date of issuance: January 28, 2019.
    Effective date: As of the date of issuance and shall be implemented 
prior to the next refueling outage.
    Amendment No.: 200. A publicly-available version is in ADAMS under 
Accession No. ML19007A090; 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 Renewed Facility Operating License and Technical Specifications.
    Date of initial notice in Federal Register: February 27, 2018 (83 
FR 8518). The supplemental letters dated April 24, 2018, October 23, 
2018 and November 20, 2018, provided additional

[[Page 3514]]

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 January 28, 2019.
    No significant hazards consideration comments received: No.

PSEG Nuclear LLC and Exelon Generation Company, LLC, Docket Nos. 50-272 
and 50-311, Salem Nuclear Generating Station, Unit Nos. 1 and 2, Salem 
County, New Jersey

    Date of amendment request: May 16, 2018, as supplemented by letters 
dated June 14, 2018; October 18, 2018; October 20, 2018; and October 
30, 2018.
    Brief description of amendments: The amendments revised Technical 
Specification 3.8.2.1, ``A.C. [Alternating Current] Distribution--
Operating,'' to increase the vital instrument bus inverters allowed 
outage time from 24 hours for the A, B, and C inverters to 7 days, and 
from 72 hours for the D inverter to 7 days. The extended allowed outage 
time is based on application of the Salem Nuclear Generating Station 
probabilistic risk assessment in support of a risk-informed extension, 
and on additional considerations and compensatory actions.
    Date of issuance: January 25, 2019.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days from the date of issuance.
    Amendment Nos.: 326 (Unit No. 1) and 307 (Unit No. 2). A publicly-
available version is in ADAMS under Accession No. ML19009A477; 
documents related to these amendments are listed in the Safety 
Evaluation enclosed with the amendments.
    Renewed Facility Operating License Nos. DPR-70 and DPR-75: The 
amendments revised the Renewed Facility Operating Licenses and 
Technical Specifications.
    Date of initial notice in Federal Register: July 3, 2018 (83 FR 
31186). The supplemental letters dated June 14, October 18, October 20, 
and October 30, 2018, 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 January 25, 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: March 9, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18071A363.
    Brief description of amendments: The amendments revised the Unit 
No. 1 and Unit No. 2 Technical Specifications (TS) requirements of TS 
3.3.8.1, ``Loss of Power (LOP) Instrumentation,'' by modifying the 
instrument allowable values for the 4.16 kilovolt (kV) emergency bus 
degraded voltage instrumentation and by deleting the annunciation 
requirements for the 4.16 kV emergency bus undervoltage instrumentation 
for Unit No. 2. The amendment for Unit No. 2 also revises License 
Condition 2.C(3)(i) to clarify its intent.
    Date of issuance: January 28, 2019.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days from the date of issuance.
    Amendment Nos.: Unit 1--293, Unit 2--238. A publicly-available 
version is in ADAMS under Accession No. ML19010A009; 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 
Technical Specifications.
    Date of initial notice in Federal Register: September 11, 2018 (83 
FR 45987).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated January 28, 2019.
    No significant hazards consideration comments received: No.

Southern Nuclear Operating Company, Inc., Docket Nos. 50-424 and 50-
425, Vogtle Electric Generating Plant (Vogtle), Units 1 and 2, Burke 
County, Georgia

    Date of amendment request: October 11, 2017, as supplemented by 
letters dated July 26 and September 14, 2018.
    Brief description of amendments: The amendments revised the Renewed 
Facility Operating Licenses to authorize revision of the Vogtle Units 1 
and 2 Updated Final Safety Analysis Report to incorporate the process 
based on the Tornado Missile Risk Evaluator Methodology described in 
its application, as supplemented. This methodology will only be applied 
to discovered conditions where tornado missile protection is not 
currently provided, and cannot be used to avoid providing tornado 
missile protection in the plant modification process.
    Date of issuance: January 11, 2019.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days of issuance.
    Amendment Nos.: Vogtle Unit 1--198; Unit 2--181. A publicly-
available version is in ADAMS under Accession No. ML18304A394; 
documents related to these amendments are listed in the Safety 
Evaluation enclosed with the amendments.
    Renewed Facility Operating License Nos. NPF-68 and NPF-81: 
Amendments revised the Renewed Facility Operating Licenses.
    Date of initial notice in Federal Register: March 27, 2018 (83 FR 
13150). The supplemental letters dated July 26 and September 14, 2018, 
provided additional information that clarified the application, and 
taken together, 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 January 11, 2019.
    No significant hazards consideration comments received: No.

    Dated at Rockville, Maryland, this 1st day of February, 2019.

    For the Nuclear Regulatory Commission.
Kathryn M. Brock,
Deputy Director, Division of Operating Reactor Licensing, Office of 
Nuclear Reactor Regulation.
[FR Doc. 2019-01215 Filed 2-11-19; 8:45 am]
 BILLING CODE 7590-01-P