808 Federal Register / Vol. 84, No. 21 / Thursday, January 31, 2019 / Notices 

August 27, 2018. The exemptions and 

amendments were issued on December 

18, 2018, as part of a combined package 

to SNC (ADAMS Package Accession No. 

ML18341A078). 

Dated at Rockville, Maryland, this 25th day 

of January 2019. 

For the Nuclear Regulatory Commission. 

Jennifer L. Dixon-Herrity, 

Chief, Licensing Branch 2, Division of 

Licensing, Siting, and Environmental 

Analysis, Office of New Reactors. 

[FR Doc. 2019–00391 Filed 1–30–19; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2018–0287; NRC–2019–0020] 

Biweekly Notice; Applications and 

Amendments to Facility Operating 

Licenses and Combined Licenses 

Involving No Significant Hazards 

Considerations 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Biweekly notice; extension of 

comment period. 

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 December 

15, 2018, to December 28, 2018. The last 

biweekly notice was published on 

January 2, 2019 (84 FR 20). The 

comment period for the document 

published in the Federal Register on 

January 2, 2019 (84 FR 20), was 

originally scheduled to close on 

February 1, 2019. Because this 

document was posted to 

Regulations.gov on January 18, 2019, the 

NRC has decided to extend the public 

comment period to allow more time for 

stakeholders to develop and submit 

their comments. Due to the Federal 

government shutdown, there was no 

biweekly publication on January 15, 

2019. 

DATES: Comments must be filed by 

March 4, 2019. A request for a hearing 

must be filed by April 1, 2019. The due 

date for comments requested in the 

document published on January 2, 2019 

(84 FR 20) is extended. Comments 

should be filed no later than March 4, 

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 on or 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–2019–0020. Address 

questions about Docket IDs in 

Regulations.gov to Krupskaya Castellon; 

telephone: 301–287–9221; email: 

Krupskaya.Castellon@nrc.gov. For 

technical questions, contact the 

individual(s) listed in the FOR FURTHER

INFORMATION CONTACT section of this 

document. 

• Mail comments to: Office of 

Administration, Mail Stop: TWFN–7– 

A60M, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001, ATTN: Program Management, 

Announcements and Editing Staff. 

For additional direction on obtaining 

information and submitting comments, 

see ‘‘Obtaining Information and 

Submitting Comments’’ in the 

SUPPLEMENTARY INFORMATION section of 

this document. 

FOR FURTHER INFORMATION CONTACT: 

Shirley Rohrer, Office of Nuclear 

Reactor Regulation, U.S. Nuclear 

Regulatory Commission, Washington DC 

20555–0001; telephone: 301–415–5411, 

Shirley.Rohrer@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and 

Submitting Comments 

A. Obtaining Information 

Please refer to Docket ID NRC–2019– 

0020, 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 publiclyavailable 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–2019–0020. 

• NRC’s Agencywide Documents 

Access and Management System 

(ADAMS): You may obtain publiclyavailable 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 pdr.resource@

nrc.gov. 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– 

0020, 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. 


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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 

§ 50.92 of title 10 of the Code of Federal 

Regulations (10 CFR), this means that 

operation of the facility in accordance 

with the proposed amendment would 

not (1) involve a significant increase in 

the probability or consequences of an 

accident previously evaluated; or (2) 

create the possibility of a new or 

different kind of accident from any 

accident previously evaluated; or (3) 

involve a significant reduction in a 

margin of safety. The basis for this 

proposed determination for each 

amendment request is shown below. 

The Commission is seeking public 

comments on this proposed 

determination. Any comments received 

within 30 days after the date of 

publication of this notice will be 

considered in making any final 

determination. 

Normally, the Commission will not 

issue the amendment until the 

expiration of 60 days after the date of 

publication of this notice. The 

Commission may issue the license 

amendment before expiration of the 60- 

day period provided that its final 

determination is that the amendment 

involves no significant hazards 

consideration. In addition, the 

Commission may issue the amendment 

prior to the expiration of the 30-day 

comment period if circumstances 

change during the 30-day comment 

period such that failure to act in a 

timely way would result, for example in 

derating or shutdown of the facility. If 

the Commission takes action prior to the 

expiration of either the comment period 

or the notice period, it will publish in 

the Federal Register a notice of 

issuance. If the Commission makes a 

final no significant hazards 

consideration determination, any 

hearing will take place after issuance. 

The Commission expects that the need 

to take this action will occur very 

infrequently. 

A. Opportunity To Request a Hearing 

and Petition for Leave To Intervene 

Within 60 days after the date of 

publication of this notice, any persons 

(petitioner) whose interest may be 

affected by this action may file a request 

for a hearing and petition for leave to 

intervene (petition) with respect to the 

action. Petitions shall be filed in 

accordance with the Commission’s 

‘‘Agency Rules of Practice and 

Procedure’’ in 10 CFR part 2. Interested 

persons should consult a current copy 

of 10 CFR 2.309. The NRC’s regulations 

are accessible electronically from the 

NRC Library on the NRC’s website at 

http://www.nrc.gov/reading-rm/doccollections/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 Federallyrecognized 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 


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810 Federal Register / Vol. 84, No. 21 / Thursday, January 31, 2019 / Notices 

its boundaries. Alternatively, a State, 

local governmental body, Federallyrecognized Indian Tribe, or agency 

thereof may participate as a non-party 

under 10 CFR 2.315(c). 

If a hearing is granted, any person 

who is not a party to the proceeding and 

is not affiliated with or represented by 

a party may, at the discretion of the 

presiding officer, be permitted to make 

a limited appearance pursuant to the 

provisions of 10 CFR 2.315(a). A person 

making a limited appearance may make 

an oral or written statement of his or her 

position on the issues but may not 

otherwise participate in the proceeding. 

A limited appearance may be made at 

any session of the hearing or at any 

prehearing conference, subject to the 

limits and conditions as may be 

imposed by the presiding officer. Details 

regarding the opportunity to make a 

limited appearance will be provided by 

the presiding officer if such sessions are 

scheduled. 

B. Electronic Submissions (E-Filing) 

All documents filed in NRC 

adjudicatory proceedings, including a 

request for hearing and petition for 

leave to intervene (petition), any motion 

or other document filed in the 

proceeding prior to the submission of a 

request for hearing or petition to 

intervene, and documents filed by 

interested governmental entities that 

request to participate under 10 CFR 

2.315(c), must be filed in accordance 

with the NRC’s E-Filing rule (72 FR 

49139; August 28, 2007, as amended at 

77 FR 46562; August 3, 2012). The EFiling 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 

hearing.docket@nrc.gov, 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 EFiling 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/esubmittals.html, by email to 

MSHD.Resource@nrc.gov, or by a tollfree 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 


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information related to this document, 

see the ‘‘Obtaining Information and 

Submitting Comments’’ section of this 

document. 

Duke Energy Carolinas, LLC, Docket 

Nos. 50–269, 50–270, and 50–287, 

Oconee Nuclear Station, Units 1, 2, and 

3, Oconee County, South Carolina 

Date of amendment request: 

November 1, 2018. A publicly-available 

version is in ADAMS under Accession 

No. ML18318A320. 

Description of amendment request: 

The amendments would revise the dose 

consequences for the facility, as 

described in the Updated Final Safety 

Analysis Report, to provide fission gas 

gap release fractions for high-burnup 

fuel rods that exceed the linear heat 

generation rate limit detailed in 

Regulatory Guide (RG) 1.183, 

‘‘Alternative Radiological Source Terms 

for Evaluating Design Basis Accidents at 

Nuclear Power Reactors’’ (ADAMS 

Accession No. ML003716792), Table 3, 

Footnote 11. The amendments would 

allow a higher bounding rod power 

history and the removal of a restriction 

on the number of rods per assembly that 

can exceed the rod power burnup 

criteria of Footnote 11 in RG 1.183. 

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? 

The proposed change involves using gap 

release fractions for high-burnup fuel rods 

(i.e., greater than 54 GWD/MTU [gigawatt 

days per metric ton of uranium]) that exceed 

the 6.3 kW/ft [kilowatt per foot] linear heat 

generation rate (LHGR) limit detailed in 

Table 3, Footnote 11 of RG 1.183. Increased 

gap release fractions were determined and 

accounted for in the dose analysis for ONS 

[Oconee Nuclear Station]. The dose 

consequences reported in the ONS Updated 

Final Safety Analysis Report (UFSAR) were 

reanalyzed for fuel handling accidents only. 

Dose consequences were not reanalyzed for 

other non-fuel-handling accidents since no 

fuel rod that is predicted to enter departure 

from nucleate boiling (DNB) will be 

permitted to operate beyond the limits of RG 

1.183, Table 3, Footnote 11. The current NRC 

requirements, as described in 10 CFR 50.67, 

specifies [sic] dose acceptance criteria in 

terms of Total Effective Dose Equivalent 

(TEDE). The revised dose consequence 

analyses for the fuel handling events at ONS 

meet the applicable TEDE dose acceptance 

criteria (specified also in RG 1.183). 

The changes proposed do not affect the 

precursors for fuel handling accidents 

analyzed in Chapter 15 of the ONS UFSAR. 

The probability remains unchanged since the 

accident analyses performed and discussed 

in the basis for the UFSAR changes involve 

no change to a system, structure or 

component that affects initiating events for 

any UFSAR Chapter 15 accident evaluated. 

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? 

The proposed change involves using gap 

release fractions for high-burnup fuel rods 

(i.e., greater than 54 GWD/MTU) that exceed 

the 6.3 kW/ft LHGR limit detailed in Table 

3, Footnote 11 of RG 1.183. Increased gap 

release fractions were determined for certain 

isotopes, and were accounted for in the dose 

analysis for ONS. The dose consequences 

reported in the ONS UFSAR were reanalyzed 

for fuel handling accidents only. Dose 

consequences were not reanalyzed for other 

non-fuel-handling accidents since no fuel rod 

that is predicted to enter departure from 

nucleate boiling (DNB) will be permitted to 

operate beyond the limits of RG 1.183, Table 

3, Footnote 11. 

The proposed change does not involve the 

addition or modification of any plant 

equipment. The proposed change has the 

potential to affect future core designs for 

ONS. However, the impact will not be 

beyond the standard function capabilities of 

the equipment. The proposed change 

involves using gap release fractions that 

would allow high-burnup fuel rods (i.e., 

greater than 54 GWD/MTU) to exceed the 6.3 

kW/ft LHGR limit detailed in Table 3, 

Footnote 11 of RG 1.183. Accounting for 

these new gap release fractions in the dose 

analysis for ONS does not create the 

possibility of a new accident. 

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? 

The proposed change involves using gap 

release fractions for high-burnup fuel rods 

(i.e., greater than 54 GWD/MTU) that exceed 

the 6.3 kW/ft LHGR limit detailed in Table 

3, Footnote 11 of RG 1.183. Increased gap 

release fractions were determined for certain 

isotopes, and were accounted for in the dose 

analysis for ONS. The dose consequences 

reported in the ONS UFSAR were reanalyzed 

for fuel handling accidents only. Dose 

consequences were not reanalyzed for other 

non-fuel-handling accidents since no fuel rod 

that is predicted to enter departure from 

nucleate boiling (DNB) will be permitted to 

operate beyond the limits of RG 1.183, Table 

3, Footnote 11. 

The proposed change has the potential for 

an increased postulated accident dose at 

ONS. However, the analysis demonstrates 

that the resultant doses are within the 

appropriate acceptance criteria. The margin 

of safety, as defined by 10 CFR 50.67 and 

Regulatory Guide 1.183, has been 

maintained. Furthermore, the assumptions 

and input used in the gap release and dose 

consequences calculations are conservative. 

These conservative assumptions ensure that 

the radiation doses calculated pursuant to 

Regulatory Guide 1.183 and cited in this LAR 

are the upper bounds to radiological 

consequences of the fuel handling accidents 

analyzed. The analysis shows that with 

increased gap release fractions accounted for 

in the dose consequences calculations there 

is margin between the offsite radiation doses 

calculated and the dose limits of 10 CFR 

50.67 and acceptance criteria of Regulatory 

Guide 1.183. The proposed change will not 

degrade the plant protective boundaries, will 

not cause a release of fission products to the 

public, and will not degrade the performance 

of any structures, systems or components 

important to safety. 

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: Kate Nolan, 

Deputy General Counsel, Duke Energy 

Carolinas, 550 South Tryon Street, 

Charlotte, NC 28202. 

NRC Branch Chief: Michael T. 

Markley. 

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: October 

18, 2018. A publicly-available version is 

in ADAMS under Accession No. 

ML18291A628. 

Description of amendment request: 

The proposed amendments would 

revise the allowable value associated 

with Function 1.b (i.e., 4.16 kiloVolt 

Emergency Bus Undervoltage (Loss of 

Voltage)—Time Delay) of Table 3.3.8.1– 

1, ‘‘Loss of Power Instrumentation,’’ in 

Technical Specification 3.3.8.1. 

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 involve a 

physical alteration of the plant (i.e., no new 

or different type of equipment will be 

installed). The proposed change revises the 

Allowable Value for the Time Delay Loss of 

Voltage relays to resolve a design 

vulnerability potentially impacting the 

Emergency Diesel Generator (EDG) output 


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breaker logic; thereby ensuring reliability of 

the onsite AC electrical sources. Therefore, 

the proposed change does not adversely 

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. Further, the proposed 

change does not increase the types and the 

amounts of radioactive effluent that may be 

released, nor significantly increase 

individual or cumulative occupation/public 

radiation exposures. 

Therefore, the proposed amendments do 

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 accident previously 

evaluated? 

Response: No. 

The proposed change revises the Allowable 

Value for the Time Delay Loss of Voltage 

relays. It does not require any modification 

to the plant and it does not alter the design 

configuration, or method of operation of 

plant equipment beyond its normal 

functional capabilities. The proposed change 

will not introduce failure modes that could 

result in a new accident, and the change does 

not alter assumptions made in the safety 

analysis. 

Therefore, the proposed amendments do 

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 change revises the Allowable 

Value for the Time Delay Loss of Voltage 

relays to resolve a design vulnerability 

potentially impacting the EDG output breaker 

logic; thereby ensuring reliability of the 

onsite AC electrical sources. It does not alter 

or exceed a design basis or safety limit. There 

is no change being made to safety analysis 

assumptions or the safety limits that would 

adversely affect plant safety as a result of the 

proposed change. Margins of safety are 

unaffected by the proposed change and the 

applicable requirements of 10 CFR 

50.36(c)(3) and 10 CFR 50, Appendix A will 

continue to be met. 

Therefore, the proposed amendments do 

not result in a significant reduction in the 

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: Kathryn B. 

Nolan, Deputy General Counsel, 550 

South Tryon Street, M/C DEC45A, 

Charlotte, NC 28202. 

NRC Branch Chief: Undine Shoop. 

Northern States Power Company, 

Docket Nos. 50–282 and 50–306, Prairie 

Island Nuclear Generating Plant, Units 

1 and 2 (PINGP), Goodhue County, 

Minnesota 

Date of amendment request: October 

2, 2018, as supplemented by letter dated 

December 4, 2018. Publicly-available 

versions are in ADAMS under 

Accession Nos. ML18275A370 and 

ML18338A431, respectively. 

Description of amendment request: 

The amendments would revise the 

PINGP licensing basis regarding the 

safety classification of certain fuel 

handling equipment. The amendments 

would revise the PINGP Updated Safety 

Analysis Report (USAR) regarding 

specific fuel handling equipment to 

relax the PINGP-specific classification 

scheme to allow them to be classified as 

quality assurance (QA) Type III, nonsafety related. 

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 fuel handling accident is the only 

previously evaluated accident for the fuel 

handling equipment being addressed. The 

proposed amendment does not result in a 

significant increase in the probability of an 

accident because the change in definition of 

substantial amount of radioactivity as 

applied to determining the safety 

classification of the specified fuel handling 

equipment will not alter the results of fuel 

handling accidents analyzed in Chapter 14 of 

the PINGP Updated Safety Analysis Report. 

[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 previously evaluated? 

Response: No. 

The proposed reclassification of specified 

refueling handling equipment does not alter 

existing system interactions or introduce new 

system interactions. The change will not 

affect how the specified equipment is 

operated or maintained. Neither will the 

change affect the QA requirements for 

equipment that is required to maintain 

integrity for seismic category II/I 

requirements, so no new potential accidents 

need be postulated as a result of the proposed 

change. 

Therefore, the proposed change does not 

create the possibility of a new or different 

kind of accident from any accident 

previously evaluated in the USAR. 

3. Does the proposed amendment involve 

a significant reduction in a margin of safety? 

Response: No. 

The proposed amendment revises the 

current licensing basis to apply a criterion for 

designating equipment as safety-related that 

is consistent with the definition of 

‘‘Comparable Off-site Exposures’’ in 

[American Nuclear Standards Institute/ 

American Nuclear Society (ANSl/ANS)- 

58.14–1993] for the purposes of equipment 

quality assurance type. The proposed 

amendment is consistent with existing 

regulatory guidance. The proposed 

amendment does not reduce compliance with 

[Atomic Energy Commission (AEC) General 

Design Criteria (GDC) 1]. 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: Peter M. Glass, 

Assistant General Counsel, Xcel Energy 

Services, Inc., 414 Nicollet Mall, 

Minneapolis, MN 55401. 

NRC Branch Chief: David J. Wrona. 

Southern Nuclear Operating Company, 

Inc., Docket Nos. 52–025 and 52–026, 

Vogtle Electric Generating Plant, Units 3 

and 4, Burke County, Georgia 

Date of amendment request: 

November 20, 2018. A publiclyavailable version is in ADAMS under 

Accession No. ML18324A823. 

Description of amendment request: 

The requested amendment proposes to 

depart from information in the Updated 

Final Safety Analysis Report (UFSAR) 

(which includes the plant-specific 

Design Control Document 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 requested amendment 

proposes changes that are editorial in 

nature to promote consistency with the 

licensing basis. 

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 consistency and editorial 

changes to Tier 2 information in the UFSAR, 

COL Appendix C (and associated plantspecific Tier 1) information, and COL 

Appendix A Technical Specifications do not 


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involve a technical change (e.g., there is no 

design parameter or requirement, calculation, 

analysis, function or qualification change). 

No structure, system, or component (SSC) 

design or function would be affected. No 

design or safety analysis would be 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 

radioactive 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. 

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 consistency and editorial 

changes to Tier 2 information in the UFSAR, 

COL Appendix C (and associated plantspecific Tier 1) information, and COL 

Appendix A Technical Specifications do not 

change the design of safety-related SSCs. The 

proposed changes do not affect plant 

electrical systems, and does not affect the 

design function, support, design, or operation 

of mechanical and fluid systems. The 

proposed changes do not result in a new 

failure mechanism or introduce any new 

accident precursors. No design function 

described in the UFSAR is affected by the 

proposed changes. 

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 consistency and editorial 

changes to Tier 2 information in the UFSAR, 

COL Appendix C (and associated plantspecific Tier 1) information, and COL 

Appendix A Technical Specifications do not 

involve any change to the design as described 

in the COL. There would be no change to an 

existing design basis, design function, 

regulatory criterion, or analyses. 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: Mr. M. Stanford 

Blanton, Balch & Bingham LLP, 1710 

Sixth Avenue North Birmingham, AL 

35203–2015. 

NRC Branch Chief: Jennifer L. DixonHerrity. 

IV. Previously Published Notices 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 notices were previously 

published as separate individual 

notices. The notice content was the 

same as above. They were published as 

individual notices either because time 

did not allow the Commission to wait 

for this biweekly notice or because the 

action involved exigent circumstances. 

They are 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. 

Exelon Generation Company, LLC, 

Docket No. 50–461, Clinton Power 

Station (CPS), Unit No.1, DeWitt 

County, Illinois 

Date of amendment request: 

September 17, 2018. A publiclyavailable version is in ADAMS under 

Accession No. ML18260A307. 

Description of amendment request: 

The amendment would recapture lowpower testing time to extend the fullpower operating license (FPOL) to 

expire on April 17, 2027, instead of the 

current expiration date of September 29, 

2026. 

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 does not involve 

a significant increase in the probability or 

consequences of an accident previously 

evaluated because it does not involve a 

change to the design configuration or 

operation of the facility. The proposed 

change does not affect the source term, 

containment isolation or radiological release 

assumptions used in evaluating the 

radiological consequences of an accident 

previously analyzed in the CPS Updated 

Safety Analysis Report (USAR). 

CPS was designed and constructed to 

ensure at least a 40-year service life. Design 

features provide for inspection of structures, 

systems, and components during this service 

life. Surveillance, inspection, and 

maintenance practices, which have been 

implemented in accordance with the 

American Society of Mechanical Engineers 

(ASME) Boiler and Pressure Vessel Code and 

the CPS Technical Specifications, provide 

assurance that any degradation in plant 

safety-related equipment will be identified 

and corrected to ensure continued safe 

operation of the unit throughout the duration 

of the facility operating license. 

The low-power testing recapture period 

requested by this amendment is for 6.5 

months. This time period is insignificant 

from an aging effects perspective, particularly 

when considered in conjunction with the 

surveillance, inspection, and maintenance 

programs described above. 

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 previously evaluated? 

Response: No. 

The proposed amendment would revise the 

expiration date of the facility operating 

license to base it upon the issuance date of 

the FPOL and not the issuance date of the 

low-power testing license. The proposed 

change does not involve physical alteration 

of plant systems, structures, or components, 

or changes in parameters governing the 

manner in which the plant is operated and 

maintained. 

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 amendment would revise the 

expiration date of the facility operating 

license to base it upon the issuance date of 

the FPOL and not the issuance date of the 

low-power testing license. No physical 

changes are being made to the design features 

or operation of the facility. 

Margin of safety is associated with 

confidence in the ability of the fission 

produce barriers (i.e., fuel cladding, reactor 

coolant system pressure boundary, and 

containment structure) to limit the 

radiological dose to the public and control 

room operators in the event of an accident. 

The proposed amendment to the facility 

operating license has no impact on the 

margin of safety and robustness provided in 

the design and construction of the facility. In 

addition, the proposed amendment will not 

relax any of the criteria used to establish 

safety limits, nor will the proposed 

amendment relax safety system settings or 

limiting conditions for operation as defined 

in the Technical Specifications. 

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. 


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Attorney for licensee: Tamra Domeyer, 

Associate General Counsel, Exelon 

Generation Company, 4300 Winfield 

Road, Warrenville, IL 60555. 

NRC Branch Chief: David J. Wrona. 

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 Carolinas, LLC, Docket 

Nos. 50–269, 50–270, and 50–287, 

Oconee Nuclear Station, Units 1, 2, and 

3, Oconee County, South Carolina 

Date of amendment request: October 

20, 2017, as supplemented by letters 

dated June 15, July 20, and September 

21, 2018. 

Brief description of amendments: The 

amendments revise the Updated Final 

Safety Analysis Report (UFSAR) to 

provide off-nominal success criteria for 

maintaining the reactor in a safe 

shutdown condition when using the 

Standby Shutdown Facility (SSF) to 

mitigate a Turbine Building Flood 

occurring when an Oconee Unit is not 

at nominal full power conditions. The 

amendments also revise the UFSAR to 

allow the use of the Main Steam 

Atmospheric Dump Valves, when 

available, to enhance SSF mitigation 

capabilities. 

Date of issuance: December 17, 2018. 

Effective date: As of the date of 

issuance and shall be implemented 

within 90 days of issuance. 

Amendment Nos.: 410, 412, and 411. 

A publicly-available version is in 

ADAMS under Accession No. 

ML18311A134; documents related to 

these amendments are listed in the 

Safety Evaluation enclosed with the 

amendments. 

Facility Operating License Nos. DPR– 

38, DPR–47 and DPR–55: Amendments 

revised the UFSAR. 

Date of initial notice in Federal 

Register: July 3, 2018 (83 FR 31193), as 

corrected by a notice published on July 

10, 2018 (83 FR 31979), that changed 

the period for filing petitions to account 

for a Federal holiday. The supplemental 

letters dated June 15, July 20, and 

September 21, 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 amendment is contained in a 

Safety Evaluation dated December 17, 

2018. 

No significant hazards consideration 

comments received: No. 

Entergy Louisiana, LLC, and Entergy 

Operations, Inc., Docket No. 50–458, 

River Bend Station, Unit 1 (RBS), West 

Feliciana Parish, Louisiana 

Date of amendment request: January 

29, 2018, as supplemented by letters 

dated June 21, August 15, and 

November 13, 2018. 

Brief description of amendment: The 

amendment revised the RBS Updated 

Safety Analysis Report to reflect the 

relocation of the reactor core isolation 

cooling injection point from the reactor 

vessel head spray nozzle to the ‘A’ 

Feedwater line via the ‘A’ Residual Heat 

Removal shutdown cooling return line. 

Date of issuance: December 21, 2018. 

Effective date: As of the date of 

issuance and shall be implemented 

within 30 days from the date of 

issuance. 

Amendment No.: 194. A publiclyavailable version is in ADAMS under 

Accession No. ML18345A342; 

documents related to this amendment 

are listed in the Safety Evaluation 

enclosed with the amendment. 

Facility Operating License No. NPF– 

47: The amendment revised the 

Updated Safety Analysis Report. 

Date of initial notice in Federal 

Register: May 22, 2018 (83 FR 23732). 

The supplemental letters dated June 21, 

August 15, and November 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 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 December 21, 

2018. 

No significant hazards consideration 

comments received: No. 

Entergy Nuclear Operations, Inc., 

Docket No. 50–286, Indian Point 

Nuclear Generating Unit No. 3 (Indian 

Point 3), Westchester County, New York 

Date of amendment request: 

December 8, 2017, as supplemented by 

letter dated July 3, 2018. 

Brief description of amendment: The 

amendment revised Technical 

Specification 5.5.15, ‘‘Containment 

Leakage Rate Testing Program,’’ to 

extend the frequency of the primary 

containment integrated leak rate test, or 

Type A test, at Indian Point 3. 

Specifically, the amendment allows for 

a one-time extension of the integrated 

leak rate test frequency from 15 years to 

no later than the plant restart after the 

Indian Point 3 Spring 2021 (3R21) 

Refueling Outage (i.e., approximately 16 

years). 

Date of issuance: December 20, 2018. 

Effective date: As of the date of 

issuance, and shall be implemented 

within 30 days. 

Amendment No.: 265. A publiclyavailable version is in ADAMS under 

Accession No. ML18337A422; 

documents related to this amendment 

are listed in the Safety Evaluation 

enclosed with the amendment. 

Amended Facility Operating License 

No. DPR–64: The amendment revised 

the Amended Facility Operating License 

and Technical Specifications. 

Date of initial notice in Federal 

Register: March 13, 2018 (83 FR 10916). 

The supplemental letter dated July 3, 

2018, provided additional information 

that clarified the application, did not 

expand the scope of the application as 

originally noticed, and did not change 


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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 December 20, 

2018. 

No significant hazards consideration 

comments received: No. 

Entergy Operations, Inc., Docket No. 50– 

368, Arkansas Nuclear One, Unit 2 

(ANO–2), Pope County, Arkansas 

Date of amendment request: 

December 14, 2017. 

Brief description of amendment: The 

amendment revised the technical 

specification (TS) requirements in 

ANO–2 TS 3.3.3.6, ‘‘Post-Accident 

Instrumentation,’’ to ensure both 

Category 1 and Type A Regulatory 

Guide 1.97, Revision 3, 

‘‘Instrumentation for Light-WaterCooled Nuclear Power Plants to Assess 

Plant and Environs Conditions During 

and Following an Accident,’’ 

instrumentation is included in the 

specification (unless already addressed 

within another specification) and gains 

greater consistency with NUREG–1432, 

Revision 4, ‘‘Standard Technical 

Specifications, Combustion Engineering 

Plants.’’ 

Date of issuance: December 19, 2018. 

Effective date: As of the date of 

issuance and shall be implemented 

within 90 days from the date of 

issuance. 

Amendment No.: 313. A publiclyavailable version is in ADAMS under 

Accession No. ML18317A382; 

documents related to this amendment 

are listed in the Safety Evaluation 

enclosed with the amendment. 

Renewed Facility Operating License 

No. NPF–6: The amendment revised the 

Renewed Facility Operating License and 

TS. 

Date of initial notice in Federal 

Register: February 27, 2018 (83 FR 

8515). 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated December 19, 

2018. 

No significant hazards consideration 

comments received: No. 

Exelon Generation Company, LLC, 

Docket Nos. 50–373 and 50–374, LaSalle 

County Station (LSCS), Units 1 and 2, 

LaSalle County, Illinois 

Date of amendment request: February 

27, 2018. 

Brief description of amendment: The 

amendments revised the LSCS 

Technical Specification 3.4.4, ‘‘Safety/ 

Relief Valves (S/RVs).’’ Specifically, the 

amendments change the as-found 

tolerances with respect to the lift 

setpoint lower tolerance limit for the S/ 

RVs as delineated in Surveillance 

Requirement 3.4.4.1 from ¥3 percent to 

¥5 percent. The as-found tolerances are 

used for determining operability and to 

increase sample sizes for S/RV testing 

should the tolerance be exceeded. 

Date of issuance: December 19, 2018. 

Effective date: As of the date of 

issuance and shall be implemented 

within 45 days of issuance. 

Amendment No.: Unit 1—232; Unit 

2—218. A publicly-available version is 

in ADAMS under Accession No. 

ML18278A030; documents related to 

these amendments are listed in the 

Safety Evaluation enclosed with the 

amendments. 

Renewed Facility Operating License 

Nos. NPF–11 and NPF–18: The 

amendments revised the Renewed 

Facility Operating Licenses and 

Technical Specifications. 

Date of initial notice in Federal 

Register: April 10, 2018 (83 FR 15416). 

The Commission’s related evaluation 

of the amendments is contained in a 

Safety Evaluation dated December 19, 

2018. 

No significant hazards consideration 

comments received: No. 

Exelon Generation Company, LLC, 

Docket No. 50–289, Three Mile Island 

Nuclear Station, Unit 1, Dauphin 

County, Pennsylvania 

Date of amendment request: 

November 10, 2017, as supplemented by 

letters dated October 10, 2018, and 

October 29, 2018. 

Brief description of amendment: The 

amendment revised Section 6.0, 

‘‘Administrative Controls,’’ of the Three 

Mile Island Nuclear Station, Unit 1, 

Technical Specifications, which makes 

changes to the organization, staffing, 

and training requirements. The 

amendment also revised Section 1.0, 

‘‘Definitions,’’ of the Technical 

Specifications to add two new positions 

for Certified Fuel Handler and NonCertified Operator. 

Date of issuance: December 14, 2018. 

Effective date: The amendment will 

be effective upon the licensee’s 

submittal of the certifications required 

by 10 CFR 50.82(a)(1)(i) and (ii), and 

shall be implemented within 60 days of 

the effective date of the amendment, but 

may not exceed December 31, 2019. 

Amendment No.: 295. A publiclyavailable version is in ADAMS under 

Accession No. ML18305B419; 

documents related to this amendment is 

listed in the Safety Evaluation enclosed 

with the amendment. 

Renewed Facility Operating License 

No. DPR–50: The amendment revised 

the Renewed Facility Operating License 

and Technical Specifications. 

Date of initial notice in Federal 

Register: February 13, 2018 (83 FR 

6225). The supplemental letters dated 

October 10, 2018, and October 29, 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 December 14, 

2018. 

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: 

December 18, 2017. 

Brief description of amendments: The 

amendments revised Technical 

Specification 3/4.3.1, ‘‘Reactor Trip 

System Instrumentation,’’ and Technical 

Specification 3/4.3.2, ‘‘Engineered 

Safety Feature Actuation System 

Instrumentation,’’ to increase the 

completion times and bypass test times 

at Salem Nuclear Generating Station, 

Unit Nos. 1 and 2. These changes are 

consistent with the NRC-approved 

Technical Specifications Task Force 

(TSTF) Travelers TSTF–411, Revision 1, 

‘‘Surveillance Test Interval Extension 

for Components of the Reactor 

Protection System (WCAP–15376–P),’’ 

and TSTF–418, Revision 2, ‘‘RPS 

[Reactor Protection System] and ESFAS 

[Engineered Safety Feature Actuation 

System] Test Times and Completion 

Times (WCAP–14333),’’ or are 

supported by plant-specific analysis. 

Date of issuance: December 19, 2018. 

Effective date: As of the date of 

issuance and shall be implemented 

within 90 days from the date of 

issuance. 

Amendment Nos.: 325 (Unit No. 1) 

and 306 (Unit No. 2). A publiclyavailable version is in ADAMS under 

Accession No. ML18318A266; 

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. 


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Date of initial notice in Federal 

Register: March 13, 2018 (83 FR 

10921). The supplemental letters dated 

February 9, 2018 and July 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 December 19, 

2018. 

No significant hazards consideration 

comments received: No. 

Tennessee Valley Authority, Docket No. 

50–391, Watts Bar Nuclear Plant, Unit 2, 

Rhea County, Tennessee 

Date of amendment request: October 

31, 2018. 

Brief description of amendment: The 

amendment revised the completion date 

for License Condition 2.C.(5) for the 

Watts Bar Nuclear Plant, Unit 2, 

regarding the completion of action to 

resolve the issues identified in NRC 

Bulletin 2012–01, ‘‘Design Vulnerability 

in Electric Power System’’ (ADAMS 

Accession No. ML12074A115), from 

December 31, 2018, to December 31, 

2019, to align with the remainder of the 

Tennessee Valley Authority fleet and 

with the nuclear industry. 

Date of issuance: December 21, 2018. 

Effective date: As of the date of 

issuance and shall be implemented 

immediately. 

Amendment No.: 23. A publiclyavailable version is in ADAMS under 

Accession No. ML18334A333; 

documents related to this amendment 

are listed in the Safety Evaluation 

enclosed with the amendment. 

Facility Operating License No. NPF– 

96: The amendment revised the Facility 

Operating License. 

Date of initial notice in Federal 

Register: November 14, 2018 (83 FR 

56876). 

The Commission’s related evaluation 

of the amendment and final 

determination of no significant hazards 

consideration is contained in a Safety 

Evaluation dated December 21, 2018. 

No significant hazards consideration 

comments received: One comment was 

received on December 14, 2018. The 

public comment and the NRC staff 

response are provided in the Safety 

Evaluation. 

Dated at Rockville, Maryland, this 25th day 

of January 2019. 

For the Nuclear Regulatory Commission. 

Gregory F. Suber, 

Director, Division of Operating Reactor 

Licensing, Office of Nuclear Reactor 

Regulation. 

[FR Doc. 2019–00358 Filed 1–30–19; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 50–293 and 72–1044; NRC– 

2018–0279] 

Pilgrim Nuclear Power Station; 

Consideration of Approval of Transfer 

of License and Conforming 

Amendment 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Application for direct and 

indirect transfers of license; opportunity 

to comment, request a hearing, and 

petition for leave to intervene. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) received and is 

considering approval of an application 

filed by Entergy Nuclear Operations, 

Inc. (ENOI) on November 16, 2018. The 

application seeks NRC approval of the 

direct and indirect transfers of Renewed 

Facility Operating License No. DPR–35 

for Pilgrim Nuclear Power Station 

(Pilgrim) as well as the general license 

for Pilgrim Independent Spent Fuel 

Storage Installation (ISFSI), collectively 

the Licenses. ENOI on behalf of itself 

and Entergy Nuclear Generation 

Company (ENGC), Holtec International 

(Holtec), and Holtec Decommissioning 

International, LLC (HDI) requests that 

the NRC consent to (1) the indirect 

transfer of control of the Licenses to 

Holtec; and (2) the direct transfer of 

ENOI’s operating authority to HDI. The 

NRC is also considering amending the 

renewed facility operating license for 

administrative purposes to reflect the 

proposed transfer. The application 

contains sensitive unclassified nonsafeguards information (SUNSI). 

DATES: Comments must be filed by 

March 4, 2019. A request for a hearing 

must be filed by February 20, 2019. Any 

potential party as defined in § 2.4 of title 

10 of the Code of Federal Regulations 

(10 CFR), who believes access to SUNSI 

is necessary to respond to this notice 

must follow the instructions in Section 

VI of the SUPPLEMENTARY INFORMATION

section of this notice. 

ADDRESSES: You may submit comments 

by any of the following methods (unless 

this document describes a different 

method for submitting comments on a 

specific subject): 

• Federal Rulemaking website: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2018–0279. Address 

questions about Docket IDs in 

Regulations.gov to Krupskaya Castellon; 

telephone: 301–287–9221; email: 

Krupskaya.Castellon@nrc.gov. For 

technical questions, contact the 

individual(s) listed in the FOR FURTHER

INFORMATION CONTACT section of this 

document. 

• Email comments to: 

Hearingdocket@nrc.gov. If you do not 

receive an automatic email reply 

confirming receipt, then contact us at 

301–415–1677. 

• Fax comments to: Secretary, U.S. 

Nuclear Regulatory Commission at 

301–415–1101. 

• Mail comments to: Secretary, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001, ATTN: 

Rulemakings and Adjudications Staff. 

• Hand deliver comments to: 11555 

Rockville Pike, Rockville, Maryland 

20852, between 7:30 a.m. and 4:15 p.m. 

(Eastern Time) Federal workdays; 

telephone: 301–415–1677. 

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: John 

G. Lamb, Office of Nuclear Reactor 

Regulation, telephone: 301–415–3100, 

email: John.Lamb@nrc.gov; U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001. 

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and 

Submitting Comments 

A. Obtaining Information 

Please refer to Docket ID NRC–2018– 

0279 when contacting the NRC about 

the availability of information for this 

action. You may obtain publiclyavailable 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–2018–0279. 

• NRC’s Agencywide Documents 

Access and Management System 

(ADAMS): You may obtain publiclyavailable 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 pdr.resource@

nrc.gov. The ADAMS accession number 

for each document referenced (if it is 


amozie on DSK3GDR082PROD with NOTICES1