[Federal Register Volume 83, Number 233 (Tuesday, December 4, 2018)]
[Notices]
[Pages 62618-62626]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-25728]
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NUCLEAR REGULATORY COMMISSION
[NRC-2018-0269]
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 November 6, 2018, to November 19, 2018. The
last biweekly notice was published on November 20, 2018.
DATES: Comments must be filed by January 3, 2019. A request for a
hearing must be filed by February 4, 2019.
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-2018-0269. Address
questions about Docket IDs in Regulations.gov to Jennifer Borges;
telephone: 301-287-9127; email: [email protected]. For technical
questions, contact the individual listed in the FOR FURTHER INFORMATION
CONTACT section of this document.
Mail comments to: May Ma, Office of Administration, Mail
Stop: TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001.
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: Lynn Ronewicz, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC
20555-0001; telephone: 301-415-1927, email: [email protected].
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2018-0269, 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-2018-0269.
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-2018-0269, 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 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.
[[Page 62619]]
III. Notice of Consideration of Issuance of Amendments to Facility
Operating Licenses and Combined Licenses and Proposed No Significant
Hazards Consideration Determination
The Commission has made a proposed determination that the following
amendment requests involve no significant hazards consideration. Under
the Commission's regulations in Sec. 50.92 of title 10 of the Code of
Federal Regulations (10 CFR), this means that operation of the facility
in accordance with the proposed amendment would not (1) involve a
significant increase in the probability or consequences of an accident
previously evaluated; or (2) create the possibility of a new or
different kind of accident from any accident previously evaluated; or
(3) involve a significant reduction in a margin of safety. The basis
for this proposed determination for each amendment request is shown
below.
The Commission is seeking public comments on this proposed
determination. Any comments received within 30 days after the date of
publication of this notice will be considered in making any final
determination.
Normally, the Commission will not issue the amendment until the
expiration of 60 days after the date of publication of this notice. The
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment
involves no significant hazards consideration. In addition, the
Commission may issue the amendment prior to the expiration of the 30-
day comment period if circumstances change during the 30-day comment
period such that failure to act in a timely way would result, for
example in derating or shutdown of the facility. If the Commission
takes action prior to the expiration of either the comment period or
the notice period, it will publish in the Federal Register a notice of
issuance. If the Commission makes a final no significant hazards
consideration determination, any hearing will take place after
issuance. The Commission expects that the need to take this action will
occur very infrequently.
A. Opportunity To Request a Hearing and Petition for Leave To Intervene
Within 60 days after the date of publication of this notice, any
persons (petitioner) whose interest may be affected by this action may
file a request for a hearing and petition for leave to intervene
(petition) with respect to the action. Petitions shall be filed in
accordance with the Commission's ``Agency Rules of Practice and
Procedure'' in 10 CFR part 2. Interested persons should consult a
current copy of 10 CFR 2.309. The NRC's regulations are accessible
electronically from the NRC Library on the NRC's website at http://www.nrc.gov/reading-rm/doc-collections/cfr/. Alternatively, a copy of
the regulations is available at the NRC's Public Document Room, located
at One White Flint North, Room O1-F21, 11555 Rockville Pike (first
floor), Rockville, Maryland 20852. If a petition is filed, the
Commission or a presiding officer will rule on the petition and, if
appropriate, a notice of a hearing will be issued.
As required by 10 CFR 2.309(d) the petition should specifically
explain the reasons why intervention should be permitted with
particular reference to the following general requirements for
standing: (1) The name, address, and telephone number of the
petitioner; (2) the nature of the petitioner's right under the Act to
be made a party to the proceeding; (3) the nature and extent of the
petitioner's property, financial, or other interest in the proceeding;
and (4) the possible effect of any decision or order which may be
entered in the proceeding on the petitioner's interest.
In accordance with 10 CFR 2.309(f), the petition must also set
forth the specific contentions which the petitioner seeks to have
litigated in the proceeding. Each contention must consist of a specific
statement of the issue of law or fact to be raised or controverted. In
addition, the petitioner must provide a brief explanation of the bases
for the contention and a concise statement of the alleged facts or
expert opinion which support the contention and on which the petitioner
intends to rely in proving the contention at the hearing. The
petitioner must also provide references to the specific sources and
documents on which the petitioner intends to rely to support its
position on the issue. The petition must include sufficient information
to show that a genuine dispute exists with the applicant or licensee on
a material issue of law or fact. Contentions must be limited to matters
within the scope of the proceeding. The contention must be one which,
if proven, would entitle the petitioner to relief. A petitioner who
fails to satisfy the requirements at 10 CFR 2.309(f) with respect to at
least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene.
Parties have the opportunity 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
[[Page 62620]]
its boundaries. Alternatively, a State, local governmental body,
Federally-recognized Indian Tribe, or agency thereof, may participate
as a non-party under 10 CFR 2.315(c).
If a hearing is granted, any person who is not a party to the
proceeding and is not affiliated with or represented by a party may, at
the discretion of the presiding officer, be permitted to make a limited
appearance pursuant to the provisions of 10 CFR 2.315(a). A person
making a limited appearance may make an oral or written statement of
his or her position on the issues but may not otherwise participate in
the proceeding. A limited appearance may be made at any session of the
hearing or at any prehearing conference, subject to the limits and
conditions as may be imposed by the presiding officer. Details
regarding the opportunity to make a limited appearance will be provided
by the presiding officer if such sessions are scheduled.
B. Electronic Submissions (E-Filing)
All documents filed in NRC adjudicatory proceedings, including a
request for hearing and petition for leave to intervene (petition), any
motion or other document filed in the proceeding prior to the
submission of a request for hearing or petition to intervene, and
documents filed by interested governmental entities that request to
participate under 10 CFR 2.315(c), must be filed in accordance with the
NRC's E-Filing rule (72 FR 49139; August 28, 2007, as amended at 77 FR
46562; August 3, 2012). The E-Filing process requires participants to
submit and serve all adjudicatory documents over the internet, or in
some cases to mail copies on electronic storage media. Detailed
guidance on making electronic submissions may be found in the Guidance
for Electronic Submissions to the NRC and on the NRC website at 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
application(s), see the application for amendment which is available
for public inspection in ADAMS and at the NRC's PDR. For additional
direction on accessing
[[Page 62621]]
information related to this document, see the ``Obtaining Information
and Submitting Comments'' section of this document.
Union Electric Company, Docket No. 50-483, Callaway Plant, Unit 1,
Callaway County, Missouri
Date of amendment request: September 4, 2018. A publicly-available
version is in ADAMS under Accession No. ML18247A467.
Description of amendment request: The amendment would revise
Emergency Action Levels (EALs) CA6.1, ``Cold Shutdown/Refueling System
Malfunction--Hazardous event affecting a SAFETY SYSTEM needed for the
current operating MODE: Alert,'' and SA9.1, ``System Malfunction--
Hazardous event affecting a SAFETY SYSTEM needed for the current
operating MODE: Alert.'' The amendment would also add a new definition
for the term ``Loss of Safety Function (LOSF),'' while redefining the
term ``Visible Damage,'' and deleting the term Initiating Condition
(IC) HG1 and associated EAL HG1.1, ``Hazard--Hostile Action resulting
in loss of physical control of the facility: General Emergency,''
within the Callaway Plant's Radiological Emergency Response Plan
(RERP).
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 the Callaway Plant emergency action
levels do not impact the physical function of plant structures,
systems, or components (SSC) or the manner in which SSCs perform
their design function. The proposed changes have no effect on
accident initiators or precursors, nor do they alter design
assumptions. The proposed changes do not alter or prevent the
ability of SSCs to perform their intended function to mitigate the
consequences of an initiating event within assumed acceptance
limits. No operating procedures or administrative controls that
function to prevent or mitigate accidents are affected by the
proposed changes. Therefore, the proposed changes do 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 do not involve a physical alteration of the
plant (i.e., no new or different type of equipment will be
installed, and no equipment will be removed), nor do the proposed
changes involve a change in the method of plant operation. The
proposed changes will not introduce failure modes that could result
in a new accident, nor do the changes alter 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.
There is no change being made to safety analysis assumptions,
safety limits, or limiting safety system settings that would
adversely affect plant safety as a result of the proposed changes.
There are no changes to setpoints or environmental conditions of any
SSC or the mariner in which any SSC is operated. Margins of safety
are unaffected by the proposed changes. The applicable requirements
of 10 CFR 50.47 and 10 CFR 50, Appendix E will continue to be met.
Therefore, the proposed changes do not involve any 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: John O'Neill, Pillsbury Winthrop Shaw
Pittman LLP, 2300 N Street NW, Washington, DC 20037.
NRC Branch Chief: Robert J. Pascarelli.
Pacific Gas and Electric Company, Docket Nos. 50-275 and 50-323, Diablo
Canyon Nuclear Power Plant, Units 1 and 2 (DCPP), San Luis Obispo
County, California
Date of amendment request: September 12, 2018. A publicly-available
version is in ADAMS under Accession No. ML18255A368.
Description of amendment request: The proposed amendments would
revise the Emergency Plan for DCPP to extend staff augmentation times
for Emergency Response Organization (ERO) functions.
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 increase in staff augmentation times has no effect
on normal plant operation or on any accident initiator or precursors
and does not impact the function of plant structures, systems, or
components. The proposed change does not alter or prevent the
ability of the ERO to perform their intended functions to mitigate
the consequences of an accident or event. The ability of the ERO to
respond adequately to radiological emergencies has been demonstrated
as acceptable in a staffing analysis as required by 10 CFR 50
Appendix E.IV.A.9.
Therefore, the proposed DCPP Emergency Plan changes 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 does not impact the accident analysis. The
change does not involve a physical alteration of the plant (i.e., no
new or different type of equipment will be installed), a change in
the method of plant operation, or new operator actions. The proposed
change does not introduce failure modes that could result in a new
accident, and the change does not alter assumptions made in the
safety analysis. This proposed change increases the staff
augmentation response times in the DCPP Emergency Plan, which are
demonstrated as acceptable through a staffing analysis as required
by 10 CFR 50 Appendix E.IV.A.9. The proposed change does not alter
or prevent the ability of the ERO to perform their intended
functions to mitigate the consequences of an accident or event.
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.
Margin of safety is associated with confidence in the ability of
the fission product barriers (i.e., fuel cladding, reactor coolant
system pressure boundary, and containment structure) to limit the
level of radiation dose to the public. The proposed change is
associated with the DCPP Emergency Plan staffing and does not impact
operation of the plant or its response to transients or accidents.
The change does not affect the Technical Specifications. The
proposed change does not involve a change in the method of plant
operation, and no accident analyses will be affected by the proposed
change. Safety analysis acceptance criteria are not affected by this
proposed change.
A staffing analysis and a functional analysis were performed for
the proposed change on the timeliness of performing major tasks for
the functional areas of the DCPP Emergency Plan. The analyses
concluded that an extension in staff augmentation times would not
significantly affect the ability to perform the required Emergency
Plan tasks. Therefore, the proposed change is determined to not
adversely affect the ability to meet 10 CFR 50.54(q)(2), the
requirements of 10 CFR 50 Appendix E, and the emergency
[[Page 62622]]
planning standards as described in 10 CFR 50.47 (b).
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: Jennifer Post, Pacific Gas and Electric
Company, P.O. Box 7442, San Francisco, CA 94120.
NRC Branch Chief: Robert J. Pascarelli.
Southern Nuclear Operating Company, Inc.; Georgia Power Company;
Oglethorpe Power Corporation; Municipal Electric Authority of Georgia;
and 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: June 29, 2018. A publicly-available
version is in ADAMS under Accession No. ML18180A396.
Description of amendment request: The amendments would revise the
Technical Specification (TS) requirements for the Hatch Nuclear Plant,
Unit Nos. 1 and 2. Specifically, the amendments would increase the
allowable values (AV) specified in TS Table 3.3.5.1-1 for automatic
transfer of the high pressure coolant injection (HPCI) pump suction
alignment from the condensate storage tank (CST) to the suppression
pool for Unit Nos. 1 and 2. The proposed change would also increase the
AV specified in TS Table 3.3.5.2-1 for automatic transfer of the
reactor core isolation cooling (RCIC) pump suction alignment from the
CST to the suppression pool for Unit No. 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 ensures the HPCI and RCIC pump automatic
suction transfer functions from the CST to the suppression pool
occur without introducing the possibility of vortex formation or air
intrusion in the HPCI or RCIC pump suction path. The water level of
the CST on automatic suction transfer of the HPCI and RCIC systems
to the suppression pool is not an initiator or precursor to any
accident previously evaluated. The CST water source is not assumed
to mitigate the consequences for any design basis accident, but is
assumed as a water source for the RCIC when mitigating a station
blackout event. The revised AV will ensure the RCIC can perform this
function.
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 accident previously evaluated?
Response: No.
The proposed change ensures the HPCI and RCIC pump automatic
suction transfer functions from the CST to the suppression pool
occur without introducing the possibility of vortex formation or air
intrusion in the HPCI or RCIC pump suction path. HPCI, RCIC, and CST
design functions are unaffected by this change. The change to the
HPCI and RCIC automatic suction transfer functions would not create
the possibility of any credible failure mechanism not considered in
the design and licensing basis. Additionally, no new credible
failure modes for the CST are introduced by the proposed changes.
Therefore, the proposed changes do not create the possibility of
a new or different kind of accident from any previously evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The proposed change ensures the HPCI and RCIC pump automatic
suction transfer functions from the CST to the suppression pool
occur without introducing the possibility of vortex formation or air
intrusion in the HPCI or RCIC pump suction path. The applicable
margins of safety are the AVs for the HPCI and RCIC pump automatic
suction transfer functions. The proposed change increases the margin
of safety by revising the affected AVs to address more severe
circumstances than considered in the current AVs. The proposed
change does not exceed or alter a design basis or safety limit.
Therefore, the proposed change does not involve 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: Millicent Ronnlund, Vice President and
General Counsel, Southern Nuclear Operating Co., Inc., P.O. Box 1295,
Birmingham, AL 35201-1295.
NRC Branch Chief: Michael T. Markley.
Southern Nuclear Operating Company, Inc.; Georgia Power Company;
Oglethorpe Power Corporation; Municipal Electric Authority of Georgia;
and 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: August 6, 2018. A publicly-available
version is in ADAMS under Accession No. ML18218A297.
Description of amendment request: The amendments would revise the
technical specification (TS) end state for the required actions of the
drywell spray function of the residual heat removal system for the
Hatch Nuclear Plant, Unit Nos. 1 and 2. Specifically, TS 3.6.2.5,
``Residual Heat Removal (RHR) Drywell Spray,'' would be revised to
modify the required end state of Cold Shutdown (Mode 4) to the new
required end state of Hot Shutdown (Mode 3) if the needed action
statements are not met for Unit Nos. 1 and 2.
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, with NRC staff edits in square
brackets:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The RHR drywell spray function is not an initiator of any
accident previously evaluated but is assumed to mitigate some
accidents previously evaluated. However, the proposed change does
not alter the design or safety function of the RHR system, including
the drywell spray mode. The proposed change revises the end state
when the time allowed by TS to continue operation is exceeded for
the drywell spray mode of the RHR system. This request is limited to
an end state where entry into the shutdown mode is for a short
interval and the primary purpose is to correct the initiating
condition and return to power operation as soon as practical. Risk
insights from both the qualitative and quantitative risk assessment
were used to support a change in end state for similar boiling water
reactor (BWR) systems as summarized in GE [General Electric] topical
report NEDC-32988. These assessments provide an integrated
discussion of deterministic and probabilistic issues focusing on
specific TSs used to support similar TS end states and associated
restrictions. SNC [Southern Nuclear Operating Company] finds that
the risk insights also support the conclusion of the proposed change
to the RHR drywell spray TS. Therefore, the probability of an
accident previously evaluated is not significantly increased, if at
all.
The consequences of accidents previously evaluated that assume
the drywell spray
[[Page 62623]]
function in accident mitigation are based on the plant operating
with the reactor critical and at power. A DBA in hot shutdown would
be considerably less severe than a DBA [design-basis accident]
occurring during power operation since hot shutdown is associated
with lower initial energy level and reduced decay heat load. The
risk and defense-in-depth reasoning, provided in GE topical report
NEDC-32988, supports the conclusion that hot shutdown is as safe as
cold shutdown (if not safer) for repairing an inoperable RHR
subsystem. SNC concludes the proposed change is acceptable in light
of defense-in-depth considerations and because the time spent in hot
shutdown to perform the repair is infrequent and limited. Therefore,
the consequences of any accident that assumes the drywell spray
function are not significantly affected by this change.
Consequently, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed change does not change the design function or
operation of the RHR drywell spray function. No plant modifications
or changes to the plant configuration or method of operation are
involved. If risk is assessed and managed, allowing a change to the
end state for the RHR drywell spray TS when the allowed time for
remaining in power operation with one or more RHR drywell spray
subsystem inoperable is exceeded, i.e., entry into hot shutdown
rather than cold shutdown to repair equipment, will not introduce
new failure modes or effects and will not, in the absences of other
unrelated failures, lead to an accident whose consequences exceed
the consequences of accidents previously evaluated. The addition of
a requirement to assess and manage the risk introduced by this
change and the commitment to adhere to the industry guidance related
to TS end states further minimizes possible concerns.
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 does not affect any of the controlling
values of parameters used to avoid exceeding regulatory or licensing
limits. The proposed change does not exceed or alter the design
basis or safety limits, or any limiting safety system settings. The
requirement for the drywell spray mode of the RHR system to perform
its designated safety function is unaffected. The risk assessment
approach used in the GE topical report NEDC-32988 is comprehensive
and follows NRC staff guidance. The risk assessment, summarized in
GE topical report NEDC-32988, included evaluations of systems with
similar functions as the drywell spray function of the RHR system.
In addition, the NEDC-32988 risk analyses show that the criteria of
the three-tiered approach for allowing TS changes, in accordance
with NRC staff guidance, are met. The risk assessments used to
justify TS changes associated with containment heat removal systems
are also applicable [to] the RHR drywell spray TS because these
systems perform an equivalent function as the drywell spray mode of
the RHR system and there are no unique aspects of the RHR drywell
spray containment heat removal function that would change the
conclusion that a hot shutdown end state is acceptable. The risk
assessment used to justify the TS change associated with fission
product cleanup systems is also applicable to the RHR drywell spray
TS because the systems are functionally similar and there are no
aspects of the HNP [Hatch Nuclear Plant] RHR drywell spray fission
product cleanup function that would change the conclusion that a hot
shutdown end state is acceptable. Therefore, SNC has determined that
the acceptability of hot shutdown end state for systems previously
evaluated with similar functions is also acceptable for the HNP RHR
drywell spray TS. As such, the net change to the margin of safety as
a result of the proposed change is insignificant.
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: Millicent Ronnlund, Vice President and
General Counsel, Southern Nuclear Operating Co., Inc., P.O. Box 1295,
Birmingham, AL 35201-1295.
NRC Branch Chief: Michael T. Markley.
Tennessee Valley Authority (TVA), Docket No. 50-391, Watts Bar Nuclear
Plant (WBN), Unit 2, Rhea County, Tennessee
Date of amendment request: March 5, 2018. A publicly-available
version is in ADAMS under Accession No. ML18064A192.
Description of amendment request: The amendment would revise WBN
Unit 2 Operating License (OL) Condition 2.C(4) to permit the use of the
PAD4TCD computer program to continue to establish core operating limits
until the WBN Unit 2 steam generators (SGs) are replaced with SGs
equivalent to those in WBN Unit 1. The proposed change to allow the
continued use of PAD4TCD to establish core operating limits until the
installation of the WBN Unit 2 replacement SGs reflects TVA's plan for
transitioning to PAD5 as part of the full spectrum loss-of-coolant
accident (LOCA) Evaluation Methodology.
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 Emergency Core Cooling System (ECCS) response to a large
break LOCA as described in the WBN Unit 2 dual-unit Updated Final
Safety Analysis Report (UFSAR) Section 15.4.1 incorporated an
explicit evaluation of the effects of TCD [thermal conductivity
degradation]. The UFSAR evaluation considered fuel burn-up values
that represent multi-cycle cores where the effects of TCD would be
more evident. These analyses showed that the criteria specified in
Title 10 of the Code of Federal Regulations (CFR) Sec. 50.46 are
met. The core design process evaluates each reload core to verify
that no fuel rods exceed the peaking limits shown in the WBN dual-
unit UFSAR Table 15.4-24. This ensures that the LOCA analysis in the
WBN Unit 2 dual-unit UFSAR remains bounding for future operating
cycles.
The change to WBN Unit 2 OL Condition 2.C(4) does not change the
safety analysis or any plant feature or design. Thus, it is
concluded that a significant increase in the consequences of an
accident previously evaluated will not occur as a result of the
proposed change.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed change does not create the possibility of a new or
different kind of accident from any accident previously evaluated.
The proposed change to WBN Unit 2 OL condition 2.C(4) does not
change or modify the plant design, introduce any new modes of plant
operation, change or modify the design of the ECCS, or change or
modify the accident analyses presented in the UFSAR.
Therefore, the proposed change does not create the possibility
of a new or different kind of accident from any previously
evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The LOCA safety analysis for WBN Unit 2 as described in the
UFSAR explicitly accounts for the effect of TCD. The results of this
analysis has established that WBN Unit 2 can operate safely in the
unlikely event that a design basis LOCA event occurs, there are
large margins to the regulatory limits when explicitly accounting
for TCD. This proposed change to OL condition 2.C(4) does not change
this analysis or its conclusions. Thus, the proposed change does not
result in a significant reduction in a margin of safety.
[[Page 62624]]
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.
III. 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.
Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457,
Braidwood Station, Units 1 and 2, Will County, Illinois
Date of amendment request: February 1, 2018, as supplemented by
letters dated July 9, 2018, and August 3, 2018. Publicly-available
versions are in ADAMS under Accession Nos. ML18036A227, ML18191B304,
and ML18215A421, respectively.
Brief description of amendments: The amendments revised the
licensing basis for protection from tornado-generated missiles by
identifying the TORMIS Computer Code as the methodology used for
assessing tornado-generated missile protection of unprotected plant
structures, systems, and components.
Date of issuance: November 8, 2018.
Effective date: As of the date of issuance and shall be implemented
within 90 days from the date of issuance.
Amendment Nos: 199 (Unit 1) and 199 (Unit 2). A publicly-available
version is in ADAMS under Accession No. ML18291A980; documents related
to these amendments are listed in the related Safety Evaluation
enclosed with the amendments.
Renewed Facility Operating License Nos. NPF-72 and NPF-77: The
amendments revised the licensing basis.
Date of initial notice in Federal Register: May 22, 2018 (83 FR
23734). The supplemental letters dated July 9, 2018, and August 3,
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 November 8, 2018.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket Nos. 50-317 and 50-318, Calvert
Cliffs Nuclear Power Plant (Calvert Cliffs), Units 1 and 2, Calvert
County, Maryland; Exelon Generation Company, LLC, Docket Nos. 50-220
and 50-410, Nine Mile Point Nuclear Station (Nine Mile Point), Units 1
and 2, Oswego County, New York; Exelon Generation Company, LLC, Docket
No. 50-244, R. E. Ginna Nuclear Power Plant (Ginna), Wayne County, New
York
Date of amendment request: March 26, 2018.
Brief description of amendments: The amendments revised the
licenses to eliminate the Nuclear Advisory Committee requirements for
each facility.
Date of issuance: November 15, 2018.
Effective date: As of the date of issuance and shall be implemented
within 60 days of the date of issuance.
Amendment Nos.: 327 (Calvert Cliffs, Unit 1), 305 (Calvert Cliffs,
Unit 2), 232 (Nine Mile Point, Unit 1), 173 (Nine Mile Point, Unit 2),
and 133 (Ginna). A publicly-available version is in ADAMS under
Accession No. ML18309A301. Documents related to these amendments are
listed in the Safety Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-53, DPR-69, DPR-63,
NPF-69, and DPR-18: The amendments revised the Renewed Facility
Operating Licenses.
Date of initial notice in Federal Register: May 8, 2018 (83 FR
20861).
The Commission's related evaluation of the amendments is contained
in a safety evaluation dated November 15, 2018.
No significant hazards consideration comments received: No.
Energy Northwest, Docket No. 50-397, Columbia Generating Station,
Benton County, Washington
Date of amendment request: December 18, 2017.
Brief description of amendment: The amendment revised Section 4.2
of Appendix B, ``Environmental Protection Plan (Nonradiological),'' of
the Columbia Generating Station Renewed Facility Operating License to
incorporate the terms and conditions of the incidental take statement
included in the biological opinion issued by the National Marine
Fisheries Service on March 10, 2017.
Date of issuance: November 8, 2018.
Effective date: As of the date of issuance and shall be implemented
within 60 days from the date of issuance.
Amendment No.: 252. A publicly-available version is in ADAMS under
Accession No. ML18283A125; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-21: The amendment
revised the Renewed Facility Operating License and Environmental
Protection Plan.
Date of initial notice in Federal Register: March 13, 2018 (83 FR
10916).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated November 8, 2018.
No significant hazards consideration comments received: No.
[[Page 62625]]
Indiana Michigan Power Company, Docket Nos. 50-315 and 50-316, Donald
C. Cook Nuclear Plant, Unit Nos. 1 and 2, Berrien County, Michigan
Date of amendment request: June 11, 2018.
Brief description of amendments: The amendments allow for deviation
from National Fire Protection Association 805 requirements to allow the
use of performance-based methods for flexible metallic conduit in
configurations other than to connect components, and for flexible
metallic conduit in lengths greater than short lengths.
Date of issuance: November 16, 2018.
Effective date: As of the date of issuance and shall be implemented
within 90 days of issuance.
Amendment Nos.: 342 (Unit 1) and 324 (Unit 2). A publicly-available
version is in ADAMS under Accession No. ML18284A254; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. DPR-58 and DPR-74: The
amendments revised the Renewed Facility Operating Licenses.
Date of initial notice in Federal Register: August 28, 2018 (83 FR
43905).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated November 16, 2018.
No significant hazards consideration comments received: No.
Indiana Michigan Power Company, Docket Nos. 50-315 and 50-316, Donald
C. Cook Nuclear Plant, Unit Nos. 1 and 2, Berrien County, Michigan
Date of amendment request: November 7, 2017, as supplemented by
letters dated January 19, 2018, and August 14, 2018.
Brief description of amendments: The amendments revised the
Emergency Plan to move the Technical Support Center to a different
location in a new facility located within the existing protected area.
Date of issuance: November 13, 2018.
Effective date: As of the date of issuance and shall be implemented
within 180 days of issuance.
Amendment Nos.: 341 (Unit No. 1) and 323 (Unit No. 2). A publicly-
available version is in ADAMS under Accession No. ML18249A019;
documents related to these amendments are listed in the Safety
Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-58 and DPR-74: The
amendments revised the Renewed Facility Operating Licenses.
Date of initial notice in Federal Register: January 2, 2018 (83 FR
169). The supplemental letters dated January 19, 2018, and August 14,
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 November 13, 2018.
No significant hazards consideration comments received: No.
Southern Nuclear Operating Company, Docket Nos. 50-348 and 50-364,
Joseph M. Farley Nuclear Plant, Units 1 and 2, Houston County, Alabama
Date of amendment request: December 21, 2017, as supplemented by
letter dated June 7, 2018.
Brief description of amendments: The amendments change Technical
Specification (TS) 3.3.2, ``Engineered Safety Feature Actuation System
(ESFAS) Instrumentation,'' by adding TS Actions that allow time to
restore one high steam flow channel per steam line to Operable status
before requiring a unit shutdown in the event two channels in one or
more steam lines are discovered inoperable due to the trip setting not
within Allowable Value.
Date of issuance: November 7, 2018.
Effective date: As of the date of issuance and shall be implemented
within 30 days of issuance.
Amendment Nos.: 221 (Unit 1) and 218 (Unit 2). A publicly-available
version is in ADAMS under Accession No. ML18271A207; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. NPF-2 and NPF-8: The
amendments revised the Renewed Facility Operating Licenses and TSs.
Date of initial notice in Federal Register: July 31, 2018 (83 FR
36977).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated November 7, 2018.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket No. 50-244, R. E. Ginna Nuclear
Power Plant, Wayne County, New York
Date of amendment request: November 16, 2017.
Brief description of amendment: The amendment revised the R. E.
Ginna Nuclear Power Plant Technical Specifications for selected Reactor
Trip System (RTS) and Engineered Safety Feature Actuation System
(ESFAS) instrumentation channels. The change allows selected RTS (Table
3.3.1-1) and ESFAS instrumentation channels (Table 3.3.2-1) to be
bypassed during surveillance testing. Additionally, the change allows
RTS and ESFAS input relays to be excluded from the Channel Operational
Test. The change allows testing of Nuclear Instrumentation System power
range functions, which are part of the RTS, with a permanently
installed bypass capability, while other RTS and ESFAS functions will
be capable of being bypassed utilizing permanent connections in the
racks to connect a portable test box.
Date of issuance: November 13, 2018.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment No.: 132. A publicly-available version is in ADAMS under
Accession No. ML18213A369; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-18: The amendment
revised the Renewed Facility Operating License and Technical
Specifications.
Date of initial notice in Federal Register: February 6, 2018 (83 FR
5281).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated November 13, 2018.
No significant hazards consideration comments received: No.
Entergy Louisiana, LLC, and Entergy Operations, Inc., Docket No. 50-
458, River Bend Station, Unit 1, West Feliciana Parish, Louisiana
Date of amendment request: November 15, 2017, as supplemented by
letter dated April 26, 2018.
Brief description of amendment: The amendment revised the River
Bend Station, Unit 1, Technical Specifications by replacing the
existing specifications related to ``operations with a potential for
draining the reactor vessel'' with revised requirements for reactor
pressure vessel water inventory control to protect Safety Limit
2.1.1.3. Safety Limit 2.1.1.3 requires reactor vessel water level to be
greater than the top of active irradiated fuel. The amendment adopted
changes with variations, as noted in the license amendment request, and
was based on the NRC-approved safety evaluation for Technical
Specifications Task Force (TSTF) Traveler TSTF-542, Revision 2,
``Reactor Pressure Vessel Water
[[Page 62626]]
Inventory Control,'' dated December 20, 2016.
Date of issuance: November 7, 2018.
Effective date: As of the date of issuance and shall be implemented
within 120 days from the date of issuance.
Amendment No.: 193. A publicly-available version is in ADAMS under
Accession No. ML18267A341; 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
Facility Operating License and Technical Specifications.
Date of initial notice in Federal Register: January 30, 2018 (83 FR
4292). The supplemental letter dated April 26, 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 November 7, 2018.
No significant hazards consideration comments received: No.
Florida Power & Light Company, Docket Nos. 50-250 and 50-251, Turkey
Point Nuclear Generating Unit Nos. 3 and 4, Miami-Dade County, Florida
Date of amendment request: December 21, 2017, as supplemented by
letter dated June 12, 2018.
Brief description of amendments: The amendments revised the
Technical Specifications (TSs) pertaining to the Engineered Safety
Features Actuation System instrumentation to resolve non-conservative
actions associated with the Containment ventilation isolation and the
Control Room ventilation isolation functions. In addition, the
amendments revised the Control Room ventilation isolation function to
no longer credit Containment radiation monitoring instrumentation,
eliminated redundant radiation monitoring instrumentation requirements,
eliminated select core alterations applicability requirements,
relocated radiation monitoring and Reactor Coolant System leakage
detection requirements within the TSs to align with their respective
functions, and relocated the Spent Fuel Pool area monitoring
requirements to licensee-controlled documents.
Date of issuance: November 14, 2018.
Effective date: As of the date of issuance and shall be implemented
within 90 days of issuance.
Amendment Nos.: 283 (Unit No. 3) and 277 (Unit No. 4). A publicly-
available version is in ADAMS under Accession No. ML18255A360;
documents related to these amendments are listed in the Safety
Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-31 and DPR-41: The
amendments revised the Renewed Facility Operating Licenses and TSs.
Date of initial notice in Federal Register: February 27, 2018 (83
FR 8516). The supplemental letter dated June 12, 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 November 14, 2018.
No significant hazards consideration comments received: No.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated November 14, 2018.
No significant hazards consideration comments received: No.
Dated at Rockville, Maryland, on November 20, 2018.
For the Nuclear Regulatory Commission.
Craig G. Erlanger,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. 2018-25728 Filed 12-3-18; 8:45 am]
BILLING CODE 7590-01-P